Abbreviations
 NUREG-0933 Resolution of Generic Safety Issues 

Contents

Abbreviations........................................................................................................................... 1
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Abbreviations

Acronym Description

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
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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
 | NUREG-0933 Resolution of Generic Safety Issues | Abbreviations | 3

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
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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
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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
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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-0933 Resolution of Generic Safety Issues | Abbreviations | 7

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
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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
 | NUREG-0933 Resolution of Generic Safety Issues | Abbreviations | 9

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
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SSE safe shuentryown 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

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