The below abbreviations relate to both the website and the Preliminary Safety Report (PSR) document, which can be found in the Step 2 Documents library. The PSR itself contains a full glossary, which should be referred to when reading the submission.
| Abbreviation | Description |
|---|---|
| ABWR | Advance Boiling Water Reactor |
| AC | Alternating Current |
| ACC | Accumulator |
| ACI | American Concrete Institute |
| ACP | Auxiliary Control Panel |
| ACPR | Advanced Chinese Pressurized Reactor |
| ACT | Average Coolant Temperature |
| ADU | Adsorption & Demineralizing Units |
| AFCEN | French Association for Design, Construction and In-Service Inspection Rules for Nuclear Steam Supply System Components |
| AFFF | Aqueous Film-forming Foam Concentrate |
| AFoE | Annual Frequency of Exceedance |
| Ag-In-Cd | Silver-Indium-Cadmium |
| AI | Analogue Input |
| ALARP | As Low As Reasonably Practicable |
| ALARA | As Low As Reasonably Achievable |
| ANT | Advanced Nuclear Technology |
| AO | Analogue Output |
| AOO | Anticipated Operational Occurrence |
| AOPs | Abnormal Operating Procedures |
| AOT | Allowed Outage Time |
| APC | Airplane Crash |
| API | Axial Power Imbalance |
| ARI | All Rods In |
| ARO | All Rods Out |
| AS | Alloy Steel |
| ASEP | Accident Sequence Evaluation Program Human Reliability Analysis Procedure |
| ASF | Active Single Failure |
| ASME | American Society of Mechanical Engineers |
| AT | Auxiliary Transformer |
| ATWS | Anticipated Transient Without Scram |
| AVT | All Volatile Treatment |
| BAT | Best Available Technique |
| BSSD | Basic Safety Standards Directive |
| B 4 C | Boron Carbide |
| BDBA | Beyond Design Basis Accident |
| BE | Best Estimate |
| BGS | British Geological Survey |
| BNI | Balance of Nuclear Island |
| BOC | Beginning Of Cycle |
| BOL | Beginning Of Life |
| BOP | Balance of Plant |
| BP | Break Preclusion |
| BR | Battery Room |
| BRGM | Bureau de Recherches Géologiques et Minières |
| BSL | Basic Safety Level |
| BSO | Basic Safety Objective |
| BSS | Basic Safety Standards |
| BTA | Main Transformer Platform |
| BTP | Branch Technical Position |
| BU | Burnup |
| BUP | Back-up Panel |
| CAE | Claims ， Argument ， Evidence |
| CB 1 | Concentration of Boron |
| CB 2 | Core Barrel |
| C/C | Control of Containment |
| CCH | Core Cavity Height |
| CDF | Core Damage Frequency |
| CDM | Construction & Design Management |
| CET 1 | Containment Event Tree |
| CI | Conventional Island |
| C/I | Control of RCP water Inventory |
| CIC | Component Interface Cabinet |
| CISO | Chief Information Security Officer |
| CIPS | Crud Induced Power Shifts |
| C/P | Control of RCP pressure |
| C/R | Control of Reactivity |
| C/T | Control of RCP water Temperature |
| CCF | Common Cause Failure |
| CDF | Core Damage Frequency |
| CEFAS | Centre for Environment, Fisheries and Aquaculture Science |
| CFS | Capable Faulting Study |
| CFT | Cold Functional Test |
| CFTRVO | Cold Functional Test With Reactor Vessel Open |
| CGN | Chinese state-owned China General Nuclear Power Corporation |
| CHF | Critical Heat Flux |
| CIM | Component Interface Module |
| CL | Cold Leg |
| CNS | Civil Nuclear Security |
| COL | Crossover Leg |
| COMAH | Control of Major Accident Hazards |
| COT | Core Outlet Temperature |
| CP | Circulation Pump |
