| AAB |
Accident Analysis Branch, NRR (defunct) |
| AC |
alternating current |
| ACRR |
Annular Core Research Reactor |
| ACRS |
Advisory Committee on Reactor Safeguards |
| ADM |
Office of Administration |
| ADS |
automatic depressurization system |
| A/E |
Architect/Engineer |
| AEB |
Accident Evaluation Branch, DSI, NRR (defunct) |
| AEC |
Atomic Energy Commission (now NRC) |
| AEOD |
Office for Analysis and Evaluation of Operational Data |
| AFW |
auxiliary feedwater |
| AFWS |
auxiliary feedwater system |
| AGS |
Atlantic Generating Station |
| AI |
artificial intelligence |
| AIF |
Atomic Industrial Forum |
| AISC |
American Institute of Steel Construction |
| ALARA |
as low as reasonably achievable |
| ANL |
Argonne National Laboratory |
| ANO |
Arkansas Nuclear One |
| ANPRM |
advance notice of proposed rulemaking |
| ANS |
American Nuclear Society |
| ANSI |
American National Standards Institute |
| AOP |
abnormal operating procedure |
| AOV |
air-operated valve |
| APRM |
average power range monitor |
| ASLAB |
Atomic Safety and Licensing Appeal Board |
| ASLB |
Atomic Safety and Licensing Board |
| ASME |
American Society of Mechanical Engineers |
| ATWS |
anticipated transient without scram |
| |
|
| BNL |
Brookhaven National Laboratory |
| BOC |
beginning of cycle |
| BOP |
balance-of-plant |
| BTP |
Branch Technical Position |
| B&W |
Babcock & Wilcox Company |
| BWR |
boiling water reactor |
| |
|
| CCF |
common cause failure |
| CDF |
core damage frequency |
| CE |
Combustion Engineering Company |
| CERC |
Coastal Engineering Research Center |
| CFR |
Code of Federal Regulations |
| Ci |
Curies |
| CLB |
current licensing basis |
| CP |
construction permit |
| CPB |
Core Performance Branch, DSI, NRR (defunct) |
| CPI |
containment performance improvement |
| CRAC |
calculation of reactor accident consequences |
| CRBR |
Clinch River Breeder Reactor |
| CRBRP |
Clinch River Breeder Reactor Project |
| CRD |
control rod drive |
| CRGR |
Committee for the Review of Generic Requirements |
| CRT |
collet retaining tube |
| CSB |
Containment Systems Branch, DSI, NRR (defunct) |
| CSS |
containment spray system |
| CVCS |
Charging and Volume Control System |
| |
|
| DAS |
data acquisition system |
| DBA |
design basis accident |
| DBE |
design basis event |
| DC |
direct current |
| DE |
Division of Engineering, NRR (defunct) |
| DEDROGR |
Deputy Executive Director for Regional Operations and Generic Requirements |
| DES |
Draft Environmental Statement |
| DFO |
Division of Facility Operations, RES (defunct) |
| DHFS |
Division of Human Factors Safety, NRR (defunct) |
| DHR |
decay heat removal |
| DL |
Division of Licensing, NRR (defunct) |
| DNB |
departure from nucleate boiling |
| DNBR |
departure from nucleate boiling ratio |
| DOC |
U.S. Department of Commerce |
| DOD |
U.S. Department of Defense |
| DOE |
U.S. Department of Energy |
| DOI |
U.S. Department of Interior |
| DOR |
Division of Operating Reactors, NRR (defunct) |
| DOT |
U.S. Department of Transportation |
| DSI |
Division of Systems Integration, NRR (defunct) |
| DST |
Division of Safety Technology, NRR (defunct) |
| |
|
| E |
energy |
| ECC |
emergency core cooling |
| ECCS |
emergency core cooling system |
| ECI |
emergency coolant injection |
| EDG |
emergency diesel generator |
| EDO |
Executive Director for Operations |
| EEI |
Edison Electric Institute |
| EELB |
