ML20236Y389

NRC Collection of Abbreviations

ML20236Y389
Person / Time
Issue date:	07/31/1998
From:	NRC (Affiliation Not Assigned)
To:
References
NUREG-0544, NUREG-0544-R04, NUREG-544, NUREG-544-R4, NUDOCS 9808120162
Download: ML20236Y389 (147)

Text

1. e# ~'"% U.S. Nuclear Regulatory g Commission NRC Collection of Abbreviations Information Management Division Office of the Chief Information Officer U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 1

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AVAILABILITY NDTICE Availabihty of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:

1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001

2. The Superintendent of Documents, U.S. Government Printing Office, P. O. Box 37082, Washington, DC 20402-9328

3. The National Technical information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive.

Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda: NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence: Commission papers; and applicant and licensee docu-ments and correspondence.

The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-ceedings, international agreement reports, grantee reports, and NRC booklets and bro-chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula-tions, and Nuclear Regulatory Commission issuances.

Documents available from the National Technical information Service include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.

Documents available from public and special technical libraries include all opon literature items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries.

Documents such as theses, dissenations, foreign reports and translations, and non-NRC con-ferenco proceedings are available for purchase from the organization sponsoring the publica-tion cited.

Single copies of NRC draf', reports are available free, to the extent of supply, upon written request to the Office d Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001.

Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, Two White Flint North,11545 Rockville Pike, Rock-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards institute,1430 Broadway, New York, NY 10018-3308.

ABSTHACT This collection of abbreviations in common use in the nuclear industry and regulatory community was compiled from Nuclear Regulatory Cornmission (NRC) and nuclear industry sources. It was published to assist agency authors, readers, and stakeholder in identifying abbreviations for the numerous organiza-tional, scientific, and engineering terms that appear in NRC printed and electronic information. The compilation is descriptive rather than prescriptive. No one abbreviation is recommended to the exclusion of another because the same abbreviation may with equal validity apply to two or more terms.

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INTRODUCTION

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The U.S. Nuclear Regulatory Commission (NRC) publishes this collection of abbreviations to assist agency authors and readers and members of the public in identifying the abbreviations for the numerous organizational, scientific, and engineering terms that appear in NRC printed and electrenic information.

This collection has been compiled from NRC and nuclear industry sources and is descriptive rather than prescriptive. No one abbreviation is recommended to the exclusion of another because the same abbreviation may with equal validity apply to two or more terms.

An abbreviation is a shortened, condensed form of a word or term. Some technical abbreviations, such as laser and scuba, have been so widely disseminated that they now communicate . successfully without funher defm' ition.

Acronyms and initialisms are types of abbreviations.

• An acronym is an abbreviation that forms a pronounceable term from the initial letters of a group of words: ANSI is formed from American National Standards Institute anni LOCA from loss-of-coolant accident.

• An initialism is an abbreviation formed from the initial letters of a group of words for which each .

letter is pronounced separately: EPZ is formed from emergency planning zone and SGTS Pom )

standby gas treatment system.

The NRC editorial staff offers the following suggestions for using abbreviations:

• Spell out the term for an abbreviation the first time you use it in text and follow the spelled-out term with the abbreviation in parentheses: control rod drive (CRD). Repeat this process at the beginning of each new section or chapter for printed publications.

• Restrict an abbreviation to one meaning in any one document. If you designate NDT to mean nondestructive testing, do not designate NDT to mean nil ductility temperature or any other term l beginning with the letters NDT in the same document. Spell out any other term that could be abbreviated as NDT in that document.

This compilation includes major NRC program and staff offices, advisory groups, panels, and boards but not NRC divisions, branches, and sections, which can be found in the NRC Telephone Directory (NUREG/BR-0046). Some abbreviations for organizations that no longer exist are included as historical references.

This compilation does not include chemical elements, computer codes, and most units of measurement.

l Many of these abbreviations appear in readily accessible sources such as dictionaries, the Government Printing Office (GPO) Style Manual, and other manuals.

Identical abbreviations appear in various forms (e.g., AA or A/A); they are listed in this compilation in the following order: AA, aa, A/A, A-A, A&A.

In general, the editorial staff observes the following rules for forming plurals and for capitalizing and hyphenating abbreviations:

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INT RODUCT ION .

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o Plurals To form most plurals, add a lowercase s without an apostrophe preceding it to the abbreviation. ,

DBAs for design-basis accidents PWRs for pressurized-water reactors However, some abbreviations are identical in both singular and plural constructions.

ATWS for anticipated transient or transients without scram GDC for general design criterion or criteria LCO for limiting condition or conditions for operation MOU for memorandum or memoranda of understanding Use the same abbreviation for a plural construction when a word in a term is an irregular plural (e.g., LRB for licensing review basis or bases) or when any word in a term except the last word is a regular plural, that is, formed by adding s (e.g., COLSS for core operating limit or limits support system). Only the irregular plurals, such as bases, are given in this collection; plurals formed by adding s to an internal or 6nal word of a term are generally not given.

• Capitalization Although most abbreviated terms are lowercase when written out, most of their abbreviations are uppercase.

Do not capitalize specific parts of a nuclear system or facility, the many job titles at a nuclear facility, or generic terms designating equipment, systems, or programs.

ACCWS for auxiliary component cooling water system RPM for radiation protection manager However, capitalize the names of specific facilities or reactors, companies or organizations, and committees or special interest groups.

ACNW for Advisory Committee on Nuclear Waste RRA for Radiation Research Associates,Inc.

RRR for Raleigh Research Reactor e Hyphenation I

To hyphenate a term from which an abbreviation is formed, follow the general rules of hyphenation, particularly those given in the GPO Style Manual.

Hyphenate unit modifiers used as adjectives and adverbs before a noun in each term:

LOCA for loss-of-coolant accident, but not LOOP for loss of offsite power vi

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IN I HOI )UC])ON Do not hyphenate most short prefixes, such as co, de, pre, pro, and re.

DWCS for defueling water cleanup system I'TP for preoperational test program The NRC welcomes new entries for future revisions of this collection. Please send suggestions for new entries to the e-mail address <jfbl @NRC. GOV > or write to the Technical Publications Section, Publishing Services Branch, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

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NHO COL l FCTION Of ABBHE VIA'ilONS AA access authorization ABST auxiliary building sump tank AAA Agency Allegations Advisor ABSVS auxiliary building special ventilation AAAC Affirmative Action Advisory system Committee ABT automatic bus transfer i

Aac alternate ac ABV auxiliary building ventilation 1 AACC American Association for ABWR advanced boiling-water reactor Contamination Control ABWRP American Boiling Water Reactor AAEC Australian Atomic Energy Program Commission AC acid concentrator AAECS auxiliary area environmental control A&C adequacy and compatibility

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• AC administrative control AAEGTS auxiliary area emergency gas treatment system advisory committee AAHP American Academy of Health air conditioning Physics allegations coordinator AAM airborne activity monitor ac alternating current AAPM American Association of Physicists A/C air conditioning in Medicine A-C AAR Aktiebolaget Atomenergi Research Allis~Chalmers Allis-Chalmers CoIu. or Ma facturing Reactor Company AARR Argonne Advanced Research ACA Arms Control Association Reactor ACAD air containment atmosphere dilution AASHTO American Association of State ACB air-operated circuit breaker Highway and Transportation Officials Ateliers et Chantiers de Bretagne AATN Asociaci6n Argentina de Tecnologfa

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Nuclear (Argentina) ACC accumulator AB auxiliary boiler air-cooled condenser ABACC Argentine-Brazil 3n Agency for ACCWS auxiliary component cooling water Accounting and Control of Nuclear system Material ACDA Arms Control and Disarmament ABB-CE Asea Brown Boveri-Combustion Agency Engineering, Inc. ACEC Ateliers de Constructions Electriques ABCC Atomic Bomb Casualty Commission de Charleroi, S.A. (Belgium)

ABET Accreditation Board for Engineering ACF acid concentrator feed and Technology ampacity correction factor ABFS auxiliary building filter system automatic control feature ABGTS auxiliary building gas treatment acfm actual cubic foot / feet per minute system ACHP Advisory Council on Historic ABHP American Board of Health Physics Preservation ABHX air blast heat exchanger ACI American Concrete Institute ABI aunliary building isolation automatic closure and interlock ABLE activity balance line evaluation ACIWA ac-independent water addition ABMA American Boiler Manufacturers ACL access controllist Association and Affiliated Industries alternate concentration limit ABNP Alan R. Barton Nuclear Plant ACLP above-core load pad ABR as-built reconciliation above-core load plane ABRR as-built reverification record l

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, NHC col t FCTION QF ABBJYVIAT[ONS ACM alternate contact mode ADC authorized derivative classifier auxiliary cooling method ADDS applied digital data system ACMUI Advisory Committee on the Medical ADEA Association Belge pour le Uses of Isotopes (NRC) D6veloppement Pacifique de i ACNFS Advisory Committee on Nuclear l'Energie Atomique (Belgium) l Facility Safety (DOE) ADFCER Assistant Director for Fuel Cycle and ACNP American College of Nuclear Environmental Research Physiciens ADI Applied Dynamics International ACNS Advisory Committee on Nuclear ADM Administration, Office of(NRC)

Safety (Canada) ADN apparent discrepancy notification 1 ACNW Advisory Committee on Nuclear ADP automated data processing I Waste (NRC) .

1 ACORN Association of Community ADPE, E' ##**!"E .

Organizations for Reform Now automatic data processmg equipment ACOT analog channel operational test ADR audit discrepancy report ACP auxiliary control panel ADRS automated data retrieval system ACPDS Advisory Committee on Personal ADS automated data system Dosimetry Services (NSF) automatic depressurization system ACPR ad vanced core performance reactor automatic dispatch system advanced core pulsed reactor ADT aerated drain tank annular core pulsed reactor ADU ammonium diuranate ACR advanced converter reactor ADV atmospheric dump valve attribute coverage report AE acoustic emission ACRE advanced compact reactor air ejector experiment architect-engineer ACRG Advanced Code Review Group A/E architect-engineer (NRC)

A-E architect-engineer ACRI Air Conditioning and Refrigeration Institute AEA Atomic Energy Act of 1954 ACRR annular core research reactor Atomic Energy Authority ACRS Advisory Committee on Reactor AEB Atomic Energy Bureau (Korea)

Safeguards (NRC) auxiliary equipment building ACS Advanced Computer System AEC Alternative Energy Coalition alternate core spray Atomic Energy Commission, U.S.

American Chemical Society (Became ERDA and NRC) auxiliary cooling system AECB Atomic Energy Control Board ACSNI Advisory Committee on Safety of (Canada)

Nuclear Installations (U.K.) AECC Aerojet Energy Conversion Co.

ACTS automated commitment tracking AECL AECL Technologies system Atomic Energy of Canada, Ltd.

ACU air cleanup unit AECLT Atomic Energy of Canada, Ltd.,

AD assistant director Technologies A/D analog to digital AECM Atomic Energy Commission Manual ADAMS Agencywide Documents Access and AECPR Atomic Energy Commission Management S stem Procurement Regulation ADAS automatic data acquisition and AEDE annual effective dose equivalent storage A 2

NHC COLLECTION OF ABBREVIATIONS l

AEE Atomic Energy Establishment AFDC auxiliary feedwater discharge (Libya) cross-connection l

AEEN Agenzia Europea per l'Energia AFDS automatic fire detection system Nucleare AFI Air Filter Institute i Agence Europeenne pour l'Energie AFL active fuel length Nucl6 aire AFNE Americans for Nuclear Energy l AEEW Atomic Energy Establishment of i Winfrith (Umted Kingdom) AF NETF Air Force Nuclear Engineering Test Facility AEF Argonne Experimental Facility AFO auxiliary fuel oil AEGTS annulus exhaust gas treatment system AFOS auxiliary fuel oil system I

AEI Associated Electric Industries Ltd.

(United Kingdom) AFP auxiliary feedwater pump AEN Aj;ence pour l'Energie Nucl6 aire AFR acid fractionation recycle (I rance) acid fractionator recycle AENJ Atlantic Electric of New Jersey away from reactor AEO Atomic Energy Organization (Iran) AFRRI Armed Forces Radiobiology AEOD Analysis and Evaluation of Research Institute Operational Data, Office for (NRC) AFS auxiliary feedwater system AEOF alternate emergency operations AFSR Argonne Fast-Source Reactor facility AFW auxiliary feedwater AEOI Atomic Energy Organization of Iran AFWAS auxiliary feedwater actuation system AEOR Annual Environmental Operating AFWC auxiliary feedwater control Report American Electric Power Co., Inc.

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• AEP AG Aerojet-General Corp.

AEPSC American Electric Power Service Corp. AGA automatic gas analyzer AERCW auxiliary essential raw cooling water AGC advanced gas centrifuge AERE Atomic Energy Research Aerojet-General Corp.

Establishment (United Kingdom) AGCR advanced gas-cooled reactor AERO Association for Excellence in AGL above-ground level j Reactor Operations AGMA American Gear Manufacturers AES aerospace and electronic systems Association AESJ Atomic Energy Society of Japan AGN Aerojet-General Nucleonics AETR advanced engineering test reactor AGNS Allied-General Nuclear Services advanced epithermal thorium reactor AGR advanced gas-cooled reactor AF alternating field AGS alternating gradient synchrotron auxiliary feed annular gas system auxiliary feedwater AGU American Geophysical Union l AF/AL as found, as left AGVC automatic governing valve control I

AFAS auxiliary feedwater actuating system automatic governor valve control AFB Air Force base AGW accident-generated water AFBMA Anti-Friction Bearing Manufacturers AGZ actual ground zero Association, Inc.