| CPR1000 | Chinese Pressurized Reactor |
| CPR1000 + | Chinese Improved Pressurized Reactor |
| CPU | Central Process Unit |
| CR | Computer Room |
| CRDM | Control Rod Drive Mechanism |
| CRGA | Control Rod Guide Assembly |
| CRGT | Control Rod Guide Tube |
| CS 1 | Carbon Steel |
| CS 2 | Core Support Structure |
| CSA | Conceptual Security Arrangements |
| CSP | Core Support Plant |
| CSR | Current Stress Regime |
| CTO | Chief Technical Officer |
| CW | Civil Works |
| CWP | Circulating Water Pump |
| CZP | Cold Zero Power |
| DAC 1 | Design Acceptance Confirmation |
| DAC 2 | Diverse Actuation Cabinet |
| DAS | Diverse Actuation System |
| DB | Dose Band |
| DBT | Design Basis Threat |
| DBA 1 | Design Basis Analysis |
| DBA 2 | Design Basis Accident |
| DBC | Design Basis Condition |
| DBE | Design Basis Earthquake |
| DBF | Design Basis Flood |
| DC | Direct Current |
| DCS | Digital Control System |
| DCH | Direct Containment Heating |
| DCO | Development Consent Order |
| DEC | Design Extension Condition |
| DEC-A | Design Extension Condition A |
| DEC-B | Design Extension Condition B |
| DEI | Dose Equivalent Iodine |
| DHP | Diverse Human interface Panel |
| DI | Digital Input |
| DL | Chinese Electrical Industrial Standards |
| DN | Nominal Diameter |
| DNB 1 | Departure from Nucleate Boiling |
| DNBR | Departure from Nucleate Boiling Ratio |
| DO | Digital Output |
| DP | Design Pressure |
| DPUR | Dose Per Unit Release |
| DR | Drive Rod |
| DRC | De-aerated Reactor Coolant |
| DSM | Defect Size Margin |
| DSO | Departmental Security Officer |
| DTC | Data Transmission Cabinet |
| EA | Environment Agency |
| EAST | Engineering Application Software Toolkit |
| EBA 1 | Enriched Boric Acid |
| EC | European Code |
| ECC | Emergency Core Cooling |
| ECCS | Emergency Core Cooling System |
| ECP | Emergency Control Panel |
| EDG | Emergency Diesel Generator |
| ED | Eddy Current |
| EDF | French state-owned Électricité de France (EDF) |
| EDF Energy | EDF Energy is a British subsidiary of EDF Group |
| EDF S. A. | Electricite de France |
| EDMG | Extended Damage Mitigation Guidance |
| EFPD | Equivalent Full Power Day |
| EFWP | Emergency Feedwater Pump |
| EHF | Engineering Principles-Human Factors |
| EIR | Environmental Impact Report |
| EJ | Chinese Standards for Nuclear Industry |
| ELLDS | E nd of L ife L imiting D efect S ize |
| EMC | Electromagnetic Compatibility |
| EMCL | Environmental Medic Concentration Limit |
| EMR | End of Manufacturing Report |
| EOC | End Of Cycle |
| EOF | Emergency Operation Facilities |
| EOL | End Of Life |
| EOMM | Equipment Operation and Maintenance Manuals |
| EN | European Norm |
| EOPs | Emergency Operating Procedures |
| EOGs | Emergency Operating Guidelines |
| EPR | Environmental Permitting Regulations |
| EPRI | The Electric Power Research Institute |
| EPRRSR | Environmental Permitting Regulations – Radioactive Substances Regulations |
| EPW | Explosion Pressure Wave |
| EQSs | Environmental Quality Standards |
| ESFAC | Engineered Safety Feature Actuation Cabinet |
| ESFAS | Engineered Safety Feature Actuation System |
| ETC | EPR Technical Codes |
| ETS | Emissions Trading Scheme |
| EU | European Union |
| EUR | European Utility Requirements |
| FA | Fuel Assembly |
| FAC | Flow-Accelerated Corrosion |
