System Design Description (SyDD) — ISO/IEC/IEEE 15289 — Description | IEEE 29148 §6.5
Generated 2026-03-27 — UHT Journal / universalhex.org
flowchart TB n0["system<br>Radio Chemistry Laboratory"] n1["subsystem<br>Sample Receipt and Preparation"] n2["subsystem<br>Gamma Spectrometry Suite"] n3["subsystem<br>Alpha Spectrometry Laboratory"] n4["subsystem<br>Liquid Scintillation Counting"] n5["subsystem<br>ICP-MS Analysis Suite"] n6["subsystem<br>Radiochemical Separations"] n7["subsystem<br>Hot Cell Facility"] n8["subsystem<br>Ventilation and Containment"] n9["subsystem<br>Active Effluent Treatment"] n10["subsystem<br>Solid Waste Management"] n11["subsystem<br>Radiation Protection"] n12["subsystem<br>LIMS"] n13["system<br>System"]
Radio Chemistry Laboratory — Decomposition
| Ref | Requirement | V&V | Tags |
|---|---|---|---|
| SUB-REQS-001 | The Biological Shielding Structure SHALL attenuate gamma radiation from sources up to 1E14 Bq (Co-60, Cs-137, Ce-144) to achieve a dose rate of less than 7.5 microsieverts per hour at any accessible external surface. Rationale: The 7.5 µSv/h limit derives from the Ionising Radiations Regulations 2017 (IRR17) designation boundary for controlled areas and ALARP principles. At 1E14 Bq source terms (typical of irradiated fuel samples and activated corrosion products from submarine reactor circuits), the shielding must reduce dose rates to levels permitting continuous operator presence without additional PPE. Co-60 (1.17/1.33 MeV), Cs-137 (0.662 MeV), and Ce-144 (multiple gamma lines) represent the dominant radionuclides in submarine reactor maintenance samples. Failure to meet this threshold would require re-designation of the operator area as a controlled area, severely restricting occupancy and throughput. | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-002 | The Master-Slave Manipulator System SHALL provide a minimum payload capacity of 10 kg at full extension with at least 6 degrees of freedom per arm, sufficient to perform dissolution vessel loading, pipetting, and source preparation operations. Rationale: The 10 kg payload at full extension reflects the combined weight of dissolution vessels (stainless steel, ~3 kg) plus sample material and acid reagent loads during in-cell chemical processing. Six degrees of freedom per arm is the minimum required for the dexterous positioning needed in dissolution vessel loading, quantitative pipetting, and source preparation within the constrained hot cell geometry. Lower payload or fewer DOF would necessitate redesigning cell layout or accepting reduced operational capability for high-activity sample handling. | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-003 | The Lead Glass Shielding Windows SHALL maintain optical transmission of at least 80% in the visible spectrum (400-700 nm) after 10 years of continuous exposure to a gamma dose rate of 1 Gy/h at the hot face. Rationale: Operators require direct visual observation of in-cell operations to guide manipulator movements safely. 80% visible transmission after 10 years at 1 Gy/h represents the radiation-induced browning threshold below which operators report significant difficulty performing fine manipulative tasks. The 10-year design life aligns with the expected hot cell refurbishment cycle at UK naval dockyards. Cerium-stabilised lead glass resists radiation browning but still degrades; this requirement ensures adequate visual acuity throughout the service interval. | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-004 | The In-Cell Ventilation Extract System SHALL maintain a minimum negative pressure differential of 50 Pa between the hot cell interior and the adjacent operator area during all normal operating conditions. Rationale: The 50 Pa negative pressure differential is the minimum required to ensure inward airflow through any breach in the cell containment boundary, preventing outward migration of radioactive particulates and gases to the operator area. This value derives from nuclear industry standard practice for hot cells handling high-activity open sources (IAEA Safety Guide SSG-43) and ensures containment integrity even during transient events such as transfer port operations or manipulator boot changes. | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-005 | The In-Cell Ventilation Extract System SHALL incorporate dual-stage HEPA filtration achieving a combined decontamination factor of at least 1E6 for particulate radioactive aerosols at the most penetrating particle size (0.3 microns). Rationale: A combined decontamination factor of 1E6 ensures that airborne radioactive particulates from high-activity dissolution operations (source terms up to 1E14 Bq) are reduced to below derived air concentration limits before discharge to the building extract system. Dual-stage filtration provides defence in depth — a single HEPA filter achieves ~1E3 DF, but the second stage ensures continued containment if the first stage develops a pinhole or is challenged by acid aerosol degradation. Testing at 0.3 microns (most penetrating particle size) provides worst-case assurance per BS EN 1822. | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-006 | The Sample Transfer Port System SHALL incorporate mechanical interlocks preventing simultaneous opening of the inner cell door and outer face door on any transfer port. Rationale: Simultaneous opening of inner and outer transfer port doors would create a direct pathway between the high-activity cell interior and the operator area, potentially exposing operators to lethal dose rates. Mechanical interlocks (as opposed to electrical-only) provide a passive safety barrier that cannot be defeated by control system failure, power loss, or software error. This is a nuclear safety class requirement consistent with defence-in-depth principles for engineered barriers in ONR Safety Assessment Principles (SAP EKP.3). | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-007 | The In-Cell Dissolution and Chemical Processing Equipment SHALL include at least one dissolution vessel constructed from Hastelloy C-276 or equivalent corrosion-resistant alloy, with a working volume of 1 to 5 litres and capable of operating with 8-12M nitric acid at temperatures up to 120 degrees Celsius. Rationale: Hastelloy C-276 provides resistance to both oxidising (nitric acid) and reducing environments encountered in radiochemical dissolution of irradiated fuel and activated metals. The 1-5 litre working volume balances batch size for dockyard sample throughput (typically 0.5-2g dissolved per batch) with minimising the quantity of radioactive acid waste generated. The 120°C/8-12M HNO3 operating envelope covers the dissolution conditions required for uranium oxide fuel, stainless steel activation products, and zircaloy cladding encountered in submarine reactor maintenance. | Inspection | subsystem, hot-cell, session-226 |
| SUB-REQS-008 | The In-Cell Radiation Monitoring Instrumentation SHALL include at least two independent criticality incident detection channels, each providing gamma and neutron detection with an alarm response time of less than 500 milliseconds from onset of a criticality excursion. Rationale: Nuclear dockyard radiochemistry laboratories handle fissile materials (enriched uranium, potentially plutonium from fuel examinations), creating a non-zero criticality risk during dissolution operations. Two independent channels provide the minimum redundancy for a safety-critical detection function — no single failure can defeat the alarm capability. The 500 ms response time is driven by the need to trigger evacuation before occupational dose from a criticality excursion exceeds emergency reference levels. Both gamma and neutron detection are required because the relative emissions vary with the type of excursion. | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-009 | The Cell Decontamination System SHALL be capable of reducing surface contamination levels on cell interior surfaces to below 4 Bq/cm2 alpha and 40 Bq/cm2 beta-gamma within 8 hours of decontamination operation. Rationale: The 4 Bq/cm2 alpha and 40 Bq/cm2 beta-gamma surface contamination clearance levels are derived from IRR17 Schedule 7 for surfaces that may be accessed during maintenance. The 8-hour decontamination time window aligns with a single shift, enabling cell maintenance to begin the following shift. Inability to decontaminate to these levels would require all cell maintenance to be performed remotely, significantly increasing cost and duration of hot cell refurbishment campaigns. | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-010 | The In-Cell Ventilation Extract System SHALL incorporate activated carbon iodine adsorbers achieving a minimum decontamination factor of 1000 for elemental iodine and methyl iodide at the maximum cell operating temperature of 40 degrees Celsius and 70% relative humidity. Rationale: Iodine-131 and other radioiodine isotopes are volatile fission products released during fuel dissolution. Methyl iodide is particularly challenging as it penetrates standard HEPA filters. A DF of 1000 ensures iodine discharges remain within site authorisation limits even during dissolution campaigns. The 40°C/70% RH conditions represent worst-case performance for activated carbon and drive the specification of impregnated (TEDA or KI) carbon beds rather than plain activated carbon. | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-011 | When the In-Cell Ventilation Extract System is not maintaining the required negative pressure differential, the Sample Transfer Port System SHALL prevent opening of any transfer port and the cell access door SHALL remain locked. Rationale: Loss of negative pressure differential means the containment barrier is compromised. Locking transfer ports and cell access doors prevents any action that could release contamination into the operator area during this abnormal condition. This is a defence-in-depth measure ensuring that ventilation system failure does not cascade into a contamination event. The EARS 'When' trigger pattern ensures the interlock is explicitly linked to the abnormal condition and is testable. | Test | subsystem, hot-cell, session-226 |
| SUB-REQS-012 | The Active Effluent Storage Tanks SHALL operate in fill-hold-sample-transfer batch mode with a minimum hold time of 72 hours to allow decay of short-lived radionuclides before transfer to the treatment circuit. Rationale: Fill-hold-sample-transfer batch mode is mandated by Environment Agency discharge authorisation conditions for nuclear licensed sites. The minimum 24-hour hold time allows radioactive decay of short-lived isotopes and provides the time window for sampling, analysis, and formal authorisation before any discharge to the environment. A single-pass flow-through system would not permit pre-discharge verification, creating unacceptable environmental risk. | Test | subsystem, aetp, session-227 |
| SUB-REQS-014 | The Evaporation and Concentration Unit SHALL achieve a volume reduction factor of at least 20:1 on neutralised effluent while maintaining condensate total alpha activity below 0.05 Bq/L and total beta activity below 0.5 Bq/L. Rationale: A 20:1 volume reduction factor minimises the volume of radioactive concentrate requiring long-term storage or disposal as intermediate-level waste. This ratio is achievable with forced-circulation evaporators for typical dockyard effluent compositions (predominantly nitric acid with dissolved salts). Lower VRF would increase ILW drum production rates and overwhelm the interim waste store capacity within the facility design life. | Test | subsystem, aetp, session-227 |
| SUB-REQS-015 | The Ion Exchange Treatment Columns SHALL achieve a decontamination factor of at least 100 for Cs-137 and at least 50 for Sr-90 per column, with online gamma monitors at each column outlet detecting breakthrough within 60 seconds of the effluent activity exceeding 10% of the column inlet activity. Rationale: A DF of 100 for Cs-137 by ion exchange polishing reduces the residual activity in treated effluent to levels well below site discharge authorisation limits for this dominant fission product. Cs-137 is poorly removed by evaporation alone due to its volatile chloride form, making ion exchange the critical polishing step. The requirement covers both Cs-selective zeolites and mixed-bed resins depending on the treatment regime. | Test | subsystem, aetp, session-227 |
| SUB-REQS-016 | The Discharge Authorisation and Control System SHALL close the discharge isolation valve within 5 seconds of the Effluent Monitoring and Sampling Station detecting effluent activity exceeding 10% of any individual radionuclide monthly discharge authorisation limit, and the safety function SHALL be rated to SIL 2 in accordance with BS EN 61511. Rationale: The 5-second closure time limits the volume of out-of-specification effluent that could be discharged if the monitoring system detects an exceedance during authorised discharge. At typical discharge flow rates (1-5 m3/h), 5 seconds limits the uncommitted volume to less than 7 litres, a recoverable quantity. Slower closure would risk a notifiable environmental incident. | Test | subsystem, aetp, session-227 |
| SUB-REQS-017 | The Active Drain Collection System SHALL provide double containment for all pipework carrying radioactive liquid effluent, with leak detection sensors in the annular space capable of detecting a leak of 0.5 litres or greater within 15 minutes. Rationale: Double containment for active drain pipework is required by ONR SAPs (ECV.1) for pipework carrying radioactive liquids in nuclear facilities. A leak in single-wall pipework could contaminate building voids, creating a significant decommissioning liability and potential groundwater contamination pathway. Double containment with leak detection provides early warning and prevents uncontrolled release to the environment. | Test | subsystem, aetp, session-227 |
| SUB-REQS-018 | The Neutralisation and Chemical Dosing Plant SHALL adjust the pH of batch effluent transfers to between 7.0 and 9.0 with a control accuracy of plus or minus 0.3 pH units, using triple-redundant inline pH probes with automatic changeover on probe failure. Rationale: The pH 6-9 range is required to protect downstream ion exchange resins from acid degradation and to ensure optimal performance of the evaporator (acidic feeds cause excessive corrosion of heat transfer surfaces). The range also meets Environment Agency discharge consent pH limits for the receiving watercourse. Neutralisation before treatment extends equipment life and improves decontamination factor consistency. | Test | subsystem, aetp, session-227 |
| SUB-REQS-019 | The Effluent Monitoring and Sampling Station SHALL provide continuous online measurement of gross alpha activity with a minimum detectable activity of 0.02 Bq/L and gross beta activity with a minimum detectable activity of 0.2 Bq/L in treated effluent, with measurement cycle time not exceeding 30 minutes. Rationale: Continuous online measurement of gross alpha/beta activity provides real-time verification that each treatment stage is performing to specification before effluent progresses to the next stage. Without continuous monitoring, a treatment plant upset could go undetected until the final batch sample is analysed, potentially filling downstream tanks with inadequately treated effluent. This is a condition of the site discharge authorisation. | Test | subsystem, aetp, session-227 |
| SUB-REQS-020 | The Concentrate and Sludge Handling System SHALL fill, weigh, and seal 200-litre stainless steel drums to within 2 kg of target fill weight, and the filled drum surface dose rate SHALL not exceed 2 mSv/h at contact, all operations performed remotely from a shielded control position. Rationale: 200-litre stainless steel drums are the standard UK nuclear industry waste container for intermediate-level waste concentrates, compatible with waste acceptance criteria for interim storage and eventual geological disposal. Automated filling, weighing, and sealing minimises operator dose from handling concentrated radioactive waste and ensures consistent, traceable waste package production. | Demonstration | subsystem, aetp, session-227 |
| SUB-REQS-021 | The Evaporation and Concentration Unit SHALL operate at sub-atmospheric pressure between 20 kPa and 80 kPa absolute to maintain boiling temperature below 95 degrees Celsius, limiting volatilisation of ruthenium tetroxide and iodine species to less than 0.1% of feed inventory per batch. Rationale: Sub-atmospheric operation (20-50 kPa) lowers the boiling point of the effluent, reducing corrosion rates on heat transfer surfaces and minimising the volatilisation of radioactive species such as ruthenium tetroxide. This pressure range is standard for nuclear effluent evaporators and balances energy efficiency against the mechanical complexity of maintaining vacuum on a radioactive system. Higher pressures would increase Ru-106 carryover into the distillate. | Test | subsystem, aetp, session-227 |
| SUB-REQS-022 | The Discharge Authorisation and Control System SHALL maintain cumulative discharge records for each radionuclide specified in the Environmental Agency permit, calculating running daily, monthly, and annual totals against permit limits, and SHALL prevent discharge when any cumulative total exceeds 80% of the corresponding permit limit period. Rationale: Environment Agency discharge authorisations for nuclear licensed sites impose annual limits on the cumulative activity of specific radionuclides discharged. Real-time cumulative tracking ensures the operator can manage discharges within these limits and avoid breaching conditions that would constitute a regulatory offence. The system must track by radionuclide because different isotopes have different authorised limits. | Demonstration | subsystem, aetp, session-227 |
| SUB-REQS-023 | The Active Effluent Storage Tanks SHALL be housed within a secondary containment bund constructed of impermeable concrete with acid-resistant coating, sized to contain at least 110% of the volume of the largest single tank, with bund leak detection and sump pump to return any spill to the treatment circuit. Rationale: Secondary containment bunding is a legal requirement under the Environmental Permitting Regulations for tanks containing hazardous radioactive liquids. The bund must retain the full contents of the largest tank plus 10% (standard UK nuclear industry sizing) to prevent uncontrolled release to the environment in the event of catastrophic tank failure. Concrete construction with acid-resistant lining withstands the nitric acid-based effluent composition. | Inspection | subsystem, aetp, session-227 |
| SUB-REQS-024 | The Supply Air Handling Unit SHALL deliver conditioned supply air at a minimum flow rate of 5000 m3/h to maintain room air change rates of at least 6 air changes per hour in all active laboratory areas. Rationale: The 5000 m3/h supply air flow rate is derived from the sum of extract rates from all active areas (hot cells, fume cupboards, gloveboxes) plus building leakage, sized to maintain the required pressure cascade. The supply system must deliver slightly less air than the extract system removes, creating the net inward flow that prevents contamination escape. Conditioned air (temperature, humidity, filtration) protects sensitive analytical instruments and ensures consistent laboratory operating conditions. | Test | subsystem, ventilation, session-228 |
| SUB-REQS-025 | The Active Area Extract System SHALL incorporate duty and standby extract fans with automatic changeover, achieving full extract flow restoration within 30 seconds of duty fan failure. Rationale: Duty/standby configuration with automatic changeover ensures continuous extract ventilation even during fan failure, which is critical because loss of extract would collapse the pressure cascade and compromise containment of radioactive materials across all active areas. The automatic changeover must complete within seconds to prevent transient positive pressurisation. This is a nuclear safety class requirement — ONR expects high availability for containment ventilation systems. | Test | subsystem, ventilation, session-228 |
| SUB-REQS-026 | The HEPA Filtration Bank SHALL be designed for in-situ DOP or PAO aerosol challenge testing of each HEPA filter stage without interrupting the extract airflow to the remaining stages. Rationale: In-situ DOP/PAO testing verifies that each individual HEPA filter and its housing seal achieve the rated efficiency after installation. Factory-tested filters can be damaged during transport, installation, or by in-service degradation from acid fumes. Without in-situ testing capability, filter integrity cannot be verified without removal, which would release the contained contamination. This is a standard requirement for nuclear HEPA installations per BS EN ISO 29463 and ASME N510. | Demonstration | subsystem, ventilation, session-228 |
| SUB-REQS-027 | The Pressure Cascade Control System SHALL maintain the following pressure hierarchy: corridors at ambient, non-active laboratories at minus 10 Pa, active laboratories at minus 30 Pa, and fume cupboard interiors at minus 80 Pa minimum, all relative to external atmospheric pressure. Rationale: The pressure cascade hierarchy ensures that air always flows from areas of lower contamination potential towards areas of higher contamination potential. Corridors at ambient, general labs at -15 Pa, active labs at -30 Pa, fume cupboards at -50 Pa, and hot cells at -75 Pa creates a progressive containment gradient. These values are consistent with IAEA guidance on ventilation for nuclear facilities and UK nuclear industry good practice. Failure to maintain the cascade could result in cross-contamination between zones. | Test | subsystem, ventilation, session-228 |
| SUB-REQS-028 | The Iodine Adsorption Unit SHALL achieve a minimum decontamination factor of 100 for methyl iodide (CH3I) at inlet conditions of 30 degrees C and 70% relative humidity with a maximum pressure drop of 500 Pa across the adsorber bed. Rationale: Methyl iodide is the most challenging form of radioiodine to remove from ventilation exhaust. A DF of 1000 at the CH3I challenge concentration ensures that the building discharge meets environmental authorisation limits for I-131 during dissolution campaigns when volatile iodine is released. TEDA-impregnated activated carbon achieves this DF when fresh but performance degrades with humidity and temperature — the requirement therefore drives bed sizing and replacement frequency. | Test | subsystem, ventilation, session-228 |
| SUB-REQS-029 | The Stack Monitoring Instrumentation SHALL detect a step increase in particulate alpha activity from background to 10% of the derived air concentration limit within 60 seconds and trigger an audible and visual alarm at the ventilation control panel and the Radiation Protection office. Rationale: Stack monitoring must detect abnormal releases rapidly enough to trigger automatic extract system shutdown before cumulative discharge exceeds daily authorised limits. The sensitivity threshold for particulate alpha must be low enough to detect a single HEPA filter breach during normal background conditions. Step-change detection capability is specifically required because a gradual increase could indicate filter degradation while a step indicates acute failure. | Test | subsystem, ventilation, session-228 |
| SUB-REQS-030 | The Ventilation Discharge Stack SHALL have a minimum effective height of 20 metres and an exit velocity of at least 10 m/s to achieve adequate atmospheric dispersion such that ground-level concentrations at the site boundary do not exceed 1% of the derived air concentration limit under worst-case meteorological conditions. Rationale: The 20-metre effective stack height ensures adequate atmospheric dispersion of discharged radionuclides to reduce ground-level concentrations at the site boundary below annual dose constraints for members of the public. Exit velocity specification prevents rain ingress and ensures thermal buoyancy enhances the effective release height. These parameters are derived from atmospheric dispersion modelling (Gaussian plume model, R-91 methodology) specific to the dockyard's coastal meteorology and proximity to public areas. | Analysis | subsystem, ventilation, session-228 |
| SUB-REQS-031 | The Area Gamma Dose Rate Monitoring Network SHALL provide continuous gamma dose rate measurement in all occupied and controlled areas of the laboratory, with at least one detector per active laboratory zone, one per hot cell operating position, and one per waste handling area, using ionisation chamber detectors for the range 0.1 microsievert/h to 10 sievert/h. Rationale: IRR17 Regulation 19 requires adequate monitoring of dose rates in controlled and supervised areas. The detector range of 0.1 μSv/h to 10 Sv/h covers normal background through criticality-event levels. One detector per zone ensures no spatial gaps in coverage; ionisation chambers are chosen for energy-independent response and stability in mixed radiation fields typical of radiochemistry facilities handling fission and activation products. | Test | subsystem, radpro, session-229 |
| SUB-REQS-032 | The Area Gamma Dose Rate Monitoring Network SHALL trigger a local audible and visual alarm when the dose rate at any detector location exceeds 7.5 microsieverts per hour, and SHALL trigger a facility evacuation alarm when any detector exceeds 2 millisieverts per hour, with alarm actuation within 5 seconds of the dose rate exceeding the threshold. Rationale: The 7.5 μSv/h alarm threshold is derived from the IRR17 instantaneous dose rate investigation level (3/8 of the 20 mSv annual limit pro-rated to working hours). The 2 mSv/h evacuation threshold reflects immediate danger levels per PHE emergency reference levels. The 5-second actuation time ensures personnel receive warning before accumulating a significant fraction of the investigation dose at the alarm threshold. | Test | subsystem, radpro, session-229 |
| SUB-REQS-033 | The Airborne Contamination Monitoring System SHALL provide continuous measurement of airborne alpha particulate activity concentration with a minimum detectable concentration of 0.02 DAC and beta particulate activity concentration with a minimum detectable concentration of 0.1 DAC in each active laboratory zone, with a measurement cycle time not exceeding 10 minutes and automatic radon/thoron background compensation. Rationale: Continuous airborne monitoring with radon compensation is essential in a radiochemistry laboratory where dissolution, evaporation, and separation of irradiated materials can release volatile fission products and actinide aerosols. The 0.02 DAC alpha sensitivity detects intake-significant concentrations before committed effective dose reaches investigation levels. The 10-minute cycle balances statistical counting accuracy with response time for transient releases from fume cupboards or hot cell breaches. | Test | subsystem, radpro, session-229 |
| SUB-REQS-034 | The Area Gamma Dose Rate Monitoring Network SHALL provide continuous gamma dose rate measurement in all occupied and controlled areas. Rationale: Continuous area gamma monitoring is required by IRR17 for controlled and supervised areas in nuclear facilities. Measurement in all areas handling unsealed radioactive sources provides early warning of source misplacement, contamination spread, or shielding failure. The monitoring network feeds the centralised alarm system, enabling rapid operational response. Coverage of all areas (not just the highest-risk ones) ensures that anomalies in lower-activity laboratories are detected before they escalate. | Test | duplicate-of-SUB-REQS-031, session-229 |
| SUB-REQS-035 | The Criticality Warning System SHALL employ a minimum of three independent gamma and neutron detector assemblies per monitored zone, with 2-out-of-3 coincidence voting logic, activating evacuation sounders and visual beacons throughout the facility within 500 milliseconds of a criticality excursion exceeding 20 mGy/h gamma coincident with a tenfold increase above neutron background. Rationale: NRC Regulatory Guide 3.71 and UK ONR NS-TAST-GD-038 require criticality warning systems with redundant detection and voting logic to prevent false alarms while ensuring prompt evacuation. The 2-out-of-3 coincidence logic provides single-failure tolerance. The 500 ms actuation time derives from the dose rate expected during a nuclear criticality excursion — at the threshold of 20 mGy/h with potential for rapid escalation to lethal levels, sub-second response is necessary to initiate evacuation before personnel receive significant doses. Coincident gamma and neutron detection discriminates criticality events from non-criticality gamma sources. | Test | subsystem, radpro, criticality, session-229 |
| SUB-REQS-036 | The Criticality Warning System SHALL be electrically and physically independent of the Area Gamma Dose Rate Monitoring Network, with a dedicated uninterruptible power supply providing at least 8 hours of battery backup, dedicated signal cabling, and self-test capability that verifies detector response and alarm circuit integrity at intervals not exceeding 24 hours. Rationale: Independence from the area monitoring network is a nuclear safety requirement (ONR Safety Assessment Principle ECS.1) ensuring that common-cause failure of the general monitoring system cannot simultaneously disable the criticality warning function. The 8-hour UPS capacity covers the maximum credible site power outage duration for a nuclear-licensed site per ONR expectations. The 24-hour self-test interval ensures latent faults are detected within one working day. | Inspection | subsystem, radpro, criticality, session-229 |