A/H air handling AFC automatic flow control AHFR Argonne High-Flux Reactor AFD acid fractionator distillat AHJ authority housing jurisdiction axial flux difference AHM auxiliary handling machine 3

NHC COMYCT ON OF ABfkREVIATlONS AHPA Archeological and Historic advanced instrumentation for reflood Preservation Act studies AHR aqueous homogeneous reactor Automated Inspection Report System AHTG ad hoc task group AIS accumulator injection system AHU air-handling unit advanced isotope separation Al artificial intelligence automated information system Atomics International AISC American Institute of Steel authorized inspector Construction automatic isolation AISE Association ofIron and Steel Engineers AIA authon. zed m.spection agency AISI American Iron and Steel Institute AICE American Institute of Chemical Engineers AISS automated information systems

• 1. '"" Y AID accident identification display automated information system

. AISSP Agency for International security plan Development

. . AIT American Industrial Technologies air inlet damper .

merican Institute in Taiwan AIEE American Institute of Electrical Engineers augmented inspection team AIF Atomic Industrial Forum, Inc. (now AITS action item tracking system NEI) AIX after ion exchanger AIG antitrust and indemnity group AKK Atomkraftdonsortiet Krangede Ad &

AIGS auxiliary inerting gas subsystem Co. (Sweden)

AIHA American Industrial Hygiene AL action level Association analytical laboratory AIHX auxiliary intermediate heat analytical limit exchanger AIN as low as possible AIMME American Institute of Mining and as low as practicable Metallurgical Engineers as low as practical AIMMPE American Institute of Mm. .ing, Metallurgical, and Petroleum ALARA as low as reasonably ach.ievable Engineers ALARP as low as reasonably practicable AIMS automated information management ALATA as low as technically achievable system ALCP area local control panel automatic isotopic measurement ALD acoustic leak detection AU """""I '* vel f intake AINSE r lian Institute of Nuclear .

Science and Engineering (now ALIP annular linear mduction pump ANSTO) ALJ administrative law judge AI&O annual inspection and overhaul ALKEM Alpha Chemie und Metallurgic, AIP American Institute of Physics G.m.b.H. (Germany) approval in principle ALMPC Agency Labor-Management AIRI Atomic Industry Research Institute artnersy Committee air intake, recirculation, and ALMR advanced liquid metal reactor AIRP purification ALMS auxi!!ary hquid metal system AIRS Advanced Incident Reporting System ALP assembly language preprocessor (IAEA/NEA) ALPHGR average linear planar heat generation ute A 4

NHC COL L ECTION OF AHHHEVIATIONS ALPR Argonne Low Power Reactor ANF actinide nitride fuel Army low-power reactor actinide nitride fueled ALRR Ames Laboratory Research Reactor Advanced Nuclear Fuels Corporation ALRS Apache Leap Research Site ANFO ammonium nitrate and fuel oil ALSI aluminum silicon alloy ANGRY Anti-Nuclear Group Representing ALUPA Association Luxembourgeoise pour Y rk l' Utilization Pacifique de ANI American Nuclear Industries l'Energie Atomique (Luxeinbourg) American Nuclea-Insurers ALWR advanced light-water reactor authorized nuclear inspector AM accident management ANIM Association of Nuclear Instrument AMAD activity median aerodynamic Manufacturers diameter ANL Argonne National Laboratory AMASS automated material accounting ANMC American National Metric Council AMCA r.10 ing n Conditioning Association ANO Arkansas Nuclear One AMCF alkali metal-cleaning facility ANOVA analysis of variance AMCO Aerojet Manufacturing Company ANP aircraft nuclear propulsion AMD alpha activity median diameter ANPR advunce notice of pioposed

• '#* "8 AMDEL Australian Mineral Development Laboratories ANPRM advance notice of proposed AMF automated materials frisker ANR

• '**k"E Association of Neutron AMI automat.ic motion inhibit Radiographer AMIC Arkwright Mutual Insurance Co. ANRA Armenian Nuclear Regulatory AMN Ansaldo Meccanico Nucleare, spa Authority (Italy) ANRE Agency of Natural Resources and AMPERE Atomes et Molecules pour Etudes Energy (Japan)

Radio-Electriques (Switzerland) ANS American Nuclear Society AMRR Army Materiels Research Reactor aquatic nuisance species AMS aerial monitoring system autodial network system Allegations Management System ANSI American National Standards Army Map Service Institute AMSAC ATWS (anticipated transient without ANSTO Australian Nuclear Science and scram) mitigatmg system actuation Technology Organization (formerly circuitry AINSE)

AMU aqueous makeup AO abnormal occurrence atomic mass unit air operator A/N alphanumeric auxiliary operator as needed axial offset ANC advanced nodal code AOA axial offset anomaly Aerojet Nuclear Company AOC action office contact ANCC Associazione Nazionale per il augmented operator capability Controllo della Combustione (Italy) AOG acid fractionator off-gas ANDIN Associazione Nazionale di acid off-gas Ingegneria Nucicare (Italy)

ANEC American Nucle ir Energy Council "" E** "'* E"'

AOI abnormal operating instruction 5

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NHC 'OLLECTION OF ABBFiEVIATIONS ,

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advance o' .mg information AP&L Arizona Power & Light Company AOO anticie s.:d operational occurrence APLHGR average planar linear heat generation rate AOP abnormal operating procedure AOR abnormal occurrence report APM air paniculate monitor AOT action outage time aluminum powder metallurgy allowable outage time APP advance procurement plan allowed outage time APPA American Public Power Association APPR Army Package Power Reactor AOTA absorber open test assembly APR advance production release AOV air-operated valve AP access permit Army Power Reactor access permittee automatic pressure relief administrative procedure APRF Aberdeen Pulsed Reactor Facility advanced plant APRM average power range monitor alkaline permanganate APS accident-prone situation annulus pressurization American Physics Society antennas and propagation Arizona Public Service Co.

APA Administrative Procedure Act atomic power station APC administration and project control auxiliary power system AP600 Advanced Plant,600 MWe agency program coordinator argon purge cart APSR asial power shaping rod Atomic Power Construction Ltd. APSRA axial power shaping rod assembly (United Kingdom) Afrr accelerator-produced tritium APCA Air Pollution Control Association Applied Physical Technology APCEF Advanced Power Conversion Incorporated Experimental Facility AIYTR advanced pressure tube reactor APCO Alabama Power Company APU auxiliary power unit APD axial power distribution APWG action plan work group APDA Atomic Power Development APWR advanced pressurized-water reactor Associates, Inc. acceptable quality level AQL APDMS auxiliary power distribution AR action request

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activity ratio axial power distribution monitoring system ARAC atmos hen.c release advisory APET accident progression event tre ARACOR Ad anc d Research and Applications APEX Advanced Plant Experiment Corp.

APFA accelerator pulsed fast critical ARAVS auxiliary and radwaste area assembly ventilation system APHA American Public Health Association ARB Allegation Review Board API absolute podrion indication ARBOR Argonne Boiling Water Reactor 1 American Petroleum Institute ARC alarm response card f antecedent precipitation index Alliance Research Center APL Applied Physics Laboratory alternate repair criteria (University of Chicago) alternative repair criteria Arkansas Power & Light Co.

auxiliary relay cabinet l authorized possession limit A e

NHC COI l E C IlON OF ABBHFVlhllONS ,

ARDA Atomic Research and Development Agreement State Authority air supply ARDM age-related degradation mechanism auto sequential ARDUTLR a,ging-relatM Nradation unique to auxiliary steam heense renewal .

ARE aircraft reactor equipment air SyP l y ASA AREA Amencan Standards Association l Ameri,can Peilway Eng.meenng Associati' ", (now ANSI) {

ASADA Atomic Space and Development Army Reactor Area Authority ARG Accident Review Group (NRC) ASC Administrative Services Center Argonaut Argonn,e nuclear assembly for ASCE Amencan Society of Civil Engineers -

ARHCO A i Richf d Hanford Co.

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Elec ne nd Gas In e ARI alternate rod insertion ASCII American Standard Code for ATWS (anticipated transient without Information Interchange scram) rod injection ASCO American Switch Co.

ARIS automated reactor inspection system ASCS Agricultural Stabilization and ARM area radiation monitor Conservation Service ARMF Advanced Reactivity Measurement ASD adjustable speed drive Facility atmospheric steam dump ARMS aerial radiological measurement and ASDP alternative shutdown procedure

• ""#I ASEE American Society of Electrical aerial radiological measurements Engineers "I' #

• ASEP accident sequence evaluation area radiation monitoring system program area radiological monitoring system ASG auxiliary steam generator ARO all rods out ASGT asymmetric steam generator transient ARP accelerated requalification program ASGTPTF asymmetric steam generator transient alarm response procedure protective trip function annunciator response procedure ASHAE American Society of Heating and Air ARPA Archeological Resources Protection Conditioning Engineers Act ASHRAE American Society of Heating,  !

ARPI absolute rod position indication Refrigeration and Air Conditioning Engineers ARR Armour Research Reactor . .

. . ASI adverse systems mteraction Assoc.iation for Radiation Researcl- -

(United Kingdom) axial shape index ARRS airborne radioactivity removal ASIS American Society for Industrial system Secunty ARS acute radiation syndrome ASL approved suppliers list advance record system ASLAB Atomic Safety and Licensing Appeal Board (NRC) air return system ASLAP Atomic Safety and Licensing Appeal amplified response spectrum / spectra Panel (NRC)

ART aerosol release and transport ASLB Atomic Safety and Licensing Board anticipatory reactor trip (NRC)

ARTS anticipatory reactor trip system ASLBP Atomic Safety and Licensing Board l AS action statement Panel (NRC) l 7

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l NHC cot LECTlON OF ABBHEVIATlONS ASM American Society for Metals (now Bureau of (U.S. Department of ASM International) Treasury)

ASME American Society of Mechanical ATH artificial time history Engineers ATHEANA A Technique for Human Event ASME Analysis Code American Society of Mechanical ATOG abnormal transient operational Engineers Boiler and Pressure guideline Vessel Code anticipated transient operating ASNT American Society for Nondestructive guideline Testing ATP acceptance test plan Australian School of Nuclear acceptance test procedure Technology A&TP assembly and test pit ASP accident sequence precursor ATR advanced test reactor administrative site procedure ATRCE advanced test reactor critical auxiliary shutdown panel experiment ASPEA Association Suisse pour l'Energie ATS agency training system Atomique (Switzerland) Arkwn. ght Techm. cal Services, Inc.

ASQC merican Society for Quah.ty Atomtekniska Sullskapet i Finland (Finland)

ASR automatic send and receive ATSR Argonne Thermal Source Reactor ASS auxiliary steam systeso

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• ASSE American Society of Safety automatic turbine tester Engineers ASSP acoustics, speech, and sigral ATTU ATWS (anticipated transient without scram) transnutter trip unit processing American Society for Testing and ATU analog trip unit ASTM Materials ATWS anticipated transient without scram ASTPO Accident Source Term Program ATWS-RPT anticipated transient without Office scram-recirculation pump trip ASTR Aerospace Systems Test Reactor ATWT anticipated transient without trip ASW auxiliary saltwater AU authorized user auxiliary service water AUDIT automatic unattended detection inspection transmitter AT acceptable test AUEA auxiliary utility equipment area acceptance tag AUO auxiliary unit operator acceptance test ATBA advanced technical business area AUT automated ultrasonic test adiabatic toroidal compressor AUTODIN automated digital network ATC AUTOS automatic turbine control agncy upt;rade of technology for ce systems ATEL Aare Tessin Aktiengesellschaft fur Elektrizitut (Switzerland)

AUXI-ATOME Societ6 Auxiliaire pourl'Energie ATEN Association Technique de l'Energie Atomique (France)

Nucl6 aire (France)

AVB antivibration bar Association Technique, pour la Production et l' Utilization de AVIS atomic vapor isotope sgaration l'Energie Nucleaire (France) AVLIS atomic vapor her isotope separation ATF acceptance test facility AVMS annulus i acuum maintenance system Alcohol, Tobacco and Firearms, A B

l NHC COL LE CTIO'N OF ABBREVIATIONS AVR Arbeitsgemeinschaft AWNS ABB Westinghouse Nuclear Services Versuchsreaktor, G.m.b.H.

AWO automated work order (Germany)

. AWP automatic withdrawal prohibit automatic volume recognition AWRE Atomic Weapons Research AVSS automated vendor selection system Establishment (United Kingdom)

AVT all-volatile treatment AWS American Welding Society AVV atmospheric vent valve AWSF alpha waste storage facility AW acid waste AWWA American Water Works Association AWCC active well coincidence counter AZPS Arizona Public Service Co.