| F&B | Feed and Bleed |
| FCG | Fangchenggang Nuclear Power Plant |
| FCL | First Core Load |
| FCS | Field Control Station |
| FDF | Fuel Damage Frequency |
| F-Gas | Fluorinated Greenhouse Gases |
| FGC | Functional Group Control |
| FL | Full Load |
| FLCV | Full Load Control Valve |
| FLB | Feedwater Line Break |
| FLIV | Full Load Line Isolation Valve |
| FM | Fuel Management |
| FMEA | Failure Mode and Effects Analysis |
| FP | Full Power |
| FPST | Fault and Protection Schedule Table |
| FR | Fuel Rod |
| FRS | Floor Response Spectra |
| FSAR | Final Safety Analysis Report |
| FWH | Feedwater Heater |
| FWP | Feedwater Pump |
| GB | Chinese National Standards |
| GBD | Graphical Block Diagram |
| GC | Group Control |
| GCB | Generator Circuit Breaker |
| GDA | Generic Design Assessment |
| GDA JV | Generic Design Assessment Joint Venture |
| GDF | Geological Disposal Facility |
| GDS | Generator Disconnecting Switch |
| GEP | Generic Environmental Permit |
| GEP-RSR | Generic Environmental Permit-Radioactive Substance Regulation |
| GHG | Greenhouse Gas |
| GI | Ground Investigation |
| GIS | Graphical Information System |
| GMC | Ground Motion Characterisation |
| GMM | Ground Motion Model |
| GMPE | Ground Motion Prediction Equation |
| GNI | General Nuclear International Limited, UK subsidiary of CGN |
| GRCAs | Grey Rod Cluster Assemblies |
| GSR | Generic Security Report |
| GW | Gateway |
| HAD | Chinese Nuclear Safety Guidelines |
| HAF | Chinese Nuclear Safety Regulations |
| HVAC | Heating, Ventilation and Air Conditioning System |
| HAW | Higher Activity Waste |
| HBSC | Human-Based Safety Claim |
| HBSO | Human-Based Safety Objective |
| HCP | Hard Control Panel |
| HELB | High Energy Line Break |
| HEP | Human Error Probability |
| HEPA | High Efficiency Particulate Air Filter |
| HF | Human Factors |
| HFE | Human Factors Engineering |
| HFI | Human Factors Integration |
| HFP | Hot Full Power |
| HFT | Hot Functional Test |
| HIC | High Integrity Component |
| HIRE | Hazard Identification and Risk Evaluation |
| HL | Hot Leg |
| HLPD | High Linear Power Density |
| HLW | High Level Waste |
| HMG | Her Majesty’s Government |
| HOF | Human & Organisational Factors |
| HP | High Pressure |
| HPC | Hinkley Point C |
| HPME | High Pressure Melt Ejection |
| HPR1000 | Hua-long Pressurized Reactor |
| HPR1000 (FCG3) | Hua-long Pressurized Reactor under construction at Fangchenggang nuclear power plant unit 3 |
| HPS | High Pressure Steam |
| HPT | High Pressure Turbine |
| HRA | Human Reliability Analysis |
| H&S | Health & Safety |
| HSE | Health and Safety Executive |
| HSG | HSE Guidance Note |
| HSW Act | Health and Safety at Work etc Act 1974 |
| HT 1 | High Temperature |
| HT 2 | Heat treatment |
| HYH | Hongyanhe Nuclear Power Plant |
| HZP | Hot Zero Power |
| IAEA | International Atomic Energy Agency |
| IAOs | Information Asset Owners |
| I&C | Instrumentation and Control |
| ICI | Inside Containment Isolation |
| ICRP | International Commission on Radiological Protection |
| ID | Inner Diameter |
| iDAC | Interim Design Acceptance Confirmation |
| IE | Initiating Event |
| IEC | International Electrotechnical Commission |
| IED | Industrial Emissions Directive |
| IEEE | Institute of Electrical and Electronics Engineers |