| SUB-REQS-037 | The Personal Dosimetry Management System SHALL issue electronic personal dosemeters to all workers entering controlled areas, providing real-time dose rate display with 10% accuracy in the range 1 microsievert/h to 1 sievert/h, cumulative dose display, and audible alarm at preset dose thresholds of 0.5 mSv (investigation) and 2 mSv (intervention) per entry, with automatic data upload to the central dose recording system on exit from the controlled area. Rationale: Electronic personal dosemeters provide real-time dose awareness that passive dosemeters (TLDs/OSLDs) cannot, enabling workers to manage their own dose budgets during complex radiochemistry operations. The 0.5 mSv investigation and 2 mSv intervention alarm thresholds are derived from IRR17 dose constraints and ALARP principles — at 10% of the 20 mSv annual limit per entry, an alarm ensures operational review before significant dose accumulation. Automatic upload on exit eliminates manual transcription errors in dose records and enables immediate access control decisions. | Test | subsystem, radpro, dosimetry, session-229 |
| SUB-REQS-038 | The Surface Contamination Monitoring Equipment SHALL include hand and clothing monitors at every exit from a controlled area, with detection sensitivity of less than 0.4 Bq/cm2 for alpha emitters and less than 4 Bq/cm2 for beta emitters, and a monitoring cycle time not exceeding 30 seconds, preventing exit gate release if contamination exceeds clearance levels. Rationale: Exit monitoring prevents spread of contamination beyond controlled areas, a fundamental ALARP measure under IRR17 Regulation 8. The 0.4 Bq/cm² alpha and 4 Bq/cm² beta clearance levels align with UK nuclear industry standard clearance values derived from IAEA GSR Part 3. The 30-second cycle time balances detection sensitivity with personnel throughput at shift change — a longer cycle would cause queuing and incentivise bypass. Gate interlock ensures no unmonitored exit. | Test | subsystem, radpro, contamination, session-229 |
| SUB-REQS-039 | The Radiological Access Control System SHALL prevent entry to any controlled area by personnel whose cumulative dose recorded in the Personal Dosimetry Management System exceeds 10 mSv in the current calendar year, and SHALL maintain a time-stamped entry and exit log for all personnel with dose readings at each transition, accessible to the Radiation Protection Adviser within 60 seconds of query. Rationale: Automated dose-based access control prevents administrative errors that could allow overexposed personnel to re-enter controlled areas. The 10 mSv calendar-year threshold is the UK nuclear industry site dose constraint (half the IRR17 20 mSv annual limit), reflecting ALARP optimisation for a facility where multiple entries are routine. The 60-second query response time supports the Radiation Protection Adviser's statutory duty to investigate abnormal exposures promptly. | Test | subsystem, radpro, access-control, session-229 |
| SUB-REQS-040 | The Centralised Radiation Monitoring Display and Alarm System SHALL store all dose rate, airborne activity, contamination survey, and personal dose records for a minimum of 30 years with 1-minute time resolution for continuous monitors and per-event resolution for alarms, supporting retrieval of any 24-hour period within 5 minutes of query. Rationale: The 30-year retention period satisfies IRR17 Regulation 21 dose record retention requirements and supports epidemiological studies. One-minute time resolution for continuous monitors enables dose reconstruction for incident investigation — coarser resolution would introduce unacceptable uncertainty in worker dose assignment during short-duration events such as hot cell window breaches. The 5-minute retrieval time supports operational and regulatory queries without specialist database intervention. | Test | subsystem, radpro, monitoring, session-229 |
| SUB-REQS-041 | The Waste Sorting and Segregation Facility SHALL categorise all solid radioactive waste into VLLW, LLW compactable, LLW non-compactable, and ILW streams within 24 hours of receipt, using hand-held contamination and dose rate instruments to confirm categorisation at the point of sorting. Rationale: Early categorisation into VLLW/LLW/ILW streams is essential because each waste category has fundamentally different conditioning, packaging, storage, and disposal routes under the UK radioactive waste management framework. The 24-hour sorting window prevents accumulation of unsegregated waste in the sorting facility, which would complicate dose management and create a fire load. Hand-held instrument confirmation at the point of sorting provides a defence against mis-categorisation, which could result in a package exceeding its Waste Acceptance Criteria for the intended disposal route. | Inspection | subsystem, solid-waste, session-230 |
| SUB-REQS-042 | The Non-Destructive Assay System SHALL achieve a measurement uncertainty of less than 20% at 2-sigma confidence for all gamma-emitting radionuclides contributing more than 1% of total package activity, using segmented gamma scanning with a minimum of 12 axial segments and full drum rotation. Rationale: The 20% measurement uncertainty at 2-sigma is the maximum acceptable for UK radioactive waste Waste Acceptance Criteria compliance (per LLWR WAC and RWM guidance). Segmented gamma scanning with 12 axial segments corrects for non-uniform activity distribution within drums, which is common for radiochemistry laboratory waste containing discrete high-activity items (filters, glassware, PPE). Without segmentation, matrix and self-absorption effects can cause underestimates exceeding a factor of 3 for heterogeneous waste. | Test | subsystem, solid-waste, session-230 |
| SUB-REQS-043 | The LLW Compaction and Packaging System SHALL compact standard 200-litre mild steel drums to a puck height of no more than 120 mm using a minimum compaction force of 1500 tonnes, achieving a volume reduction factor of at least 5:1 for compactable LLW. Rationale: The 5:1 volume reduction factor is the minimum needed to achieve economic LLW disposal given LLWR container charges and the projected 30-year waste arisings. The 120 mm puck height ensures compacted pucks fit within half-height ISO containers (HHISO) in a single layer, maximising container utilisation. The 1500-tonne compaction force is specified because radiochemistry laboratory LLW includes metal items (tools, small vessels) requiring high force to achieve target volume reduction. | Test | subsystem, solid-waste, session-230 |
| SUB-REQS-044 | The ILW Conditioning and Encapsulation Plant SHALL immobilise Intermediate Level Waste within 500-litre stainless steel drums using an OPC/BFS grout formulation conforming to the RWM Letter of Compliance, achieving a minimum 28-day compressive strength of 4 MPa and a waste-to-grout volume ratio not exceeding 30%. Rationale: OPC/BFS grout is the UK reference ILW immobilisation matrix, with decades of characterisation data supporting the RWM generic Disposal System Safety Case. The 4 MPa 28-day compressive strength ensures structural integrity for handling, transport, and long-term geological disposal. The 30% waste-to-grout ratio limit ensures sufficient grout matrix to encapsulate and immobilise radionuclides while maintaining pourability during the conditioning process. Exceeding this ratio risks incomplete encapsulation and reduced chemical containment performance. | Test | subsystem, solid-waste, session-230 |
| SUB-REQS-045 | The Interim Radioactive Waste Store SHALL provide segregated, shielded storage capacity for a minimum of 30 years of facility waste arisings, with the ILW storage area maintaining surface dose rates below 2 mSv/h at the package handling face and designed for 3-high stacking of 500-litre drums on seismically restrained storage racks. Rationale: The 30-year storage capacity reflects the minimum period before a UK Geological Disposal Facility is expected to accept ILW from smaller producers. The 2 mSv/h surface dose rate limit at the handling face ensures manual handling operations remain within ALARP dose budgets for store operators (derived from a 10 mSv/year constraint with estimated 2500 hours of access). Seismic restraint for 3-high stacking is required by ONR expectations for ILW stores in seismic hazard zone 1. | Inspection | subsystem, solid-waste, session-230 |
| SUB-REQS-046 | The Waste Tracking and Records System SHALL maintain a complete cradle-to-grave record for every waste package for a minimum of 150 years from the date of package creation, with each record including waste description, generator, radionuclide inventory, conditioning method, assay results, storage location history, and disposal route. Rationale: The 150-year record retention period covers the anticipated operational period of a UK Geological Disposal Facility plus closure monitoring. Cradle-to-grave traceability is a condition of the RWM Letter of Compliance and a regulatory expectation under EPR16 environmental permits. The specified data fields constitute the minimum dataset required by the UK Radioactive Waste Inventory and LLWR/GDF Waste Acceptance Criteria, enabling disposal route determination and package retrievability. | Demonstration | subsystem, solid-waste, session-230 |
| SUB-REQS-047 | The Non-Destructive Assay System SHALL quantify fissile material content in each waste package using passive neutron coincidence counting, with a minimum detectable mass of 0.1 g Pu-239 equivalent, to verify compliance with the transport and storage criticality safety limits. Rationale: Fissile material quantification is a nuclear safety requirement — waste packages exceeding criticality safety limits for transport (per IAEA SSR-6) or storage (per facility-specific criticality safety assessment) must be identified before entering the disposal pathway. The 0.1 g Pu-239 equivalent detection limit is derived from the criticality safety mass limit for the intended storage geometry divided by the number of packages in a single storage module, providing a margin of safety factor 10 against inadvertent criticality from accumulation of undetected fissile material. | Test | subsystem, solid-waste, session-230 |
| SUB-REQS-048 | The Spent Sealed Source Management System SHALL maintain a real-time inventory of all sealed radioactive sources, schedule and record wipe tests at intervals not exceeding 26 weeks per IRR17, and automatically flag any source exceeding its certificate expiry date or exhibiting leakage above 200 Bq removable contamination. Rationale: IRR17 Regulation 27 requires holders of sealed sources to maintain adequate records and conduct regular leak testing. The 26-week wipe test interval is the maximum permitted under IRR17 for high-activity sealed sources used in calibration and quality control. Automatic flagging of expired certificates and leaking sources prevents continued use of compromised sources, which could cause facility contamination and worker dose. A real-time inventory supports the statutory obligation to account for all sources at any time. | Demonstration | subsystem, solid-waste, session-230 |
| SUB-REQS-049 | While an ILW drum is in the 28-day curing period, the ILW Conditioning and Encapsulation Plant SHALL continuously monitor the grout centre-line temperature and SHALL trigger an alarm if the temperature exceeds 80 degrees Celsius, indicating potential thermal cracking. Rationale: Exothermic hydration of cementitious grout in ILW drums can generate significant heat, particularly with high waste loadings. Centre-line temperatures exceeding 80°C cause thermal cracking that compromises the wasteform's long-term radionuclide containment performance, as validated by RWM thermal modelling studies. Continuous monitoring during the 28-day curing period ensures early detection of thermal excursions, enabling intervention (cooling or rejection) before irreversible damage occurs to the wasteform matrix. | Test | subsystem, solid-waste, session-230 |
| SUB-REQS-050 | The Sample Reception Bay SHALL measure the dose rate of every incoming sample container at 100mm distance within 60 seconds of receipt, using a calibrated instrument with a measurement range of 0.1 microsieverts per hour to 10 millisieverts per hour. Rationale: Dose rate measurement at receipt is required for radiation protection of laboratory personnel and for regulatory compliance with IRR17 Regulation 8 (prior risk assessment). The 0.1 µSv/h to 10 mSv/h range covers the full spectrum from environmental background samples to activated reactor components. The 60-second time limit prevents bottlenecks during peak campaign intake. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-051 | When a submarine reactor maintenance campaign is in progress, the Sample Receipt and Preparation Laboratory SHALL process a minimum of 80 samples per week from receipt through to prepared aliquots ready for analysis, without exceeding a 48-hour turnaround from receipt to delivery of prepared samples to the analytical laboratories. Rationale: Submarine reactor maintenance campaigns generate the laboratory's peak analytical demand. The 80 samples/week throughput derives from the typical defuelling/refuelling campaign schedule where coolant, swab, and structural samples must be processed within the maintenance window. The 48-hour turnaround is driven by the reactor maintenance programme's critical path — delays in radiochemistry results stall the defuelling sequence. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-052 | The Sample Reception Bay SHALL measure the dose rate of every incoming sample container at 100mm distance within 60 seconds of receipt, using a calibrated instrument with a measurement range of 0.1 microsieverts per hour to 10 millisieverts per hour. Rationale: Dose rate measurement at sample receipt is required by the laboratory radiation protection programme to classify incoming samples, determine appropriate handling procedures, and verify that consignment documentation is accurate. The 100mm measurement distance is a standard reference geometry that provides a reproducible result for comparison against laboratory handling limits and transport regulations (IAEA SSR-6). | Test | subsystem, sample-prep, session-232, duplicate-of-SUB-REQS-050 |
| SUB-REQS-053 | When a submarine reactor maintenance campaign is in progress, the Sample Receipt and Preparation Laboratory SHALL process a minimum of 80 samples per week from receipt through to prepared aliquots ready for analysis, without exceeding a 48-hour turnaround from receipt to delivery of prepared samples to the analytical laboratories. Rationale: Submarine reactor maintenance campaigns generate high sample volumes over short periods — typically 60-100 primary coolant, resin, and swab samples per week. The 48-hour turnaround ensures analytical results are available within the maintenance planning cycle, preventing costly reactor maintenance hold points while waiting for radiochemical clearance data. | Test | subsystem, sample-prep, session-232, duplicate-of-SUB-REQS-051 |
| SUB-REQS-054 | The Sample Logging and Labelling Station SHALL assign a unique barcode identifier to every sample within 5 minutes of reception and create a LIMS record capturing: sample origin, collection date and time, requested analyses, estimated radionuclide inventory, measured dose rate, sample matrix type, and chain-of-custody signoff. Rationale: Unique barcode identification at point of receipt establishes chain of custody required for ISO 17025 accreditation and legal defensibility of analytical results used in safety case and discharge consent evidence. The 5-minute registration window prevents sample queuing during high-intake periods. | Inspection | subsystem, sample-prep, session-232 |
| SUB-REQS-055 | The Sample Preparation Fume Cupboard SHALL maintain a minimum face velocity of 0.5 metres per second across the working aperture at all sash heights up to 500mm, as measured at any point across the aperture face. Rationale: The 0.5 m/s face velocity is mandated by nuclear site licence conditions and IAEA Safety Guide RS-G-1.7 for work with unsealed radioactive sources. Maintaining this velocity at all sash positions up to the maximum 500mm working height ensures containment during routine operations. Failure to meet this threshold would require cessation of radiochemistry work under the site's ALARP demonstration. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-056 | The Analytical Balance and Gravimetric Station SHALL provide a readability of 0.01 mg with a linearity of plus or minus 0.02 mg, calibrated against UKAS-traceable mass standards, and SHALL automatically record each weighing result to the LIMS with timestamp and environmental conditions. Rationale: Gravimetric measurements directly enter activity concentration calculations (Bq/g), so balance accuracy propagates linearly into reported results. The 0.01mg readability and ±0.02mg linearity are required to keep weighing uncertainty below 1% for typical 20mg-100mg sample aliquots. UKAS traceability is mandatory for ISO 17025 accreditation. Automatic LIMS transfer eliminates transcription errors in the measurement chain. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-057 | The Sample Storage Refrigerator Array SHALL maintain refrigerator compartments at 2 to 8 degrees Celsius and freezer compartments at minus 20 degrees Celsius plus or minus 5 degrees, with continuous temperature logging at intervals of no more than 15 minutes and automatic alarm on excursion beyond these limits. Rationale: Aqueous environmental and biological samples degrade through bacterial action, radiolytic decomposition, and volatilisation if not stored at controlled temperatures. The 2-8°C refrigerator range preserves sample integrity for standard matrices. The -20°C freezer accommodates biological tissue samples from the dockyard's environmental monitoring programme. Temperature excursion alarms prevent undetected loss of sample integrity that would invalidate analytical results. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-058 | The Sample Drying and Ashing Oven SHALL exhaust all fumes and particulate emissions through a HEPA-filtered duct connection to the active area extract system, with an over-temperature safety trip that isolates the heating elements at 120 degrees Celsius for the drying oven and 950 degrees Celsius for the muffle furnace. Rationale: Drying and ashing at high temperatures volatilises tritium, iodine, and caesium from contaminated samples. HEPA filtration of the exhaust prevents these radionuclides entering the general extract ductwork. The over-temperature trip at 600°C protects the HEPA filter media (rated to 250°C) and prevents furnace damage that could release activity from incompletely ashed samples. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-059 | The Contamination Control and Waste Segregation Point SHALL provide surface contamination monitoring instruments capable of detecting 0.4 Bq per square centimetre alpha and 4 Bq per square centimetre beta-gamma on personnel and equipment exiting the controlled area, with audible and visual indication of contamination above these limits. Rationale: Surface contamination monitoring at the waste segregation boundary is the primary control preventing spread of activity from active to supervised areas. The 0.4 Bq/cm² alpha and 4 Bq/cm² beta-gamma thresholds correspond to clearance levels in the Radioactive Substances Regulations, below which items can be managed as non-active waste — a significant cost and dose saving compared to solid radioactive waste disposal. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-060 | The Acid Digestion System SHALL dissolve solid radioactive samples including soil, sediment, concrete, and metal swarf in concentrated mineral acids to achieve a minimum dissolution efficiency of 95 percent by mass, with a batch capacity of at least 20 samples for microwave digestion and 6 samples for open-vessel hotplate digestion. Rationale: Complete dissolution of solid samples is prerequisite for representative aliquoting and accurate radiochemical analysis. The 95% dissolution efficiency target ensures that refractory matrices (concrete, reactor structural alloys) yield analytically representative solutions. Failure to achieve complete dissolution leads to biased low results for radionuclides locked in undissolved residues, undermining waste characterisation and dose assessment accuracy. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-061 | The Sample Reception Bay SHALL incorporate a shielded pass-through hatch with interlocked inner and outer doors, providing a minimum shielding of 50mm lead equivalent, to prevent direct radiation streaming between the external delivery area and the preparation laboratory during sample transfer. Rationale: The shielded pass-through hatch prevents direct radiation streaming between the sample reception area and the laboratory interior, protecting personnel on both sides. The 50mm lead equivalent attenuates gamma radiation from the highest-activity dockyard samples (activated reactor structural specimens up to 10 mSv/h contact) to below the general area dose rate limit. Interlocked doors prevent simultaneous opening which would create an unshielded line of sight. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-062 | The Contamination Control and Waste Segregation Point SHALL route all active liquid waste through a dedicated sump to the Active Drain Collection System, with a sump capacity of at least 50 litres and a high-level alarm at 80 percent capacity. Rationale: All active liquid waste from the contamination control area must be captured and routed to the active drain system with no uncontrolled discharge. The 50-litre sump capacity accommodates a worst-case spill volume from a single decontamination operation. The high-level alarm prevents sump overflow that would result in uncontrolled contamination spread and a potential regulatory reportable event. | Test | subsystem, sample-prep, session-232 |
| SUB-REQS-063 | The Extraction Chromatography Station SHALL achieve chemical recovery yields of at least 70% for each individual actinide isotope (Pu, Am, Cm, U, Np) separation, verified by yield tracer measurement on every sample batch. Rationale: Chemical recovery yield directly determines analytical accuracy for actinide measurements. The 70% minimum ensures that yield corrections remain within the acceptable uncertainty range for regulatory reporting. Below 70%, matrix effects and separation column breakthrough introduce systematic biases that cannot be reliably corrected by yield tracer measurement alone, particularly for Am and Cm where spectral interference with Pu isotopes increases at low yields. | Test | subsystem, radiochem-sep, session-233 |
| SUB-REQS-064 | The Electrodeposition and Source Preparation Unit SHALL produce alpha counting sources with a deposit mass of less than 50 micrograms per square centimetre and diameter uniformity within 5% of the target 20mm deposition area. Rationale: Alpha spectrometry resolution depends critically on source thickness. Deposits exceeding 50 µg/cm² cause peak broadening through self-absorption, degrading energy resolution below the 30 keV FWHM needed to resolve Pu-238/Am-241 and Pu-239/Pu-240 peaks. Diameter uniformity within 5% ensures consistent geometry calibration factors across the detector array, which is essential for accurate quantification. | Test | subsystem, radiochem-sep, session-233 |
| SUB-REQS-065 | The Radiochemical Separations Laboratory SHALL limit fissile material in any single fume cupboard to a maximum of 15 grams fissile equivalent, with individual sample aliquots not exceeding 5 grams fissile equivalent. Rationale: Criticality safety in the radiochemical separations laboratory is governed by the facility criticality safety assessment. The 15g fissile equivalent per fume cupboard and 5g per aliquot limits derive from the assessed safe mass for the laboratory geometry and moderation conditions, providing a margin of safety below the minimum critical mass. Exceeding these limits would invalidate the criticality safety case and require facility shutdown. | Inspection | subsystem, radiochem-sep, session-233 |
| SUB-REQS-066 | The Glassware Decontamination and Quality Control Bay SHALL verify that all decontaminated glassware has surface activity below 0.4 Bq per square centimetre for alpha emitters and 4 Bq per square centimetre for beta-gamma emitters before return to service. Rationale: Reuse of glassware that retains residual contamination above clearance levels would introduce cross-contamination between samples, producing false-positive results. The 0.4 Bq/cm² alpha and 4 Bq/cm² beta-gamma thresholds match the regulatory clearance values and the laboratory's quality system acceptance criteria for decontaminated equipment under ISO 17025. | Test | subsystem, radiochem-sep, session-233 |
| SUB-REQS-067 | The Reagent Storage and Dispensing System SHALL supply only analytical-grade or higher purity reagents with certificates of analysis, and SHALL maintain LIMS-tracked records of reagent identity, batch number, date opened, and expiry date for every reagent in use. Rationale: Reagent impurities introduce blank contributions that degrade detection limits for trace-level radionuclide measurements. Analytical-grade or higher purity minimises blank activity, particularly for ICP-MS where elemental impurities in acids cause isobaric interferences. LIMS-tracked batch and expiry records support root-cause investigation when analytical QC flags systematic deviations. | Inspection | subsystem, radiochem-sep, session-233 |
| SUB-REQS-068 | The Active Laboratory Drain and Effluent Segregation System SHALL segregate high-activity laboratory waste streams containing greater than 100 Bq/L total alpha from low-activity rinse water, routing high-activity streams to dedicated AETP collection vessels. Rationale: Segregation of high-activity (>100 Bq/L total alpha) waste from low-activity rinse water reduces the volume of Category 3 effluent requiring full treatment, lowering operational costs and dose uptake during treatment. The 100 Bq/L threshold aligns with the site's environmental discharge authorisation categorisation. Mixing high and low streams would require the entire combined volume to be treated as high-activity, overwhelming the treatment plant's ion exchange capacity. | Test | subsystem, radiochem-sep, session-233 |
| SUB-REQS-069 | The Tracer and Reference Standard Store SHALL maintain an auditable inventory of all radioactive tracer solutions with individual activity concentrations traceable to national standards (NPL or NIST), reference dates, expanded uncertainties, and remaining volumes updated after each dispensing event. Rationale: Radioactive tracers and reference standards provide the metrological foundation for all quantitative measurements. Traceability to NPL or NIST national standards is mandatory for ISO 17025 accreditation and for regulatory acceptance of analytical results. An auditable inventory prevents use of expired or depleted standards, which would introduce systematic measurement bias into reported activity concentrations. | Inspection | subsystem, radiochem-sep, session-233 |
| SUB-REQS-070 | While any sash is open beyond the 100mm service access position, each fume cupboard in the Radiochemical Fume Cupboard Array SHALL maintain a face velocity of 0.5 metres per second plus or minus 10% across the full sash opening. Rationale: This EARS 'While' pattern requirement ensures containment is maintained during the most hazardous operational condition — open sash with active radiochemistry in progress. The ±10% tolerance on the 0.5 m/s face velocity accounts for transient fluctuations from door openings and personnel movement while maintaining the minimum containment velocity required by nuclear site licence conditions. | Test | subsystem, radiochem-sep, session-233 |
| SUB-REQS-071 | The Radiochemical Separations Laboratory SHALL have the capacity to process at least 30 radiochemical separation batches per week across all analytical streams during a submarine reactor maintenance campaign. Rationale: The 30 separations/week capacity is sized to support the 80 samples/week receipt rate during submarine reactor campaigns (SUB-REQS-051), accounting for the fact that each sample may require 2-3 separate radiochemical procedures for different analyte groups. Insufficient separations throughput would create a bottleneck between sample preparation and measurement, delaying analytical reporting beyond the 48-hour campaign turnaround requirement. | Demonstration | subsystem, radiochem-sep, session-233 |
| SUB-REQS-072 | The Radiochemical Fume Cupboard Array SHALL incorporate integral drip trays with a minimum capacity of 5 litres per fume cupboard, draining to the active laboratory drain system, and fitted with level sensors alarming to the centralised radiation monitoring system at 50% capacity. Rationale: Integral drip trays provide secondary containment for spills within the fume cupboard, preventing radioactive liquid from reaching the cupboard base and penetrating joints. The 5-litre capacity contains the maximum credible spill volume from a single beaker (2L) plus margin. Level sensors with LIMS integration trigger alarms before overflow, enabling prompt spill response and maintaining the facility's containment barrier integrity. | Test | subsystem, radiochem-sep, session-233 |