AWG American wire gauge I

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BA biological assessment BCL Battelle Columbus Laboratories B/A budget authority Bechtel client letter BAA broad agency announcement BCMS boron concentration measurement l BAC blood alcohol content system boric acid concentrator BCS Boeing Computer Services BACT best available control technology BCT best conventional technology BAF bioaccumulation factor BD blowdown bottom of active fuel BDAT best demonstrated available technology BAM Bundesanstalt fur Materialforschung und -pr0 fung (Germany) BDBA beyond-design-basis accident BAMT boric acid mix tank BDBE beyond-design-basis event BAP branch arm piping BDE beyond demonstrable effect BAPE branch arm piping enclosure BD/ECC blowdown / emergency core cooling BAPL Bettis Atomic Power Laboratory BDHT blowdown heat transfer BAPS branch arm piping shielding BDPS boric dilution protection system BARC Bhabha Atomic Research Centre BDS blowdown system

(. India) BDT best demonstrated technology BART butterfly analysis and review test BE best estimate BAST boric acid storage tank binding energy BAT backup auxiliary transformer bounding event best available technology BEA Bureau of Economic Analysis  ;

boric acid tank BEAR Biological Effects of Atomic i boric acid transfer Radiation, Committee on the BATAN Badan Tena BEC beginning-of-equilibrium cycle  ;

(Indonesia) ga Atom Nasional BECO Boston Edison Co. l BATEA best available technology BEEN Bureau d' Etude de l'Energie l economically available Nucl6 aire (Belgium)

BATF Bureau of Alcohol, Tobacco and BEF best-estimate flow Firearms (U.S. Department of BEIR Biological Effects of Ionizing Treasury) Radiation, Committee on the BAWTR Babcock & Wilcox Nuclear BEN Bureau d' Etudes Nucleaires, S.A.

Development Center Test Reactor (Belgium)

BBC Brown Boveri et Cie (Switzerland) BEPO British Experimental Pile Operation BBR Babcock-Brown Boveri Reaktor, BFN Browns Ferry Nuclear Power Plant G.m.b.H. (Germany)

BBRR Brookhaven Beam Research Reactor **"* #"I "** **' ""

BFNPP Browns Ferry Nuclear Performance BBS battery backup system Plan bulletin board system Browns Ferry Nuclear Power Plant BBV Bayrische Biologische BFO best and final offer Versuchsanstalt (Germany.)

BFY budget fiscal year BG&E Baltimore Gas & Electric Co. l

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BCD Battelle Columbus Division BGRR Brookhaven Graphite Research binary coded dec.imal Reactor BCIIFT beyond critical heat flux test BGV below-ground vault 11

NHC COLL ECTlON OF ABBREVIATIONS l

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BH Blue Hills Station boron measurement system BHEC Bangor Hydro-Electric Co. BMT basement melt-through ,

BHEP basic human error probability BN Belgonucl6 aire S. A. (Belgium)

BHL bottom of heated length board notific . tion j BHP biological hazard potential Buestra Neutron (Soviet-designed I BHS Blue Hills Station fast-neutron reactor) )

BHSP basic human success probability BNC Berkeley Nucleonics Corporation {

BI background information BNDC British Nuclear Design &  !

Construction Ltd. i BIA buyers information advisory BNEC British Nuclear Energy Conference

. BNES British Nuclear Energy Society BIFEN Banque International pour le Financement de l'Energie Nucl6 aire BNF British Nuclear Forum (France) BNFL British Nuclear Fuels, Limited BIOMASS Biosphere Modeling and BNFP Barnwell Nuclear Fuel Plant Assessments (project) BNI Bechtel National, Inc.

BIOMOVS BNL Brookhaven National Laboratory II Biosphere Model Validation Study, BNP Bellefonte Nuclear Plant Phase II

. . BNWL Battelle Northwest Laboratory BIOS basic input-output system BO biological opinion biologicalinvestigation of space

" S#t oveday BIR boron injection recirculation

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BIST boron injection surge tank bas. '" der agreement BOA ic or BIT boron injection tank Bernische Kraftwerke, A.G. an t w er agreement BKW (Switzerland) BOC beginning of cycle BLBE beyond-licensing-basis event Bevitron orbit code BLIS baffle / liner interface seal bottom of conduit BLM Bureau of Land Management budget object classification BLP basket loading pool BOD biochemical oxygen demand BLTC bottcm loading transfer cask biological oxygen demand BM bill of material BOEC beginning-of-equilibrium cycle boron measurement BOG burner off-gas BMEP brake mean effective power BOL beginning oflife brake mean effective pressure BONUS boiling nuclear superheat reactor BMEWS ballistic missile early warning system BONUS BMFT Bundesministerium fiir Forschung -CX boiling nuclear superheat critical und Technologies (Germany) experiment BMI Battelle Memorial Institute BOP balance of plant BML bidders mailing list BOPSSAR balance-of-plant standard safety an lysis rep rt bulk material length BORAX boiling-water reactor experiment BMR Bureau of Mineral Resources (Australia) BORE beryllium oxide reactor experiment (f rmerly EBOR)

BMRR .Brookhaven Medical Research Reactor B&OTF bulletins and orders task force BMS boron management system B/P blueprint B 12

' NHC COL LECTION OF ABBREVIATIONS 1 ,

BPA blanket purchase agreement boron recycle system Bonneville Power Administration BRWM Board on Radioactive Waste BPC Bechtel Power Corporation Management BPF blueprint file BS Braidwood Station BPFM bypass flow module Byron Station BPHA benzoylphenylhydroxylamine B/S bistable BPID book physical inventory difference BSEP Brunswick Steam Electric Plant BPN breakdown pulse noise BSF bulk shielding facility BPNL Battelle Pacific Northwest BSI British Standards Institution ,

Laboratory BSL Bignier Schmid-Laurent (France)

BPR beryllium physics reactor BSR Board of Standards Review burnable poison rod (American National Standards Institute) business process redesign bulk shielding reactor i business process reengineering BSS basic safety standard BPRA burnable poison rod assembly l BST bleed storage tank l BPV boiler and pressure vessel blowdown suppression tank bypass valve B&PV boiler and pressure vessel BT 1 gt n tion BPVC Boiler and Pressure Vessel l Committee broadcast technology BPWS blanked position withdrawal BTFA benzoyltrifluoroacetone l

sequence BTP backfit test program i Bq becquerel branch technical position BR breeder reactor BTR boron thermal regeneration breeding ratio BTRS boron thermal regeneration system B&R Brown and Root, Inc. BTS Brazilian thorium sludge budget and reponing BUSS backup scram system Burns and Roe,Inc. B&V Black & Veatch BRC below regulatory concern BVFA Bundesversuchs- und Breeder Reactor Corporation Forschungsanstalt Arsenal (Austria)

Bureau of Radiation Control (State BVPS Beaver Valley Power Station i of Texas) B&W Babcock & Wilcox Co. (now BREDAT Breda Tennomeccanica, spa (Italy) Framatome) l i BREN Bare Reactor Experiment Nevada B&WC Babcock & Wilcox Canada l

BREV. BWC Bingham-Willamette Co.

BWF building wake factor ATOME.Jes Soci6t6 BrevetsFranhaise bour App cation Nucl6 airela Gestion B&WFC Babcock & Wilcox Fuel Co.

l (France) BWIP basalt waste isolation program BRG budget review group B&WNT Babcock & Wilcox Nuclear BRil Bureau of Radiological Health Technologies BRP Bureau of Radiation Protection B&WOG Babcock & Wilcox Owners Group 1 BRPNP Big Rock Point Nuclear Plant BWR boiling-water reactor BRR Battelle Research Reactor BWROG Boiling Water Reactor Owners ,

Brookhaven Research Reactor Group l l

BRS Bibliographic Retrieval System 13 l

NHC COLL ECTION OF ABBREVIATIONS BWRVIP Boiling Water Reactor Vessel and B&WSSAR Babcock & Wilcox Standard Safety Internals Project Analysis Report BWST borated water storage tank i

l B ,4

CA charge amplifier CANE Connecticut Aircraft Nuclear construction aut dzation Experiment contract authorization CAOC constant axial offset control critical assembly CAP codes and paging C/A co Tective action continuous audit program CAA Clean Air Act corrective action plan CAC carrier access code corrective action program containment atmosphere control CAPCG Central Area Power Coordination Group CACS containment air cooling system CAPES containment atmosphere purge core auxiliary cooh.ng system exhaust system CACW core auxiliary cooling water CAPS cell atmosphere processing system CACWS core auxiliary cooling water system construction advanced planning and CAD code applicability document sequencing computer-aided design CAQ condition adverse to quality construction aid document CAQR condition adverse to quality report containment atmosphere dilution CAR condenser air removal CAES compressed air energy storage configuration acceptance review CAF chemical analysis facility containment air recirculation CAFEE critical assembly fuel element control advu,ory release exchange corrective action report CAFTA cutset and fault tree analysis CARA Compagnie d' Applications et de CAGT collaborative advanced gas turbine Recherches Atomiques(France)

CAHE core auxiliary heat exchanger CARA'IDM Compagnie d' Applications et de CAI constmction action item Recherches Atomiques(France) computer-assisted instruction CARC containment air recirculation and l cooling

! CAIT corrective action investigation team  !

CARS condenser air removal system l CAL confirmatory action letter containment atmosphere release corrective action letter system CALU- containment atmosphere l

TRON California University Cyclotron re:irculation system CAM constant air monitor CAS central alarm station containment atmospheric monitoring central alarm system continuous air monitor chemical addition system CAMEL component and material evaluation circuits and systems ,

l 100P compressed air system i CAMEN Centro Aut6nomo Militari Energia CASE Citizens Action for Safe Nucleare (Italy) Environment l

i CAN Citizen's Awareness Network Citizens Association for Sound CANDU Canadian Deuterium-Natural Energy Uranium Reactor consolidated aerospace supplier Canadian Deuterium Uranium evaluation l Reactor coordinating agency for supplier Canadian Natural-Uranium, evaluation Heavy-Water-Moderated and CAT chemical addition tank

-Cooled Power Reactor 15

NHC LOl l F TION OF ARHHF VIATIONS .

I computerized axial tomography core components conditioning station conditionally accepted tag core components conditioning construction appraisal team system crack arrest technology CCD coarse control damper crack arrest temperature counter-current digestion crack arrest test CCDF complementary cumulative distribution function CATD corrective action tracking document CCDP conditional core damage probability CAV crack arrest verification

. CCF common-cause failure cumulative absolute velocity

. .. CCFA common-cause failure CAVALIER Cooperatively Assembled Virgima analysis / analyses Low-Intensity Educational Reactor CCFL counter-current flow limitation CB containment buildmg CCFP conditional containment failure control building probability CBAST concentrated boric acid storage tank CCGC containment combustible gas control CBD Commerce Business Daily CCHEN Comisi6n Chilena de Energfa CBDT cause-based decision tree (method) Nuclear (Chile)

CBE Citizens for a Better Environment CCI core-concrete interaction CBECS control building environmental corium-concrete interaction control system CCM Sulzer Compagnie de Constmetion CBI Chesapeake Bay Institute Mscamque Sulzer (France)

CBI Industries (formerly Chicago CCN contract change notice Bridge and Iron Co.) CCNB Concerned Citizens for the Nuclear CB&l Chicago Bridge and Iron Co. 'iater Breeder CBI Industries) CCNPP Calvert Cliffs Nuclear Power Plant CBL Chesapeake Bay Laboratory CCP centrifugal charging pump Chesapeake Biological Laboratory chemical control procedure CBLA cost-beneficial. licensing action core component pot CBM circuit breaker m.mufacturer CCRC core component receiving container CBP computer-based procedure CCRS computerized cable routing system condensate booster pump CCS Carroll County Station CBPC Corn Belt Power Cooperative commitment control system CBFT closed-loop in-reactor assembly component cooling system backup plug tool c ndensate cleanup system CBR commercial breeder reactor c ndensate cooling system CBSR coupled breeding superheating reactor containment cooling system CBV containment building ventilation CCSS centrifugally cast stainless steel CC centrifugal charging CCSW component cooling service water coarse control CCTF cylindrical core test facility component check CCTL core component test loop component cooling CCTV closed <ircuit television CCAS containment cooling actuation signal CCU containment cooling unit CCB change control board CCW closed cooling water I chemical cleaning building component cooling water CCCJ core components cleaning system compound cooling water C' ,e

I 1

l condenser circulating water Chesapeake Energy Alliance condenser cooling water Commissariat & l'Energie Atomique counterclockwise (France)

CCWS closed cooling water system control element assembly component cooling water system Council of Economic Advisors CD civil defense CEAC control element assembly calculator C/D cooldown CEADS control element assembly drive CDA ntai ent depressurization CEAN e r d' Etudes ourles Applications de fEnergie Nucleaire core disruptive accident (Belgium)

CDAs controls, displays, and alarms CEBEL-CDBA containment design-basis accident COR Centre Belge d' Etude de la Corrosion CDC Center for Disease Control (Belgium) computer design code CEC Citizens Energy Council Control Data Corp. Claiborne Enrichment Center CDE condensate demineralization effluent Commission of the European CDF core damage frequency Communities cumulative damage function CECO Commonwealth Edison Co.

CDM central data management c st estimate change order certified design material CECS containment environmental control system CDN corporate data network CEDE committed effective dose equivalent CDP cask decontammation pit CEDM control element drive mechanism CDPA Civil Defense Preparedness Agency CEDMCS control element drive mechanism CDPr core damage probabihty control system CDR conceptual design requirement CEDS control element drive system CDRG Catastrophic Disaster Response CEEA Comisi6n Ecuatoriana de Energia l Group At6 mica (Ecuador) i CD-ROM compact disk / read-only memory Communaut6 Europeenne de CDS cask decontamination station l'Energie Atomique component disassembly station CEEN Centre d' Etude de l'Energie Nucl6 aire (Belgium) comput:r data screening CEER Center for Energy and Environment conceptual design study

. Research (Puerto Rico) den te demineralization Cbsyt u

CEFILAC Compagnie du Filage des Metaux et des Joint Curty (France) current d.isposal site CEG Contractor Engineering Group CDV capacitance discharge vaporization CEGB Central Electricity Generating Board CE Combustion Engineering,Inc. (United Kingdom)

Commonwealth Edison Co. cella contact equipment handling area conductivity element CEIC Cleveland Electric illuminating Co.