| IFA | Irradiated Fuel Assemblies |
| IMS | Information Management System |
| I/O | Input/Output |
| IPS | Integrated Protection Solution |
| IRA | Initial Radiological Assessment |
| IT | Information Technique |
| IRWST | In-containment Refueling Water Storage Tank |
| ISI | In-Service Inspection |
| ISO | International Standard Organization |
| iSoDA | Interim Statement of Design Acceptability |
| IVR | In-Vessel Retention |
| JPO | Joint Project Office |
| K IC | Critical Stress Intensity Factor |
| LA | Ling’ao Nuclear Power Plant |
| LBB | Leak Before Break |
| LBD | Licensing Basis Documentation |
| LCO | Limiting Condition of Operation |
| LCP | Local Control Panel/Low Core Plate |
| LCS | Local Control Station |
| LDP | Large Display Panel |
| LDS | Leak Detection System |
| LFCG | Life Time Fatigue Crack Growth |
| LHSI | Low Head Safety Injection |
| LLCV | Low Load Control Valve |
| LLIV | Low Load Isolation Valve |
| LLW/ | Low Level Waste |
| ILW | Intermediate Level Waste |
| LLWR | Low Level waste repository Ltd |
| LoC | Letter of Compliance |
| LOCA | Loss of Coolant Accident |
| 2A-LOCA | double-ended guillotine LOCA |
| SB-LOCA | Small Break(Loss of Coolant Accident) |
| IB-LOCA | Intermediate Break(Loss of Coolant Accident) |
| LB-LOCA | Large Break(Loss of Coolant Accident) |
| LoPCA | Loss of Primary Coolant Accident |
| LOOP | Loss of Offsite Power |
| LP | Low Pressure |
| LPSD | Low Power and Shutdown |
| LPT 1 | Low Pressure Turbine |
| LPT 2 | Liquid Penetrant Test |
| LRF | Large Release Frequency |
| LSFPC | Loss of Spent Fuel Pool Cooling |
| LT 1 | Low Temperature |
| LT 2 | Lower Tier |
| LUHS | Loss of Ultimate Heat Sink |
| MCCI | Molten Core-Concrete Interaction |
| MCD | Medium Pressure Rapid Cooldown |
| MCERTS | Monitoring Certification Scheme |
| MCL | Main Coolant Line |
| MCM | Main Computerized control Mean |
| MCR | Main Control Room |
| MCS | Maintenance Cold Shutdown |
| MDEP | Multinational Design Evaluation Programme |
| MDSL | Master Document Submission List |
| MEP | Ministry of Environmental Protection of China |
| MHSI | Medium Head Safety Injection |
| MIV | Main Isolation Valve |
| MER | Mass and Energy Release |
| MFIV | Main Feedwater Isolation Valve |
| MFL | Minimum Flow Line |
| MG | Mixing Grid |
| MLO | Mid-Loop Operation |
| MMO | Marine Management Organisation |
| MMR | Monitoring and Reporting Regulation |
| M-NET | Management Network |
| MOC | Middle of Cycle |
| MOL | Middle of Life |
| MRF | Mass Release Frequency |
| MS | Main Steam |
| MSH | Main Steam Header |
| MSMG | Mid Span Mixing Grid |
| MSR | Moisture Separator Reheater |
| MSTM | Multi-Stud Tensioning Machine |
| MSL | Main Steam Line |
| MSLB | Main Steam Line Break |
| MSIV | Main Steam Isolation Valve |
| MSQA | Management System and Quality Assurance |
| MSRCV | Main Steam Relief Control Valve |
| MSRIV | Main Steam Relief Isolation Valve |
| MSRT | Main Steam Relief Train |
| MSSV | Main Steam Safety Valve |
| MT | Magnetic Penetrant Testing |
| MW th | Megawatt (thermal input) |
| NB | Chinese Energy Standard |
| NC | Non-classified |
| ND | Ningde Nuclear Power Plant |
| NDA | Nuclear Decommissioning Authority |
| NDT | Non Destructive Test |
| NEA | National Energy Association |
| NEPRG | Nuclear Emergency Planning and Response Guidance |