Electrical Engineering Branch, DE, NRR |
| EHEB |
Environmental and Hydrologic Engineering Branch, DE, NRR (defunct) |
| EI |
environmental issue |
| EIS |
Environmental Impact Statement |
| EICSB |
Electrical, Instrument, and Control Systems Branch, NRR (defunct) |
| EMP |
electromagnetic pulse |
| EN |
enforcement notification |
| EOP |
emergency operating procedure |
| EPA |
U.S. Environmental Protection Agency |
| EPRI |
Electric Power Research Institute |
| EPZ |
emergency planning zone |
| EQB |
Equipment Qualification Branch, DE, NRR (defunct) |
| ERF |
emergency response facility |
| ESF |
engineered safety feature |
| ESFAS |
engineered safety features actuation system |
| ESRP |
Environmental Standard Review Plan |
| ESW |
essential service water |
| ETS |
Environmental Technical Specification |
| ETSB |
Effluent Treatment Systems Branch, NRR (defunct) |
| |
|
| FAA |
U.S. Federal Aviation Administration |
| FBI |
U.S. Federal Bureau of Investigation |
| FCC |
U.S. Federal Communication Commission |
| FDA |
final design analysis |
| FEIS |
Final Environmental Impact Statement |
| FEMA |
U.S. Federal Emergency Management Agency |
| FIN |
Financial Identification Number |
| FIST |
full integral simulation test |
| FMEA |
failure modes and effects analysis |
| FPS |
fire protection system |
| FSAR |
Final Safety Analysis Report |
| FWPCA |
Federal Water Pollution Control Act |
| FY |
fiscal year |
| |
|
| GALE |
gaseous and liquid effluent |
| GAO |
U.S. Government Accountability Office |
| GDC |
general design criterion |
| GE |
General Electric Company |
| GIB |
Generic Issues Branch, DST, NRR (defunct) |
| GITS |
Generic Issues Tracking System (obsolete) |
| gpm |
gallons per minute |
| GSI |
generic safety issue |
| GWd |
gigawatt-days |
| |
|
| HELB |
high energy line break |
| HFIR |
High Flux Isotope Reactor |
| HFPP |
Human Factors Program Plan |
| HMR |
Hydrometeorological Report |
| HOV |
hydraulic-operated valve |
| HPCI |
high pressure coolant injection |
| HPI |
high pressure injection |
| HPSI |
high pressure safety injection |
| HVAC |
heating, ventilating, and air-conditioning |
| HWC |
hydrogen water chemistry |
| HX |
heat exchanger |
| |
|
| IAS |
instrument air system |
| I&C |
instrument and control |
| ICS |
integrated control system |
| IE |
inspection and enforcement |
| IEEE |
Institute of Electrical and Electronics Engineers |
| IGR |
Impulse Graphite Reactor (Russia) |
| IGSCC |
intergranular stress corrosion cracking |
| INEL |
Idaho Nuclear Engineering Laboratory |
| INPO |
Institute for Nuclear Power Operations |
| IP |
Office of International Programs (defunct) |
| IPE |
individual plant examination |
| IPEEE |
individual plant examination of external events |
| IPRDS |
In-plant Reliability Data System |
| IRC |
Incident Response Center |
| IREP |
Interim Reliability Evaluation Program |
| IRM |
intermediate range monitor |
| ISA |
Instrument Society of America |
| ISAP |
integrated safety assessment program |
| ISI |
in-service inspection |
| ISLOCA |
interfacing systems loss-of-coolant accident |
| IST |
in-service test |
| |
|
| KI |
potassium iodide |
| |
|
| LASL |
Los Alamos Scientific Laboratory |
| LBLOCA |
large-break LOCA |
| LCO |
limiting condition for operation |
| LER |
Licensee Event Report |
| LI |
licensing issue |
| LLNL |
Lawrence Livermore National Laboratory |
| LMFBR |
liquid metal fast breeder reactor |
| LOCA |