Consumer Electronics CEICO Cleveland Electric illuminating Co.

Corps of Engineers, U.S. Army CEL carbon equilibrium loop C/E calculation / experiment coating exempt log C-E Combustion Engineering,Inc. CEM Compagnie Electro-Mecanique CEA Cambridge Electron Accelerator (France) 17

CEN Centre d' Etudes Nucleaires (France) core exit thermocouple Centre d' Etude de l'Energie critical experiment tank Nucl6 aire (Belgium) CETR Consolidated Edison Thorium CENC Centre d' Etudes Nucl6aires de Reactor Cadarache (France) CETS control element test stand CENFAR Centre d' Etudes Nucl6aires de CEVAR consumable-electrode vacuum-arc Fontenay-aux-Roses (France) remelt CENG Centre d' Etudes Nucl6aires de CF column feed Grenoble (France)

CENS Centre d' Etudes Nucl6aires de Saclay

~ nha fuor (France) continuous How CENUSA Centrales Nucleares, S.A. (Spain) core flooding CENY Consolidated Edison Co. of New correction factor York CFAR component failure analysis report CEOG Combustion Engineering Owners CFB C.F. Braun and Co.

Group CFC Constructions Ferroviaires du CEPC Central Electric Power Cooperative, Centre, S.A. (Belgium) j Inc. CFCCS condensate and feedwater chemistry l CEQ Council on Environmental Quality control system

{ CER complete engineering release CFCU containment fan cooler unit condition evaluation report CFD cell Door drain critical experiment reactor computational fluid dynamics CERC Coastal Engineering Research CFDT Conf 6deration Fran aise Center, U.S. Army Democratique da Travail (France)

CERCA Centre de Recherches pour CFE clandestine fission explosive Combustibles Atomiques (France) Comisi6n Federal de Electricidad Compagnie pour l' Etude et la (Mexico)

R6alqation de Combustibles CFFTR Canadian Fusion Fuel Technology Atomiques (France) Project CERCLA Comprehensive Environmental CFH certified fuel handler Response, Compensation, and Liability Act CFI core Dooding interlock CERES Coalition for Environmentally CFM containment failure mode Responsible Economies CFO Chief Financial Officer CERL Construction Engineering Research CFR Code of FederalRegulations Laboratory commercial fast reactor CERMET ceramic and metal (fuel) condensate filter demineralized CERT candidate evaluation, certification, CFRE circulating-fuel reactor experiment and selection record CFRMF ou led fast reactor measurement constant extension rate test (ing) l Council of Energy Resources Tribes CFS cavity fission source CES critical experiment station condensate and feedwater system CESNEF Centro di Studi Nucleari Enric Fermi (Italy) core Good system CESR colliding electron-beam storage ring c re f nner stmeture CESSAR Combustion Engineering Standard CFT core flood tank Safety Analysis Repon core flooding tank CET containment event tree CFTC cooler flusher tank cell C 18

l NRC COLLECTION OF ABBREVIATIONS CFTE cooler flusher tank equipment containment isolation A  ;

CFTL component flow test loop CIAS containment isolation actuation CFU cumulative fatigue usage signal CFUR Citizens for Fair Utility Regulation CIB containment isolation B )

CFW condensate and feedwaar CIC carrier identification code j CFWS condensate and feedwater system CICA Competition in Contracting Act CGCS combustion gas control system CICAF Compagnie Industrielle des Combustibles Atomiques Frittes CGE Canadian General Electric (France)

CGEC Cincinnati Gas and Electric Co. CID component identification ,

CGEL cover gas evaluation loop CIEMAT Centro de Investi aciones CGI commercial-grade item Energeticas, Medfo Ambientales CGMS cover gas monitoring subsystem (SPam) cGy centigray CIIP condenser inservice inspection Program CHAP composite HTGR (high-temperature gas reactor) analysis program CILRT containment integrated leak rate test CHAT CLIRA (closed-loop in-reactor CIMI Compagnia Italiana Montaggi assembly) holddown assembly tool Industnali, spa (Italy)

CHCF component handling and cleaning CINDA computer index of neutron data facihty CIO Chief Information Officer CHEP conditional human error probability CIP containment improvement program CHF critical heat Dux C/IP construction / inspection procedure CHFR critical heat flux ratio CIPC Central lowa Power Cooperative CHGE Central Iludson Gas and Electric CIPP customized inspection program pilot Corp. customized inspection program CHLA candidate high-level action process CHLW commercial high-level waste customized inspection planning ,

CHMT components, hybrids, and Process (now IPAP) ]

manufacturing technology CIR Canada-India Reactor (India) i CHN construction hold notice CIREA Commission Interminist6rielle des f CHP certified health physicist Radio 616ments Artificiels (France)

C&HP chemistry and heal th physics CIRGA Critical Isotope Reactor, General ,

Atomic Co. I CHR cooling water / hot water retum CIRRPC Committee on Intera ency Radiation I CHRS containment heat removal system Research and Policy Coordination CHU centigrade heat unit CIRS containment iodine removal system CHWR cooling water / hot water retum CIS chemical injection system C/HWR cooling water / hot water return containment internal structure C-HWR cooling water / hot water return containment isolation signal C1 center island containment isolation system chemical injection contract information sheet containment integrity CISDEN Centro Italiano di Studi di Diritto containment isolation dell'Energia Nucleare (Italy)

C&I control and instrumentation CISE Centro Informazioni Studi Esperienze, spa (Italy)

Ci curie CISF centralized interim storage facility CIA CentralIntelligence Agency ,

l 19

l CISIP condenser inservice inspection CLSD Central Laboratories Services Dept. l program (TVA) l I CISSCO Comprehensive Information Systems CLSMDA closed-loop-system meltdown Support Consolidation accident CIT conductivity indicator transmitter CLWR commercial light-water reactor corporate investigation team CM coarse mixing critical incident technique condition monitoring CIV center island vessel configuration management combined intercept valve coolant mixing combined intermediate valve core melt containment isolation valve corrective maintenance CIWA condition identification work CMA classified mail address authorization CMAA Crane Manufacturers Association of CL closed loop America containment leakage CMC component modification card CLA cold-leg accumulator core monitoring computer CLAA Centre Lyonnais d' Applications CMCI core-melt / coolant interaction Atomiques (France) CMEA Council for Mutual Economic CLB current licensing basis Assistance (U.S.S.R.)

CLC closed-loop condensate CMEP Critical Mass Energy Project CLCGM closed-loop cover gas monitor CMF central maintenance facility CLCIS closed-loop control and common-mode failure instrumentation system core-melt frequency CLCS consequence limiting control system CMFA common-mode failure CLCV cold-leg check valve analysis / analyses CLCW closed-loop cooling water CMFLPD core maximum fraction of limiting CLEI Cleveland Electric Illuminating Co. p wer density CLEM closed-loop ex-vessel machine CMI care and maintenance instruction CLEMT closed-loop ex-vessel machine CML Critical Mass Laboratory transporter CMM core mechanical mockup CLIRA closed-loop in-reactor assembly CMMF component maintenance and mockup CLIV cold leg isolation valve facihty CLJA closed-loop jumper assembly CMOD crack mouth opening displacement CLLRW commercial low-level radioactive CMP CLEM (closed-loop ex-vessel waste machine) mamtenance pit CLOF complete loss of feedwater coastal management program CLOFA complete loss-of-fluid accident condition monitoring program CLOllS complex loss-of-heat sink configuration management plan CLP Connecticut Light and Power Co. controlled materials production CLR core lateral restraint CMPC Central Maine Power Co.

CLRWS clean liquid radioactive waste system CMRG Core Melt Review Group CLS cask loading station CMT core makeup tank closed-loop system CMTR certified material test report consequence limiting system certified mill test report CNA Canadian Nuclear Association 20

NHC COLLECTION OF ABBREVIATIONS Centrale Nucl6 aire des Ardennes CNWRA Center for Nuclear Waste Regulatory (Belgium) Analyses CNB Centrale Nucidaire Belge (Bugium) CO change order CNC condensation nuclei counter check open CNEA Comisi6n Nacional de Energfa chief operator At6 mica (Argentina) confirmatory order CNEN Comisi6n Nac,ional de Energfa contracting officer Nuclear (Mexico)

Comiss50 Nacional de Energfa COB close of business Nuclear (Brazil) COBOL common business-oriented language Comitato Nazionale per l'Energia COBRA Consolidated Omnibus Budget Nucleare (Italy) Reconciliation Act Conseil National de l'Energie coolant boiling and in-rod array Nucl6 aire (Luxembourg) COC cenificate of compliance CNET Center for Nuclear Engineering and certificate of conformance Technology Cleveland open cup (method)

CNEUPEN Commission Nationale pour l' Etude. COCA consent order and compliance de l' Utilization Pacifi Nucleaire (Belgium) que de l'Energie agreement CNFP commercial nuclear fuel plant COCORP Consortium of Continental Reflection Profiling CNI Consolidated National Interveners COD chemical oxygen demand CNN Cable Network News crack opening displacement CNNA China National Nuclear Corporation COE Corps of Engineers, U.S. Army CNO Chief Nuclear Officer COFIN-CNPP corporate nuclear performance plan ATOME Compagnie de Financement de CNR Committee for Nuclear l'Industrie Atomique (France)

Responsibility COG cell off-gas ,

CNRA Commi,ttee on Nuclear Re ulatory condenser off-gas Activities (of the OECD- EA)

CNRAG co orate nuclear review and audit COGAP co ustion g n1 r program company nuclear review and audit COI conflict of interest group COL combined operating license f

CNRM Centre National de Recherches construction / operating license M6tallurgiques (Belgium) COLR core operating limit report CNRN Comitato Nazionale per le Ricerche COLSS core operating limit supervisory Nucleare (Italy) system CNRS National de la Recherche core operating limit support system Centre,fique Scienti (France)

COM communications CNS Catawba Nuclear Station .

c mPuter output on microfiche Cherokee Nuclear Station C mPuter cutput on nucomm Cooper Nuclear Station COMET computer-operated management corporate nuclear safety evaluation technique  !

l CNSI Chem-Nuclear Sys2 ems, Inc. COM- i CNSN' Comisi6n Nacional de Seguridad RADEX containment and meteorology for Nuclear y Salvaguardias (Mexico) radiation exposure CNSR combination neutron source rod COMSEC communications security 2, C

NRC COLLECTION OF ABBREVIATIONS CONAGT Committee on Nuclear Air and Gas CPDO containment performance design Treatment (ASME) objective CONS Consolidation, Office of (NRC) CPDS condensate polishing demineralized COOP continuity of operations plan system committee on power plant siting CPE contractor performance evaluation COPPS COPS containment overpressure protection CPER construction permit environmental systems report CORAPRO Contrale-Radioprotection (Belgium) CPFF cost plus fixed fee CORAR Council on Radionuclides and CPG containment performance goal Radiopharmaceuticals CPI center pressure index COREN Combustibili per Reattori Nucleari, containment performance spa (Italy) improvement CORS catalytic oxygen removal system CPIC Capital Planning and Investment COS change of station Control COTS commercial off-the-shelf CPIS containment purge isolation signal COV center of vortex CP&L Carolina Power & Light Co.

coefficient of variation cpm count per mmute CP Callaway Plant CPM critical path method change proposal CPP Center for Plutonium Production charging pump coil power programmer Chicago Pile containment pre-entry purge civil penalty containment protection professional cold pipe CPPMU containment pre-entry purge makeup column product CPPR construction permit for a power

""'I I Comanche Peak CPR critical power ratio Commission paper CPRR construction permit for a research construction Permit reactor construction procedure CPRRG Comanche Peak Report Review containment purge Group coolant pump CPRT Comanche Peak Response Team critical power CPRW condensate polishing regeneration C/P current / pneumatic waste CP-5 Chicago Pile #5 CPRWCT condensate polishin regeneration waste c Hection tan '

CPA Cooperative Power Association CPS canister positioning system CPC Consumers Power Co.

c thodic protection system contact process cell Clinton Power Station controlled-potential coulometer c mputerized procedure system core protection calculator c ndensate polishing system core protection computer c ntamnwnt purge system CPCo Consumers Power Company c namn program system CPCSF construction permit containment support fixture core and plant system CPD condensate pump discharge cps count per second CPDD conceptual project design description CPSC Consumer Products Safety Commission C 22

NHC COLL ECTION OF ABHHEVIATIONS CPSCI central personnel security clearance CRDD control rod disconnect driveline index CRDHS control rod drive hydraulic system CPSES Comanche Peak Steam Electrical Station CRDM control rod drive mechanism CPU central processing unit CRDMS control rod drive mechanism shroud CPVC chlorinated polyvinyl chloride CRDR/A control room design review / audit CPWF cementitious pelletized waste form CRDS control rod drive system i CRDVF control rod drive ventilating fan I CQ Congressional Guarterly