| NHS | Non-human Species |
| NI | Nuclear Island |
| NII | Nuclear Installations Inspectorate |
| NIMCA | Nuclear Industries Malicious Capabilities Planning Assumptions |
| NMA | Nuclear Material Accountancy |
| NMAC | Nuclear Maintenance Applications Centre |
| NMAS | Nuclear Material Accountancy and Safeguards |
| NNB GenCo | EDF Nuclear New Build Generating Company |
| NNSA | National Nuclear Safety Administration |
| NP | Nominal Power |
| NPC | National People's Congress |
| NPP | Nuclear Power Plant |
| NPSH | Net Positive Suction Head |
| NR | Narrow Range |
| NRC | Nuclear Regulatory Commission |
| NSC 1 | Nuclear Security Case |
| NSC 2 | Nuclear and Radiation Safety Centre |
| NSL | Nuclear Site License |
| NSSP | Nuclear Site Security Plan |
| NSSS | Nuclear Steam Supply System |
| OAF | Operator Aid Function |
| OBE | Operating Basis Earthquake |
| OCNS | Office for Civil Nuclear Security |
| OD | Outside Diameter |
| ODS | Ozone-depleting Substances |
| OECC | On-site Emergency Control Center |
| OF | Operating Function |
| ONR | Office for Nuclear Regulation |
| OPEX | Operating Experience |
| ORE | Occupational Radiation Exposure |
| OSM | Outline Study Methodology |
| OTS | Operating Technical Specification |
| OWP | Operator Workplace |
| PAMC | Post-Accident Monitoring Cabinets |
| PAMS | Post-Accident Monitoring System |
| PARs | Passive Autocatalytic Recombiners |
| PC 1 | Partial Cooldown |
| PC 2 | Project Correspondent |
| PCC | Plant Condition Categories |
| PCER | Pre-Construction Environment Report |
| PCI | Pellet - Cladding Interaction |
| PCSR | Pre-Construction Safety Report |
| PCmSR | Pre-Commissioning Safety Report |
| PCT | Peaking Cladding Temperature |
| PDMS | Plant Design Management Tool |
| PDS 1 | Primary Depressurization System |
| PDS 2 | Plant Damage State |
| PFDHA | Probabilistic Fault Displacement Hazard Analysis |
| PGA | Peak Ground Acceleration |
| PHC | Primary Hazard Calculation |
| PHE | Public Health England |
| pH T | The high-temperature pH value |
| PI | Pulse Input |
| PICS | Process Information and Control System |
| PIE | Postulated Initiating Event |
| P&ID | Piping and Instrumentation Diagram |
| PIPS | Process Instrumentation Pre-processing System |
| PLC | Programmable Logic Controller |
| PNS | Primary Neutron Source |
| PNSA | Primary Neutron Source Assembly |
| POS | Plant Operating State |
| POSR | Pre-Operational Safety Report |
| P&T | Pressure and Temperature |
| PQR | Welding Procedure Qualification |
| PRA | Probabilistic Risk Assessment |
| PRB | Pressure Retaining Boundary |
| PRC | People’s Republic of China |
| PRD | Power Range Detector |
| Pre-GDA | Pre Generic Design Assessment |
| PRT 1 | Peer Review Team |
| PRT 2 | Pressurizer Relief Tank |
| PS | Protection System |
| PSA 1 | Probabilistic Safety Assessment |
| PSA 2 | Primary Source Assembly |
| PSAR | Preliminary Safety Analysis Report |
| PSAS | Plant Standard Automation System |
| PSF | Passive Single Failure |
| PSHA | Probabilistic Seismic Hazard Assessment |
| P SI | Pre-Service Inspection |
| PSR | Preliminary Safety Report |
| PSV | Pressurizer Safety Valve |
| PSIV | Pressurizer Safety Isolation Valve |
| PT 1 | Periodic Test |
| PT 2 | Liquid Penetrant Testing |
| PWHT | Post Weld Heat Treatment |