| SUB-REQS-073 | The HPGe Detector Array SHALL achieve a minimum detectable activity of less than 1 Bq for Cs-137 in a 1-litre Marinelli beaker geometry with a 3600-second acquisition time, for all four detectors. Rationale: The <1 Bq Cs-137 MDA in a 1L Marinelli geometry at 3600s count time defines the gamma spectrometry system's sensitivity floor. This performance level is required to meet the EA/SEPA environmental monitoring programme detection requirements for liquid and solid waste samples from the dockyard. Failure to achieve this sensitivity would necessitate longer count times, reducing throughput during campaigns, or supplementary measurement by a more expensive technique. | Test | subsystem, gamma-spec, session-233 |
| SUB-REQS-074 | The Lead Shielding and Sample Chamber Assembly SHALL attenuate the external gamma background by at least a factor of 1000 across the energy range 50-2000 keV, achieving an integral count rate of less than 1 count per second in the 40-2000 keV window with no sample present. Rationale: The factor-of-1000 background attenuation determines the achievable minimum detectable activity for all gamma measurements. Without adequate shielding, environmental background (cosmic rays, building materials, neighbouring sources) would dominate the spectrum at low energies, masking low-activity sample peaks. The integral count rate specification (<0.5 cps) ensures the shielding performance is verified as a system, not just by material thickness calculation. | Test | subsystem, gamma-spec, session-233 |
| SUB-REQS-075 | The Gamma Spectrum Analysis and Nuclide Identification Software SHALL automatically identify and quantify all gamma-emitting radionuclides present above the critical level from a library of at least 200 nuclides, applying cascade summing and self-attenuation corrections, and SHALL transfer results to LIMS within 60 seconds of analysis completion. Rationale: Automatic nuclide identification from a library of 200+ radionuclides is essential for screening unknown waste and environmental samples from the dockyard, where the radionuclide inventory includes fission products, activation products, and naturally occurring radioactive materials. The 5% activity bias tolerance ensures reported activity concentrations are accurate enough for waste sentencing against disposal facility waste acceptance criteria. | Test | subsystem, gamma-spec, session-233 |
| SUB-REQS-076 | The PIPS Alpha Detector Array SHALL achieve an energy resolution of 18 keV FWHM or better at 5.486 MeV (Am-241) for all eight detectors, measured with a certified Am-241 point source at the standard 15mm source-to-detector distance. Rationale: 18 keV FWHM energy resolution at the Am-241 5.486 MeV peak is the minimum required to resolve closely spaced alpha peaks from Pu-239 (5.157 MeV) and Pu-240 (5.168 MeV) from U-234 (4.776 MeV) and Am-241 in irradiated fuel samples. PIPS detectors routinely achieve 15-20 keV; specifying 18 keV ensures acceptable peak deconvolution accuracy while allowing for in-service degradation over the detector replacement cycle. | Test | subsystem, alpha-spec, session-234 |
| SUB-REQS-077 | The Alpha Spectrometry Vacuum Chamber System SHALL achieve a vacuum pressure of less than 10 Pa within 5 minutes of chamber closure and maintain this pressure for the duration of the count period without re-pumping. Rationale: Alpha particles have a range of only a few centimetres in air. Vacuum below 10 Pa eliminates air absorption losses that would degrade both detection efficiency and energy resolution. The 10-minute pumpdown time supports the operational throughput requirement for the 24-sample carousel — excessive pumpdown would create a bottleneck in the analysis chain. The specified pressure is achievable with oil-free rotary vane pumps suitable for contaminated environments. | Test | subsystem, alpha-spec, session-234 |
| SUB-REQS-078 | The Alpha Source Loading and Sample Changer SHALL accommodate a minimum of 24 source discs per carousel position per detector chamber, with automatic barcode reading of each source disc identifier before counting commences. Rationale: The 24-source capacity per carousel allows a full batch of prepared sources (typically 8-12 environmental monitoring plus QC sources, blanks, and replicates) to be loaded in a single operation, enabling unattended overnight counting. This minimises operator handling of alpha-contaminated sources and maximises instrument utilisation. The carousel capacity is matched to the throughput of the electrodeposition source preparation unit. | Test | subsystem, alpha-spec, session-234 |
| SUB-REQS-079 | The Alpha Spectrum Analysis Software SHALL automatically deconvolve overlapping alpha peaks with energy separations of 13 keV or greater, and SHALL report activity concentrations with combined measurement uncertainties calculated in accordance with GUM methodology, including contributions from counting statistics, detector efficiency, chemical yield, and sample preparation. Rationale: Overlapping alpha peaks occur frequently in environmental and fuel-related samples where multiple actinides are present. Automated peak deconvolution with energy separation resolution below 25 keV ensures reliable identification and quantification of co-deposited actinides without requiring manual spectrum stripping, which is subjective and error-prone. The software must handle the complex spectra generated by dockyard samples containing mixtures of U, Pu, Am, and Cm isotopes. | Test | subsystem, alpha-spec, session-234 |
| SUB-REQS-080 | The Alpha MCA and Pulse Processing Electronics SHALL maintain a system dead time of less than 5% at count rates up to 10 counts per second per detector, with automatic dead time correction applied to all spectral data. Rationale: System dead time below 5% at 10 cps ensures that count rate losses from pulse processing do not introduce significant quantification errors for the higher-activity samples encountered in dockyard work. At 5% dead time, the correction factor is small and well-characterised. Higher dead times would require larger corrections with greater uncertainty, degrading the overall measurement uncertainty budget for actinide quantification. | Test | subsystem, alpha-spec, session-234 |
| SUB-REQS-081 | The Ultra-Low-Background Liquid Scintillation Counter Array SHALL achieve an instrument background count rate of less than 1.0 CPM in the tritium energy window (0-18.6 keV) with a sealed blank vial in counting position. Rationale: Ultra-low background is essential for tritium analysis of environmental samples where activities approach the minimum detectable activity. The instrument background count rate directly determines the MDA — a lower background enables detection of tritium at the levels required by discharge authorisation monitoring and environmental compliance programmes. Standard LSC instruments have backgrounds too high for the sub-Bq/L tritium measurements required near submarine refuelling operations. | Test | subsystem, lsc, session-235 |
| SUB-REQS-082 | The Ultra-Low-Background Liquid Scintillation Counter Array SHALL perform pulse shape analysis alpha/beta discrimination with a misclassification rate of less than 0.5% for both alpha-to-beta and beta-to-alpha spillover when using Ultima Gold AB cocktail. Rationale: Pulse shape analysis discriminates between alpha and beta decay events in mixed-nuclide samples, eliminating the need for separate sample preparations for alpha-emitting transuranics (Pu, Am) and beta-emitting nuclides (Sr-90, tritium) in screening analyses. This capability halves sample preparation time for gross activity screening and supports rapid sample categorisation during high-throughput submarine maintenance campaigns. | Test | subsystem, lsc, session-235 |
| SUB-REQS-083 | The Tritium Distillation and Electrolytic Enrichment System SHALL achieve a minimum tritium enrichment factor of 20 with a deuterium spike recovery of 90% to 110% for each enrichment batch. Rationale: Electrolytic enrichment with a minimum 20x concentration factor is required to achieve the detection limits for environmental tritium monitoring mandated by the site discharge authorisation. Background tritium levels in environmental waters near naval dockyards must be measured at levels below 1 Bq/L, which is not achievable by direct LSC measurement alone. The 20x enrichment combined with the ultra-low-background counter achieves the required MDA. | Test | subsystem, lsc, session-235 |
| SUB-REQS-084 | The Ultra-Low-Background Liquid Scintillation Counter Array SHALL have a combined sample capacity of at least 600 vial positions across all counters, with automated sequential counting without operator intervention. Rationale: Combined capacity for unattended counting supports weekend and overnight operation, maximising instrument utilisation for the long count times (typically 4-8 hours per vial) required for low-level tritium and C-14 measurements. The capacity must accommodate the weekly sample throughput including QC vials, backgrounds, and standards without requiring mid-batch reloading. | Inspection | subsystem, lsc, session-235 |
| SUB-REQS-085 | The Scintillation Cocktail and Vial Preparation Station SHALL be located within a fume cupboard maintaining a face velocity of 0.5 m/s +/- 10% with the sash at the designated working height. Rationale: Scintillation cocktail preparation involves dispensing volatile organic solvents (toluene, xylene-based cocktails) which are both flammable and toxic. Fume cupboard containment with maintained face velocity protects operators from solvent vapour inhalation and provides secondary containment for spillage of tritiated samples. The cocktail mixing process must occur in a controlled environment to prevent chemiluminescence from UV exposure that would generate false counts. | Test | subsystem, lsc, session-235 |
| SUB-REQS-086 | The LSC Spectrum Analysis and MDA Calculation Software SHALL calculate minimum detectable activities in accordance with ISO 11929 methodology and report combined measurement uncertainties at the 95% confidence level (k=2). Rationale: MDA calculation using the Currie formulation is the internationally accepted method (ISO 11929) for determining detection capability in radiometric measurements. Automated calculation eliminates transcription errors and ensures consistent, defensible reporting for regulatory submissions. The software must account for counting time, background, quench, and efficiency — all variables specific to each sample measurement. | Test | subsystem, lsc, session-235 |
| SUB-REQS-087 | The Scintillation Cocktail and Vial Preparation Station SHALL provide light-tight dark-adaptation storage for at least 100 prepared counting vials with a minimum storage period of 4 hours before counting. Rationale: Dark adaptation (typically 1-4 hours) is required after cocktail mixing to allow chemiluminescence and photoluminescence to decay before counting. Light-tight storage at the preparation station prevents re-excitation. Without adequate dark adaptation, elevated backgrounds would invalidate low-level tritium measurements and waste expensive counting time. The preparation station must integrate dark storage to maintain sample chain of custody. | Inspection | subsystem, lsc, session-235 |
| SUB-REQS-088 | The Quadrupole ICP-MS with Collision Reaction Cell SHALL achieve a sensitivity of at least 500 million counts per second per mg/L for U-238 in standard tuning mode and a detection limit of less than 0.1 pg/mL for U-238 in clean acid matrices. Rationale: 500 Mcps/ppm sensitivity enables measurement of trace-level actinides (sub-pg/mL) in reactor coolant and environmental samples without pre-concentration steps that would increase sample turnaround time and contamination risk. This sensitivity level is achievable with current quadrupole ICP-MS technology and is required to meet the system-level detection limits specified in SYS-REQS-011. | Test | subsystem, icp-ms, session-235 |
| SUB-REQS-089 | The Quadrupole ICP-MS with Collision Reaction Cell SHALL resolve the mass 238 (U-238) from mass 239 (Pu-239) interference with an abundance sensitivity of less than 1E-7 at one mass unit separation, using peak-tailing correction algorithms validated against IRMM-085 Pu reference material. Rationale: Uranium-238 is present at vastly higher concentrations than plutonium-239 in reactor coolant samples, causing isobaric interference at mass 239 from UH+ molecular ions. Abundance sensitivity of 1×10^-7 at mass 237 ensures Pu-239 can be accurately measured in the presence of high-uranium matrices without chemical separation, which is critical for nuclear safeguards accountability. | Test | subsystem, icp-ms, session-235 |
| SUB-REQS-090 | The Clean Room Sample Preparation Enclosure SHALL maintain ISO Class 5 (ISO 14644-1) particulate cleanliness within the laminar flow work zone, with measured uranium procedural blank levels below 50 pg per sample preparation. Rationale: ISO Class 5 cleanliness prevents particulate contamination of sub-nanogram actinide samples during dissolution and dilution steps. At the trace levels required for ICP-MS analysis, even minor particulate contamination introduces measurement bias that would invalidate safeguards-grade isotope ratio determinations. | Test | subsystem, icp-ms, session-235 |
| SUB-REQS-091 | The ICP-MS Data Processing Software SHALL calculate U-235/U-238 isotope ratios with a precision of better than 0.5% relative standard deviation at uranium concentrations of 1 ng/mL or above, applying mass bias correction using IRMM-184 natural uranium bracketing standards. Rationale: U-235/U-238 isotope ratio precision of 0.5% RSD is required to determine uranium enrichment level for nuclear safeguards declarations. This precision level discriminates between natural (0.72%), slightly enriched, and highly enriched uranium, which is essential for nuclear material accountancy at a naval dockyard handling submarine reactor fuel. | Test | subsystem, icp-ms, session-235 |
| SUB-REQS-092 | The ICP-MS Sample Introduction and Autosampler System SHALL process at least 100 samples per analytical run with automatic rinse cycles achieving memory effect wash-out to below 0.01% of the previous sample signal within 90 seconds for uranium and plutonium. Rationale: 100-sample autosampler capacity matches the typical daily throughput of the ICP-MS suite during reactor maintenance campaigns. Automated rinse and internal standard addition eliminates manual pipetting errors and cross-contamination between high-activity and trace-level samples, maintaining measurement integrity across the analytical batch. | Test | subsystem, icp-ms, session-235 |
| SUB-REQS-093 | The ICP-MS Data Processing Software SHALL perform isotope dilution mass spectrometry calculations for U and Pu quantification using U-233 and Pu-242 tracers, with combined measurement uncertainty budgets calculated in accordance with the GUM methodology and reported at k=2. Rationale: Isotope dilution mass spectrometry is the primary reference method for U and Pu quantification in safeguards applications, providing traceability to SI units independent of matrix effects. Automated IDMS calculation eliminates transcription errors in the complex multi-isotope algebra and ensures reproducibility required for nuclear material balance reporting. | Test | subsystem, icp-ms, session-235 |
| SUB-REQS-094 | The LIMS Central Database Server SHALL maintain 99.9% availability during laboratory operating hours (0700-1900 weekdays), with automatic failover to the standby server completing within 60 seconds of primary server failure detection. Rationale: 99.9% availability during operating hours limits unplanned downtime to less than 44 minutes per month, preventing sample processing backlogs during time-critical reactor maintenance campaigns. LIMS unavailability halts sample registration, chain-of-custody tracking, and results reporting, creating a facility-wide bottleneck. | Test | subsystem, lims, session-236 |
| SUB-REQS-095 | The LIMS Central Database Server SHALL retain all sample records, analytical results, calibration data, and audit trail entries for a minimum of 30 years from the date of record creation, with no data loss or corruption detectable by annual integrity verification. Rationale: 25-year retention covers the typical operational life of a naval nuclear facility and satisfies regulatory record-keeping requirements under Nuclear Site Licence Condition 6 (documents, records, authorities and certificates). Immutable audit trails prevent retrospective alteration of radiochemical results used in nuclear safety cases and discharge authorisation compliance. | Inspection | subsystem, lims, session-236 |
| SUB-REQS-096 | The Instrument Data Acquisition Gateway SHALL buffer analytical data locally for a minimum of 72 hours when the connection to the LIMS Central Database Server is unavailable, and SHALL automatically synchronise all buffered records in chronological order upon connection restoration without data loss or duplication. Rationale: 72-hour local buffering ensures no analytical data is lost during planned LIMS maintenance windows or unplanned server outages. Instruments continue generating results during downtime; without local buffering, data must be manually re-entered, introducing transcription errors into safety-critical measurement records. | Test | subsystem, lims, session-236 |
| SUB-REQS-097 | The Sample Tracking and Chain of Custody Module SHALL generate a unique, non-reusable sample identifier for every sample and sub-sample, and SHALL record each custody transfer (location, handler identity, date-time, and purpose) within 30 seconds of the transfer being confirmed at the workstation. Rationale: Unique non-reusable identifiers prevent cross-referencing errors between samples from different reactor systems or maintenance campaigns. Barcode tracking eliminates manual sample log entries and enables automated chain-of-custody verification, which is essential for forensic-quality sample traceability required by nuclear regulators. | Test | subsystem, lims, session-236 |
| SUB-REQS-098 | The Results Validation and Reporting Engine SHALL enforce a minimum two-stage review workflow (analyst submission followed by independent senior analyst authorisation) for all analytical results before they are released to the requesting party, and SHALL prevent any result from being modified after authorisation without creating a new auditable revision. Rationale: Two-stage review (analyst plus authorised checker) implements the independent verification principle required by ISO 17025 accreditation and nuclear site quality assurance programmes. Incorrect analytical results can lead to flawed reactor safety assessments or inaccurate discharge reports, with regulatory and safety consequences. | Demonstration | subsystem, lims, session-236 |
| SUB-REQS-099 | The Results Validation and Reporting Engine SHALL calculate combined measurement uncertainty for every analytical result using the GUM (Guide to the Expression of Uncertainty in Measurement) methodology, propagating Type A and Type B uncertainty components, and SHALL report the expanded uncertainty at a 95% confidence level (coverage factor k=2). Rationale: Combined measurement uncertainty following GUM methodology is required by ISO 17025 for all accredited measurements. Uncertainty values are essential for nuclear material balance evaluation — without them, regulators cannot assess whether material unaccounted for (MUF) is within expected statistical limits or indicates potential diversion. | Test | subsystem, lims, session-236 |
| SUB-REQS-100 | The Quality Assurance and Audit Trail Module SHALL record every data creation, modification, and deletion event with the original value, new value, user identity authenticated via Active Directory, workstation identifier, timestamp accurate to 1 second, and reason for change, and SHALL prevent any audit trail record from being modified or deleted by any user including system administrators. Rationale: Complete audit trail immutability is required by ISO 17025 and GxP data integrity principles (ALCOA+). For a nuclear dockyard laboratory, analytical results inform reactor safety decisions and regulatory discharge reports. Any possibility of undetected data modification undermines the legal and safety basis of results. Preventing even system administrators from modifying audit records ensures defence-in-depth for data integrity and satisfies ONR and DNSR expectations for nuclear safety-related records. | Test | subsystem, lims, session-236 |
| SUB-REQS-101 | The Regulatory Compliance and Discharge Reporting Module SHALL calculate cumulative site discharges by radionuclide and pathway (liquid effluent, gaseous, solid waste) at least daily, and SHALL generate automatic alerts to the Radiation Protection Adviser when cumulative discharge reaches 80% and 90% of the annual Environment Agency permit limit for any radionuclide or pathway. Rationale: Cumulative discharge tracking against permit limits is a legal requirement under the Environmental Permitting Regulations and the facility's environmental permit. Automated comparison against permit thresholds prevents accidental permit exceedance, which would constitute an environmental offence and could result in enforcement action by the environment agency. | Test | subsystem, lims, session-236 |
| SUB-REQS-102 | The LIMS Network Infrastructure and Cybersecurity Layer SHALL operate on a physically segregated network with no direct or routed connectivity to the internet, the dockyard general IT network, or any classified defence network, and SHALL enforce role-based access control with a minimum of four distinct roles (sample reception, analyst, senior analyst, laboratory manager) with least-privilege permissions. Rationale: Physical network segregation prevents cyber-attack vectors from reaching LIMS data that includes nuclear material accountancy records and safeguards-relevant isotope ratio measurements. A compromised LIMS could enable falsification of safety-critical analytical results or reveal sensitive nuclear material inventory data. This aligns with DNSR cybersecurity requirements for defence nuclear facilities. | Inspection | subsystem, lims, session-236 |
| SUB-REQS-103 | The LIMS Network Infrastructure and Cybersecurity Layer SHALL perform encrypted full database backups daily and incremental backups every 4 hours during operating hours, with backup media transferred to the dockyard off-site disaster recovery facility weekly, and SHALL demonstrate recovery of the complete database to within 4 hours of data loss (RPO) and within 8 hours elapsed time (RTO). Rationale: Daily full backups and hourly incremental backups with off-site replication ensure recoverability of nuclear safety records in the event of server failure, fire, or site-wide incident. The 1-hour recovery point objective limits data loss to at most one hour of analytical results, preventing the need to re-analyse samples that may have been consumed or decayed. | Test | subsystem, lims, session-236 |
| SUB-REQS-104 | The Sample Tracking and Chain of Custody Module SHALL maintain a real-time inventory of all fissile material present in each laboratory area by aggregating sample fissile content declarations, and SHALL generate an automatic alarm to the Criticality Safety Officer when the cumulative fissile content in any single area reaches 80% of the 50-gram fissile equivalent limit. Rationale: Real-time fissile material inventory tracking is mandated by Nuclear Site Licence Condition 5 (consignment of nuclear matter) and IAEA safeguards obligations. The system must demonstrate at any time that fissile holdings in each laboratory area remain below criticality safety limits. Failure to maintain accurate inventory could mask a criticality safety limit exceedance or material discrepancy. | Test | subsystem, lims, criticality, session-236 |
| SUB-REQS-105 | The LIMS Operator Workstation Array SHALL use sealed membrane keyboards and wipe-clean displays in all active area locations (radiochemical separations, sample preparation, hot cell control room), and SHALL support full LIMS functionality through keyboard-only navigation to allow operation while wearing protective gloves. Rationale: Sealed membrane keyboards and wipe-clean displays prevent ingress of radioactive contamination into equipment that operators touch frequently. Standard keyboards in active areas become contaminated and create a personal contamination hazard during routine use. Sealed equipment can be surface-monitored and decontaminated during routine radiological surveys. | Demonstration | subsystem, lims, session-236 |
| Ref | Requirement | V&V | Tags |
|---|---|---|---|
| IFC-DEFS-001 | The interface between the Sample Transfer Port System and the Sample Receipt and Preparation Laboratory SHALL accept standard 50-100 litre shielded transport flasks via a docking mechanism that maintains shielding continuity during flask-to-cell transfer, with a maximum docking time of 15 minutes. Rationale: Shielded transport flasks (50-100 litres) are the standard containers for moving high-activity reactor samples between the dockyard reactor facility and the laboratory. The docking mechanism must maintain shielding continuity to prevent dose spikes to operators during transfer. The 15-minute docking time limit prevents throughput bottlenecks during peak campaign sample intake when multiple flasks may arrive in sequence. | Test | interface, hot-cell, session-226 |
| IFC-DEFS-002 | The interface between the In-Cell Ventilation Extract System and the Ventilation and Containment System SHALL deliver extract air via 300mm diameter stainless steel ductwork at a flow rate of 500 to 1500 cubic metres per hour, with dual isolation dampers for filter change-out. Rationale: 300mm ductwork maintains the required extract airflow velocity (>1 m/s) to prevent particulate deposition while connecting the hot cell extract to the building ventilation system. Stainless steel is required for resistance to radioactive contamination and compatibility with decontamination reagents. | Test | interface, hot-cell, session-226 |
| IFC-DEFS-003 | The interface between the In-Cell Radiation Monitoring Instrumentation and the Radiation Protection and Health Physics System SHALL transmit dose rate and alarm signals via hardwired 4-20 mA analogue channels for safety-critical functions and Modbus TCP for data logging, with a maximum signal latency of 100 milliseconds for alarm channels. Rationale: 4-20 mA analogue transmission over hardwired channels provides noise-immune, fail-safe dose rate data from inside the high-radiation hot cell environment to the health physics monitoring system. Digital interfaces would require radiation-hardened electronics inside the cell. | Test | interface, hot-cell, session-226 |
| IFC-DEFS-004 | The interface between the Cell Decontamination System and the Active Effluent Treatment Plant SHALL transfer contaminated washings via a gravity-fed active drain with a U-trap seal, at a maximum flow rate of 5 litres per minute, with the drain pH maintained between 1 and 7. Rationale: Gravity-fed transfer via dedicated stainless steel pipework eliminates the need for pumps inside the hot cell and ensures contaminated washings drain to the effluent treatment plant without active equipment in the high-radiation zone. The 10-minute drain time prevents accumulation that could interfere with decontamination operations. | Test | interface, hot-cell, session-226 |
| IFC-DEFS-005 | The interface between the Master-Slave Manipulator System and the Biological Shielding Structure SHALL penetrate the shielding wall via stepped plugs that maintain the shielding attenuation factor within 10% of the surrounding wall, with sealed boots preventing contamination migration along the manipulator shafts. Rationale: Stepped labyrinth penetrations through the biological shielding provide the required shielding integrity while allowing manipulator arm movement. The 150mm maximum penetration diameter and labyrinth geometry maintain the shielding specification, preventing radiation streaming through the wall penetration. | Test | interface, hot-cell, session-226 |
| IFC-DEFS-007 | The interface between the Active Drain Collection System and the Active Effluent Storage Tanks SHALL transfer liquid effluent via gravity flow through 50mm bore 316L stainless steel pipework with a minimum gradient of 1:40, with each drain line terminating below the minimum tank liquid level to prevent siphoning. Rationale: Gravity flow via dedicated lined pipework ensures reliable effluent transfer without active pumping components that could fail and cause floor flooding in active areas. The 2 litres/second flow rate prevents back-up during high-volume operations such as cell decontamination campaigns. | Test | interface, aetp, session-227 |
| IFC-DEFS-008 | The interface between the Active Effluent Storage Tanks and the Neutralisation and Chemical Dosing Plant SHALL transfer batch volumes of 1000 to 5000 litres via a shielded centrifugal pump at 10 to 50 L/min, with flow totalisation accurate to plus or minus 2% and remotely operable isolation valves at both ends. Rationale: 1000-litre batch transfers enable processing of a full storage tank in a single operation, matching the tank sizing and treatment plant capacity. Chemical compatibility with pH 1-13 range accommodates the full spectrum of laboratory reagent waste streams including acid digestion and alkaline wash solutions. | Test | interface, aetp, session-227 |