. CRE collective radiation exposure (NRC CQAA corporate quality assurance audit performance indicator)

CQD code qualification document control room envelope CQE cogniz mt quality engineer controlled residual element critical quality element CREACS control room emergency air cleanup CR Chicago Reactor system civil rights CREATCS control room emergency air condition report temperature control system conditional release CREDO centralized reliability data organization Congressional Record CREFAS control room emergency fresh air containment rupture system contractor report CREFS control room emergency filtration control rod system control room CREH-CRA control rod assembly VACS contral room emergency heating, CRAC calculation of reactor accident ventilation, and air conditioning consequences system consequences of reactor accident CREST Committee on Reactor Safety and code Technology CRACS control room air conditioning system CREV control room emergency ventilation CRATS control room air temperature system CREVS control room emergency ventilation system CRAVS control room area ventilation system CRF capacity reduction factor CRB control rod blade correspondence routing form cost review board CRFAS control room fresh air system CRBR Clinch River Breeder Reactor CRFCU containment recirculation fan coil controlled-recirculation unit l boiling-water reactor CRG Center Review Group CRBRP Clinch River Breeder Reactor Plant CRGR Committee To Review Generic l Clinch River Breeder Reactor Project Requirements (NRC)

CRC critical reactor component CRGT control rod guide tube CRCPD Conference, of Radiation Control CRI Centre de Recherches et Program Directors irradiations (France)

CRCTA composite reactor components test control room indicator activity control room isolation CRD control rod drive criterion-referenced instruction control rod driveline CRIS control room isolation signal CRDA control rod drop accident CRM Centre de Recherches Metallurgiques CRDCS control rod drive control system (Belgium) 23 1

NRC COL L f CIIf HJ (>f AHHf E VIATIONS Centrum voor Research in de containment spray cooling Metallurgic (Belgium) core suppon cylinder certified reference material CSCC caustic stress-corrosion cracking chemical remnant magnetization CSCS core standby cooling system core restraint mechanism CSD cold shutdown count rate meter constant speed drive CRNGP Crystal River Nuclear Generating CSDD conceptual system design description Plant CSDF core segment development facility CRNL Chalk River Nuclear Laboratories CSE components and structures CRO control room operator engineering CRPI control rod position indication containment steam explosion CRS conductivity recording switch containment systems experiment Congressional Research Service CSF central service facility containment recirculation spray condensate storage facility CRSS containment recirculation spray containment suppon fixture SY ***

• Coulter Steel and Forge CRT cathode-ray tube critical safety factor collet retaining tube critical safety function CRTF core restraint test facility CSHX containment spray heat exchange CRU combmed rotating unit containment safety initiatives CSIP CRUD Chalk River unidentified depos.it program CRVICS containment and reactor vessel CSIS Center for Strategic and International isolation control system Studies CRW clean radwaste containment spray injection system CRWSS condensate and refueling water CSN Consejo de Seguridad Nuclear storage system (Spain)

CS carbon steel CSNE Citizens for Safe Nuclear Energy commumcations system CSNI Committee on the Safety of Nuclear component suppon Installations (NEA) containment safety CSOEC Columbus and Southern Ohio containment spray Electric Co.

contract specialist CSP Coalition for Safe Power control system conditional success probability core spray contamment spray pump current status core spray pump CSA chemical storage area CSirr core suppon performance test core special assembly CSR cable spreading room core stmeture accident CSRS containment spray recirculation system CSAS containment spray actuating signal CSS cask suppon stmeture containment spray actuating system cast stainless steel containment spray actuation signal c ndensate storage system CSAU code, scaling, applicability, and uncenainty (methodology) contamment spray system CSB core support barrel core spray system CSC Computer Sciences Corporation core support structure C 24

NRC C,OLL ECTION OF ABBREVIATIONS CST condensate storage tank CURE Citizens United for Responsible CSTB condensate storage tank building Energy CSTR continuously stirred tank reactor CUSP City Utilities of Springfield CSTS condensate storage and transfer C'U W S cask unloading warm shop system CV check valve CSTS construction and startup/ turnover containment vessel surveillance group control valve cSv centisievert CVA consecutive-valve actuation CSWS Central and Southwest Services, Inc. CVAS controlled ventilation area system CT cable test CVC chemical and volume control CLEM (closed-loop ex-vessel CVCS charging and volume control system machine) transporter chemical and volume control system compact tension CVH containment vent header computerized tomography CVI certified vendor information c Ung tower containment ventilation isolation cumnt trans[ormer CVIS containment ventilation isoletion CTBT Comprehensive (Nuclear) Test Ban signal eaty CVL continuous vent line CTD charged tape detection CVN Charpy V-notch CTF cask tilting fixture construction verification notification CTG combustion turbine generator CVP continuous vacuum priming C/Th carbon-to-thorium atomic rati CVPETS condenser vacuum pump effluent CTI Cooling Tower Institute treatment system CTL Canatom Ltd. (Canada) CVPSC Central Vermont Public Service CTM cable transfer machine Corp.

collimation test module CVPV containment vacuum pump valve CTOS cassette operations system CVTR Carolinas-Virginia Tube Reactor CTP construction test procedure CW case work controlled temperature profile circulating water CTR certified test result cold worked controlled thermonuclear reactor column waste CTRM control room cooling water CTS concentrate transfer system CWA Clean Water Act condensate transfer and storage CWB chilled water building current technical specification CWIP construction work in progress CTT cask transfer tunnel CWO capital work order CTTP cask transport and testing program CWP contractor work plan l CTVC cable tray vertical chase control withdrawal prohibit l

C/U carbon-to-uranium atomic ratio CWPC calcined waste packaging cell CUB Citizen's Utility Board CWPH circulating water pump house CUC cask unloading cell CWR cooling water return CUF cumulative usage factor CWS circulating water system CUP cask unloading pool chilled-water system ,

l compressed work schedule i

2s C

I l

NHG GOL LE CTION OF ABHf 4E VIAIlONS cooling water system CYAP Connecticut Yankee Atomic Power CX column enractant , Co.

criticality experiment CYAPCO nnecticut Yankee Atomic Power j CY calendar year i l

1 26

~

.NHC col L EC1 ION OF ABBHE VIATIONS DA deaerator DBR design-basis reconstitution dose assessment DBT design-basis tomado DAC datived air concentration DB'IT ductile-to-brittle transition aesign acceptance criteria temperature discretionary access control DBVP design baseline and verification distance amplitude correction E*E'"*

DC data control DAE Department of Atomic Energy (India) design contractor DAEC Duane Arnold Energy Center document control DAF dynamic amplification factor drain channel DANATOM Danish Association for Industrial de direct current Development of Atomic Energy DCA design change and authorization DAR design assessment report Dosimeter Corporation of America DAS data acquisition system drain channel A disturbance analysis system DCAA Defense Contract Audit Agency diverse actuation system DCB drain channel B DASHO Designated Agency Safety and DCC damaged core coolability Ilealth OfFcial Dam.e ls Construction Company DAT disconnect actuating tool degraded core coolability DatF Deutsches Atomforum e.V. DCCA Data Computer Corporation of (Germany) Amenca DAVDS . da acquisition and visual display DCD design certification document design control document DAW dry active waste document control desk DAYP Dairyland Power Cooperative DCF dose conversion factor DB dry bulb DCFO Deputy Chief Financial Officer DBA design-basis accident DCGL derived concentration guideline DBD design-basis document DCH direct containment heating design-basis documentation drain collectica header DBDA desi n-basis depressurization accibent DCIP design change improvement program DBE design-basis earthquake l DCIR daily Cadweld inspection report design-basis event DCM Delaware Custom Material DBF design-basis fault DCN design change notice dominant bubble frequency document change notice l DBFA design-basis fuel assembly DCNPP Diablo Canyon Nuclear Power Plant l DBFB deep-bed filter and blower DCP design change package DBFL design-basis flooding level design change proposal DBI design-basis incident document control procedure i DBLOCA design-basis loss-of-coolant accident Donald C. Cook Plant DBMS database management system DCPD direct current potential drop l DBNPS Davis-Besse Nuclear Power Station DCR defueling completion report DBOA delayed breeder or altemative design change request DBP dibutyl phosphate direct conversion reactor DBPB design-basis pipe break DCRDR detailed control room design review 27

NHC'COLRCTf0N OF ABBREVlATlONS

~

l DCRN dashpot cup retention nut DEG double-ended guillotine DCS document control system DEGB double-ended guillotine break DCSP dry cask storage project DEH digital electrohydraulic DCSS dry cask storage system DEHL double-ended hot leg DCT differential current transformer DEHLG double-ended hot-leg guillotine DCV directional control valve DEI dielectric and electrical insulation DCX direct current experiment dose equivalent iodine DD deputy director DEIS draft environmental impact statement Director's Decision DEMA Diesel Engine Manufacturers D-D deuterium 4euterium Ass ciation D&D decontamination and DEP design external pressure decommissioning diagnostic evaluation plan defueling and decommissioning diagnostic evaluation program DDD direct distance dialing (NRC)

DDH&DS digital data handling and display DEPS double-ended pump suction system DEPSG double-ended pump suction DDL detergent and decontamination liquid guillotine

[ system] DER Department of Environmental DDNB Research delayed departure from nucleate boilmg Departmera of Environmental DDR deficiency and disposition report Resources DDS digital data service design electrical rating DDT deflagration-to-detonation transition Deviation Event Report design data transmittal double-ended rupture DDTT drag disc-turbine transducer DERE Dounreay Experimental Reactor

. Establishment (Scotland)

DE diagnostic evaluation Detroit Edison Co. n dose equivalent DES data encryption standard double ended Department of Emergency Services DEA driver evaluation assembly double-ended slot Dmg Enforcement Administration draft environmental statement DEB double-ended break DESL double-ended suction leg DEC Digital Equipment Corporation DESLS double-ended suction leg slot DECL double-ended cold leg DET decomposition event tree DECLG double-ended cold-leg guillotine diagnostic evaluation team DECO Detroit Edison Co. DEW Deutsche Edelstahlwerke, A.G.

DECON decontamination and dismantlement (Germany)

DEDE Deputy Executive Director for DF debris formation Regulatory Effectiveness (NRC) decontamination factor DEDM Deputy Executive Director for D&F determination and fm' dings Management Services NRC dF dilution factor (also Fd)

DEDR Deputy Executive Director for Regulatory Programs (NRC) DF dilution factor DEFAS diverse emergency feedwater dose factor actuation system Df dose factor 28

'- 9 NRC COLLECTION OF ABBREVIATIONS DFA driver fuel assembly DHXCS dump heat exchanger control system dummy fuel assembly DID defense in depth DFBN debris-filter bottom nozzle DIE direct inspection effort DFC design field change DIMPLE Deuterium Moderated Pile Low DFCS digital feedwater control system Energy Reactor DFFR dynamic forcing function report DIP design internal pressure DFI demand for information DIPS dynamic isotope power system DFO designated Federal official DIS diverse indication system DFOS diesel fuel oil system DIV drywell isolation valve DFP decommissioning funding plan DL dead load diesel fire pump Duquesne Light Co.

DFR damaged fuel relocation DLAT discharge-line air temperature Dounreay Fast Reactor (Scotland) DLF dynamic load factor DFRP downcomer flow resistance plate DLL discharge-line length DFT dry film thickness DLRWS dirty liquid radioactive waste system DG diesel-engine generator DLV discharge-line volume diesel generator DLWL discharge-line water-leg length D/G diesel generator DM damage monitor DGA dummy guide assembly demineralized DGAS diesel generator auxiliary system DMA direct memory access DGB diesel generator building DMIMS digital metal impact morsring "Y S* **

DGCAIES diesel generator combustion air ,

intake and exhaust sy stem DMPL Delmarva Power and Light Co. i DGCWS diesel generator cooling water DMS data management subsystem system Defense Message Service DGEA draft generic environmental DMT dispersive mechanism test assessment DMTR Dounreay Materials Testing Reactor DGTOSTS diesel generator fuel oil storage and (Scotland) transfer system DMUX distributed multiplex DGFOTS diesel generator fuel oil trande: DMW demineralized makeup water

1. "Y# "#"I' "

DGLS ese generatorlubrication system discrepancy notice DGSS diesel generator starting system

^ # "** "# '#"

DGZ desired ground zero deoxyribonucle.' ic acid ^E "#Y DH decay heat does not apply DHHS Department of Health and Human departure from nucleate boiling Services DNB DH1 department head instruction DNBR departure from nucleate boiling ratio ;

DHP department head procedure DNFSB Defense Nuclear Facility Safety Board 1

DHR decay heat removal DNM delayed neutron monitor DHRS decay heat removal system DNMS delayed neu.ron monitoring direct heat removal service subsysterr direct heat removal system DNPS Dresder. Nuclear Power Station DHS decontamination hot shop DNRC Demccritos Nuclear Research Center l DHX dump heat exchanger (Greece) l 29

i 1

NHC col l E CllON Of AHHHEVIATIONS DNS domain name server DPP drip pan pot DNT dinitrotoluene DPR developmental power reactor DO designated official demonstration power reactor digital output DPRK Democratic People's Republic of dissolved oxygen Korea duty officer DPS demand position system DOC Department of Commerce DPV differing professional view dissolver off-gas condensate DR design review DOD Depanment of Defense designated representative DOE Department of Energy Danish Reactor DOG dissolver off-gas deficiency report DOI Department of the Interior discrepancy report DOL Department of Labor DRA dropped rod accident DOJ Department of Justice DRAP design reliability assurance program DOP detailed operating procedure DRC dropped rod control dioctyl phosphate D/RE disassemblyheassembly equipment

' disaster operations plan DRES direct reading emission spectrograph di-sec, octyl phthalate DRF dose reduction factor DORF Diamond Ordnance Radiation DRMW demineralized reactor makeup water Facility DRP disaster recovery plan DOS degree of sensitization discrete radioactive particle Department of State DRPI digital rod position indication disk operating system digital rod position indicator DOSAR Dosimetry Applications Research DRPIS digital rod position indication system Facility design review / quality revalidation DR/QR DOT Department of Transportation DRR document release record DP data processing DRS development requirements differential pressure specification D/P differential pressure disassembly / reassembly station DPA delegation of procurement authority DRW dirty radwaste DPC Dairyland Power Cooperative DS decoritamination shop Duke Power Co. design standard DPD decontamination as precursor to D/S dynamic / static decommissioning DSA diagnostic self-assessment DPE development project engineer DSAR defueled safety analysis repon discipline project engineer DSC design safety criterion / criteria DPIS differential pressure indicating dry shielded canister switch DPIV drywell purge isolation valve DPLC DSE d f safe y e aluation Dayton Power and Light Co.