| PWR | Pressurized Water Reactor |
| PZR | Pressurizer |
| QA | Quality Assurance |
| QEDS | Qualified Examination Defect Size |
| QD | Quick Disconnect |
| QMS | Quality Management System |
| RAM | Reliability, Availability, Maintainability |
| RCA | Radiation Controlled Area |
| RCCA | Rod Cluster Control Assembly |
| RCC-E | Design and Building Rules for Electric Equipment for Pressurized Water Reactor Nuclear Islands |
| RCC-M | Design and Building Rules for Mechanical Equipment for Pressurized Water Reactor Nuclear Islands |
| RCD | Reactor Complete Discharge |
| RCPB | Reactor Coolant Pressure Boundary |
| RCP | Reactor Coolant Pump |
| RCS | Refuelling Cold Shutdown |
| R&D | Research and Development |
| REDACE | Real-time and Deterministic Application Coding Environment |
| REP | Radioactive Substances Regulation – Environmental Principles |
| REPPIR | The Radiation (Emergency Preparedness and Public Information) Regulations |
| RfQ | Request for Quotation |
| RFSAR | Revised Final Safety Analysis Report |
| RG | Regulatory Guidance |
| RGP | Relevant Good Practice |
| RHR | Residual Heat Removal |
| RI | Regulator Issue |
| RIN | French national identification code for valves |
| RO | Regulator Observation |
| RoA | Report of Assessment |
| ROU | Reverse Osmosis Unit |
| RP 1 | Radiation Protection |
| RP 2 | Requesting Party |
| RPC | Reactor Protection Cabinet |
| RPCS | Reactor Power Control System |
| RPI | Rod Position Instrumentation |
| RPS | Reactor Protection System |
| RPV | Reactor Pressure Vessel |
| RPVL | Reactor Pressure Vessel Level |
| RQ 1 | Regulator Query |
| RQ 2 | Risk Quotient |
| RSS | Remote Shutdown Station |
| RT 1 | Reactor Trip |
| RT 2 | Radiographic Testing |
| RTP | Rated Thermal Power |
| RT NDT | Reference Nil Ductility Transition Temperature |
| RTS | Reactor Trip System |
| RVI | Reactor Pressure Vessel Internals |
| RWM | Radioactive Waste Management Ltd |
| /ry | per reactor year |
| SA 1 | Severe Accident |
| SA 2 | Spectral Amplitude |
| SAC | Safety Automation Cabinet |
| SADV | Severe Accident Dedicated Valve |
| SAGE | Safe video Graphic console panel Environment |
| SAMG | Severe Accident Management Guideline |
| SAPs | Safety Assessment Principles for Nuclear Facilities |
| SAS | Safety Automation System |
| SA I&C | Severe Accident I&C |
| SBO | Station Black Out |
| SC1 | Safety Classification 1 |
| SC2 | Safety Classification 2 |
| SCC | Stress Corrosion Cracking |
| SCCA | Stationary Cluster Control Assembly or Stationary Core Component Assembly |
| SCID | Safety Control and Information Device |
| SDR | System Design Report |
| SDRS | Standard Design Response Spectra |
| SEDS | Self-Engaging Dewatering System |
| SF | Spent Fuel |
| SFA | Spent Fuel Assembly |
| SFAIRP | So Far As Is Reasonably Practicable |
| SFC | Single Failure Criterion |
| SFIS | Spent Fuel Interim Storage |
| SFP | Spent Fuel Pool |
| SFPC | Spent Fuel Pool Crane |
| SFRs | Safety Function Requirements |
| SG | Steam Generator |
| SGa | Affected Steam Generator |
| SGTR | Steam Generator Tube Rupture |
| SHP | Severe accident Human interface Panel |
| SHWP | Seismic Hazard Working Party |
| SI | Safety Injection |
| SIC-1 | Structural Integrity Class 1 |
| SIC-2 | Structural Integrity Class 2 |
| SIC-3 | Structural Integrity Class 3 |