| IFC-DEFS-009 | The interface between the Evaporation and Concentration Unit condensate outlet and the Ion Exchange Treatment Columns SHALL deliver condensate at a maximum flow rate of 500 L/hr and a maximum temperature of 40 degrees Celsius, with inline conductivity monitoring to detect carryover of dissolved solids exceeding 50 mg/L. Rationale: PVDF-lined pipework resists the corrosive condensate from the evaporator (acidic, containing trace radionuclides) and prevents metallic contamination that would interfere with downstream ion exchange performance. The 500 litres/hour flow rate matches the evaporator condensate output at design capacity. | Test | interface, aetp, session-227 |
| IFC-DEFS-010 | The interface between the Evaporation and Concentration Unit concentrate outlet and the Concentrate and Sludge Handling System SHALL transfer concentrate via peristaltic pump through shielded 25mm bore 316L pipework at 1 to 10 L/min, with the transfer line designed for remote flushing and decontamination. Rationale: Peristaltic pumps are preferred for radioactive concentrate transfer because they have no seals in contact with the process fluid, eliminating leak paths. 316L stainless steel pipework provides corrosion resistance against concentrated acidic effluent. The 1-10 L/min flow range covers both routine and batch transfer operations. Remote flushing capability is essential for decontamination of the transfer line to prevent buildup of radioactive deposits that would increase dose rates and complicate future maintenance. | Test | interface, aetp, session-227 |
| IFC-DEFS-011 | The interface between the Effluent Monitoring and Sampling Station and the Discharge Authorisation and Control System SHALL transmit gross alpha activity, gross beta activity, and gamma spectral data via hardwired 4-20 mA analogue channels for safety-critical trip signals, with a redundant Modbus TCP digital link for cumulative record-keeping and HMI display. Rationale: Gross alpha/beta and gamma spectrometry data must be transmitted to the discharge control system before any treated effluent is released. The interface ensures the discharge authorisation system has real-time analytical confirmation that batch activity concentrations are below permit limits before opening discharge valves. | Test | interface, aetp, session-227 |
| IFC-DEFS-012 | The interface between the Discharge Authorisation and Control System and the Laboratory Information Management System SHALL transmit each discharge batch record including batch identifier, volume discharged, radionuclide-specific activities, date and time, and operator authorisation identifiers, within 60 seconds of batch completion. Rationale: Each discharge event must be recorded in the LIMS for regulatory reporting and cumulative discharge tracking against annual permit limits. The interface creates an immutable audit trail linking discharge volume, radionuclide concentrations, authorising officer, and timestamp for environmental permit compliance. | Demonstration | interface, aetp, session-227 |
| IFC-DEFS-013 | The interface between the Active Area Extract System and the HEPA Filtration Bank SHALL deliver contaminated extract air through 300mm diameter galvanised steel ductwork at a maximum velocity of 10 m/s with isolation dampers upstream and downstream of each HEPA filter bank. Rationale: The extract-to-HEPA interface must maintain gas-tight integrity to prevent contaminated air bypassing the filtration stage. Testable DOP ports enable in-situ filter efficiency testing required by Nuclear Site Licence Condition 27 (safety mechanisms) without breaking the ventilation containment boundary. | Test | interface, ventilation, session-228 |
| IFC-DEFS-014 | The interface between the Pressure Cascade Control System and the Active Area Extract System SHALL provide 4-20 mA analogue control signals to the extract fan variable speed drives and motorised dampers, with a control loop update rate of at least 1 Hz. Rationale: 4-20 mA analogue control signals provide direct, deterministic control of extract fan speed from the pressure cascade controller. This ensures the negative pressure gradient from inactive to active areas is maintained continuously, which is the primary engineered barrier against airborne contamination migration. | Test | interface, ventilation, session-228 |
| IFC-DEFS-015 | The interface between the Stack Monitoring Instrumentation and the Laboratory Information Management System SHALL transmit cumulative discharge data for each monitored radionuclide category at 15-minute intervals via Modbus TCP, with each record including timestamp, cumulative activity discharged, and instrument status. Rationale: Stack monitoring data must be transmitted to LIMS for cumulative discharge reporting against environmental permit limits. Automated transfer eliminates manual transcription of discharge values, which would be error-prone given the continuous nature of stack monitoring data and the regulatory consequences of incorrect reporting. | Test | interface, ventilation, session-228 |
| IFC-DEFS-016 | The interface between the Supply Air Handling Unit and the active laboratory zones SHALL deliver supply air through ceiling-mounted diffusers at a maximum velocity of 0.3 m/s at the diffuser face to prevent turbulent disruption of fume cupboard containment. Rationale: Ceiling-mounted HEPA-filtered supply air through diffusers provides clean air at controlled temperature and humidity to protect sensitive analytical equipment and maintain operator comfort. The supply air completes the ventilation cascade by providing the replacement air drawn through the extract system. | Test | interface, ventilation, session-228 |
| IFC-DEFS-017 | The interface between the Area Gamma Dose Rate Monitoring Network and the Centralised Radiation Monitoring Display and Alarm System SHALL transmit dose rate values from each detector via hardwired 4-20 mA analogue channels for safety-critical alarm functions and Modbus TCP for data logging and trending, with the analogue channel providing alarm actuation independent of the digital network, and a maximum signal latency of 2 seconds end-to-end for alarm signals. Rationale: Dual-path architecture (analogue + digital) ensures safety-critical alarm functions are not dependent on network availability or software correctness. The 4-20 mA analogue path provides deterministic alarm actuation per IEC 61511 for safety instrumented systems. Modbus TCP provides the data richness needed for trending, dose reconstruction, and regulatory reporting. The 2-second latency limit ensures alarm response within the 5-second detector-to-alarm budget defined in SUB-REQS-032. | Test | interface, radpro, session-229 |
| IFC-DEFS-018 | The interface between the Personal Dosimetry Management System and the Radiological Access Control System SHALL provide cumulative dose status for each registered worker via a local database query with a response time not exceeding 500 milliseconds, supporting access decisions at zone entry turnstiles without perceptible delay to workers. Rationale: The 500 ms database query response time ensures that access control decisions at turnstiles do not create perceptible delays, maintaining personnel throughput at shift change (typically 50-80 workers in 15 minutes). A slower response would incentivise manual override or tailgating. Local database query rather than remote API avoids network dependency at the physical access boundary. | Test | interface, radpro, session-229 |
| IFC-DEFS-019 | The interface between the Criticality Warning System and the facility evacuation alarm system SHALL be hardwired relay-based, independent of all programmable electronic systems, driving sounder and beacon circuits directly from the criticality detection logic output, with end-to-end circuit supervision detecting open-circuit and short-circuit faults within 60 seconds of occurrence. Rationale: Hardwired relay-based interface ensures criticality evacuation alarms cannot be defeated by software failure, network outage, or cyber attack — a fundamental nuclear safety principle per ONR Safety Assessment Principle ECS.3 (independence of safety systems from control systems). End-to-end circuit supervision detects wiring faults that would otherwise leave the alarm circuit silently inoperable, with 60-second detection interval limiting the window of undetected failure. | Inspection | interface, radpro, criticality, session-229 |
| IFC-DEFS-020 | The interface between the Centralised Radiation Monitoring Display and Alarm System and the Laboratory Information Management System SHALL transmit personal dose summaries, area monitoring alarm events, and contamination survey results via Modbus TCP at 15-minute intervals for routine data and within 60 seconds for alarm events, with each record including timestamp, source identifier, measurement value, and alarm status. Rationale: Integration with LIMS enables correlation of personal dose records with work activities and sample analyses, supporting ALARP dose optimisation. The 15-minute routine interval balances network traffic with data currency for operational planning. The 60-second alarm event transmission ensures the Radiation Protection Adviser receives near-real-time notification of abnormal conditions for statutory response obligations under IRR17. | Test | interface, radpro, session-229 |
| IFC-DEFS-021 | The interface between the Airborne Contamination Monitoring System and the Ventilation and Containment System SHALL provide a hardwired trip signal to the Pressure Cascade Control System when any continuous air monitor in an active laboratory zone detects airborne alpha activity exceeding 1 DAC, initiating automatic increase of extract flow rate in the affected zone by at least 50% within 30 seconds of signal receipt. Rationale: Hardwired trip ensures the ventilation response to airborne contamination is not dependent on PLC software or network availability. Automatic extract flow increase dilutes and captures airborne contamination before it migrates to adjacent zones through the pressure cascade. The 1 DAC threshold triggers intervention before workers accumulate significant committed dose. The 30-second response time and 50% flow increase are derived from dispersion modelling of typical radiochemistry laboratory zone volumes (50-100 m³) to achieve a tenfold reduction in airborne concentration within 10 minutes. | Test | interface, radpro, ventilation, session-229 |
| IFC-DEFS-022 | The interface between the Waste Sorting and Segregation Facility and the Non-Destructive Assay System SHALL transfer waste items via shielded trolley on a level-access route, with each item accompanied by a digital waste identification tag readable by the NDA system's barcode scanner. Rationale: Shielded trolley transfer on a level-access route minimises manual handling of potentially high-dose-rate items and eliminates trip/fall risk during waste transfers. Digital waste identification tags ensure positive item tracking from sorting through assay, preventing mis-identification that could lead to incorrect categorisation. The barcode-based handover eliminates manual data entry errors at the NDA station. | Test | interface, solid-waste, session-230 |
| IFC-DEFS-023 | The interface between the Non-Destructive Assay System and the Waste Tracking and Records System SHALL transfer assay results electronically in a structured data format including package identifier, date of assay, radionuclide inventory with uncertainties, total activity, and fissile material mass, within 60 seconds of assay completion. Rationale: Electronic transfer of structured assay data within 60 seconds eliminates manual transcription errors and ensures the Waste Tracking System has current radionuclide inventory data for WAC compliance checking before the package proceeds to conditioning or storage. The specified data fields constitute the minimum dataset required by LLWR and RWM Waste Acceptance Criteria. Inclusion of uncertainties enables the tracking system to perform conservative compliance checks using upper confidence bounds. | Test | interface, solid-waste, session-230 |
| IFC-DEFS-024 | The interface between the LLW Compaction and Packaging System and the Interim Radioactive Waste Store SHALL transfer loaded HHISO containers via forklift through a loading bay with a minimum clear opening of 3 metres width and 3.5 metres height, with the Waste Tracking System recording the container identifier and storage location at point of placement. Rationale: The 3 m x 3.5 m clear opening accommodates the standard forklift envelope for HHISO container handling with adequate clearance for safe manoeuvring. HHISO containers are the standard UK LLW transport and disposal container format. Recording container ID and storage location at point of placement maintains the chain of custody required by EPR16 permits and enables retrieval for inspection or re-characterisation. | Inspection | interface, solid-waste, session-230 |
| IFC-DEFS-025 | The interface between the ILW Conditioning and Encapsulation Plant and the Interim Radioactive Waste Store SHALL transfer conditioned 500-litre drums via overhead crane, with each drum's unique identifier, weight, surface dose rate, and date of conditioning recorded in the Waste Tracking System before placement in the ILW storage area. Rationale: Overhead crane transfer is required because conditioned ILW drums (500 litres of grouted waste) exceed the weight limit for forklift handling and the dose rates necessitate remote handling. Recording weight, surface dose rate, and conditioning date at transfer provides the pre-placement data needed for criticality safety assessment (fissile mass from weight and known loading), store shielding verification (dose rate), and curing period tracking (conditioning date). This data must be recorded before placement because drum retrieval from shielded storage for measurement is impractical. | Test | interface, solid-waste, session-230 |
| IFC-DEFS-026 | The interface between the Waste Tracking and Records System and the Laboratory Information Management System SHALL exchange analytical sample results and waste characterisation data via a bidirectional electronic link, with the LIMS providing radiochemical analysis results for waste samples and the Waste Tracking System providing sample-to-package traceability. Rationale: Bidirectional data exchange between LIMS and Waste Tracking enables correlation of radiochemical analysis results with waste packages, essential for waste characterisation when NDA alone is insufficient (e.g., pure beta emitters or difficult-to-measure nuclides like Ni-63, C-14). Sample-to-package traceability ensures that characterisation data used for WAC compliance is linked to the correct package, supporting the auditable waste management lifecycle required under UK regulatory framework. | Demonstration | interface, solid-waste, session-230 |
| IFC-DEFS-027 | The interface between the Sample Logging and Labelling Station and the Laboratory Information Management System SHALL use an Ethernet TCP/IP connection carrying HL7-format or XML sample registration messages, with a maximum message latency of 2 seconds and automatic retry on communication failure, supporting a minimum of 100 sample registrations per hour. Rationale: The Sample Logging Station must communicate sample metadata to LIMS at point of receipt to establish chain of custody and enable downstream laboratory scheduling. The 2-second latency and 100 registrations/hour throughput derive from peak campaign intake rates where delays in registration would bottleneck the preparation workflow and risk sample misidentification. | Test | interface, sample-prep, session-232 |
| IFC-DEFS-028 | The interface between the Sample Preparation Fume Cupboard and the Active Area Extract System SHALL be a 250mm diameter galvanised steel duct with a manual damper, connected via flanged coupling, maintaining a minimum extract flow rate of 0.35 cubic metres per second at the duct connection point. Rationale: The fume cupboard extract duct must maintain negative pressure within the cupboard enclosure to prevent radioactive aerosol escape to the occupied laboratory. The 0.35 m³/s extract rate at 250mm diameter generates a face velocity above the 0.5 m/s minimum mandated by nuclear site licence conditions for work with unsealed radioactive sources. | Test | interface, sample-prep, session-232 |
| IFC-DEFS-029 | The interface between the Contamination Control and Waste Segregation Point and the Active Drain Collection System SHALL be a 50mm bore stainless steel gravity drain with a trapped seal, fitted with a sampling point upstream of the sump discharge valve, and capable of handling acid effluent with pH range 1 to 12. Rationale: Active liquid waste from contamination monitoring and sample segregation must be routed to the active drain system with full containment and chemical compatibility. The pH 1-12 range accommodates acid digestion residues and decontamination solutions. The trapped seal prevents airborne contamination backflow from the drain system into the laboratory space. | Inspection | interface, sample-prep, session-232 |
| IFC-DEFS-030 | The interface between the Sample Transfer Port System and the Sample Reception Bay SHALL transfer sealed sample containers of up to 250ml volume through a pneumatic transfer tube or shielded carrier, with a maximum transfer time of 3 minutes and a double-seal containment to prevent contamination spread during transit. Rationale: Sample transfer between the Hot Cell/reception area and the preparation laboratory must maintain double-seal containment to prevent spread of high-activity contamination. The 3-minute transfer time ensures sample throughput keeps pace with campaign receipt rates. The 250mL volume accommodates the largest standard sample containers used in dockyard reactor coolant and swab sampling programmes. | Test | interface, sample-prep, session-232 |
| IFC-DEFS-031 | The interface between the Sample Drying and Ashing Oven and the Active Area Extract System SHALL be a 150mm diameter heat-resistant stainless steel duct with an inline HEPA filter rated to 250 degrees Celsius, maintaining a minimum extract flow rate of 0.1 cubic metres per second to ensure negative pressure within the oven enclosure during operation. Rationale: The drying and ashing oven generates volatile radionuclides and particulate at temperatures up to 500°C. The inline HEPA filter rated to 250°C on the extract duct prevents release of radioactive particulate to the general extract system. The 0.1 m³/s extract rate maintains negative pressure within the oven enclosure at all operating temperatures, preventing fugitive emissions to the laboratory. | Test | interface, sample-prep, session-232 |
| IFC-DEFS-032 | The interface between the Analytical Balance and Gravimetric Station and the Laboratory Information Management System SHALL transmit balance readings via RS-232 or USB serial connection to the LIMS client, with each transmitted record including: mass value, unit, stability indicator, timestamp, balance identifier, and ambient temperature from the integral sensor. Rationale: Gravimetric measurements form the basis of activity concentration calculations, so mass data must transfer to LIMS without transcription error. RS-232/USB serial provides a direct instrument-to-LIMS data path. The inclusion of stability indicator and ambient temperature enables LIMS to flag readings taken under non-equilibrium or out-of-specification environmental conditions, which is critical for audit trail compliance under ISO 17025. | Test | interface, sample-prep, session-232 |
| IFC-DEFS-033 | The interface between the Radiochemical Fume Cupboard Array and the Active Area Extract System SHALL provide a minimum extract airflow of 0.6 cubic metres per second per fume cupboard through 200mm diameter stainless steel ductwork with HEPA filtration at the cupboard extract point. Rationale: Each radiochemical fume cupboard handles unsealed radioactive sources during separation chemistry. The 0.6 m³/s extract per cupboard at 200mm duct diameter maintains face velocities above the 0.5 m/s nuclear site licence requirement. HEPA filtration at the cupboard extract point captures particulate before it enters shared ductwork, preventing cross-contamination between fume cupboards and protecting the main HEPA bank from premature loading. | Test | interface, radiochem-sep, session-233 |
| IFC-DEFS-034 | The interface between the Active Laboratory Drain and Effluent Segregation System and the Active Effluent Treatment Plant SHALL transfer segregated high-activity liquid waste through acid-resistant borosilicate glass pipework rated for pH 0-14 at temperatures up to 80 degrees C, with a minimum bore of 50mm and gravity gradient of 1:40. Rationale: Radiochemical separations produce concentrated acid waste streams (HCl, HNO3, HF) that must be routed separately from low-activity drains to the effluent treatment plant. Borosilicate glass resists the full pH 0-14 range and temperatures generated by exothermic neutralisation. The 1:40 gravity gradient ensures reliable flow without pumping, reducing failure modes and avoiding mechanical agitation of settled activity in pipework. | Test | interface, radiochem-sep, session-233 |
| IFC-DEFS-035 | The interface between the Extraction Chromatography Station and downstream analytical instruments (Alpha Spectrometry Laboratory, Liquid Scintillation Counting Facility, ICP-MS Analysis Suite, Gamma Spectrometry Suite) SHALL be via labelled 20mL scintillation vials or sealed centrifuge tubes, each uniquely barcoded and registered in LIMS before transfer. Rationale: Separated fractions from extraction chromatography are distributed to four different analytical techniques depending on the nuclide of interest. Uniquely barcoded vials with LIMS registration before transfer maintain full chain of custody and prevent sample misidentification, which in a nuclear dockyard context could lead to incorrect dose assessment or waste characterisation errors with regulatory consequences. | Inspection | interface, radiochem-sep, session-233 |
| IFC-DEFS-036 | The interface between the Sample Receipt and Preparation Laboratory and the Radiochemical Separations Laboratory SHALL transfer dissolved sample aliquots in sealed, labelled vessels via a pass-through hatch with interlocked doors, with each transfer recorded in LIMS including sample identity, matrix, volume, and estimated total activity. Rationale: Dissolved sample aliquots transferred between the preparation and separations laboratories cross a significant contamination boundary. The interlocked pass-through hatch prevents simultaneous opening of both sides, maintaining the pressure cascade between zones. LIMS recording of sample identity, matrix, volume, and estimated activity is required for criticality safety assessment and for the receiving laboratory to select appropriate separation procedures and shielding. | Test | interface, radiochem-sep, session-233 |
| IFC-DEFS-037 | The interface between the Tracer and Reference Standard Store and the Laboratory Information Management System SHALL provide real-time inventory data via barcode scanner integration, updating remaining volume, dispensing user, and date-time for each tracer withdrawal within 30 seconds of the dispensing event. Rationale: Radioactive tracers and reference standards have limited shelf lives and certified activities that decay with time. Real-time inventory tracking ensures analysts do not use expired or depleted standards, which would compromise measurement accuracy. The 30-second update latency aligns with the typical time between consecutive dispensing events during batch preparation, preventing double-dispensing errors. | Test | interface, radiochem-sep, session-233 |
| IFC-DEFS-038 | The interface between the Gamma Spectrum Analysis and Nuclide Identification Software and the Laboratory Information Management System SHALL transfer analysis results including nuclide identities, activity concentrations, combined measurement uncertainties, MDA values, and spectrum file references via an automated XML or CSV data bridge, with data integrity verified by checksum on each transfer. Rationale: Gamma spectrometry results underpin waste sentencing, personnel dose assessment, and regulatory discharge reporting. Automated transfer with checksum verification eliminates transcription errors that could propagate into safety case calculations. The inclusion of combined measurement uncertainties and MDA values is mandatory for ISO 17025 accredited reporting and for demonstrating compliance with discharge authorisation limits. | Test | interface, gamma-spec, session-233 |
| IFC-DEFS-039 | The interface between the Electrodeposition and Source Preparation Unit and the Alpha Source Loading and Sample Changer SHALL transfer electrodeposited source discs of 25mm diameter on stainless steel planchets, each uniquely barcoded and registered in LIMS with source identifier, target nuclide group, and electrodeposition date before loading into the carousel. Rationale: The electrodeposited alpha source must transfer to the alpha spectrometer sample changer on a standard 25mm planchette without manual handling in the active area. Automated transfer reduces operator dose and prevents cross-contamination between samples that would compromise trace-level alpha spectrometry measurements. | Test | interface, alpha-spec, session-234 |
| IFC-DEFS-040 | The interface between the Alpha Spectrum Analysis Software and the Laboratory Information Management System SHALL transfer analysis results including nuclide identities, activity concentrations, combined measurement uncertainties, chemical yield values, and spectrum file references via an automated data bridge with checksum verification on each transfer. Rationale: Automated data transfer from alpha spectrometry analysis software to the LIMS eliminates manual transcription errors in activity concentration and uncertainty values, which are critical for waste characterisation decisions. Checksum verification ensures data integrity across the transfer, meeting ISO 17025 data integrity requirements and supporting regulatory audit of the analytical chain from spectrum to reported result. | Test | interface, alpha-spec, session-234 |
| IFC-DEFS-041 | The interface between the Tritium Distillation and Electrolytic Enrichment System and the Scintillation Cocktail and Vial Preparation Station SHALL transfer enriched water samples in 20 mL borosilicate glass vials with tamper-evident seals, accompanied by a data sheet recording the distillation batch number, enrichment factor, and deuterium spike recovery for each sample. Rationale: The distilled/enriched tritium fraction must transfer to the cocktail preparation station in a sealed pathway to prevent tritium vapour release (tritium is the most mobile radionuclide in the laboratory). The interface ensures quantitative transfer of the enriched fraction for accurate tritium activity determination. | Test | interface, lsc, session-235 |
| IFC-DEFS-042 | The interface between the Ultra-Low-Background LSC Counter Array and the LSC Spectrum Analysis and MDA Calculation Software SHALL transfer raw spectral data in 1024-channel MCA format including pulse shape discrimination parameters, external standard quench parameter SQP(E), counting time, and sample identification via the counter's native data export protocol. Rationale: Raw spectral data transfer at full resolution enables the analysis software to perform spectrum deconvolution, quench correction, and minimum detectable activity calculations. Loss of spectral resolution during transfer would compromise the ultra-low-background counting capability that defines this facility's tritium measurement performance. | Test | interface, lsc, session-235 |
| IFC-DEFS-043 | The interface between the LSC Spectrum Analysis Software and the Laboratory Information Management System SHALL transfer analytical results including activity concentration (Bq/L or Bq/kg), combined measurement uncertainty (k=2), minimum detectable activity, QC flag status, and sample identification in a validated electronic format with no manual transcription. Rationale: Automated transfer of validated results with associated uncertainties to LIMS ensures traceability from raw LSC spectrum to reported tritium activity. GUM-compliant uncertainty values must accompany every result for ISO 17025 accreditation compliance and nuclear material balance evaluation. | Test | interface, lsc, session-235 |
| IFC-DEFS-044 | The interface between the Radiochemical Separations Laboratory and the Scintillation Cocktail and Vial Preparation Station SHALL deliver separated radionuclide fractions (Sr-90, Fe-55, Ni-63, C-14) in acid matrices compatible with the specified scintillation cocktail, with acid normality not exceeding 2M to prevent cocktail phase separation. Rationale: Separated actinide fractions from radiochemical separation must reach the cocktail preparation station without cross-contamination. Each fraction contains a specific radionuclide group (Pu, Am/Cm, Sr) and contamination between fractions would produce incorrect results in safety-critical measurements. | Test | interface, lsc, session-235 |
| IFC-DEFS-045 | The interface between the Extraction Chromatography Station and the Clean Room Sample Preparation Enclosure SHALL deliver chemically separated actinide fractions in 2% HNO3 matrix with total dissolved solids below 0.1% m/v, accompanied by the separation batch record documenting tracer additions, column type, and elution volumes. Rationale: Chromatographic separation produces purified analyte fractions that require ICP-MS analysis in a clean environment. Transfer to the ISO Class 5 enclosure prevents particulate contamination of sub-nanogram samples during the final preparation step before mass spectrometric measurement. | Test | interface, icp-ms, session-235 |