loss-of-coolant accident |
| LOFT |
loss-of-fluid test |
| LOOP |
loss of offsite power |
| LPCI |
low pressure coolant injection |
| LPCS |
low pressure core spray |
| LPRM |
low power range monitor |
| LPSI |
low pressure safety injection |
| LSSS |
limiting safety system setting |
| LTOP |
low temperature overpressure protection |
| LWR |
light water reactor |
| |
|
| M |
million |
| MCPR |
minimum critical power ratio |
| MEB |
Mechanical Engineering Branch, DE, NRR (defunct) |
| METB |
Meteorology and Effluent Treatment Branch, DSI, NRR (defunct) |
| MeV |
million electron volts |
| ML |
manufacturing license |
| MOU |
memorandum of understanding |
| MOV |
motor-operated valve |
| MPA |
multiplant action |
| MSIV |
main steam isolation valve |
| MSIVLCS |
main steam isolation valve leakage control system |
| MSLB |
main steam line break |
| MTEB |
Materials Engineering Branch, DE, NRR (defunct) |
| |
|
| NASA |
U.S. National Aeronautics and Space Administration |
| NDE |
non-destructive examination |
| NDL |
nuclear data link |
| NDT |
non-destructive testing |
| NDTT |
nil ductility transition temperature |
| NEA |
Nuclear Energy Agency |
| NEPA |
National Environmental Policy Act |
| NIOSH |
U.S. National Institute of Occupational Safety and Health |
| NMSS |
Office of Nuclear Materials Safety and Safeguards |
| NNI |
non-nuclear instrumentation |
| NPRDS |
Nuclear Plant Reliability Data System |
| NREP |
National Reliability Evaluation Program |
| NRR |
Office of Nuclear Reactor Regulation |
| NSAC |
Nuclear Safety Analysis Center |
| NSRR |
Nuclear Safety Research Reactor (Japan) |
| NSSS |
nuclear steam supply system |
| NTOL |
near-term operating license |
| NUMARC |
Nuclear Utility Management and Resources Council |
| NUREG |
NRC publication |
| NVLAP |
National Voluntary Laboratory Accreditation Program |
| |
|
| OBE |
operating basis earthquake |
| OC |
NRC Operations Center |
| OIE |
Office of Inspection and Enforcement (also IE, I&E defunct) |
| OL |
operating license |
| OLB |
Operator Licensing Branch, DHFS, NRR (defunct) |
| OPS |
Offshore Power Systems |
| ORAB |
Operating Reactors Assessment Branch, DL, NRR (defunct) |
| ORE |
occupational radiological exposure |
| ORNL |
Oak Ridge National Laboratory |
| ORPBR |
Occupational Radiation Protection Branch, DFO, RES (defunct) |
| OSTP |
Office of Science and Technology Policy, The White House |
| OTSG |
once-through steam generator |
| |
|
| PA |
Office of Public Affairs (defunct) |
| PARV |
power-actuated relief valve |
| PAS |
Probabilistic Analysis Staff, RES (defunct) |
| PBF |
Power Burst Facility |
| PCI |
pellet/cladding interaction |
| PCS |
power conversion system |
| PCT |
pellet cladding temperature |
| PDA |
preliminary design analysis |
| PEIS |
Programmatic Environmental Impact Statement |
| PGP |
procedures generation package |
| PIV |
pressure isolation valve |
| PMF |
probable maximum flood |
| PMP |
probable maximum precipitation |
| PNL |
Pacific Northwest Laboratories |
| PORV |
power-operated relief valve |
| PRA |
probabilistic risk assessment |
| PRM |
Petition for Rulemaking |
| PSB |
Power Systems Branch, DSI, NRR (defunct) |
| PTS |
pressurized thermal shock |
| PWR |
pressurized water reactor |
| |
|
| QA |
quality assurance |
| QC |
quality control |
| |
|
| RAB |
Radiological Assessment Branch, DSI, NRR (defunct) |
| RBCCW |
reactor building closed cooling water |