DSER draft safety evaluation report dpm decade per minute DSI direction-setting issue disintegrations per minute . .

DSIR Department of Scientific and DPMM dewpoint moisture momtor Industrial Research (United DPO differing professional opinion Kingdom)

D 30

NHC COLLECTION OF ABBREVI TIONS A

DSL drawing and specification listing DVI direct vessel injection DSM defect-specific management DVM digital voltmeter DSO designated senior official DW deadweight director of site operations demineralized water D-T deuterium-tritium drywell DTA differential thermal analysis / analyses DWCS defueling water cleanup system DTER draft technical evaluation report DWEDS drywell equipment drain sump DTI diagnostic team inspection DWFDS drywell floor drain sump INNSRDC David Taylor Naval Ship Research DWG drawing and Development Center DWICA deep-water isotopic current analyzer DTPA diethylenetriamine pentaacetic acid DWK Deutsche Gesellschaft fur DTR document transmittal record Wiederaufarbeitung von DTRF data transmittal and routing form Kernbrennstoffen, m.b.H. (Germany)

DTRS development test requirement DWL depressed water leg specification drywell DTS differential temperature switch DWMS demineralized water makeup system DTT design thermal transient DWOC Don't Waste Oregon Council design transition temperature DWP detailed work plan DTV direct torus vent DWR Department of Waste Resources DUEGG dual-energy gamma group DWS demineralized water system DUN Douglas United Nuclear development work statement DUNC deep underwater nuclear counting DWST demineralized water storage tank dup-SR E.I. DuPont de Nemours and DWT drop weight test Company-Savannah River DYNAL dynamic analysis / analyses DUTS decision unit tracking system DVAL degraded voltage analytical limits l

31 D

NHC COLT ECTION OF ABBREVIATIONS i

EA enforcement action EC eddy current l l

engineering assurance emergency coordinator environmental assessment enforcement coordinator i element and attribute European Communities l E/A erratum / errata and event category addendum / addenda E/C erosion / corrosion E&A erratum / errata and ECA energy-conversion area addendum / addenda eng neering change authorization EAB exclusion area boundary ECAR East Central Area Reliability EAC emergency assessment coordinator Coordination Agreement EACC Environmental Assessment ECC emergency control center j Command Center entgency com coolant  !

EACRP European-American Committee on Reactor Physics emergency core cooling EACT emergency action and coordination ECCS emergency core cooling system team ECCW emergency core cooling water EAES European Atomic Energy Society (system)

EAG emergency action guidelines ECD electron capture device EAL emergency action level ECF emergency cooling function equipment air lock ECFM eddy current flowmeter EAP emergency action plan ECl emergency coolant injection Event Assessment Panel essential controls and l instrumentation i experimental activity proposal ECN Energieonderzoek Centrum EAPS essential auxiliary power system Nederland (Netherlands) l EAR event analysis report engineering change notice EAS essential auxiliary support ECNG East Central Nuclear Group, Inc.

expenment asstirance system ECNP Environmental Coalition on Nuclear EASE elastic analysis for structural Power engineenng ECP emergency cooling pond EASI estimate,of adversary sequence employee concerns program mterruption eng neering change proposal EAST Eastern Utilities Associates estim ted cntical position EATL energy-absorbing torque limiter EATS Enforcement Action Tracking EWA c"8 " ""8 " " ""

a s rance System ECR emergency coolant recirculation EB electron beam estim te change request EBASCO Electric Bond and Share Company ECS emergency control station EB ASCO Services Inc.

envir nmental control shroud EBOR experimental beryllium oxide reactor envir nmental contml system EBR experimental breeder reactor ECSP employee concerns special program EBS emergency barrier system EN entgency condensate storage tank Emergency Broadcast System ECT eddy current test EBTF ECC (emer ene core cooling) bypass test hacilfty emergency cooling tower ECTG employee concerns task group EBWR experimental boiling-water reactor ECTS electronic custom telephone set l 33 E

. NHC COLLECTION OF ABBREVIATIONS electronic custom telephone system explosives detector team ECU environmental control unit EDTA ethylenedinitrilo tetraacetic acid ECW emergency cooling water EDTS equipment drain treatment system essential chilled water EEC end-of-equilibrium cycle ECWP emergency cooling water pond European Economic Community ECWPH emergency cooling water pump EECW emergency equipment cooling water house EEI Edison Electric Institute ED electron device EEM extrapolated endpoint method exhaust damper EEPVS electrical equipment protection EDAX energy dispersive x-ray ventilation system analysis / analyses EEQML electrical equipment qualification EDB engineering database master list EDC emergency decontamination center EEQSP environmental equipment ED&C electrical distribution and control qualification summary package EDCN engineering drawing change notice EER engineering evaluation request EDCP emergency design change package EERF as m Environmental Radiation E&DCR engineering and design coordination report EES economizer-evaporator superheater EDECWS emergency diesel engine cooling emergency exhaust system j

water system EESWS emergency equipment service water EDELS emergency diesel engine lubrication system system EFAPP Enrico Fermi Atomic Power Plant EDESS emergency diesel engine starting EFAS e,mergency feedwater actuation system signal EdF Electricity de France (France) emergency feedwater actuation EDG emergency diesel generator system ED/G emergency diesel generator EFC error-forcing context i EDGCAIES emergency diesel generator EFCO Engineers and Fabricators Company combustion air intr.ke and exhaust EFCV excess flow check valve system EFD engineering flow diagram EDM electric discLrge machining EFDS equipment and floor drainage system I electrical disintegration machining EFFBR Enrico Fermi Fast Breeder Reactor i EDN engineuing discrepancy notice EDO EFI Enrico Fermi Institute )

Executive Director for Operations EFIC emergency feedwater initiation and l

(NRC) control l EDP electronic data processing EFM expected flow measurement EDRO Executive Director of Re EFNS Educational Foundation for Nuclear Operations, Office ofS.(U.gional Food and Science Drug Admmistration) I

. . . EFO equipment forced outage (NRC i l EDS electrical distribution system performance indicator) experimental data system EFOIA Electronic Freedom of Information explosives detection system Act EDSFI electrical d, distribution system EFP electric fire pump functional mspection Enrico Fermi Atomic Power Plant EDT energy dissipation test EFPD effective full-power day equipment drain tank equivalent full-power day l I

34 l

l i

i NRC COLLECTION OF ABBRE VIATid '

n .

EFPil effective full-power hour EJ environmentaljustice EFPM effective full-power month EKG effective kilogram EFPY effective full-power year EKMS Electronic Key Management System l EFS emergency feedwater system EL Elettronucleare Italiana (Italy)

EFT emergency filter treatment ELMS electrical load monitoring system l emergency filter train ELP Employees Legal Project EFW emergency feedwater ELPliR experimental low-temperature EFWS emergency feedwater system pr cess heat reactor EFWST emergency feedwater storage tank ELR effectiveness limiting risk EG emergency generator ELS error-likely situation EGCR experimental gas-cooled reactor ELU emergency lighting unit EGDN ethylene glycol dinitrate EM electromagnetic EG&G Edgerton, Germeshausen & Grier elevation model EGM enforcement guide engineermg management memorandum / memoranda environmental management EGTS emergency gas treatment system evaluation model Eli electrohydraulic E/M electromechanical EllC electrohydraulic control E-MAD engineering, maintenance, assembly, EliNP Edwin 1. lietch Nuclear Plant disassembly EHR emergency heat removal EMB engineering in medicine and biology EllT effluent holdup tank EMC electromagnetic capability FliV extra high voltage electromagnetic compatibility

{

emergency injection emergency management coordinator engineering instruction engineering mockup critical

, . . expenment i E&l electncal and instrumemation . .

EMI electromagnetic mterference EIA Energy Information Administration . .

engmeermg and manufacturing environmental impact appraisal instruction EIAP environmental impact assessment EMO electric motor operated

( pmject EMOV electromagnetically operated valve EICC emer ency information and coor nation center EMP electroma8netic Putse Ells energy industry identification system EMR electromagnetic radiation EIP emer ncy implementation EMRV electromagnetic relief valve procedure EMS earthquake monitoring system ElR Eidgenossisches Institute fur emergency management system l Reaktorforschung (Switzerland) Emergency Medical Services i engineering information request EMT electrical metallic tubing equipment inoperable record emergency management team EIS effluent inventory system executive management team electrical and instrument shop EN enforcement notification electrical isolation scheme event notification emergency injection system ENC Exxon Nuclear Company, Inc. j environmental impact statement ENDESA Empresa Nacional de Electricidad, environmental information system S.A. (Chile) 35 '

l 1

^

NRC COLT E CTlON OF ABBHE VfATlONS ENEA European Nuclear Energy emergency preparedness Association emergency procedure ENEL Ente Nazionale per l'Energia equipment piece Elettrica (Italy) .

1. '##I"#"' E"#"*

ENERGO-EPA electrical penetradon assemNy ATOM Nuclear Power Utility (Ukraine) . .

ENI Electro-Navale et Industrielle, S.A. #"E*##""E E ""*"" Y*#'

(Belgium) Environmental Protection Agency ENO extraordinary nuclear occurren:e EP Act Energy Policy Act of 1992 ENPI Ente Nazionale Prevenzione EPB emergency planning basis / bases Infortuni (Italy) EPBE emergency-planning-basis event ENRESA Empresa Nacional de Residnos EPC emergency preparedness coordinator Radiativos (Spain) engineering planning coordinator ENS emergency notification system EPDC Electric Power Development Co.

European Nuclear Society Ltd. (Japan)

ENSA Equipos Nucleares (Spain) EPDM ethylene propylene diene monomer ENSI Energia Nucleare Sud Italia (Italy) EPE emergency plan evolution ENUSA Empresa Nacional del Uranio, S.A. emergency preparedness evaluation (Spain) EPEC El Paso Electric Co.

Energie Nucl6 aire, S.A. EPFE electrical penetration filter and (Switzerland) exhaust EO emergency officer EPG emergency procedure guideline enforcement officer EPI Environmental Policy Institute equipment operator EPIA emergency preparedness E.O. Executive Order implementation appraisal EOC emergency operations center EPIP emergency plan implementing end of cycle procedure error of commission EPIX Equipme,nt Performance and Information and Exchange System EOCR experimental organic-cooled reactor (replaces NPRDS) (INPO)

EOC-RPT end-of-cycle recirculation pump trip EPL environmental protection limit EOD explosives ordnance disposal EPM electrical power monitoring EOEC end-of-equilibrium cycle end path manual EOF emergency operations facility engineering project manager EOl emergency operating instruction engineering procedure Entergy Operations, Inc. memorandum / memoranda EOL end oflife environmental project manager EOO error of omission EPP engineering program plan EOP emergency operating plan environmental protection plan emergency operating procedure EPR electromechanical potentiokinetic EOS equation of state reactivation EOY end of year emergency planning requirements EP electric power emergency planning review emergency plan enhanced participatory rulemaking emergency planning essential performance requirement emergency power EPRG emergency planning review guideline E 36

, NHL Coll I C flON Of ABBHE VIATIONS EPRI Electric Power Research Institute ERDA Energy,Research and Development EPROM electronic programmable read-only Admmistration memory ERDAM Energy Research and Development EPRTCS emergency power ride-through Admmistration Manual capability system ERDS Emergency Response Data System EPS electric power system (NRC) emergency power system ERF emergency response facility EPSL emergency power switching logic entrainment release factor EPSS emergency power sequencing explosion release factor subsystem ERFBS electrical raceway fire barrier system Elrr ethylene-propylene terpolymer ERFDADS emergency response facility data EPZ emergency planning zone acquisition and display system environmental qualification ERFIS emergency response facility EQ

'" "" ' " 'Y#

• environmentally qualified

. ERG emergency response guideline {

equipment qualification ERIE emergency resources identification i EQC equipment qualification coordm.ator equipment i EQD environmental qualification ERIS emergency response information document system EQDB equipmen; qualification database ERL emergency reference level EQDF equipment qualification data file ERO engineering release order EQDP environmental qualification data EROD executive resources and package organizational development EQEDC equipment qualification EROS earth resources observation system