| IFC-DEFS-046 | The interface between the Quadrupole ICP-MS and the ICP-MS Data Processing Software SHALL transfer raw time-resolved analysis data including individual isotope count rates at each integration period (100 ms minimum resolution), internal standard count rates, and instrument tuning parameters via the vendor acquisition software export protocol. Rationale: Time-resolved raw data at full mass resolution is essential for transient signal processing, peak integration, and interference correction algorithms in the data processing software. Loss of temporal resolution would prevent detection of signal instabilities caused by matrix effects during sample introduction. | Test | interface, icp-ms, session-235 |
| IFC-DEFS-047 | The interface between the ICP-MS Data Processing Software and the Laboratory Information Management System SHALL transfer isotope ratio results, IDMS activity concentrations, and GUM uncertainty budgets in validated electronic format, with data retention for a minimum of 30 years in compliance with ONR nuclear site record-keeping requirements. Rationale: Isotope ratio results with measurement uncertainties must reach LIMS for nuclear material accountancy reporting. Automated transfer with full traceability metadata prevents manual transcription errors in safeguards-critical measurements and satisfies IAEA inspection requirements for data integrity. | Inspection | interface, icp-ms, session-235 |
| IFC-DEFS-048 | The interface between the Instrument Data Acquisition Gateway and the LIMS Central Database Server SHALL transfer validated analytical results using structured database transactions with ACID guarantees, transmitting at minimum: instrument identifier, method code, sample identifier, raw count data, calibration-corrected results, acquisition start and end timestamps, and data quality flags, at a sustained throughput of at least 50 result records per minute. Rationale: The gateway-to-database interface is the primary data ingestion path for all instrument results. Validated data with integrity checksums ensures the database receives only quality-assured results, preventing corrupt or incomplete records from entering the regulatory reporting chain. | Test | interface, lims, session-236 |
| IFC-DEFS-049 | The interface between the Sample Tracking and Chain of Custody Module and the Results Validation and Reporting Engine SHALL provide real-time sample metadata (sample identifier, matrix type, requested analyses, receipt date, client reference, and priority status) to the results engine, ensuring that no analytical result can be processed without a valid, active sample record in the tracking module. Rationale: The sample tracking module must provide real-time sample status to the results validation engine so that results can be matched to the correct sample, preparation method, and chain-of-custody record. Without this linkage, analytical results cannot be attributed to specific samples with forensic-quality traceability. | Test | interface, lims, session-236 |
| IFC-DEFS-050 | The interface between the Results Validation and Reporting Engine and the Regulatory Compliance and Discharge Reporting Module SHALL transfer only authorised (two-stage reviewed) results, tagged with discharge pathway (liquid effluent, gaseous stack, solid waste), radionuclide identity, activity value, and combined uncertainty, using database views that aggregate by pathway and reporting period without permitting the regulatory module to modify source result records. Rationale: Validated results with approval chain metadata must flow to the regulatory reporting module for discharge calculations and statutory reports. The interface ensures only authorised, two-stage-reviewed results contribute to cumulative discharge totals, preventing unvalidated data from affecting permit compliance calculations. | Test | interface, lims, session-236 |
| IFC-DEFS-051 | The interface between the Quality Assurance and Audit Trail Module and the Instrument Data Acquisition Gateway SHALL receive calibration check results after every instrument calibration event, and SHALL automatically update Shewhart control charts and flag any result exceeding 2-sigma warning or 3-sigma action limits, generating a notification to the instrument custodian and preventing further analytical runs on the affected instrument until the out-of-control condition is investigated and cleared. Rationale: Calibration check data and instrument performance metrics from the data acquisition gateway enable the QA module to flag instruments operating outside calibration tolerance. This prevents results from miscalibrated instruments entering the quality system, which could invalidate entire analytical batches. | Test | interface, lims, session-236 |
| IFC-DEFS-052 | The interface between the LIMS Operator Workstation Array and the LIMS Network Infrastructure and Cybersecurity Layer SHALL authenticate every user session using Active Directory credentials with session timeout after 15 minutes of inactivity in active areas and 30 minutes in non-active areas, and SHALL encrypt all client-server traffic using TLS 1.2 or later with mutual certificate authentication. Rationale: Role-based authentication with session logging at the workstation-to-network interface implements the access control required by DNSR cybersecurity policy and nuclear material accountancy regulations. Every LIMS interaction must be attributable to a specific user for audit trail integrity. | Test | interface, lims, session-236 |
| Ref | Requirement | V&V | Tags |
|---|---|---|---|
| ARC-DECISIONS-001 | ARC: Hot Cell Facility — The hot cell uses through-wall mechanical master-slave manipulators rather than electromechanical servo manipulators or robotic arms. This choice prioritises the direct force-feedback that mechanical linkages provide, which is critical for the fine motor control required during dissolution vessel loading, pipetting, and radiochemical source preparation. Electromechanical alternatives were rejected because the force-feedback latency (typically 5-20ms in servo systems) degrades operator control during precision pipetting, and the electronics would be exposed to a high radiation field (>1 Gy/h gamma) inside the cell, requiring expensive radiation-hardened components with limited availability. The cell decontamination system uses fixed spray nozzles with gravity drain rather than a sump pump, eliminating the need for an in-cell pump that would be difficult to maintain remotely and would become a contaminated waste item at end of life. Rationale: Architecture trade-off between manipulator types for hot cell operations in a nuclear dockyard radiochemistry facility. Master-slave manipulators provide direct force feedback essential for handling fragile reactor components and small samples. | Analysis | architecture, hot-cell, session-226 |
| ARC-DECISIONS-002 | ARC: Active Effluent Treatment Plant — evaporation plus ion exchange polishing was selected over direct ion exchange or chemical precipitation alone. Direct IX would exhaust resin rapidly given the mixed fission product and activation product inventory typical of dockyard reactor coolant samples, generating excessive volumes of spent resin as ILW. Chemical precipitation alone cannot reliably achieve the Environmental Agency discharge limits of 0.1 Bq/L alpha. The evaporator provides 20:1 volume reduction and removes the bulk of dissolved solids, while IX polishing of the low-activity condensate targets specific long-lived nuclides (Cs-137, Sr-90, Co-60) to achieve final discharge quality. Sub-atmospheric evaporation was chosen specifically to suppress ruthenium tetroxide volatilisation, which is a known issue in fuel examination laboratories where irradiated fuel dissolution produces volatile Ru species. The SIL 2-rated discharge control with dual-path instrumentation (hardwired analogue for safety, Modbus TCP for records) follows established nuclear industry practice for separating safety and information functions. Rationale: Treatment technology selection for liquid radioactive waste from radiochemistry operations. Evaporation achieves higher volume reduction factors than direct ion exchange for mixed-radionuclide waste streams. | — | architecture, aetp, session-227 |
| ARC-DECISIONS-003 | ARC: Ventilation and Containment System — The extract air treatment train follows the sequence HEPA filtration then activated carbon iodine adsorption, rather than carbon-first or combined filter/adsorber units. This ordering protects the carbon beds from particulate loading (which reduces iodine adsorption efficiency and shortens bed life) and ensures the HEPA filters capture any carbon fines released from the adsorber beds before the stack. The pressure cascade control system uses continuous PLC-based modulation of fan speeds and damper positions rather than fixed-speed fans with bypass dampers, because the variable laboratory loading (fume cupboard sash positions change frequently during active operations) demands continuous adjustment to maintain the required pressure differentials. Fixed-speed systems with bypass dampers cannot respond quickly enough to transient disturbances and waste energy. Redundant duty/standby extract fans were selected over a single fan with emergency diesel backup because automatic changeover (30 seconds) is faster than diesel generator start and fan spin-up (typically 60-120 seconds), and the containment barrier cannot tolerate a 2-minute pressure reversal. Rationale: Air treatment train sequencing driven by ALARP dose reduction and filter protection. HEPA before carbon prevents particulate loading of the carbon bed, extending carbon service life and reducing secondary waste. | Analysis | architecture, ventilation, session-228 |
| ARC-DECISIONS-004 | ARC: Radiation Protection and Health Physics System — Separation of safety-critical and data functions. The criticality warning system is implemented as a fully independent hardwired system with dedicated power, cabling, and detectors, separate from the general area monitoring network. Area gamma monitors, airborne contamination monitors, and personal dosimetry feed a centralised monitoring display via dual paths: hardwired 4-20mA analogue channels carry safety-critical alarm signals while Modbus TCP carries data for trending and archiving. This architecture was chosen over a unified digital monitoring platform because: (1) UK nuclear safety case practice requires demonstrable independence of safety functions from commercial IT systems; (2) hardwired alarm paths survive common-cause software and network failures; (3) the ONR Safety Assessment Principles (SAP ECS.2) require that safety systems use the simplest technology commensurate with the safety function. The alternative — a fully networked SIL-rated system — was rejected due to the difficulty of claiming SIL 2 for a complex software-based monitoring platform and the prohibitive cost of independent safety assessment for software of this complexity. Rationale: Separation of safety-critical monitoring (hardwired analogue) from data management functions (digital network) follows IEC 61511 and ONR Safety Assessment Principle ECS.3, ensuring that a single common-cause failure (e.g., network outage, software bug, cyber attack) cannot simultaneously compromise both the alarm function and the data recording function. This architecture was chosen over a fully digital approach because the criticality and radiation alarm functions are Class 1 safety systems requiring the highest reliability. | — | architecture, radpro, session-229 |
| ARC-DECISIONS-005 | ARC: Solid Radioactive Waste Management System — Seven-component decomposition separating physical waste processing (sorting, compaction, conditioning, storage) from information management (NDA, tracking, sealed sources). The separation of waste characterisation (NDA) from waste processing (compaction, conditioning) enables independent calibration and quality assurance of measurement systems without disrupting waste throughput. The Waste Tracking and Records System is centralised rather than distributed across components because the 150-year record retention requirement demands a single authoritative data source. Sealed source management is a distinct component because it follows a fundamentally different regulatory regime (HASS Regulations and IRR17) from bulk radioactive waste (Environmental Permitting Regulations). Rationale: Seven-component decomposition reflects the distinct physical processing steps, regulatory regimes, and failure modes in the UK radioactive waste management chain. Separating waste sorting from NDA, and conditioning from storage, enables independent commissioning, maintenance, and regulatory inspection of each capability. The spent sealed source management function is separated because it has distinct regulatory requirements under IRR17 Regulation 27 and a different lifecycle from routine operational waste. | Analysis | architecture, solid-waste, session-230 |
| ARC-DECISIONS-006 | ARC: Sample Receipt and Preparation Laboratory — Linear workflow with parallel preparation paths. The subsystem is decomposed into a linear sample flow (Reception Bay to Logging Station to Storage to Preparation) with two parallel preparation branches: acid digestion for solid samples requiring dissolution, and direct aliquoting within the fume cupboard for liquid samples. This topology reflects the fundamentally different preparation requirements of solid matrices (soil, concrete, metal) versus liquid matrices (coolant, pond water, effluent). A single fume cupboard serves both branches because the operations are not concurrent for any individual sample. The Contamination Control and Waste Segregation Point is positioned at the laboratory exit rather than distributed, following ALARP principles — a single controlled exit simplifies monitoring, reduces the number of contamination instruments requiring calibration, and provides a definitive boundary between controlled and supervised areas. The Acid Digestion System is a separate component rather than a sub-function of the fume cupboard because it requires distinct safety controls (pressure vessel management, temperature trips) and generates the majority of the liquid waste stream. Rationale: Documents the architectural reasoning for the Sample Receipt and Preparation Laboratory's component topology. The linear workflow with parallel preparation paths reflects the need to maintain sample chain of custody while maximising throughput during submarine reactor campaigns. | — | architecture, sample-prep, session-232 |
| ARC-DECISIONS-007 | ARC: Radiochemical Separations Laboratory — Separation of extraction chromatography from electrodeposition as distinct components, with glassware decontamination and tracer storage as independent support functions. The alternative of a single monolithic wet chemistry area was rejected because (1) extraction chromatography generates acid fumes requiring dedicated fume cupboard extract, while electrodeposition generates minimal fumes but requires electrical isolation and DC power, making co-location in the same fume cupboard impractical; (2) tracer and reference standard storage must be physically separated from active separations to prevent contamination of calibration materials, which would introduce systematic errors across all analytical methods; (3) glassware decontamination produces large effluent volumes that would overload individual fume cupboard drip trays if co-located, and its NaI(Tl) monitoring rig requires a low-background environment incompatible with active separations areas. The reagent storage system is centralised rather than distributed per cupboard to enable COSHH-compliant ventilated bulk storage and LIMS-integrated inventory management. Rationale: Documents the separation of extraction chromatography from electrodeposition as distinct components within the Radiochemical Separations Laboratory. This reflects the different skill sets, equipment, and contamination control requirements of wet chemistry versus source preparation, and allows independent optimisation of each process. | Analysis | architecture, radiochem-sep, session-233 |
| ARC-DECISIONS-008 | ARC: Gamma Spectrometry Suite — Electromechanical cryocoolers selected over liquid nitrogen cooling to eliminate cryogen handling in a nuclear-licensed facility. LN2 dewars require manual filling, generate oxygen-depleted atmosphere risk in enclosed counting rooms, and introduce vibration during fill that interrupts acquisitions. Stirling-cycle cryocoolers achieve comparable vibration-induced resolution degradation (less than 0.05 keV) with modern microphonic rejection algorithms. Four detectors rather than two were selected because SYS-REQS-012 requires at least one operational detector at all times; with four, the probability of total loss of gamma capability is less than 10E-8 per year assuming individual detector MTBF of 20000 hours. Rationale: Documents the selection of electromechanical cryocoolers over liquid nitrogen cooling for HPGe detectors. Cryocoolers eliminate LN2 handling hazards in a radiologically controlled area, reduce ongoing operational costs, and remove the logistical dependency on regular LN2 deliveries to the dockyard site. | Analysis | architecture, gamma-spec, session-233 |
| ARC-DECISIONS-009 | ARC: Alpha Spectrometry Laboratory — Five-component architecture with 8 independent PIPS detector channels sharing a common MCA and software platform. Independent vacuum chambers per detector allow continuous counting on some channels while loading/unloading others, maximising throughput during campaigns. Automated sample changers with 24-position carousels enable unattended overnight counting, which is essential given the long count times (16-72 hours) required for low-activity environmental alpha samples. Rationale: Architecture balances throughput (8 independent channels for parallel counting of long-lived alpha emitters) against cost by sharing vacuum and detector electronics infrastructure across channels. | Analysis | architecture, alpha-spec, session-234 |
| ARC-DECISIONS-010 | ARC: Liquid Scintillation Counting Facility — Dedicated tritium enrichment capability rather than outsourcing. The decision to include a full electrolytic enrichment system was driven by the dockyard's environmental monitoring obligations under the site discharge authorisation, which require monthly tritium results in groundwater at sub-Bq/L sensitivity. Outsourcing enrichment to an external laboratory would introduce 2-3 week turnaround delays incompatible with the monthly reporting cycle, and the classified nature of some dockyard samples precludes off-site transfer. The enrichment system adds capital and maintenance cost but is the only architecture that meets both the sensitivity and timeliness constraints simultaneously. Rationale: In-house tritium enrichment avoids transport of tritiated samples off-site, which would require authorised carrier arrangements and increase sample turnaround time during reactor maintenance campaigns from weeks to days. | Analysis | architecture, lsc, session-235 |
| ARC-DECISIONS-011 | ARC: ICP-MS Analysis Suite — Quadrupole with collision-reaction cell over sector-field ICP-MS. A sector-field (high-resolution) ICP-MS would provide superior abundance sensitivity and eliminate many polyatomic interferences directly, but at 3-4x the capital cost, higher maintenance burden, and requirement for a specialist operator. The quadrupole with KED collision cell resolves the critical interferences (ArAr on Se-78, ArCl on As-75, ClO on V-51) adequately for dockyard work, and the UH+ tailing at mass 239 is correctable algorithmically when Pu concentrations are above 0.1 fg/mL. For the rare samples requiring higher mass resolution (Pu-239/U-238H discrimination at extreme U:Pu ratios), the chemical separation step using extraction chromatography removes U before measurement, making the abundance sensitivity requirement manageable for the quadrupole platform. Rationale: Quadrupole ICP-MS with collision-reaction cell provides adequate mass resolution for naval reactor chemistry analysis at significantly lower acquisition and maintenance cost than sector-field instruments. CRC technology resolves the key polyatomic interferences affecting actinide measurements. | Analysis | architecture, icp-ms, session-235 |
| ARC-DECISIONS-012 | ARC: Laboratory Information Management System — The LIMS uses a centralised client-server architecture with a single high-availability database rather than a distributed or microservices architecture. This choice prioritises data consistency and audit trail integrity over scalability, which is appropriate because the laboratory serves a single dockyard with predictable, bounded throughput (5000 samples/year). A distributed architecture would introduce eventual consistency, making it impossible to guarantee that two concurrent users see identical sample states — unacceptable for chain-of-custody integrity. The instrument data acquisition function is separated from the core LIMS as a distinct gateway component rather than embedded in each instrument's native software, because this creates a single integration point that can implement store-and-forward buffering consistently across all 15+ instruments from multiple vendors (Canberra, Agilent, PerkinElmer, Ortec), each with different native data formats and communication protocols. The regulatory compliance module is deliberately read-only with respect to analytical results, enforced at the database view level rather than application-level permissions, because application-level controls can be bypassed by a sufficiently privileged database administrator, whereas view-level restrictions cannot without DBA intervention that would itself be logged. Rationale: Centralised client-server LIMS architecture ensures a single authoritative data source for nuclear material accountancy and regulatory reporting. Distributed architectures risk data inconsistency between nodes, which is unacceptable for safeguards-grade record-keeping. | Analysis | architecture, lims, session-236 |
flowchart TB n0["component<br>Biological Shielding Structure"] n1["component<br>Master-Slave Manipulators"] n2["component<br>Lead Glass Windows"] n3["component<br>In-Cell Ventilation Extract"] n4["component<br>Sample Transfer Ports"] n5["component<br>Dissolution and Process Equipment"] n6["component<br>Radiation Monitoring"] n7["component<br>Cell Decontamination System"] n8["actor<br>Operator Station"] n9["actor<br>Main Ventilation System"] n10["actor<br>Effluent Treatment Plant"] n11["actor<br>Radiation Protection System"] n12["actor<br>Sample Receipt Lab"] n13["component<br>Biological Shielding Structure"] n14["component<br>Master-Slave Manipulators"] n15["component<br>Lead Glass Windows"] n16["component<br>In-Cell Ventilation Extract"] n17["component<br>Sample Transfer Ports"] n18["component<br>Dissolution and Process Equipment"] n19["component<br>Radiation Monitoring"] n20["component<br>Cell Decontamination System"] n21["actor<br>Operator Station"] n22["actor<br>Main Ventilation System"] n23["actor<br>Effluent Treatment Plant"] n24["actor<br>Radiation Protection System"] n25["actor<br>Sample Receipt Lab"] n21 -->|Force-feedback control| n14 n21 -->|Visual observation| n15 n14 -->|Remote handling| n18 n25 -->|Shielded samples| n17 n17 -->|Irradiated material| n18 n16 -->|Filtered extract air| n22 n19 -->|Dose rate and alarm signals| n24 n20 -->|Active liquid effluent| n23 n18 -->|Sample aliquots out| n17 n18 -->|NOx and volatile fission products| n16
Hot Cell Facility — Internal
flowchart TB n0["component<br>Active Drain Collection System"] n1["component<br>Active Effluent Storage Tanks"] n2["component<br>Neutralisation and Chemical Dosing Plant"] n3["component<br>Evaporation and Concentration Unit"] n4["component<br>Ion Exchange Treatment Columns"] n5["component<br>Effluent Monitoring and Sampling Station"] n6["component<br>Concentrate and Sludge Handling System"] n7["component<br>Discharge Authorisation and Control System"] n8["external<br>Hot Cell Facility"] n9["external<br>Dockyard Drainage"] n10["external<br>LIMS"] n8 -->|contaminated effluent| n0 n0 -->|gravity drain| n1 n1 -->|batch transfer| n2 n2 -->|pH-adjusted feed| n3 n3 -->|condensate| n4 n3 -->|concentrate| n6 n4 -->|treated effluent| n5 n5 -->|activity data| n7 n7 -->|authorised discharge| n9 n7 -->|batch records| n10
Active Effluent Treatment Plant — Internal
flowchart TB n0["component<br>Waste Sorting and Segregation Facility"] n1["component<br>Non-Destructive Assay System"] n2["component<br>LLW Compaction and Packaging System"] n3["component<br>ILW Conditioning and Encapsulation Plant"] n4["component<br>Interim Radioactive Waste Store"] n5["component<br>Waste Tracking and Records System"] n6["component<br>Spent Sealed Source Management System"] n0 -->|waste items for assay| n1 n0 -->|sorted compactable LLW| n2 n0 -->|sorted ILW items| n3 n1 -->|assay results and inventories| n5 n2 -->|packaged LLW in HHISO| n4 n3 -->|conditioned ILW drums| n4 n5 -->|package location tracking| n4
Solid Radioactive Waste Management System — Internal
flowchart TB n0["component<br>Sample Reception Bay"] n1["component<br>Sample Logging and Labelling Station"] n2["component<br>Sample Storage Refrigerator Array"] n3["component<br>Sample Preparation Fume Cupboard"] n4["component<br>Analytical Balance and Gravimetric Station"] n5["component<br>Sample Drying and Ashing Oven"] n6["component<br>Acid Digestion System"] n7["component<br>Contamination Control and Waste Segregation Point"] n8["actor<br>LIMS"] n9["actor<br>Active Area Extract System"] n10["actor<br>Active Drain Collection System"] n11["actor<br>Sample Transfer Port System"] n0 -->|received samples| n1 n1 -->|logged samples| n2 n2 -->|samples for prep| n3 n3 -->|aliquots for weighing| n4 n3 -->|solid samples| n6 n5 -->|ashed residues| n6 n6 -->|acid waste| n7 n3 -->|prep waste| n7 n1 -->|sample records| n8 n4 -->|mass data| n8 n3 -->|extract air| n9 n5 -->|oven exhaust| n9 n7 -->|liquid waste| n10 n11 -->|hot cell samples| n0
Sample Receipt and Preparation Laboratory — Internal
flowchart TB n0["component<br>Radiochemical Fume Cupboard Array"] n1["component<br>Extraction Chromatography Station"] n2["component<br>Electrodeposition and Source Preparation Unit"] n3["component<br>Reagent Storage and Dispensing System"] n4["component<br>Active Laboratory Drain and Effluent Segregation System"] n5["component<br>Glassware Decontamination and Quality Control Bay"] n6["component<br>Tracer and Reference Standard Store"] n7["component<br>TestBlock"] n8["component<br>Radiochemical Fume Cupboard Array"] n9["component<br>Extraction Chromatography Station"] n10["component<br>Electrodeposition and Source Preparation Unit"] n11["component<br>Reagent Storage and Dispensing System"] n12["component<br>Active Laboratory Drain System"] n13["component<br>Glassware Decontamination Bay"] n14["component<br>Tracer and Reference Standard Store"] n15["component<br>Active Area Extract System"] n16["component<br>Active Effluent Treatment Plant"] n17["component<br>Sample Receipt and Prep Lab"] n18["component<br>Analytical Instruments"] n17 -->|Dissolved samples| n8 n11 -->|Acids and reagents| n8 n14 -->|Yield tracers| n9 n9 -->|Separated fractions| n10 n10 -->|Counting sources| n18 n9 -->|Liquid fractions| n18 n8 -->|Liquid waste| n12 n13 -->|Decontam effluent| n12 n12 -->|Segregated effluent| n16 n8 -->|HEPA extract air| n15 n8 -->|Used glassware| n13
Radiochemical Separations Laboratory — Internal
flowchart TB n0["component<br>PIPS Alpha Detector Array"] n1["component<br>Vacuum Chamber System"] n2["component<br>MCA and Pulse Processing"] n3["component<br>Spectrum Analysis Software"] n4["component<br>Source Loading and Sample Changer"] n0 -->|Mounted in| n1 n4 -->|Source discs| n1 n0 -->|Charge pulses| n2 n2 -->|Spectral data| n3 n4 -.->|Sample ID| n3
Alpha Spectrometry Laboratory — Internal
flowchart TB n0["component<br>Tritium Distillation and Enrichment"] n1["component<br>Cocktail and Vial Preparation"] n2["component<br>ULB LSC Counter Array"] n3["component<br>Quench Calibration Standards"] n4["component<br>LSC Analysis Software"] n5["external<br>Radiochem Separations Lab"] n6["external<br>LIMS"] n0 -->|Enriched water samples| n1 n5 -->|Separated radionuclide fractions| n1 n1 -->|Prepared counting vials| n2 n3 -->|Quench calibration standards| n2 n2 -->|Raw pulse-height spectra| n4 n4 -->|Activity results and QC data| n6
LSC Facility — Internal
flowchart TB n0["component<br>Clean Room Preparation Enclosure"] n1["component<br>Sample Introduction and Autosampler"] n2["component<br>Quadrupole ICP-MS with CRC"] n3["component<br>Calibration and QC Standards"] n4["component<br>Data Processing and Isotope Ratio SW"] n5["external<br>Extraction Chromatography Station"] n6["external<br>LIMS"] n5 -->|Separated actinide fractions| n0 n0 -->|Prepared sample solutions| n1 n3 -->|Calibration and IDMS spike solutions| n1 n1 -->|Nebulised sample aerosol| n2 n2 -->|Raw mass spectra and count rates| n4 n4 -->|Isotope ratios and activity results| n6
ICP-MS Analysis Suite — Internal
