Resolution of Generic Safety Issues: Abbreviations ( NUREG-0933, Main Report with Supplements 1–35 )

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
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 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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