" ' ign

$i r ohen"t ria electric radiological occurrence EQML equipment qualification master list ERP e a ed release point EQ-TAP environmental qualification-task action plan emergency response procedure equipment qualification-task action ERPA emergency response planning area l

plan ERR Elk River Reactor ER emergency response ERS Economic Research Service l

environmental report ERSP earth resources survey program l ERA Economic Regulatory Administration ERT emergency repair team Energy Research Abstracts emergency response team j Energy Reorganization Act employee response team ERB Executive Resources Board event response team experiment review board ERTS environmental radiological technical ERBS emergency radio broadcast system specification ERC emergency relocation center environmental resources technology satellite emergency response coordinator ERV emergency relief valve Engineering Research Council ERVC external reactor vessel cooling ERCOT Electric Reliability Council of Texas ES engineered safeguards ERCW emergency raw cooling water examination standard essential raw cooling water  ; ,

ERCWS emergency raw coolmg water system gg g;g j 37 F

NHC COLLECTION OF ABBREVIATIONS -

ESADA Empire States Atomic Development ESSE EBASCO Site Support Engineering Associates ESSP earliest scram set point ESAS emergency safeguards actuation ESW electroslag welding "Y#* emergency service water engineered safeguards actuation  ;,;  ;

system ESCA extended source calibration area ESWD emergency service water discharge ESCO Electrical Steel Company ESWI emergency service water intake ESCOM Electricity Sup ESWS emergency service water screening (South Africa) ply Commission emergency service water system ESCP employee safety concerns program essential service water system ESCWS essential services cooling water ESWSS emergency service water supply system system ESD electrostatic discharge ET emergency tank extension shaft disconnect executive team ESDR engineered safeguards design rating ETA equipment transfer aisle ESEERC Empire State Electric Energy estimated time of arrival Research Corporation ETBS elevated tubesheet and baffle sleeve ESF engineered safety feature ETC estimated time of completion exploratory shaft facility ETE evacuation time estimate Exploratory Studies Facility ETEC Energy Technology Engineering ESFA engineered safety feature actuation Center ESFAS engineered safety features actuation ETF extended task force system ETG electrical test group ESFS engineered safety feature syste ETL environmental team leader ESFVS engineered safety feature ventilation ETP equivalent top product system ETQAP education and training in quality ESO emergency suppon organization assurance practices Engineering Service Organization ETR engineering test reactor ESP carth-surface potential ETS elevated tubesheet sleeve ESQ equipment seismic qualification Emergency Telecommunications ESR early site review System electron spin resonance emergency trip system experimental superheat reactor environmental technical specification ESRG Energy Systems Research Group events tracking system ESRP environmental standard review plan E&TI' engineering and technical training ESRR early site review report EUB emergency utility building ESS electronic switching system EURATOM European Atomic Energy engagement simulation system Community evaporation / solidification system EV evaporator vessel ES&S engineering services and safety exhaust valve ESSA Environmental Science Services EVA early valve actuation Administration EVCC ex-vessel core catcher ESSAR early site safety analysis report EVESR ESADA (Empire States Atomic EBASCO Standard Safety Analysis Development Associates) Vallecitos Report experimental Superheat Reactor 38

d NRC COL L ECTION OF ABBREVIATIONS EVFM ex-vessel flux monitor EWEB Eugene Water and Electricity Board EVHM ex-vessel handling machine EWG exempt wholesale generator EVS emergency ventilation system EWST elevated water storage tank EVSE ex-vessel steam explosion emergency water storage tank EVST ex-vessel storage tank EXSIS executive shared information system EVTM external vessel transfer machine EZB exclusion zone boundary ex-vessel transfer machine l

l l

l l

39 1

1

NHC COL l_E C TION UF ABBREVIATIONS l

FA forced air FEV fuel building ventilation l fuel assembly FC fail closed full arc fine control l F/A fuel assembly flow controller FAA Federal Aviation Administration fuel cycle fresh acid add FCA field change authorization FaAA Failure Analysis Associates FCAW flux cored are welding FAB ISO fabrication isometric FCD fine control damper FAC fmal acceptance criterion / criteria full core discharge flow-accelerated corrosion functional control diagram FACA Federal Advisory Committee Act FCE flexible critical experiment FACNFT Federal Acquisition Computer FCG fatigue crack growth Network FCI Fluid Controls Institute FAF Forum Atomique Frangais (France) fuel-coolant interaction FAI fail as is FCN field change notice FAP fatigue action plan FCO funds cenifying official FAPIG First Atomic Power Industry Group FCP field change package ast ceramic nactor FAR Federal Acquisition Regulation I"* ""#'S " '"U aux-Roses Nuclear Fontenak Researc Center (France) field change request functional analysis report FCS Fort Calhoun Station FARA Federal Acquisition Reform Act F&CS feedwater and condensate system FARET fast reactor test assembly FCTT fuel cladding transient tester FAS Federation of American Scientists FCU fan coil unit FASA Federal Acquisition Streamlining Act FCV flow control valve of 1994 Fd dilution factor (also dF)

FASAB Federal Accounting Standards F/D filter / demineralized Advisory Board F&D finding and determination FASB Financial Accounting Standards FDA final design acceptance Board fin 1 design analysis FAST fuel aerosol simulation test fuel assembly stability test FATT fracture appearance transition final des!E" "PP'"*"l ign authonzation j

temperature Food and Drug Administration '

FAX facsimile FDAA Federal Disaster Assistance I Administration FBACS fuel building air cleanup system FBC fluidized bed combustion " PP " 8" l

['e" iffcatn FBFC Soci6t6 Franco-Belge de Fabrication FDA-EDRO Food and Drug Administration, de Combustible (France) Office of Executive Director of FBFS fuel building filter system Regional Operations FBI Federal Bureau oflevestigation FDB Fahrenheit dry bulb

' FBR fast breeder reactor FDC functional design criterion / criteria FBRF fast burst reactor facility FDDR field deviation disposition request FBTA function-based task analysis FDG fluid distribution grid 41

r Jiu- ( 3 A i I (,1M ;f J Qf AHHHF VI A IlON$

FDI field disposition instruction FERMILAB Fermi National Accelerator FDLP Federal Depository Library Program Laboratory (GPO) FERP fire emergency response plan FDM frequency division multiplex FERS Federal Employees' Retirement FDR final data report System final design report FES final environmental statement functional design requirement FF filter factor FDS final docketed special fluorine facility fire detection system FFD fitness for duty floor drain system FFE Federal field exercise FDSA facility description and safety FRERP (Federal Radiological analysis / analyses Emergency Response Plan) field FDT floor drain tank FFF uel ailire ra non d

FFI full field investigation w el nwnt

. FFLA Family Friendly Leave Act FEA Federal Energy Adm. .mistration FFLS failed fuel location subsystem front-end analysis / analyses g gg g; FECCSR failure of emergncy core cooling FFP fuel fabrication plant FEDAL failed element detection and location FFR folded flow reactor fuel element detection and location FFRDC Federally Funded Research and FEDP deral Executive Development

1. E*#" #"

g ,  ;

FEF foreign event file FFTFPO Fast Flux Test Facility Project Office fuel examination facility FFWT final feedwater temperature fusion energy foundation FG fission gas FEFP fuel element failure propagation FGAA Federal Government Accountants FEFPL fuel element failure propagation loop

^** " " "

c rg as an Electdc Ught Co.

FEGL' Federal Employees' Group Life Insurance FGM fission gas monitor FEIS final environmental impact statement FGS Fulton Generating Station full electrical isolation scheme FIIA fire hazard analysis FELAP finite element analysis program fuel-handling accident FEMA Federal Emergency Management FHAR fire hazards analysis report Agency FHAVS fuel-handling area ventilation system FEO facility emergency organization FHB fuel-handling building FEP facility emergency plan FHBVI fuel-handling building ventilation FEPCA Federal Employees Pay isolation Comparabihty Act of 1990 FHBVS fuel-handling building ventilation FEPs features, events, and processes system FERC Federal Energy Regulatory FHC fuel-handling cell Commission FHE fuel-handling equipment FERD fuel element rupture detection FHES fuel-handling equipment system FHFP full height, full pressure 42

e

• NHC COLL E CIION OF AHHHEVIATIONS FIIIS fuel-handling isolation signal FLIT free limiting internal tmss FilOB fuel-handling operator booth FLST full-length source term FHP fuel-handling procedure FLTS full-length tubesheet sleeve Fl{PC fuel-handling and preparation cell FM Factory Mutual Fil&RM fuel-handling and radioactive fracture mechanics mamtenance frequency multiplier FHS fuel-handling system FMCRD fine motion control rod drive FHSR final hazards safety repon FME foreign material exclusion final hazards summary report FMEA Factory Mutual Engineering Flit feec' water holding tank Associates FHU fuel-handling unit failure modes and effects FI now indicator analysis / analyses FIA Factory Insurance Association FMEF fuels and materials examination facility FIAS flow indicator alann switch FIEN Forum Italiano dell'Energia Nucleare FMF MM feb FMIT (Italy) fusion materials irradiation test j FIFO first in, first out FMRC Factory Mutual Research FIM field inspection manual 'E '* * ' "

FMS flux monitoring system FIMA fission per initial heavy metal atom

• • ** "'8 I #'E'"*

FIN financial identification number FNP Doating nuclear plant FIP Federal information processing FNR Ford Nuclear Reactor field inspection procedure FO fail open FIPS Federal information processir.g FOA forced oil and air FIR food irradiation reactor FOAKE first-of-a-kind engineering FIRM failure introspection in rotating FOCI foreign ownership, control, or j machinery mDuence -

FIRMR Federal Information Resources FOE Friends of the Earth Management Regulation FOGG feed-only-good generator FIRR Federal Institute for Reactor FOIA Freedom ofInformation Act Research (Switzerland) FOL facility operating license FIRS field incident radio system FONSI finding of no significant impact l

FISC fuel inspection and sampling cell FONUBEL Forum Nucl6 aire Belge (Belgium)

FIST full integral simulation test FOR forced outage rate (NRC l

FIT flow indicator transmitter performance indicator)

FIV flow-induced vibration frame of reference FIVE fire-induced vulnerability evaluation FORATOM Forum Atomique Europ6en i FJO field job order FORC fluorinator off-gas recycle FLAME flame acceleration measurement and compressor experiment FOSAR foreign object search and retrieval FLD fuel-loading data FOTA fuels open test assembly FLECHT full-length emergency cooling heat FP fire protection j transfer f ssion product FLIP 00ating index point full power fuel lifetime. improvement prcgram FPC Federal Power Commission 43 L _ ---

~

1 Nju., col L E'CTION OF ABBRE VIATIONS 1 I

l

(

Florida Power Corporation Constructions Atomiqu-s (France) fuci pool cooling FRAP fuel rod analysis program FPCC fuel pool cooling r.nd cleanup FRAP-S fuel rod analysis j FPCCS fuel pool cooling and cleanup system program-steady-state FPCSTL fission product control screening test FRAP-T fuel rod analysis program--transient loop FRB Forschungsreaktor Berlin (Germany)

FPD full power day FRC Federal Radiation Council FPDD final project design description Federal Records Center i I

FPDI food processing development Federal Response Center irradiator Fire Research Center FPEB fuel pool exhaust blower flow recording controller FPFI fire protection functional inspection fractional relief capacity FPL Florida Power & Light Co. Franklin Research Center full performance level FRCS flow recording controller switch FP&L Florida Power & Light Co. FRCTF fast reactor core test facility FPM Federal Personnel Manual FRD formerly restricted data FPMR Federal property management FRERP Federal Radiological Emergency regulation Response Plan FPO Federal Proervation Officer FRF fuel reprocessing facility FPOL full-power operating license FRMAC Federal Radiological Monitoring and FPPH fire protection pump house Assessment Center FPPVS fuel pool pump ventilation system FRMAP Federal Radiological Meitoring and FPR Federal procurement regulation Assessment Plan flexible plastic reactor FRN Federal Register notice FPS final policy statement formal report number fire protection system FRP Federal Response Plan Fluor Power Services, Inc. fuel reprocessing plant FPSL fission product screening loop FRPCC Federal Radiological Preparedness Coordinating Committee FPT feedwater pump turbine FRS fast reactor safety fission product test f xed radial shield FP-TAP Fire Protection-Task Action Plan floor response spectrum / spectra FPWT fuel pool water treatment fuel receiving station FQC field quality control FRSF fuel receiving and storage facility FR Federal Register FRTEF fast reactor thermal engineering final rule facility flow regulator FS factor of safety friction ratio far side FRA flow recorder and alarm finishing superheater FRAB fuel receiving air blower flow switch FRAC Federal Regional Assistance FSAR f'mal safety analysis report Committee FSC Federal supply classification FRAF fuel receiving air filter Federal supply code FRAM-FSCR fuel storage control room ATOME Soci6te Franco-Am6ricaine de FSCS fuel storage cable spread

{ 44

NHC COL LECTION Of ABBHE VIA HONS ,

FSEB fuel storage exhaust blower file transfer protocol FSER final safety evaluation report fracture transition plastic FSF fuel storage facility fuel transfer pool FSI fluid-structure interaction fuel transfer port FSN Federal stock number FTR fast test reactor FSNM formula quani,ity of strategic special Federal travel regulation nuclear material FTRC Federal Telecommunications FSP fuel storage pool Records Center FSPA fuel storage personnel area FTRIA Dow and temperature removable FSPB fuel storage processing building instniment assembly FSPPR fast supercritical pressure power FTS Fedetal Telecommunications reactor Services FSPVS fuel storage pool ventilation system fuel transfer system FSR fast source reactor FT&SA fuel transfer and storage assembly

} FTTM few-tube test model l First Soviet Reactor FS&R filling, storage, and remelt FTTS flow-through tube sampler FS&RS filling, storage, and remelt system FTU formazine turbidity unit FSS Federal Supply Service FUETAP formed under elevated temperature and pressure fire suppression system FUFO fuel fusing option floor service station WSE oridians United for Safe Energy, FSSAR final standard safety analysis repor c, FSTF full-scale test facility FUSRAP formerly utilized sites remedial FSU former Soviet Union action program FSV Fort St. Vrain FV floor valve FSVNGS Fort St. Vrain Nuclear Generating Fussell Vesely Station FVA Goor valve adapter FT fault tree FVC filtered vented containment flow transmitter FVCS filtered vented containment system FTA fault tree analysis / analyses FV&V final verification and validation FTC Federal Telecommunications Center FW feedwater fuel temperature coefficient field weld fuel transler canal Foster Wheeler Corp.

fuel transfer cask FWB Fahrenheit wet bulb FTE FFTF (fast flux test facility) test FWC feedwater control

'"E***""E FWCl feedwater coolant injection fracture transition elastic FWCS feedwater control system full-time equivalent FWEC Co FT1 Framatome Technologies, Inc. Foster (subsidiary Wheeler of Foster Enerkheefe.

r Corp.)