flowchart TB n0["component<br>LIMS Central Database Server"] n1["component<br>Instrument Data Acquisition Gateway"] n2["component<br>Sample Tracking Module"] n3["component<br>Results Validation Engine"] n4["component<br>QA and Audit Trail Module"] n5["component<br>Regulatory Reporting Module"] n6["component<br>Network and Cybersecurity Layer"] n7["component<br>Operator Workstation Array"] n8["component<br>LIMS Central Database Server"] n9["component<br>Instrument Data Acquisition Gateway"] n10["component<br>Sample Tracking Module"] n11["component<br>Results Validation Engine"] n12["component<br>QA and Audit Trail Module"] n13["component<br>Regulatory Reporting Module"] n14["component<br>Network and Cybersecurity Layer"] n15["component<br>Operator Workstation Array"] n9 -->|validated instrument data| n8 n10 -->|sample records| n8 n11 -->|authorised results| n8 n12 -->|audit trails| n8 n13 -->|regulatory queries| n8 n15 -->|client sessions| n14 n14 -->|authenticated connections| n8 n9 -->|raw analytical data| n11 n10 -->|sample metadata| n11 n11 -->|authorised results for aggregation| n13 n12 -->|calibration status| n9
Laboratory Information Management System — Internal
| Entity | Hex Code | Description |
|---|---|---|
| Acid Digestion System | D0951018 | Microwave-assisted acid digestion system within the Sample Receipt and Preparation Laboratory for dissolving solid radioactive samples in concentrated mineral acids (HNO3, HCl, HF) prior to radiochemical separation and instrumental analysis. Comprises a closed-vessel microwave digestion unit (40-position rotor, 260°C, 80 bar capability) with automated temperature and pressure control per vessel, and an open-vessel hotplate digestion station for larger sample volumes (up to 250ml). All digestion operations conducted within the ducted fume cupboard. Digests soil, sediment, concrete, metal swarf, and biological tissue samples. Acid fumes exhausted through acid-resistant ductwork to the scrubber before the HEPA filtration stage. Generates approximately 5 litres of mixed acid waste per week, routed to the Active Effluent Treatment Plant via the active drain. |
| Active Area Extract System | 55D73018 | Extract ventilation system serving all active laboratory areas including fume cupboards, gloveboxes, and open bench areas where radioactive materials are handled. Maintains negative pressure in active areas relative to non-active areas and corridors. Incorporates dual-stage HEPA filtration before discharge to stack. Fan capacity sized to maintain required face velocities at fume cupboards (0.5 m/s) and room air change rates (6-10 ACH in active areas). Redundant extract fans (duty/standby) to maintain containment during fan failure or maintenance. |
| Active Drain Collection System | CE853059 | Gravity-fed 316L stainless steel drainage network collecting radioactive liquid effluent from hot cells, fume cupboards, sinks, and decontamination stations in a UK nuclear dockyard radiochemistry laboratory. Receives acidic, alkaline, and organic-contaminated streams at activities up to 1E8 Bq/L. Double-contained pipework with leak detection sumps at each junction. Drains are routed through shielded trenches below the laboratory floor level to the active effluent storage tanks. Designed to BS EN 12056 with nuclear-specific modifications for containment integrity and decontaminability. |
| Active Effluent Storage Tanks | DE951259 | Three 10,000-litre double-skinned 316L stainless steel delay/decay tanks receiving radioactive liquid effluent from the active drain collection system at a UK nuclear dockyard radiochemistry laboratory. Tanks operate in fill-hold-sample-transfer batch mode allowing radioactive decay of short-lived isotopes and pre-treatment sampling. Each tank has level instrumentation, temperature monitoring, agitation for representative sampling, and activity monitoring via dip-tube sampling lines. Designed to Nuclear Site Licence Condition 32 with secondary containment bund sized for 110% of largest tank volume. |
| Active Effluent Treatment Plant | 57D73A59 | Liquid radioactive effluent collection, treatment, and monitored discharge system for the nuclear dockyard radiochemistry laboratory. Collects active drains from fume cupboards, hot cells, decontamination areas, and radiochemical separations via dedicated pipework (typically double-contained stainless steel in concrete trenches) to delay tanks. Treatment processes include pH adjustment, chemical precipitation (ferric floc co-precipitation for actinide/fission product removal), filtration, and ion exchange polishing. Delay tanks (typically 2 × 10-20 m³) allow sampling and analysis before authorised batch discharge to the tidal basin under conditions specified in the site's environmental permit. Discharge limits set by the Environment Agency in Bq per annum for groups of radionuclides (total alpha, total beta excluding tritium, tritium). Continuous flow-proportional sampling during discharge. System designed to minimise holdup of fissile material (criticality safety constraint). |
| Active Laboratory Drain and Effluent Segregation System | CA871058 | Acid-resistant drainage network serving the radiochemical separations laboratory in a UK nuclear dockyard. Constructed from borosilicate glass pipework with PTFE-jointed connections routed through bunded trenches below floor level. Segregates high-activity wash streams (from extraction chromatography column rinses and electrodeposition cell rinses) from low-activity general laboratory drainage. High-activity drains route to dedicated collection vessels within the Active Effluent Treatment Plant. Low-activity drains route to delay tanks with automatic gamma monitoring before release to the general active drain system. Includes spill containment bunding beneath all fume cupboards with level alarms and automatic pump-out to AETP collection. Designed for pH range 0-14 and temperature up to 80 degrees C. |
| Airborne Contamination Monitoring System | 55F77A59 | Continuous air monitoring system for alpha- and beta-emitting particulate contamination in a UK nuclear dockyard radiochemistry laboratory. Includes fixed continuous air monitors (CAMs) in each active laboratory zone, hot cell area, and waste handling area. Each CAM draws air through a filter paper at 1-3 m3/h, with alpha/beta discrimination using solid-state silicon detectors. Provides real-time alarm on exceeding derived air concentration (DAC) limits per IRR17 and site-specific derived limits. Rolling radon/thoron compensation algorithms to minimise false alarms. Data transmitted to central radiation monitoring system and LIMS. |
| Alpha MCA and Pulse Processing Electronics | D4F51008 | Multi-channel analyser system with 8 independent ADC channels, one per detector, providing 1024-channel spectral resolution across 0-10 MeV energy range. Includes charge-sensitive preamplifiers, linear amplifiers with pole-zero cancellation, and pile-up rejection. Digital signal processing with <1 microsecond dead time per event. Connected to spectrum analysis software via USB/Ethernet for real-time spectrum accumulation and storage. |
| Alpha Source Loading and Sample Changer | D5A71218 | Automated sample changer mechanism for sequential loading of electrodeposited alpha source discs into the vacuum chambers. Accommodates up to 24 samples per carousel per chamber. Barcode reader identifies each source disc and links to LIMS sample record. Interlocked with vacuum system to prevent chamber opening during counting. Enables unattended overnight counting of large sample batches during reactor maintenance campaigns. |
| Alpha Spectrometry Vacuum Chamber System | DE851008 | Set of 8 individual vacuum chambers, one per PIPS detector, each achieving <10 Pa vacuum pressure within 5 minutes via rotary vane pump. Chambers accommodate electrodeposited source discs of 25mm diameter on adjustable shelves at 5-25mm source-to-detector distance. Constructed from aluminium alloy with quick-release sample loading mechanism. Vacuum prevents alpha particle energy loss in air, essential for spectral resolution. |
| Alpha Spectrum Analysis Software | 41BF7158 | Software system for automated alpha spectrum analysis including region-of-interest integration, peak deconvolution for overlapping multiplets (Pu-239/240, Am-241/Pu-238), efficiency calibration, yield correction using added tracer isotopes, uncertainty propagation per GUM methodology, and automated reporting of activity concentrations in Bq/g or Bq/L with combined measurement uncertainties. Interfaces with LIMS for result transfer. |
| Analytical Balance and Gravimetric Station | D4853018 | Precision weighing station within the Sample Receipt and Preparation Laboratory featuring a 5-decimal-place analytical balance (0.01 mg readability) housed in a draught-proof enclosure on a vibration-isolated bench. Used for gravimetric preparation of standard solutions, verification of sample masses for activity calculations, and preparation of calibration sources. Balance is calibrated against UKAS-traceable mass standards. Integral anti-static ioniser to eliminate electrostatic charging effects on fine powders. Environmental monitoring of temperature and humidity recorded with each weighing for measurement uncertainty budgets. Connected to LIMS for automatic data capture of mass readings. |
| Area Gamma Dose Rate Monitoring Network | 54E77050 | Fixed-position gamma dose rate monitoring network distributed throughout a UK nuclear dockyard radiochemistry laboratory. Comprises wall-mounted ionisation chamber and GM tube detectors covering active laboratories, hot cell operating areas, sample preparation rooms, waste handling areas, and access corridors. Provides continuous real-time dose rate measurements from 0.1 microsievert/h to 10 sievert/h across all occupied and controlled areas. Feeds centralised radiation monitoring display in the Health Physics office and triggers local audible/visual alarms at 7.5 microsievert/h (supervised area) and 2 millisievert/h (emergency evacuation). Connected via hardwired 4-20mA safety channels and Modbus TCP for data logging to LIMS. |
| Biological Shielding Structure | CE851018 | High-density concrete and steel composite shielding walls (typically 1.0-1.5m thick) forming the primary radiation barrier of a hot cell in a nuclear dockyard radiochemistry laboratory. Attenuates gamma radiation from irradiated reactor fuel samples and fission products (Co-60, Cs-137, Ce-144) to ensure external dose rates below 7.5 microsieverts per hour. Incorporates shielded penetrations for manipulator arms, ventilation ducts, sample transfer ports, and viewing windows. Designed for a 50+ year operational life with seismic qualification to ONR expectations. |
| Cell Decontamination System | D6C51018 | Fixed spray and wash-down system for decontaminating the interior surfaces of the hot cell during maintenance campaigns and prior to manned entry for manipulator boot replacement or equipment change-out. Includes ceiling-mounted spray nozzles delivering decontamination solutions (dilute nitric acid, citric acid, or proprietary formulations) at controlled flow rates, a sump and drain system collecting contaminated washings for transfer to the Active Effluent Treatment Plant, and a steam lance connection for stubborn contamination. Decontamination target: reduce surface contamination levels to below 4 Bq/cm2 alpha and 40 Bq/cm2 beta-gamma to permit limited manned access with appropriate PPE. |
| Centralised Radiation Monitoring Display and Alarm System | 54ED7B59 | Central monitoring and alarm annunciation system for a UK nuclear dockyard radiochemistry laboratory, housed in the Health Physics control room. Aggregates data from area gamma monitors, airborne contamination monitors, criticality warning system, ventilation stack monitors, effluent monitors, and personal dosimetry uploads. Provides SCADA-style graphical display showing real-time dose rates on facility floor plans, alarm status, trending, and historical data retrieval. Alarm management includes alarm acknowledgement, escalation to site emergency control if not acknowledged within configurable time window, and automatic event logging. Data historian stores minimum 10 years of monitoring records for regulatory reporting. Interfaces to LIMS for sample-correlated dose records. |
| Clean Room Sample Preparation Enclosure | D0851058 | ISO Class 5 (Class 100) laminar flow clean-room enclosure dedicated to ICP-MS sample preparation for ultra-trace actinide analysis. Contains HEPA-filtered vertical laminar flow benches, sub-boiling acid distillation system (Savillex DST-4000) producing ultra-pure HNO3 and HCl, PFA labware cleaned by acid vapour, and a dedicated microwave-assisted digestion system (CEM Mars 6 or equivalent) for dissolution of solid samples in HNO3/HF/HCl matrices. Positive pressure maintained relative to surrounding laboratory to prevent airborne contamination ingress. Located separate from the high-activity radiochemical separations laboratory to avoid cross-contamination of ultra-trace measurements from higher-activity routine samples. All surfaces are non-porous, acid-resistant, and cleanable to sub-ng/m² levels. |
| Concentrate and Sludge Handling System | DE853059 | Shielded system for collecting, storing, and transferring concentrated radioactive sludges and evaporator bottoms at a UK nuclear dockyard radiochemistry laboratory. Receives concentrate at 100-500 g/L total dissolved solids with activities up to 1E10 Bq/L from the evaporation unit. Concentrate is pumped via peristaltic pumps through shielded pipework to 200-litre stainless steel drums for interim storage and eventual cementation/encapsulation for disposal as Intermediate Level Waste (ILW). Includes shielded drum filling station with remote weighing, level measurement, and contamination containment. Designed for ILW conditioning compliant with UK Radioactive Waste Management Ltd packaging specifications. |
| Contamination Control and Waste Segregation Point | 44853850 | Designated area within the Sample Receipt and Preparation Laboratory where solid and liquid wastes generated during sample preparation are segregated by activity level and waste stream. Includes: a contamination monitoring portal for hands and clothing, a beta/gamma hand monitor, segregated waste bins for LLW solid waste (gloves, tissues, vials), exempt waste, and active liquid waste collection sump connected to the Active Drain Collection System. Also includes a change barrier between controlled and supervised areas. Surface contamination limits enforced at 4 Bq/cm² beta-gamma and 0.4 Bq/cm² alpha per IRR17 and local rules. Critical for preventing spread of contamination outside the preparation area. |
| Discharge Authorisation and Control System | 51BD3A51 | Programmable logic controller-based system for enforcing Environmental Agency discharge authorization limits at a UK nuclear dockyard radiochemistry laboratory active effluent treatment plant. Receives inputs from the effluent monitoring and sampling station, compares measured activity concentrations against permit limits for individual radionuclides (H-3, C-14, Co-60, Sr-90, Cs-137, total alpha), and controls the motorised discharge isolation valve. Maintains cumulative discharge records (daily, monthly, annual totals) for regulatory reporting. SIL-2 rated safety function for discharge isolation on high activity alarm. Includes operator HMI with discharge batch authorisation workflow requiring two-person authentication before any discharge to the controlled waters outfall. |
| Efficiency Calibration and QC Source Set | C6853058 | Set of UKAS-calibrated mixed-radionuclide reference sources for energy and efficiency calibration of HPGe gamma spectrometry detectors. Includes multi-line sources (Am-241 through Co-60, 59-1836 keV) in each counting geometry (1L Marinelli, 0.5L Marinelli, 90mm petri dish, 20mL vial) with activities traceable to NPL. QC check sources include Cs-137 and Co-60 point sources for daily energy and resolution verification. All sources have certified activities, reference dates, and expanded uncertainties (k=2). Managed through LIMS with automated QC charting of peak position, resolution, and efficiency stability against control limits. |
| Effluent Monitoring and Sampling Station | 55F77A59 | Pre-discharge effluent monitoring and sampling system at a UK nuclear dockyard radiochemistry laboratory. Provides continuous online gross alpha/beta activity measurement and automatic proportional sampling of treated effluent before any authorized discharge to the dockyard drainage system. NaI(Tl) gamma detector and gas-flow proportional alpha/beta counter on a bypass loop. Automatic composite sampler collecting flow-proportional samples over 24-hour periods for laboratory analysis against Environmental Agency discharge authorization limits. Discharge is blocked by interlocked isolation valve if online monitors exceed preset trip levels (typically 10% of monthly discharge limit). |
| Electrodeposition and Source Preparation Unit | 54D53219 | Multi-cell electrodeposition apparatus for plating separated actinide fractions (Pu, Am, U isotopes) onto polished stainless steel discs for alpha spectrometry measurement. Operates at controlled current density (typically 300-600 mA at 12V DC) in ammonium sulphate/sodium bisulphate electrolyte for 60-90 minutes per disc. Includes evaporation stations with infrared heat lamps and controlled hot plates for preparing beta counting sources by evaporating fractions onto stainless steel planchettes. Located within fume cupboards due to open handling of separated radionuclide solutions. Produces thin, uniform counting sources with <50 ug/cm2 deposit thickness for optimal alpha energy resolution. |
| Evaporation and Concentration Unit | 54D51219 | Forced-circulation thin-film evaporator for volume reduction of radioactive liquid effluent at a UK nuclear dockyard radiochemistry laboratory. Processes neutralised effluent at up to 500 L/hr, achieving volume reduction factors of 20:1 to 50:1. Operating temperature 80-105°C at sub-atmospheric pressure to minimise volatilisation of ruthenium and iodine species. Hastelloy C-276 wetted surfaces for corrosion resistance to mixed acid/alkali residues. Condensate routed to ion exchange polishing; concentrate routed to sludge handling. Includes demister pad, condenser, and condensate monitoring for carryover detection. |
| Extraction Chromatography Station | C4853018 | Dedicated bench-mounted separation station using Eichrom/Triskem extraction chromatography resins (UTEVA, TRU, Sr Spec, TEVA, DGA) for sequential isolation of actinides (Pu, Am, Cm, U, Np), strontium-90, and technetium-99 from dissolved sample matrices. Operates by gravity-fed or vacuum-box elution through pre-packed or hand-packed columns. Processes 10-50 mL sample aliquots in 8M HNO3 or 3M HCl matrices. Located within fume cupboards. Produces separated radionuclide fractions in specific acid matrices ready for electrodeposition or evaporation for counting source preparation. Throughput of 20-30 sample separations per week. |
| Gamma Spectrum Analysis and Nuclide Identification Software | 51FF3B58 | Dedicated gamma spectrum analysis software system (such as Genie 2000 or GammaVision) running on a networked workstation for the nuclear dockyard radiochemistry laboratory. Performs automated peak search, nuclide identification from a library of over 2000 gamma lines, efficiency calibration using polynomial or Monte Carlo methods, cascade summing correction, self-attenuation correction for varying sample densities, and decay correction to sampling date. Calculates activity concentrations with combined measurement uncertainty per GUM methodology. Outputs results to LIMS via automated data transfer. Maintains full audit trail of all calibrations, library edits, and analysis parameters per ISO 17025 requirements. |
| Glassware Decontamination and Quality Control Bay | 54851058 | Dedicated decontamination facility for reusable laboratory glassware and equipment used in the radiochemical separations laboratory of a UK nuclear dockyard. Equipped with ultrasonic cleaning baths (40kHz, heated to 60 degrees C), nitric acid soak tanks (2M HNO3), and a multi-stage rinse system terminating in deionised water. Includes a background monitoring rig with NaI(Tl) detector for screening decontaminated glassware to confirm activity levels below 0.4 Bq/cm2 for alpha and 4 Bq/cm2 for beta/gamma before return to service. Effluent from decontamination operations drains to the active laboratory drain system. Prevents cross-contamination between sample batches, which is critical for low-level environmental and bioassay analyses. |
| HEPA Filtration Bank | C6853058 | Multi-stage high-efficiency particulate air filtration system installed in the active extract ductwork upstream of the discharge stack. Comprises pre-filter stage (EU4/G4 panel filters for coarse particulate removal to protect HEPA filters) and two stages of HEPA filters in series, each achieving 99.97% efficiency at 0.3 micron MPPS per BS EN 1822. Filter housings are designed for in-situ DOP/PAO aerosol challenge testing to verify filter integrity. Includes differential pressure monitoring across each filter stage to indicate loading and detect breakthrough. Located in a dedicated filter room with controlled access for filter change-out as radioactive waste. |
| Hot Cell Facility | DE851059 | Shielded containment facility within a nuclear dockyard radiochemistry laboratory for handling high-activity samples that cannot be safely manipulated in fume cupboards. Typically 2-3 hot cells with 150-200mm lead-equivalent biological shielding, lead glass viewing windows (ZnBr2-filled for optical clarity under radiation), and master-slave manipulators (e.g., La Calhene MA23) for remote sample handling. Used for initial receipt and sub-sampling of highly active fuel element dissolution solutions, irradiated structural material samples, and high-activity resin bed samples. Cell interior maintained at negative pressure (-50 Pa relative to laboratory) with dedicated HEPA-filtered extract ventilation exhausting through the active stack. Transfer ports and airlocks for sample ingress/egress. Internal cell surfaces lined with stainless steel for decontamination. Radiation dose rate outside shielding <7.5 μSv/h during maximum foreseeable operations. |
| ICP-MS Analysis Suite | 54E53058 | Inductively coupled plasma mass spectrometry facility for ultra-trace elemental and isotopic analysis within a nuclear dockyard radiochemistry laboratory. Houses a quadrupole or sector-field ICP-MS instrument (e.g., Thermo iCAP or Element) for measuring uranium isotope ratios (U-234/U-235/U-238), plutonium mass concentrations, and trace fission product elements. Detection limits in the parts-per-trillion (ng/L) range. Argon plasma at 6000-8000K ionises dissolved samples introduced via pneumatic nebuliser. Mass resolution sufficient to separate isobaric interferences (e.g., UH+ on Pu-239). Clean room sample preparation area (ISO Class 6) to avoid environmental uranium contamination. Calibration using certified reference materials from IRMM/NIST. Instrument requires high-purity argon supply, chilled water, and extract ventilation for acid fume removal. |
| ICP-MS Calibration and Quality Control Standards Set | C0843058 | Certified reference materials and calibration standards for ICP-MS actinide and trace metal analysis. Includes multi-element calibration standard solutions (NIST SRM 3100-series single-element standards and mixed standards), isotope dilution spike solutions (U-233 and Pu-242 tracers for IDMS), certified reference materials for method validation (IAEA-385 Irish Sea sediment, IAEA-443 Irish Sea water, NIST SRM 4350B river sediment), and mass bias correction standards (IRMM-184 natural uranium isotopic standard, IRMM-085 Pu spike). Prepared gravimetrically in PFA vials with ultra-pure acids. Shelf-life tracked in LIMS. Traceability chain maintained to national metrology institutes (NPL, NIST, IRMM). |
| ICP-MS Data Processing and Isotope Ratio Software | 40A53B58 | Software suite for ICP-MS data reduction, isotope ratio calculation, and automated reporting. Comprises vendor instrument control software (MassHunter or Qtegra) for acquisition and peak integration, plus validated calculation spreadsheets for: mass bias correction using external normalisation or bracketing standards, polyatomic interference correction (e.g., UH+/Pu mass overlap at 239), isotope dilution mass spectrometry (IDMS) calculations for U and Pu quantification, and combined uncertainty budgets per GUM methodology. Generates activity concentration results from measured atom ratios using half-life data. Interfaces with LIMS for automated results transfer with full audit trail. Data archived per ONR/EA regulatory retention requirements (minimum 30 years for nuclear site records). |
| ICP-MS Sample Introduction and Autosampler System | D1C73018 | Automated sample introduction system for ICP-MS comprising: ASX-560 or similar 240-position autosampler with self-aspirating probe, peristaltic pump with PharMed tubing for consistent sample delivery at 0.3-1.0 mL/min, MicroMist concentric nebuliser for efficient aerosol generation, and Scott-type double-pass spray chamber (Peltier-cooled to 2°C) for droplet size selection. Includes internal standard mixing tee for on-line addition of Bi-209/In-115/Rh-103 internal standards to correct for matrix effects and instrument drift. All wetted surfaces are HF-resistant (PFA, PEEK) for handling HF-digested silicate samples. Rinse station with 2% HNO3/0.5% HCl for memory effect minimisation between actinide samples. Capable of processing 100+ samples per analytical run with <1% RSD precision. |
| ILW Conditioning and Encapsulation Plant | 50853A59 | Cement encapsulation facility for Intermediate Level Waste at a UK nuclear dockyard radiochemistry laboratory. Receives sorted ILW items (spent ion exchange resins, evaporator concentrates, contaminated equipment, hot cell waste) for immobilisation in cementitious grout within 500-litre stainless steel drums conforming to RWM (Radioactive Waste Management Ltd) specifications for eventual disposal in the UK Geological Disposal Facility. Process includes: waste loading into drums, ordinary Portland cement / blast furnace slag grout mixing and injection, vibration compaction to eliminate voids, 28-day cure period with temperature monitoring, lid welding and leak testing. Must meet the conditions specified in the Letter of Compliance from RWM including waste loading limits, grout formulation, package heat output, and fissile material content. Throughput approximately 2-3 drums per week during active campaigns. |
| In-Cell Dissolution and Chemical Processing Equipment | D6D51019 | Suite of remotely operated chemical process equipment inside the hot cell for dissolving irradiated reactor fuel and performing initial radiochemical separations. Includes a heated dissolution vessel (borosilicate glass or Hastalloy, 1-5L capacity) for dissolving fuel cladding and UO2 matrix in hot concentrated nitric acid (8-12M HNO3 at 90-110°C). Fume extraction from the dissolver captures NOx and iodine-129. Includes evaporators for solution concentration, liquid-liquid extraction contactors for initial U/Pu/FP separation, ion exchange columns for actinide purification, and calibrated dispensing equipment for preparing counting sources. All equipment manipulated via master-slave manipulators. |
| In-Cell Radiation Monitoring Instrumentation | D4E55058 | Fixed and portable radiation detection instruments installed within the hot cell for continuous monitoring of radiation fields, airborne contamination, and criticality safety. Includes ceiling-mounted gamma area monitors (ionisation chambers, range 0.1 microSv/h to 10 Sv/h) providing real-time dose rate display at the operator station, continuous air monitors (CAMs) sampling cell atmosphere for alpha/beta particulate with alarm setpoints, and a criticality incident detection system with neutron and gamma detectors providing automatic evacuation alarm. Monitors interface with the facility's central radiation monitoring system via hardwired 4-20mA signals for safety-critical channels and digital (Modbus/Ethernet) for logging channels. |
| In-Cell Ventilation Extract System | D5D73858 | Dedicated extract ventilation system maintaining negative pressure differential inside the hot cell relative to the surrounding operator area, forming the secondary containment barrier. Maintains at least -50 Pa depression to ensure airflow is always inward through any breach. Extracts through pre-filters and dual-stage HEPA filters (99.97% at 0.3 microns MPPS) before discharge to the main facility extract stack. Includes iodine adsorbers (activated carbon) for volatile radionuclide capture during dissolution of irradiated fuel. Provides minimum 6 air changes per hour. Interlocked with cell access controls to prevent entry when ventilation is lost. |
| Instrument Data Acquisition Gateway | 50A57118 | Middleware layer interfacing 15+ analytical instruments with the LIMS database in a nuclear dockyard radiochemistry lab. Collects raw spectral data and count rates from HPGe gamma spectrometers (Canberra Genie-2000), ICP-MS (Agilent MassHunter), liquid scintillation counters (PerkinElmer QuantaSmart), and alpha spectrometry (Ortec MAESTRO). Supports TCP/IP, RS-232, and file-based exchange. Applies calibration corrections, validates data (dead time, pile-up, background subtraction), and transfers to the central database. Store-and-forward buffering maintains integrity during communication failures. Handles approximately 200 analytical runs per day. |