| RCIC |
reactor core isolation cooling |
| RCP |
reactor coolant pump |
| RCPB |
reactor coolant pressure boundary |
| RCS |
reactor coolant system |
| RDA |
rod drop accident |
| REA |
U.S. Rural Electrification Administration |
| RES |
Office of Nuclear Regulatory Research |
| RETS |
Radiological Effluent Technical Specification |
| RHR |
residual heat removal |
| RI |
regulatory impact issue |
| RIL |
Research Information Letter |
| RNWP |
reduced notch worth procedure |
| RO |
reactor operator |
| RPS |
reactor protection system |
| RPV |
reactor pressure vessel |
| RRAB |
Reliability and Risk Assessment Branch, DST, NRR (defunct) |
| RSB |
Reactor Systems Branch, DSI, NRR (defunct) |
| RSS |
Reactor Safety Study |
| RSSMAP |
Reactor Safety Study Methodology Application Program |
| RVSS |
reactor vessel support structure |
| RWCU |
reactor water cleanup |
| RWST |
reactor water storage tank |
| RY |
reactor-year |
| |
|
| SAI |
Science Applications, Inc. |
| SALP |
systematic assessment of licensee performance |
| SAR |
Safety Analysis Report |
| SARA |
system analysis and risk assessment |
| SAS |
service air system |
| SBLOCA |
small-break loss-of-coolant accident |
| SCBA |
self-contained breathing apparatus |
| SCC |
stress corrosion cracking |
| SCF |
standard cubic feet |
| SCFH |
standard cubic feet per hour |
| SCSS |
Sequence Coding and Search System |
| SD |
Office of Standards Development (defunct) |
| SDV |
scram discharge volume |
| SE |
shift engineer |
| SEB |
Structural Engineering Branch, DE, NRR (defunct) |
| SEP |
Systematic Evaluation Program |
| SER |
Safety Evaluation Report |
| SETS |
standard environmental technical specification |
| SFP |
spent fuel pool |
| SGTR |
steam generator tube rupture |
| SGTS |
standby gas treatment system |
| SI |
safety injection |
| SIL |
service information letter |
| SIMS |
Safety Issue Management System |
| SIR |
safety issue resolution |
| SIS |
safety injection system |
| SLCS |
standby liquid control system |
| SMC |
seismic methodology chain |
| SO |
senior operator |
| SOV |
solenoid-operated valve |
| SPDS |
safety parameter display system |
| SPEB |
Safety Program Evaluation Branch, DST, NRR (defunct) |
| SQR |
Seismic Qualification Report |
| SQUG |
Seismic Qualification Utility Group |
| SR |
surveillance requirement |
| SRM |
staff requirements memorandum |
| SRO |
senior reactor operator |
| SROA |
safety-related operator action |
| SRP |
Standard Review Plan |
| SRV |
safety relief valve |
| SS |
shift supervisor |
| SSE |
safe shutdown earthquake |
| SSMRP |
Seismic Safety Margins Research Program |
| STA |
shift technical advisor |
| STS |
standard technical specification(s) |
| SV |
safety valve |
| SWGTS |
steam and waste gas treatment system |
| SWS |
service water system |
| |
|
| TAP |
Task Action Plan |
| TER |
Technical Evaluation Report |
| TI |
temporary instruction |
| TID |
Technical Information Document |
| TIP |
traveling in-core probe |
| TLD |
thermo-luminescent dosimeter |
| TMI |
Three Mile Island Nuclear Plant |
| TMIPO |
Three Mile Island Program Office, NRR (defunct) |
| TNT |
trinitrotoluene |
| TS |
technical specification(s) |
| TSIP |
Technical Specification Improvement Program |
| TVA |
Tennessee Valley Authority |
| |
|
| UHS |
ultimate heat sink |
| USI |
unresolved safety issue |
| UT |
ultrasonic test |
| |
|
| W |
Westinghouse Electric Corporation |