| SICS | Safety Information and Control System |
| SIRO | Senior Information Risk Owner |
| SL | Surge Line |
| SLA | Site License Application |
| SLB | Steam Line Break |
| SLC | Sub Loop Control |
| S-NET | System Network |
| SNI | Sensitive Nuclear Information |
| SNS | Secondary Neutron Source |
| SoDA | Statement of Design Acceptability |
| SOP | State Oriented Procedure |
| SPAR-H | Standardized Plant Risk Analysis-Human Reliability Analysis Procedure |
| SPC | Signal Pre-processing Cabinet |
| SPND | Self-Powered Neutron Detector |
| SPRHR | Secondary Passive Residual Heat Removal System |
| SPSA | Seismic Probabilistic Safety Assessment |
| SQEP | Suitably Qualified and Experienced Person |
| SRD | Source Range Detector |
| SRHT | Stress Relieve Heat Treatment |
| SRP | Standard Review Plan |
| SRTF | Site Radwaste Treatment Facility |
| SS | Stainless Steel |
| SSA | Secondary Source Assembly |
| SSCs | Structures, Systems and Components |
| SSE | Safe Shutdown Earthquake |
| SSE1 | Seismic Category 1 |
| SSFP | Star-up and Shutdown Feedwater Pump |
| SSI | Soil Structure Interaction |
| SSM | Seismic Source Model |
| SSPB | Secondary Side Pressure Boundary |
| SSR | Specific Safety Requirements |
| SSS | Standstill Seal System |
| ST | Standby Transformer |
| STP | Standard temperature and pressure (273.15 K and 1 atm) |
| SyAPs | Security Assessment Principles |
| SZC | Sizewell C |
| TBCV | Turbine Bypass Control valve |
| TBIV | Turbine Bypass Isolation Valve |
| TCD | Team of Chief Designers |
| TCLS | Thermoelectric Converter of Level Sensor |
| TD | Technical Delivery |
| TAGs | Technical Assessment Guides |
| TG | Turbine Generators |
| TGCS | Turbine Generator Control System |
| TH | Thermal Hydraulic |
| TIG | Tungsten Inert Gas |
| TLOCC | Total Loss of Cooling Chain |
| TLOFW | Total Loss of Feedwater |
| TOR | The Tolerability of Risk from Nuclear Power Stations |
| TPA | Thimble Plug Assembly |
| TSC | Technical Support Center |
| TSP | Tri-Sodium Phosphate |
| TSS | Transport Security Statement |
| TT | Top Tier |
| UCP | Upper Core Plate |
| UHS 1 | Unified Hazard Spectra |
| UHS 2 | Ultimate Heat Sink |
| UK HPR1000 | The UK version of the Hua-long Pressurized Reactor |
| UK | United Kingdom of Great Britain and Northern Ireland |
| UL | Crossover Leg |
| URC | Unacceptable Radiological Consequence |
| URD | Utility Requirements Document |
| URWP | Uncontrolled RCCA bank Withdrawal at Power |
| UPS | Uninterruptible Power Supply |
| US | Unit Supervisor |
| USP | Upper Support Plate |
| UT 1 | Ultrasonic Test |
| UT 2 | Unit Transformer |
| VAI | Vital Area Identification |
| VCT | Volume Control Tank |
| VDU | Visual Display Unit |
| VLLCV | Very Low Load Control Valve |
| VLLW | Very Low Level Waste |
| V-LOCA | Loss of Coolant Accident with Containment bypass |
| VT | Visual Testing |
| WAC | Waste acceptance criteria |
| WANO | World Association of Nuclear Operators |
| WB | Waste Treatment Building |
| WENRA | Western European Nuclear Regulators Association |
| WR | Wide Range |
| WS | Work Specification |
| WULCV | Warm-up Line Control Valve |
| WULIV | Warm-up Line Isolation Valves |
| YJ | Yangjiang Nuclear Power Plant |
| ZOI | Zone of Influence |
| YJ | Yangjiang Nuclear Power Plant |
| ZOI | Zone of Influence |