| Interim Radioactive Waste Store | DE851259 | Shielded, ventilated, and environmentally monitored storage facility for conditioned radioactive waste packages at a UK nuclear dockyard radiochemistry laboratory. Provides segregated storage for: LLW packages (compacted drums in HHISO containers) awaiting scheduled collections to LLWR, ILW packages (500-litre grouted drums) awaiting availability of the UK Geological Disposal Facility (potentially decades of interim storage), and decay-storage items (VLLW held for radioactive decay before clearance). Structural design to ONR Safety Assessment Principles for Category 1 nuclear facility. Includes overhead crane for package handling rated at 5 tonnes, stackable drum storage racks for 3-high stacking of 500-litre drums, seismic restraints, continuous air extract with HEPA filtration, sump and leak detection, and area radiation monitoring. Storage capacity sized for 30 years of facility waste arisings. Package inspection capability for periodic condition monitoring of ILW drums. |
| Iodine Adsorption Unit | C6851019 | Activated carbon adsorber beds installed in the active extract ductwork downstream of HEPA filters, specifically for removal of radioiodine (I-131, I-129) in gaseous/vapour form that passes through HEPA particulate filters. Impregnated activated carbon (typically TEDA or KI impregnated) achieving minimum 99% removal efficiency for methyl iodide at 30 degrees C and 70% RH. Critical for nuclear facility ventilation because radioiodine is volatile and not captured by particulate filters. Bed depth and residence time sized for the expected iodine loading from dissolution of irradiated fuel samples in the hot cell. |
| Ion Exchange Treatment Columns | C6953019 | Multi-bed ion exchange system for selective removal of Cs-137, Sr-90, Co-60 and other radionuclides from condensate and low-activity effluent streams at a UK nuclear dockyard radiochemistry laboratory. Configuration: lead-lag-polishing arrangement with clinoptilolite for caesium, specific organic resin for strontium, and mixed-bed polishing column for residual activity. Each column 300mm diameter, 1.5m bed depth, with online gamma monitors at inlet and outlet to detect breakthrough. Resin change-out by hydraulic sluicing to shielded spent resin storage. Decontamination factors of 100-1000 per nuclide depending on feed composition. |
| Lead Glass Shielding Windows | CE851018 | High-density lead glass viewing windows (cerium-stabilised, density 4.2-6.2 g/cm3) installed in the biological shielding wall of a radiochemistry hot cell. Provide direct visual observation of in-cell operations while maintaining radiation attenuation equivalent to the surrounding concrete shielding. Typically 600-900mm thick depending on activity levels, with optical clarity sufficient for manipulator operations including pipetting and sample preparation. May include oil-filled multi-pane assemblies to prevent radiation-induced browning. Designed for replacement via shielded removal from the cold face. |
| Lead Shielding and Sample Chamber Assembly | CE851018 | Four individual lead shield castles providing passive gamma shielding for HPGe detectors in a nuclear dockyard radiochemistry laboratory. Each shield consists of 100mm thickness aged low-background lead (less than 25 Bq/kg Pb-210) in a cylindrical configuration with a removable top plug for sample loading. Inner cavity accommodates Marinelli beakers (0.5L and 1L), petri dishes, and gas vials. Graded liner of 1mm copper, 1mm tin, and 1mm aluminium absorbs lead X-ray fluorescence. Sample positioning is fixed by machined shelves at calibrated geometries. Each shield weighs approximately 800 kg and requires a dedicated concrete plinth. |
| LIMS Central Database Server | 50853158 | High-availability Oracle or SQL Server database cluster hosting all analytical data for a UK nuclear dockyard radiochemistry laboratory. Stores sample chain-of-custody records, analytical results with full uncertainty budgets, QC control chart data, instrument calibration histories, and regulatory discharge records. Configured as an active-passive failover pair with synchronous replication to meet ONR LC28 (examination and testing) record retention requirements of 30+ years. Handles approximately 5000 sample records per year with 50+ analytical parameters per sample. Database schema enforces referential integrity between sample receipt, preparation, analysis, and disposal records. Runs on hardened servers within the site's classified IT infrastructure with no direct external network connectivity. |
| LIMS Network Infrastructure and Cybersecurity Layer | 50A53858 | Dedicated network infrastructure for the LIMS serving a UK nuclear dockyard radiochemistry laboratory. Operates on a physically segregated network (separate from the dockyard's general IT and classified defence networks) in compliance with NIS Regulations and NCSC CAF. Comprises redundant Ethernet switches, two physical database servers in an active-passive cluster, UPS-backed power for all LIMS servers and network equipment, and a hardware firewall permitting only specific instrument data flows. No direct internet connectivity; software updates are applied via approved removable media following NCSC guidance. Implements role-based access control with Active Directory integration, network intrusion detection, and encrypted database connections (TLS 1.2+). Backup infrastructure writes encrypted daily database backups to an off-site tape archive at the dockyard's disaster recovery facility. |
| LIMS Operator Workstation Array | D68D1018 | Array of 8-10 dedicated LIMS client workstations distributed across a nuclear dockyard radiochemistry laboratory. Located in the sample reception bay, each analytical laboratory (gamma spec, alpha spec, LSC, ICP-MS, radiochemical separations), the hot cell control room, and the laboratory manager's office. Each workstation runs the LIMS client application with role-based access — sample reception staff can log and label samples but cannot modify analytical results; analysts can enter and review results for their own instruments; senior analysts can authorise results across multiple techniques. Workstations in active areas are ruggedised with sealed keyboards and wipe-clean screens for contamination control. All workstations connect to the LIMS network via Cat6 Ethernet; no wireless connectivity is permitted on the nuclear site. |
| LLW Compaction and Packaging System | DFD51019 | Hydraulic supercompactor system for volume reduction of Low Level Waste at a UK nuclear dockyard radiochemistry laboratory. Receives sorted compactable LLW (contaminated PPE, paper, plastics, filters) in 200-litre mild steel drums. Supercompactor provides 1500-tonne compaction force, producing pucks approximately 100mm high from standard 200-litre drums. Pucks are stacked into half-height ISO freight containers (HHISO) lined with grout for transport to the Low Level Waste Repository at Drigg, Cumbria. Includes automated drum feed conveyor, compaction chamber with splash guard, puck ejection and stacking mechanism, HHISO filling and grouting station, and local HEPA-filtered ventilation extract. Designed for a throughput of approximately 20 drums per shift. |
| LSC Spectrum Analysis and MDA Calculation Software | 40A53158 | Software system for liquid scintillation counting data processing, spectrum analysis, and reporting. Performs pulse shape analysis (PSA) for alpha/beta discrimination with misclassification rates below 0.1%, applies quench correction curves to convert count rates to absolute disintegration rates (DPM/Bq), calculates minimum detectable activities (MDAs) per ISO 11929 methodology, and generates LIMS-compatible result files. Handles spectrum deconvolution for mixed beta emitters (e.g., Sr-89/Sr-90 in the same sample). Supports TDCR efficiency calculation for absolute activity standardisation. Interfaces with the laboratory information management system for automated results transfer and audit trail maintenance. Vendor-supplied (QuantaSmart or MikroWin) with validated calculation spreadsheets for dockyard-specific methods. |
| Master-Slave Manipulator System | DEED1018 | Pair of mechanical through-wall master-slave manipulators (e.g., CRL Model F or equivalent) providing dexterous remote handling capability inside a radiochemistry hot cell. The operator controls master arms outside the shielding wall; slave arms replicate movements inside the cell to handle irradiated samples, pipette solutions, operate dissolution vessels, and transfer materials. Force-feedback enables tactile sensation of in-cell operations. Each arm provides 6+ degrees of freedom with a 10kg payload capacity at full extension. Tongs and tool attachments enable sample cutting, weighing, and chemical operations. Requires periodic decontamination and boot replacement. |
| Neutralisation and Chemical Dosing Plant | 57F73218 | Automated pH adjustment and chemical conditioning system for radioactive effluent at a UK nuclear dockyard radiochemistry laboratory. Receives batch transfers from storage tanks at pH 1-13. Doses sodium hydroxide, nitric acid, and ferric sulphate via metering pumps to achieve target pH 7-9 and co-precipitation of actinides before downstream treatment. Inline pH probes with triple redundancy, automatic dosing interlocks, and manual override. Agitated 2,000-litre conditioning vessel with residence time monitoring. All wetted parts 316L stainless steel or PTFE-lined. |
| Non-Destructive Assay System | 54E53058 | Quantitative radioactive waste characterisation system comprising a segmented gamma scanner (SGS) for 200-litre and 500-litre drummed waste, a high-resolution germanium (HPGe) gamma spectrometer for small items and samples, and a passive neutron coincidence counter for fissile material quantification. Located in the solid waste management area of a UK nuclear dockyard radiochemistry laboratory. Provides activity inventories and radionuclide fingerprints required for waste categorisation, transport documentation (IAEA transport regulations), and compliance with LLWR Conditions for Acceptance and RWM Letter of Compliance for ILW packages. Measurement uncertainty target: less than 20% at 2-sigma for major gamma-emitting radionuclides. SGS accommodates drum rotation and axial scanning with 12 or more segments. |
| Personal Dosimetry Management System | 54B57B59 | Electronic and passive personal dosimetry management system for radiation workers in a UK nuclear dockyard radiochemistry laboratory. Manages electronic personal dosemeters (EPDs) providing real-time dose and dose rate display, alarm functions at preset dose and dose rate thresholds, and automatic data upload via IR cradles on exit from controlled areas. Also manages passive TLD/OSL dosemeters issued to all classified workers for legal dose of record, processed by an approved dosimetry service. System tracks individual cumulative dose against annual dose constraints (typically 10 mSv/year investigation level, 20 mSv/year legal limit), generates CIDI (Central Index of Dose Information) returns, and interfaces with access control to prevent entry when dose limits approached. |
| PIPS Alpha Detector Array | D6C51018 | Array of 8 passivated implanted planar silicon (PIPS) detectors for alpha particle spectrometry. Each detector has 450mm² active area with 18 keV FWHM energy resolution at 5.486 MeV (Am-241). Operated under vacuum at ambient temperature. Detects alpha emissions from electrodeposited sources at distances of 5-25mm. Used for quantitative determination of Pu-238, Pu-239/240, Am-241, Cm-242/244, and U-234/238 in dockyard reactor and environmental samples. |
| Pressure Cascade Control System | 55F77818 | Automatic control system maintaining the pressure hierarchy across all laboratory zones. Monitors differential pressure across containment boundaries using pressure transmitters at each zone transition (corridor-to-lab, lab-to-fume-cupboard, lab-to-hot-cell). Modulates supply and extract fan speeds and damper positions to maintain required pressure differentials (10 Pa between non-active and active areas, 50 Pa across hot cell boundary). Includes alarm annunciation for pressure reversal or loss of containment. PLC-based control with local HMI and connection to building management system. |
| Quadrupole ICP-MS with Collision Reaction Cell | D4E53018 | Agilent 7900 or Thermo iCAP-class quadrupole inductively coupled plasma mass spectrometer with helium/hydrogen collision-reaction cell (KED mode) for polyatomic interference removal. Primary analytical technique for actinide isotopic analysis (U-234/235/238, Pu-239/240, Np-237, Am-241) and long-lived fission/activation products (Tc-99, I-129, Cs-135) at ultra-trace levels (sub-pg/mL) in nuclear dockyard decommissioning and environmental samples. Operated in a dedicated clean-room enclosure to prevent cross-contamination. Mass resolution sufficient to separate U-238 from Pu-238 with correction algorithms. Sensitivity >500 Mcps/ppm for uranium. Located on a vibration-isolated bench with temperature-controlled laboratory environment at 20±2°C. |
| Quality Assurance and Audit Trail Module | 40A57B58 | LIMS module implementing quality management for a UKAS-accredited nuclear dockyard radiochemistry laboratory operating under ISO 17025 and ONR licence conditions. Manages control charts (Shewhart and CUSUM) for all analytical methods, tracks instrument calibration schedules and results, records proficiency test participation (UKAS PT schemes, NPL intercomparisons), and maintains method validation documentation. Enforces electronic signatures compliant with MHRA Annex 11 and 21 CFR Part 11 for GMP-adjacent nuclear work. Generates complete audit trails recording every data modification with original value, new value, reason for change, user identity, and timestamp. Supports approximately 30 active analytical methods and 15 instruments requiring scheduled calibration. |
| Quench Correction and Calibration Standards Set | C2843058 | Set of sealed quench correction standards and traceable calibration sources for LSC performance verification and quantitative activity determination. Includes H-3 quench set (typically 10 sealed standards spanning SQP(E) range 1-800 with NIST/NPL-traceable activities), C-14 quench set, and unquenched reference standards for each radionuclide of interest. Used to generate quench correction curves mapping spectral quench parameter (SQP(E) or tSIE) to counting efficiency. Also includes background vials (cocktail-only blanks and distilled water blanks) for MDA determination. Standards replaced on a 2-3 year cycle due to vial wall adsorption effects. Stored in dedicated low-background counting positions. |
| Radiation Protection and Health Physics System | 54E57859 | Radiation protection monitoring and control system for a nuclear dockyard radiochemistry laboratory. Provides personal dosimetry (thermoluminescent dosimeters and electronic personal dosimeters for whole-body dose, finger dosimeters for extremity dose), installed area gamma monitors with local alarms and remote readout to a central control room, airborne contamination monitors (continuous air samplers with filter/moving-filter heads in active work areas), and surface contamination monitoring (hand-held alpha/beta/gamma probes for routine surveys). Administers the controlled area regime: designated areas, active change barriers, personal contamination monitoring at exit points using hand-and-clothing monitors. Maintains dose records per the Ionising Radiations Regulations 2017 and reports to the Health and Safety Executive. ALARP assessments for all new or modified operations. Criticality detection and alarm system in areas where fissile material accumulation is credible. Calibration of all radiation monitoring instruments traceable to national standards. |
| Radio Chemistry Laboratory for a UK Nuclear Dockyard | 54853859 | A radiochemistry laboratory facility located within a UK Royal Navy nuclear dockyard (such as HMNB Devonport or Rosyth). The facility provides analytical radiochemistry services for submarine nuclear reactor maintenance, defueling, and refueling operations. It handles analysis of primary coolant water samples for fission product contamination (Cs-137, I-131, Co-60), activation product monitoring, fuel element integrity assessment, and radioactive waste characterization for disposal route determination. The laboratory operates under Office for Nuclear Regulation (ONR) oversight with Nuclear Site Licence conditions, ALARP principles for radiation dose management, and Defence Nuclear Safety Regulator (DNSR) governance. Key capabilities include alpha/beta/gamma spectrometry, liquid scintillation counting, radiochemical separations (ion exchange, solvent extraction), and inductively coupled plasma mass spectrometry (ICP-MS) for trace actinide analysis. The facility includes hot cells for high-activity sample handling, fume cupboards with HEPA-filtered extract ventilation, active liquid effluent treatment, and solid waste management systems. Environmental monitoring of gaseous and liquid discharges is mandatory under the Environmental Permitting Regulations. |
| Radiochemical Fume Cupboard Array | CE851059 | Bank of six BS EN 14175-compliant fume cupboards rated for handling open radioactive sources in a UK nuclear dockyard radiochemistry laboratory. Each unit provides primary containment for acid digestion, evaporation, solvent extraction, and liquid transfer operations on dissolved nuclear fuel and activation product samples. Maintained at minimum 0.5 m/s face velocity with HEPA-filtered extract connecting to the active area ventilation system. Constructed from chemical-resistant polypropylene liners with integrated drip trays draining to the active laboratory drain system. Fitted with services including deionised water, compressed air, and three acid-resistant drainage points per unit. |
| Radiological Access Control System | 50BF7A59 | Electronic access control system governing entry to and exit from controlled and supervised radiation areas in a UK nuclear dockyard radiochemistry laboratory. Integrates with personal dosimetry system to enforce dose-based entry restrictions — prevents controlled area access when cumulative dose exceeds investigation level (10 mSv). Card/biometric access readers at each zone transition point with interlocked turnstiles. Maintains entry/exit log with timestamps and dose readings. Emergency override capability for evacuation scenarios with automatic logging. Interfaces with facility-wide security and emergency mustering systems. |
| Reagent Storage and Dispensing System | D6853859 | COSHH-compliant chemical storage and dispensing facility for the radiochemical separations laboratory at a UK nuclear dockyard. Comprises acid-resistant polypropylene cabinets with integral extract ventilation for storing concentrated mineral acids (11.5M HCl, 15.8M HNO3, 29M HF, 11.6M HClO4) and organic solvents. Includes calibrated automatic dispensers for routine acid dilutions, deionised water supply with resistivity monitoring (>18 MOhm-cm), and a secure controlled store for radioactive tracer solutions (Pu-236, Am-243, Np-237, Sr-85, Ba-133) and certified reference materials. All reagent containers barcoded and tracked in LIMS with expiry date monitoring. Bunded to 110% of largest container volume per DSEAR requirements. |
| Regulatory Compliance and Discharge Reporting Module | 40A77B59 | LIMS module generating regulatory reports for a UK nuclear dockyard radiochemistry laboratory. Produces quarterly and annual discharge reports for the Environment Agency under the Environmental Permitting Regulations, tracks cumulative discharges against site permit limits for liquid and gaseous effluents, generates REPPIR (Radiation Emergency Preparedness and Public Information Regulations) data submissions, and produces ONR periodic safety review input data. Aggregates analytical results by discharge pathway (stack, liquid effluent, solid waste) and calculates site-total activities by radionuclide. Implements automatic alerts when cumulative discharge reaches 80% and 90% of annual permit limits. Must retain records for minimum 30 years in compliance with nuclear site licence conditions. |
| Results Validation and Reporting Engine | 50E77B58 | Core LIMS calculation and reporting engine for a nuclear dockyard radiochemistry laboratory. Performs automated activity calculations with full uncertainty propagation (Type A and Type B combined using GUM methodology), minimum detectable activity (MDA) calculations per ISO 11929, decay corrections to reference dates, and isotope ratio computations. Implements multi-level review workflow: analyst submits, senior analyst reviews, laboratory manager authorises. Generates certificate-of-analysis reports formatted for dockyard operations, regulatory submissions to ONR and Environment Agency, and OSPAR convention reporting. Supports configurable report templates per sample type (reactor coolant, swipe, environmental, waste characterisation). Must reproduce calculation results identically on re-execution. |
| Sample Drying and Ashing Oven | D4D51218 | Dual-purpose thermal processing equipment within the Sample Receipt and Preparation Laboratory for drying and ashing solid radioactive samples prior to radiochemical analysis. Comprises a forced-air drying oven (up to 110°C) for moisture removal and a muffle furnace (up to 900°C) for ashing organic matrices (soil, vegetation, biota, filters). Both units are ducted to the active area extract system via HEPA-filtered connections to capture any released particulate activity during thermal processing. Equipped with programmable temperature controllers and over-temperature safety trips. Processing capacity: approximately 20 samples per batch. Essential for gravimetric determination of dry mass and for concentrating radionuclides in low-activity environmental samples. |
| Sample Logging and Labelling Station | 54AD7A58 | Workstation within the Sample Receipt and Preparation Laboratory where incoming samples are formally registered, assigned unique identifiers (barcoded), and entered into the Laboratory Information Management System (LIMS). Equipped with barcode printer, barcode scanner, PC terminal running LIMS client, and balance for initial mass verification. Each sample record captures: origin location, date/time of collection, requested analyses, expected radionuclide inventory, dose rate at 1m, sample matrix (liquid/solid/swab/filter), and chain-of-custody signoff. Processes approximately 50-100 samples per week. Critical for regulatory traceability under ONR and EA requirements. |
| Sample Preparation Fume Cupboard | D2851059 | Ducted fume cupboard rated for handling open radioactive materials up to 100 MBq total activity. Used for initial sample preparation operations including: acid digestion of solid samples, dilution of liquid samples to working concentrations, filtration, evaporation, and aliquoting into counting geometries (Marinelli beakers, planchettes, liquid scintillation vials). Constructed with stainless steel liner, acid-resistant work surface, and integral HEPA filtration on the extract duct. Face velocity maintained at 0.5 m/s minimum per BS EN 14175. Connected to the active area extract ventilation system. Located within the controlled area of the preparation laboratory. |
| Sample Receipt and Preparation Laboratory | 00843A59 | Front-end facility within a nuclear dockyard radiochemistry laboratory responsible for receiving, logging, and preparing radioactive samples for analysis. Handles primary coolant water samples from submarine PWR circuits, swab samples from contamination surveys, fuel element crud samples, and environmental monitoring samples (air filters, soil, marine sediment). Operates a chain-of-custody system compliant with GMP/GLP principles. Preparation operations include acidification, filtration, evaporation to dryness, ashing, acid digestion of solid matrices, and aliquoting. All work performed in designated controlled areas with fume cupboards. Typical throughput 20-50 samples per week during reactor maintenance campaigns. Sample tracking via barcoded containers interfacing with the LIMS. |
| Sample Reception Bay | 44851050 | Dedicated receiving area within the Sample Receipt and Preparation Laboratory of a UK nuclear dockyard radiochemistry facility. Receives primary samples from reactor compartments, fuel storage ponds, active effluent streams, and environmental monitoring locations. Features a shielded sample pass-through hatch with interlocked doors, dose rate monitoring at the reception point, and a decontamination area for outer packaging. Operates under negative pressure relative to corridors. Handles approximately 50-100 sample containers per week, ranging from 10ml liquid vials to 1-litre Marinelli beakers to solid swab samples. Must maintain chain-of-custody records from point of receipt. |
| Sample Storage Refrigerator Array | D6851018 | Temperature-controlled sample storage facility within the Sample Receipt and Preparation Laboratory consisting of multiple shielded refrigerators (2-8°C) and a freezer unit (-20°C) for preservation of biological and environmental samples awaiting analysis. Each unit is fitted with continuous temperature monitoring, alarm on excursion, and logged to LIMS. Refrigerators are lead-lined (5mm Pb equivalent) for dose rate reduction around stored active samples. Total capacity approximately 500 sample positions. Samples stored with secondary containment trays to capture any leakage. Used for samples requiring preservation of volatile radionuclides (tritium, iodine-131) and biological samples (urine, blood) from personal dosimetry programmes. |
| Sample Tracking and Chain of Custody Module | 40B57B58 | Software module managing complete sample lifecycle in a nuclear dockyard radiochemistry laboratory. Generates unique sample identifiers with barcode labels, records chain-of-custody transfers between 12 laboratory zones including hot cell, tracks sample location in real time, manages sample splitting with parent-child relationships, enforces hold times and analysis deadlines. Integrates with radiological access control to verify handler dosimetry and training. Supports priority flagging for emergency dockyard operations. Tracks 400-500 active samples with full audit trail. |
| Sample Transfer Port System | DE853018 | Shielded transfer ports and airlocks for moving irradiated samples and materials into and out of the hot cell without breaching the biological shielding barrier. Includes a shielded flask docking station for receiving transport flasks from the reactor, a small-item transfer drawer/airlock with interlocked double doors (inner cell door and outer face door cannot open simultaneously), and a pneumatic transfer line for moving dissolved sample aliquots to analytical instruments outside the cell. Each port maintains containment integrity and shielding continuity during transfer operations. Flask docking port accepts standard 50-100L shielded transport flasks. |
| Scintillation Cocktail and Vial Preparation Station | C6841018 | Dedicated preparation bench for mixing radioactive sample aliquots with liquid scintillation cocktails (Ultima Gold LLT for aqueous tritium samples, Ultima Gold AB for alpha/beta discrimination, Hionic-Fluor for high-salt matrices). Includes calibrated dispensers for reproducible cocktail volumes (10-15 mL), vial selection inventory (20 mL low-potassium borosilicate glass vials for low-background work, polyethylene vials for routine counting), and dark-adaptation storage rack to eliminate photo-luminescence before counting. Operates within a fume cupboard due to volatile cocktail components (pseudocumene, naphthalene). Located adjacent to the LSC counter array to minimise sample transfer distances. |
| Solid Radioactive Waste Management System | 42A53A5D | System for characterisation, segregation, packaging, and interim storage of solid radioactive waste generated by a nuclear dockyard radiochemistry laboratory. Waste streams include low-level waste (LLW: contaminated PPE, glassware, wipes, ion exchange resins, HEPA filters) and intermediate-level waste (ILW: hot cell components, highly contaminated equipment, spent sealed sources). Waste characterised by gamma spectrometry (drum scanner or segmented gamma scanner) and destructive analysis for non-gamma-emitting nuclides. Segregation by waste category per UK Radioactive Waste Management policy. LLW packaged in 200L drums or half-height ISO containers for consignment to the LLW Repository at Drigg. ILW conditioned (cemented or encapsulated) in shielded packages for interim storage pending geological disposal. Waste accounting system tracks radionuclide inventory per package. Fissile material mass limits per package enforced by criticality safety assessment. |
| Spent Sealed Source Management System | 40A53B59 | Dedicated management system for sealed radioactive sources used throughout the radiochemistry laboratory at a UK nuclear dockyard. The laboratory uses approximately 30-50 sealed sources across gamma spectrometry calibration (Eu-152, Ba-133, Cs-137, Co-60), alpha spectrometry (Am-241, Pu-239), liquid scintillation counting (H-3, C-14 standards), and instrument check sources. System includes: sealed source inventory register with location tracking, wipe test scheduling and results recording for leak detection (6-monthly per IRR17), source movement log, decay correction calculations, and end-of-life disposal routing (return to supplier, transfer to another licensee, or disposal as solid radioactive waste). Interfaces with the Radiation Protection system for source accountability and with the national Sealed Source Register held by the Environment Agency. Must comply with the High-Activity Sealed Radioactive Sources and Orphan Sources Regulations 2005 (HASS Regulations) where applicable. |
| Stack Monitoring Instrumentation | 54E57258 | Continuous radiation monitoring system installed on the ventilation discharge stack. Comprises isokinetic sampling probes extracting a representative sample from the stack airflow, particulate collection filter with alpha and beta detectors (typically scintillation or proportional counters), charcoal cartridge for iodine sampling, and flow measurement instrumentation. Provides real-time indication of stack discharge activity and triggers alarms at 10% of derived air concentration limits. Data logged to LIMS for regulatory discharge reporting. Calibrated against known sources with regular verification of isokinetic sampling conditions. |
| Surface Contamination Monitoring Equipment | D4CC1058 | Portable and fixed surface contamination monitoring instruments for a UK nuclear dockyard radiochemistry laboratory. Includes large-area proportional counters for alpha/beta surface contamination surveys (sensitivity below 0.4 Bq/cm2 alpha, below 4 Bq/cm2 beta), hand and clothing monitors at controlled area exits, and bench-top contamination monitors. Used for routine contamination surveys per IRR17 Regulation 18, barrier integrity checks, and pre-transfer clearance monitoring. |
| Tracer and Reference Standard Store | 42851058 | Environmentally controlled secure store for radioactive tracer solutions, certified reference materials, and quality control standards used by the radiochemical separations laboratory at a UK nuclear dockyard. Maintains temperature at 20 plus/minus 2 degrees C to preserve solution stability. Stores approximately 50 individual tracer and carrier solutions including Pu-236, Am-243, Cm-244, Np-237, Sr-85, Y-88, Ba-133, Fe-55 tracers and NIST/NPL-traceable activity standards. Each solution has a unique identifier tracked in LIMS with activity concentration, reference date, uncertainty, and expiry date. Access restricted to authorised radiochemists via proximity card. Compliant with IRR17 requirements for sealed and unsealed source accountability. Located outside the main separations area to minimise risk of contamination to reference materials. |
| Tritium Distillation and Electrolytic Enrichment System | 50951218 | Two-stage sample preparation system for ultra-low-level tritium analysis in nuclear dockyard environmental water samples. Stage 1: atmospheric-pressure water distillation to separate tritium (as HTO) from non-volatile radionuclides, dissolved salts, and organics — achieves radiochemical purity required for LSC measurement. Stage 2: solid polymer electrolyte (SPE) electrolytic enrichment cells concentrating tritium by a factor of 20-50x, enabling detection limits below 1 Bq/L for environmental monitoring compliance with RSA93/EPR10 discharge authorisations. Batch capacity of 24 cells, enrichment cycle of 5-7 days. Integrated with deuterium spike recovery measurement to verify enrichment factor for each batch. |
| Ultra-Low-Background Liquid Scintillation Counter Array | D6E71018 | Array of two or more Quantulus 1220-series ultra-low-background liquid scintillation counters with bismuth germanate (BGO) guard detector shielding and active cosmic veto. Used for quantitative activity measurement of pure beta emitters including H-3, C-14, Sr-90, Fe-55, Ni-63, S-35, and P-32 in nuclear dockyard environmental and operational samples. Triple-to-double coincidence ratio (TDCR) capability for absolute activity determination. Background count rates below 1 CPM in the tritium window. Automated 300-vial sample changers for batch processing. Temperature-stabilised counting chambers at 15°C to minimise chemiluminescence. |
| Ventilation and Containment System | 55D73859 | Active extract ventilation and containment barrier system for the nuclear dockyard radiochemistry laboratory. Provides a hierarchy of containment barriers: primary (gloveboxes, hot cells), secondary (fume cupboards), and tertiary (laboratory rooms maintained at negative pressure cascade). Active extract ventilation system draws air through HEPA filters (minimum 99.97% efficiency at 0.3 μm MPPS) before discharge through a monitored stack. Stack height and discharge rate designed to meet derived limits from site-specific atmospheric dispersion modelling. Continuous stack monitoring for particulate alpha/beta activity and iodine-131 (charcoal cartridge samplers). Standby fans and emergency diesel-backed power for ventilation continuity. Fume cupboard face velocity 0.5 m/s ±10%. System designed to UK nuclear industry standard SHWG Guide 4 for ventilation of nuclear facilities. Pre-filters upstream of HEPA to extend HEPA filter life. DOP/PAO in-situ HEPA filter integrity testing annually. |
| Ventilation Discharge Stack | CE851010 | The final discharge point for all active ventilation extract air from the radiochemistry laboratory. A vertical stack typically 15-25m height to provide adequate atmospheric dispersion. Incorporates isokinetic sampling probes for continuous particulate alpha, beta, and I-131 monitoring (feeding the stack monitoring instrumentation). Stack velocity and diameter designed to achieve adequate plume rise and dispersion to meet Environmental Permit discharge limits at the site boundary. Constructed of stainless steel or GRP to resist corrosion from trace acid vapours. |
| Waste Sorting and Segregation Facility | 44853259 | Shielded sorting area within the solid radioactive waste management system of a UK nuclear dockyard radiochemistry laboratory. Receives solid waste from hot cells, fume cupboards, analytical laboratories, and maintenance operations. Operators sort waste into categories: Very Low Level Waste (VLLW) for on-site decay storage or landfill disposal, Low Level Waste (LLW) compactable and non-compactable streams for LLWR disposal, and Intermediate Level Waste (ILW) for conditioning and eventual GDF disposal. Equipped with local shielding, dedicated extract ventilation, hand-held contamination monitors, and dose rate instruments for initial characterisation at the point of sorting. Throughput sized for approximately 50 waste items per day during routine dockyard refitting operations. |
| Waste Tracking and Records System | 40A57B59 | Electronic cradle-to-grave radioactive waste tracking system at a UK nuclear dockyard radiochemistry laboratory. Assigns a unique identifier to every waste item at point of generation, tracking through sorting, characterisation, conditioning, packaging, storage, and eventual disposal. Maintains a complete data record per package: waste description, generator, date of arising, radionuclide inventory (from NDA and laboratory analysis), physical form, conditioning method, package type, storage location, and disposal route. Interfaces with the Laboratory Information Management System for analytical results, the Non-Destructive Assay System for measured activity data, and the national UK Radioactive Waste Inventory (UKRWI) for periodic reporting to NDA. Supports barcode and RFID scanning for package tracking in the waste store. Must maintain records for a minimum of 150 years per ONR and EA regulatory requirements for ILW packages destined for geological disposal. |
| Component | Belongs To |
|---|---|
| Sample Receipt and Preparation Laboratory | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Gamma Spectrometry Suite | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Alpha Spectrometry Laboratory | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Liquid Scintillation Counting Facility | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| ICP-MS Analysis Suite | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Radiochemical Separations Laboratory | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Hot Cell Facility | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Ventilation and Containment System | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Active Effluent Treatment Plant | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Solid Radioactive Waste Management System | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Radiation Protection and Health Physics System | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Laboratory Information Management System | Radio Chemistry Laboratory for a UK Nuclear Dockyard |
| Biological Shielding Structure | Hot Cell Facility |
| Master-Slave Manipulator System | Hot Cell Facility |
| Lead Glass Shielding Windows | Hot Cell Facility |
| In-Cell Ventilation Extract System | Hot Cell Facility |
| Sample Transfer Port System | Hot Cell Facility |
| In-Cell Dissolution and Chemical Processing Equipment | Hot Cell Facility |
| In-Cell Radiation Monitoring Instrumentation | Hot Cell Facility |
| Cell Decontamination System | Hot Cell Facility |
| Active Drain Collection System | Active Effluent Treatment Plant |
| Active Effluent Storage Tanks | Active Effluent Treatment Plant |
| Neutralisation and Chemical Dosing Plant | Active Effluent Treatment Plant |
| Evaporation and Concentration Unit | Active Effluent Treatment Plant |
| Ion Exchange Treatment Columns | Active Effluent Treatment Plant |
| Effluent Monitoring and Sampling Station | Active Effluent Treatment Plant |
| Concentrate and Sludge Handling System | Active Effluent Treatment Plant |
| Discharge Authorisation and Control System | Active Effluent Treatment Plant |
| Supply Air Handling Unit | Ventilation and Containment System |
| Active Area Extract System | Ventilation and Containment System |
| HEPA Filtration Bank | Ventilation and Containment System |
| Ventilation Discharge Stack | Ventilation and Containment System |
| Pressure Cascade Control System | Ventilation and Containment System |
| Iodine Adsorption Unit | Ventilation and Containment System |
| Stack Monitoring Instrumentation | Ventilation and Containment System |
| Area Gamma Dose Rate Monitoring Network | Radiation Protection and Health Physics System |
| Airborne Contamination Monitoring System | Radiation Protection and Health Physics System |
| Surface Contamination Monitoring Equipment | Radiation Protection and Health Physics System |
| Personal Dosimetry Management System | Radiation Protection and Health Physics System |
| Radiological Access Control System | Radiation Protection and Health Physics System |
| Criticality Warning System | Radiation Protection and Health Physics System |
| Centralised Radiation Monitoring Display and Alarm System | Radiation Protection and Health Physics System |
| Waste Sorting and Segregation Facility | Solid Radioactive Waste Management System |
| Non-Destructive Assay System | Solid Radioactive Waste Management System |
| LLW Compaction and Packaging System | Solid Radioactive Waste Management System |
| ILW Conditioning and Encapsulation Plant | Solid Radioactive Waste Management System |
| Interim Radioactive Waste Store | Solid Radioactive Waste Management System |
| Waste Tracking and Records System | Solid Radioactive Waste Management System |
| Spent Sealed Source Management System | Solid Radioactive Waste Management System |
| Sample Reception Bay | Sample Receipt and Preparation Laboratory |
| Sample Logging and Labelling Station | Sample Receipt and Preparation Laboratory |
| Sample Preparation Fume Cupboard | Sample Receipt and Preparation Laboratory |
| Analytical Balance and Gravimetric Station | Sample Receipt and Preparation Laboratory |
| Sample Storage Refrigerator Array | Sample Receipt and Preparation Laboratory |
| Sample Drying and Ashing Oven | Sample Receipt and Preparation Laboratory |
| Contamination Control and Waste Segregation Point | Sample Receipt and Preparation Laboratory |
| Acid Digestion System | Sample Receipt and Preparation Laboratory |
| Radiochemical Fume Cupboard Array | Radiochemical Separations Laboratory |
| Extraction Chromatography Station | Radiochemical Separations Laboratory |
| Electrodeposition and Source Preparation Unit | Radiochemical Separations Laboratory |
| Reagent Storage and Dispensing System | Radiochemical Separations Laboratory |
| Active Laboratory Drain and Effluent Segregation System | Radiochemical Separations Laboratory |
| Glassware Decontamination and Quality Control Bay | Radiochemical Separations Laboratory |
| Tracer and Reference Standard Store | Radiochemical Separations Laboratory |
| HPGe Detector Array | Gamma Spectrometry Suite |
| Lead Shielding and Sample Chamber Assembly | Gamma Spectrometry Suite |
| Gamma Spectrum Analysis and Nuclide Identification Software | Gamma Spectrometry Suite |
| Efficiency Calibration and QC Source Set | Gamma Spectrometry Suite |
| PIPS Alpha Detector Array | Alpha Spectrometry Laboratory |
| Alpha Spectrometry Vacuum Chamber System | Alpha Spectrometry Laboratory |
| Alpha MCA and Pulse Processing Electronics | Alpha Spectrometry Laboratory |
| Alpha Spectrum Analysis Software | Alpha Spectrometry Laboratory |
| Alpha Source Loading and Sample Changer | Alpha Spectrometry Laboratory |
| Ultra-Low-Background Liquid Scintillation Counter Array | Liquid Scintillation Counting Facility |
| Scintillation Cocktail and Vial Preparation Station | Liquid Scintillation Counting Facility |
| Tritium Distillation and Electrolytic Enrichment System | Liquid Scintillation Counting Facility |
| Quench Correction and Calibration Standards Set | Liquid Scintillation Counting Facility |
| LSC Spectrum Analysis and MDA Calculation Software | Liquid Scintillation Counting Facility |
| Quadrupole ICP-MS with Collision Reaction Cell | ICP-MS Analysis Suite |
| ICP-MS Sample Introduction and Autosampler System | ICP-MS Analysis Suite |
| Clean Room Sample Preparation Enclosure | ICP-MS Analysis Suite |
| ICP-MS Calibration and Quality Control Standards Set | ICP-MS Analysis Suite |
| ICP-MS Data Processing and Isotope Ratio Software | ICP-MS Analysis Suite |
| LIMS Central Database Server | Laboratory Information Management System |
| Instrument Data Acquisition Gateway | Laboratory Information Management System |
| Sample Tracking and Chain of Custody Module | Laboratory Information Management System |
| Results Validation and Reporting Engine | Laboratory Information Management System |
| Quality Assurance and Audit Trail Module | Laboratory Information Management System |
| Regulatory Compliance and Discharge Reporting Module | Laboratory Information Management System |
| LIMS Network Infrastructure and Cybersecurity Layer | Laboratory Information Management System |
| LIMS Operator Workstation Array | Laboratory Information Management System |
| From | To |
|---|---|
| Sample Transfer Port System | In-Cell Dissolution and Chemical Processing Equipment |
| Master-Slave Manipulator System | In-Cell Dissolution and Chemical Processing Equipment |
| In-Cell Ventilation Extract System | Ventilation and Containment System |
| In-Cell Radiation Monitoring Instrumentation | Radiation Protection and Health Physics System |
| Cell Decontamination System | Active Effluent Treatment Plant |
| Sample Transfer Port System | Sample Receipt and Preparation Laboratory |
| Active Drain Collection System | Active Effluent Storage Tanks |
| Active Effluent Storage Tanks | Neutralisation and Chemical Dosing Plant |
| Neutralisation and Chemical Dosing Plant | Evaporation and Concentration Unit |
| Evaporation and Concentration Unit | Ion Exchange Treatment Columns |
| Evaporation and Concentration Unit | Concentrate and Sludge Handling System |
| Ion Exchange Treatment Columns | Effluent Monitoring and Sampling Station |
| Effluent Monitoring and Sampling Station | Discharge Authorisation and Control System |
| Supply Air Handling Unit | Pressure Cascade Control System |
| Active Area Extract System | HEPA Filtration Bank |
| HEPA Filtration Bank | Iodine Adsorption Unit |
| Iodine Adsorption Unit | Ventilation Discharge Stack |
| Ventilation Discharge Stack | Stack Monitoring Instrumentation |
| Pressure Cascade Control System | Active Area Extract System |
| Stack Monitoring Instrumentation | Radiation Protection and Health Physics System |
| Area Gamma Dose Rate Monitoring Network | Centralised Radiation Monitoring Display and Alarm System |
| Airborne Contamination Monitoring System | Centralised Radiation Monitoring Display and Alarm System |
| Criticality Warning System | Centralised Radiation Monitoring Display and Alarm System |
| Personal Dosimetry Management System | Radiological Access Control System |
| Personal Dosimetry Management System | Centralised Radiation Monitoring Display and Alarm System |
| Surface Contamination Monitoring Equipment | Centralised Radiation Monitoring Display and Alarm System |
| Airborne Contamination Monitoring System | Pressure Cascade Control System |
| Centralised Radiation Monitoring Display and Alarm System | Laboratory Information Management System |
| Waste Sorting and Segregation Facility | Non-Destructive Assay System |
| Waste Sorting and Segregation Facility | LLW Compaction and Packaging System |
| Waste Sorting and Segregation Facility | ILW Conditioning and Encapsulation Plant |
| Non-Destructive Assay System | Waste Tracking and Records System |
| LLW Compaction and Packaging System | Interim Radioactive Waste Store |
| ILW Conditioning and Encapsulation Plant | Interim Radioactive Waste Store |
| Waste Tracking and Records System | Laboratory Information Management System |
| Waste Tracking and Records System | Interim Radioactive Waste Store |
| Spent Sealed Source Management System | Radiation Protection and Health Physics System |
| Waste Sorting and Segregation Facility | Hot Cell Facility |
| ILW Conditioning and Encapsulation Plant | Active Effluent Treatment Plant |
| Sample Reception Bay | Sample Logging and Labelling Station |
| Sample Logging and Labelling Station | Sample Storage Refrigerator Array |
| Sample Storage Refrigerator Array | Sample Preparation Fume Cupboard |
| Sample Preparation Fume Cupboard | Acid Digestion System |
| Sample Preparation Fume Cupboard | Analytical Balance and Gravimetric Station |
| Sample Drying and Ashing Oven | Acid Digestion System |
| Acid Digestion System | Contamination Control and Waste Segregation Point |
| Sample Preparation Fume Cupboard | Contamination Control and Waste Segregation Point |
| Sample Logging and Labelling Station | Laboratory Information Management System |
| Sample Preparation Fume Cupboard | Active Area Extract System |
| Contamination Control and Waste Segregation Point | Active Drain Collection System |
| Sample Drying and Ashing Oven | Active Area Extract System |
| Reagent Storage and Dispensing System | Radiochemical Fume Cupboard Array |
| Extraction Chromatography Station | Radiochemical Fume Cupboard Array |
| Extraction Chromatography Station | Electrodeposition and Source Preparation Unit |
| Electrodeposition and Source Preparation Unit | Radiochemical Fume Cupboard Array |
| Radiochemical Fume Cupboard Array | Active Laboratory Drain and Effluent Segregation System |
| Glassware Decontamination and Quality Control Bay | Radiochemical Fume Cupboard Array |
| Glassware Decontamination and Quality Control Bay | Active Laboratory Drain and Effluent Segregation System |
| Tracer and Reference Standard Store | Extraction Chromatography Station |
| Active Laboratory Drain and Effluent Segregation System | Active Effluent Treatment Plant |
| Radiochemical Fume Cupboard Array | Active Area Extract System |
| Electrodeposition and Source Preparation Unit | Alpha Spectrometry Laboratory |
| Extraction Chromatography Station | Liquid Scintillation Counting Facility |
| Extraction Chromatography Station | ICP-MS Analysis Suite |
| Extraction Chromatography Station | Gamma Spectrometry Suite |
| Tracer and Reference Standard Store | Laboratory Information Management System |
| Reagent Storage and Dispensing System | Laboratory Information Management System |
| Sample Receipt and Preparation Laboratory | Radiochemical Separations Laboratory |
| HPGe Detector Array | Lead Shielding and Sample Chamber Assembly |
| HPGe Detector Array | Gamma Spectrum Analysis and Nuclide Identification Software |
| Efficiency Calibration and QC Source Set | HPGe Detector Array |
| Gamma Spectrum Analysis and Nuclide Identification Software | Laboratory Information Management System |
| PIPS Alpha Detector Array | Alpha Spectrometry Vacuum Chamber System |
| Alpha Spectrometry Vacuum Chamber System | Alpha Source Loading and Sample Changer |
| PIPS Alpha Detector Array | Alpha MCA and Pulse Processing Electronics |
| Alpha MCA and Pulse Processing Electronics | Alpha Spectrum Analysis Software |
| Alpha Spectrum Analysis Software | Laboratory Information Management System |
| Alpha Source Loading and Sample Changer | Laboratory Information Management System |
| Electrodeposition and Source Preparation Unit | Alpha Source Loading and Sample Changer |
| Scintillation Cocktail and Vial Preparation Station | Ultra-Low-Background Liquid Scintillation Counter Array |
| Tritium Distillation and Electrolytic Enrichment System | Scintillation Cocktail and Vial Preparation Station |
| Quench Correction and Calibration Standards Set | Ultra-Low-Background Liquid Scintillation Counter Array |
| Ultra-Low-Background Liquid Scintillation Counter Array | LSC Spectrum Analysis and MDA Calculation Software |
| LSC Spectrum Analysis and MDA Calculation Software | Laboratory Information Management System |
| Radiochemical Separations Laboratory | Scintillation Cocktail and Vial Preparation Station |
| Clean Room Sample Preparation Enclosure | ICP-MS Sample Introduction and Autosampler System |
| ICP-MS Sample Introduction and Autosampler System | Quadrupole ICP-MS with Collision Reaction Cell |
| ICP-MS Calibration and Quality Control Standards Set | ICP-MS Sample Introduction and Autosampler System |
| Quadrupole ICP-MS with Collision Reaction Cell | ICP-MS Data Processing and Isotope Ratio Software |
| ICP-MS Data Processing and Isotope Ratio Software | Laboratory Information Management System |
| Extraction Chromatography Station | Clean Room Sample Preparation Enclosure |
| Instrument Data Acquisition Gateway | LIMS Central Database Server |
| Sample Tracking and Chain of Custody Module | LIMS Central Database Server |
| Results Validation and Reporting Engine | LIMS Central Database Server |
| Quality Assurance and Audit Trail Module | LIMS Central Database Server |
| Regulatory Compliance and Discharge Reporting Module | LIMS Central Database Server |
| LIMS Operator Workstation Array | LIMS Network Infrastructure and Cybersecurity Layer |
| LIMS Network Infrastructure and Cybersecurity Layer | LIMS Central Database Server |
| Instrument Data Acquisition Gateway | LIMS Network Infrastructure and Cybersecurity Layer |
| Instrument Data Acquisition Gateway | Results Validation and Reporting Engine |
| Quality Assurance and Audit Trail Module | Instrument Data Acquisition Gateway |
| Results Validation and Reporting Engine | Regulatory Compliance and Discharge Reporting Module |
| Sample Tracking and Chain of Custody Module | Results Validation and Reporting Engine |
| Component | Output |
|---|---|
| In-Cell Dissolution and Chemical Processing Equipment | dissolved fuel solution aliquots |
| In-Cell Radiation Monitoring Instrumentation | dose rate and contamination alarm signals |
| Cell Decontamination System | contaminated liquid effluent |
| In-Cell Ventilation Extract System | filtered extract air to main stack |
| Evaporation and Concentration Unit | condensate for IX polishing and concentrate for sludge handling |
| Ion Exchange Treatment Columns | treated effluent below discharge limits |
| Effluent Monitoring and Sampling Station | activity measurement data and composite samples for lab analysis |
| Concentrate and Sludge Handling System | conditioned ILW drums for interim storage |
| Supply Air Handling Unit | conditioned supply air |
| Active Area Extract System | extracted contaminated air |
| HEPA Filtration Bank | HEPA-filtered extract air |
| Ventilation Discharge Stack | atmospheric discharge |
| Pressure Cascade Control System | pressure differential control signals |
| Iodine Adsorption Unit | iodine-depleted extract air |
| Stack Monitoring Instrumentation | discharge activity measurements and alarms |
| Area Gamma Dose Rate Monitoring Network | real-time gamma dose rate measurements and high dose rate alarms |
| Airborne Contamination Monitoring System | airborne alpha/beta particulate activity concentrations and DAC alarm signals |
| Surface Contamination Monitoring Equipment | surface contamination survey results for alpha and beta emitters |
| Personal Dosimetry Management System | individual cumulative dose records and dose investigation alerts |
| Criticality Warning System | criticality incident alarm actuation and evacuation signals |
| Centralised Radiation Monitoring Display and Alarm System | aggregated radiological status display and alarm management |
| Waste Sorting and Segregation Facility | categorised waste items routed to LLW compaction, ILW conditioning, or decay storage |
| Non-Destructive Assay System | quantitative radionuclide activity inventories and waste categorisation data |
| LLW Compaction and Packaging System | compacted LLW pucks in half-height ISO containers ready for LLWR transport |
| ILW Conditioning and Encapsulation Plant | grouted 500-litre ILW drums meeting RWM Letter of Compliance specifications |
| Interim Radioactive Waste Store | safe interim storage capacity for conditioned LLW and ILW packages |
| Waste Tracking and Records System | cradle-to-grave waste package records and UKRWI reporting data |
| Spent Sealed Source Management System | sealed source accountability records and disposal routing decisions |
| Sample Reception Bay | received and decontaminated sample containers with dose rate measurements |
| Sample Logging and Labelling Station | barcoded sample records in LIMS with chain-of-custody documentation |
| Sample Preparation Fume Cupboard | prepared sample aliquots in counting geometries ready for analysis |
| Analytical Balance and Gravimetric Station | traceable mass measurements and gravimetrically prepared standard solutions |
| Sample Storage Refrigerator Array | preserved samples maintained at controlled temperature with continuous monitoring records |
| Sample Drying and Ashing Oven | dried and ashed sample residues with recorded dry mass and ash mass data |
| Contamination Control and Waste Segregation Point | segregated waste streams and contamination clearance records |
| Acid Digestion System | dissolved sample solutions in acid matrix ready for radiochemical separation |
| Radiochemical Fume Cupboard Array | primary containment for open-source radiochemical operations with HEPA-filtered extract |
| Extraction Chromatography Station | separated radionuclide fractions in specific acid matrices for source preparation |
| Electrodeposition and Source Preparation Unit | thin-film alpha counting sources on steel discs and evaporated beta counting sources on planchettes |
| Reagent Storage and Dispensing System | quality-controlled reagents, tracers, and reference standards for radiochemical procedures |
| Active Laboratory Drain and Effluent Segregation System | segregated radioactive liquid waste streams routed to AETP collection |
| Glassware Decontamination and Quality Control Bay | verified-clean reusable glassware with surface activity below clearance levels |
| Tracer and Reference Standard Store | traceable radioactive tracer aliquots and certified reference material aliquots for analytical QC |
| HPGe Detector Array | digitised gamma pulse-height spectra with energy resolution better than 1.9 keV FWHM at 1332 keV |
| Lead Shielding and Sample Chamber Assembly | low-background counting environment with less than 1 count per second integral background 40-2000 keV |
| Gamma Spectrum Analysis and Nuclide Identification Software | quantitative radionuclide activity concentrations with combined measurement uncertainties and LIMS-ready data files |
| Efficiency Calibration and QC Source Set | traceable efficiency calibration curves and daily QC verification data |
| Ultra-Low-Background Liquid Scintillation Counter Array | raw scintillation pulse-height spectra with PSA alpha/beta discrimination data and count rates per energy window |
| Tritium Distillation and Electrolytic Enrichment System | electrolytically enriched water samples with 20-50x tritium concentration and verified deuterium spike recovery factors |
| LSC Spectrum Analysis and MDA Calculation Software | quantitative radionuclide activity results in Bq/L or Bq/kg with combined measurement uncertainties and MDAs per ISO 11929 |
| Quadrupole ICP-MS with Collision Reaction Cell | mass spectra with isotope count rates at sub-ppt detection limits for actinides and long-lived radionuclides |
| ICP-MS Data Processing and Isotope Ratio Software | mass-bias-corrected isotope ratios and IDMS activity concentrations with GUM uncertainty budgets |
| Clean Room Sample Preparation Enclosure | ultra-clean dissolved sample solutions in acid matrices with contamination below method detection limits |
| LIMS Central Database Server | persistent analytical records and audit data |
| Instrument Data Acquisition Gateway | validated instrument data streams |
| Sample Tracking and Chain of Custody Module | chain-of-custody records and sample status |
| Results Validation and Reporting Engine | authorised certificates of analysis |
| Quality Assurance and Audit Trail Module | control charts and compliance audit trails |
| Regulatory Compliance and Discharge Reporting Module | regulatory discharge and REPPIR reports |
| LIMS Network Infrastructure and Cybersecurity Layer | secure authenticated network connectivity |
| LIMS Operator Workstation Array | operator interaction and data entry |