(formerly Babcock & Wilcox)

FWHM full width half maximum FTL full-term license FWIV feedwater isolation valve full-time license FWLB feedwater line break FTM functional test matrix FWLC feedwater level control system FTOL full-term operating license FWP Federal Women's Program FTP FFTF(fast flux test facility) test procedure 45

Nif: f,(X l E C TiOrj OF Al3HRE VI ATIONS FWPAC Federal Women's Program Advisory FWSDR final working system design review Committee FWSH fresh water supply header FWPB feedwater pipe break FWST fueling water storage tank FWPCA Federal Water Pollution Control Act FY fiscal year FWRA Federal Workforce Restructuring Act FYP five-year plan of 1994 FZPA full zero period acceleration FWRV feedwater regulating valve (method)

FWS feedwater supply FZS Forschungszentrum Seibersdorf, feedwater system G.m.b.H. (Austria)

F&WS Fish and Wildlife Service i

F 43

NIu: Cf >l 1 F r, rn >N N AhHHf VIA IION5 GA gas analysis / analyses GCRA Gas-Cooled Reactor Associates General Atomics (before 1988, GA GCRE gas-cooled reactor experiment Technologies, Inc.) GCS glued cylindrical specimen grapple adapter GCSS graphite core support structure GAAA Groupement pourles Activit6s GDC general design criterion / criteria l Atonuques et Avanc6es (France)

GDP gaseous diffusion plant GAE general analytical evaluation GDS general declassification schedule GAEC Greek Atomic Energy Commission graphical display system GAHF grapple adapter handling fixture GALE GM gadecay tank '

gaseous and liquid effluent eneral lectric Co.

GALL generic aging lessons learned GEAP General Electric Atomic Products GAMAS General Atomics material assay system GEC General Electric Co. (Umted Kingdom)

GAN Gosatomnadzor (Russia)

General Electrodynamics Corp.

GAO General Accounting Office GEIS generic environmentalimpact GAP Geor8 i a Power Co. statement Government Accountability Project generic environmental impact study GAPCO Georgia Power Company GEM graphical evaluation module GASSAR General Atomics Standard Safety GENE General Electric Nuclear Energy Analysis Report

"" ntal, and Gilbert Associates Standard Safety f*in t on hy"t m

^""* #E ' GEN'"R General Electric Nuclear Test GATT General Agreement on Tariffs and Reactor >

Trade GERA General Engineering Research and GBHC Great Bay Holdings Corp. Applications (Belgium)

GBPC Great Bay Power Company GERP general employee retraining program gBq gigabecquerel GERS general equipment ruggedness l GBR gas-cooled breeder reactor spectrumTspectra GBRA Gas-Cooled Breeder Reactor GES generic environmental statement Association (Belgium) GESMO Generic Environmental Statement on GBSR graphite-moderated boiling and Use of Mixed Oxide Fuel superheating reactor GESSAR General Electric Standard Safety GC gas chromatograph Analysis Report ,

generic communication GESTAR General Electric Standard i

GCB gravity cutback A PPlication for Reactor Fuel l GCBR gas-cooled breeder reactor GET general employee training GCCA generic compliance and GETAB Gen,eral Electric Thermal Analysis communications activity Basis GCEP gas centrifuge enrichment plant GETP general employee training program GCFBR gas-cooled fast breeder reactor GETR General Electric Test Reactor GCH gas collection header GETS Government Emergency, Telecomumcations Services GCHWR gas-cooled, heavy-water-moderated reactor GETSCO General Electric Technical Services Co.

l GCI Generic Communications Index Government-furnished equipment GFE l

GCL gas-cooled loop i GCR gas-cooled reactor l

l 47 G

• & 9 NRC COI1 f C TION OF AHHHE VIATIONS 1

GFE&M Govemment-furnished equipment GLDB General License Database and material GLEEP Graphite Low-Energy Experimental GFES generic fundamentals examination Pile (United Kingdom) section GLRP Generic License Renewal Program l GFFD gross failed fuel detector GLRWS gaseous and liquid radioactive waste GFK Gesellschaft fur Kernforschung, system ,

m.b.H. (Germany) GM Geiger-Moller (Mueller)

GFP Government-furnished property GMAW gas metal are weld / welding GFY Government fiscal year l

GMPC Green Mountain Power Corp. l GG generator gas GMRA Government Management Reform GGA Gulf General Atomic Act of 1994 i GGNS Grand Gulf Nuclear Station GMT Greenwich mean time

]

GH gate house GN general notice G&H Gibbs & Hill,Inc. GNGS Genoa Nuclear Generating Station GI gastrointestinal GNPP R.E. Ginna Nuclear Power Plant generic issue GNS Gesellschaft for Nuklear-Service, GIBBSSAR Gibbs and Hill,Inc., Standard Safety .b.H. (Germany)

Analysis Report GO-CO Government owned / contractor GIC geomagnetically induced current operated GIDEP Government-Industry Data Exchange GOI general operating instruction Program GORX graphit,e oxidation from reactor GIF gamma irradiation facility exc m n GIFT ps-ir.sulated flow tube GOS group operating service GIIN Groupe Intersyndical de l'Industrie GP general purpose Nucl6 aire (France) generic project GILS Government Information Locator GPA Governmental and Public Affairs, Service Office of(NRC)

GIMCS Generic Issue Management Control GPC Georgia Power Company System GPCL general purpose closed loop GIP generic implementation procedure GPE general purpose evaporator GIS geographic information system GPL general purpose loop geologic information system GPO Government Printing Office GKM Grosskraftwerk Mannheim, A.G.

GPO

( #"" "Y)

GKN FDLP GPO Federal Depository Library Gemeenschappelijke Program Kernenergiecentrale Nederland N.V.

(Netherlands) GPP general plant project Gemeinschaftskernkraftwerk Neckar, GPR Groupe Pernunent Charge des G.m.b.H. (Germany) R6acteurs Nucleaires GKT Gemeinschaftskernkraftwerk GPRA Government Performance and Tullnerfeld, G.m.b.H. (Austria) Results Act of 1994 GKW Gemeinschaftkraftwerk Weser, GPS global positioning system G.m.b.H. (Germany) GIrr general plant telephone GL generic letter GPU General Public Utilities Corp.

Government liaison GPUN GPU (General Public Utilities)

GLASS germanium-lithium-argon scanning Nuclear Corp.

system 48

l j

- NHC CQl LE (;IIr>N Of AHHHE VIATIONS l GPUSC GPU (General Public Utilities) guide tube assembly l Service Corp. GTAW gas tungsten are weld GQA graded quality assurance GTCC greater than Class C l GRC generation review committee GTG gas turbine generator GRI Gas Research Institute generic technical guidance GRR Greek Research Reactor GT-HTGR gas-turbine high-temperature GRS gaseous radwaste system gas-cooled reactor geoscience and remote sensing GTIG Gamma Thermometer Interest Group Gesellschaft f0r Alagen-und GTL gaseous tritium light Reaktorsicherheit, m.b.H. (Germany) GTLS gaseous tritium light source GRSA General Radioquimica, S.A. (Spain) GTR ground test reactor GRT general reactor technology GTRR Georgia Technology Research GRWS gaseous radioactive waste system Reactor GS gland seal GTS global trip subsystem GSA General Services Administration G1TF gas-turbine test facility GSB general services building GUI graphical user interface GSC gland seal condenser GUNFCO Gulf United Nuclear Fuels gland steam condenser Corporation Global Strategy Council GV guard vessel GSD generating significant dose GVR gas volume ratio GSER generic safety evaluation report GVW gross vehicle weight GSH gas surge header GWAC Government-wide agency contract GSI generic safety issue GWD gaseous waste disposal GSLO gland seal leakoff GWMS gaseous waste management system GSPS generating station protection system gas-water module storage GSR gland steam regulator GWPS gaseous waste processing system GST gas surge tank GWS gaseous waste system GSU generator stepup GWTT ground-water travel time Gulf States Utilities Co. Gy gray GTA gas tungsten arc l

I l

l 49 G

--,---,-, -.- ---r--------- -- -,s----, - - , , ---,.

l

-~Q l

1

l NHC COLL $CTION OF k3BHEVIATIONS l

l H/A hand / automatic HCS hydrazine control system IIAA head access area hydrogen control system i HAAUP hanger and analysis update program HCSS head compartment support structure l lIAC high alumina cement HCTL heat capacity temperature level 1

HACL Harvard Air Cleaning Laboratory llCU hydraulic control unit l IIAD heat-activated device HCV hand control valve -

heat-actuated device hydraulic control valve I IIAFM helium accumulation fluence monitor HCW hafnium column waste HAN hydroxylamines nitrate HDGR high-density gas reactor HAP hafnium column product 11DO Headquarters duty officer HAPS Houston automatic priority spooling HDR Heissdampfreaktor (Germany) 1 HAS holding action system high dose rate l

HASL Health and Safety Laboratory hot dry rock HAW high acid waste HDT heated detonation tube HAX hafnium column extractant HDW high-pressure demineralized water HAZ heat-affected zone HE human error HAZCAP Hazard Communication Compliance HEARTH-FIRE high-energ accelerator reactor for cu aYonalYafeIy an Health thermonuc ear fusion with ion beam Administration) of relativistic energy HAZEL Homogeneous Assembly Zer HECTOR Hot, Enriched, Carbon-Moderated, Energy Laboratory Thermal-Oscillator Reactor (United HB handbook Kingdom) horizontal baffle HED historical earthquake data HBA horizontal baffle assembly human engineering deficiency HBP hydrogen behavior program human engineering discrepancy HBPP Humboldt Bay Power Plant HEDL Hanford Engineering and HBR2 H. B. Robinson Steam Electric Plant, Development Laboratory Unit 2 HEHF Hanford Environmental Health i HBS hydrogen burn survivability Foundation HBWR Halden Boiling Heavy Water Reactor HEl Heat Exchanger Institute (Norway) HEJ hybrid expansion joint HCDA hydrodynamic core-disruptive HELB high-energy line break ,

accident HELBA high-energy line break I hypothetical core-disruptive accident analysis / analyses HCDB heat code database HELCO Hartford Electric Light Co.

HCE human-caused error HELP Health and Energy Learning Project HCGS Hope Creek Generating Station HEM homogeneous equilibrium model HCLF horizontal cask lifting fixture HEP human error probability HCLPF high confidence in low probability of HEPA high-efficiency particulate air failure HEPB high-energy pipe break HCM hydraulic core mockup HER human-error rate HCMS hydrogen concentration monitoring HERALD Heterogenous Experimental Reactor, subsystem Aldermaston (Umted Kingdom)

HCOG Hydrogen Control Owners Group 51

i NHC COL l f CIION OF ABBHL VIATIONS liigh Enriched Reactor, Aldermaston HI&D harassment, intimidation, and (United Kingdom) discrimination HERMES Ileavy, Element and Radioactive HID high-impact design Material Electromagnetic Separator high-intensity dischar8e (Umted Kingdom)

HIFAR High-Flux Australian Reactor liERO Hazards of Electromagnetic Radiation to Ordnance Reactor HIFRENSA Hispano-Francesa de Energfa (United Kingdom) Nuclear, S.A. (Spain)

IIES lianford Engineering Service 11IL helium impurities loop IIET horizontal electrical tunnel HILAC heavy son linear accelerator HETS height equivalent to a theoretical HILC high intermediate level cell stage HIP Hanford Isotopes Plant HEU highly enriched uranium HIPA high-speed interactive plant ilEW Hamburgische Electrizit!its-Werke, analysis / analyses A.G. (Germany) HIPOW hot isostatic pressing of waste HEX uranium hexafluoride HIPS hoist integrated protective system HFAR hardware failure analysis report lilR hanger inspection report HFBR high-flux beam reactor HIRDL High-Intensity Radiation HFCE2 high-flux critical experiment2 Development Laboratory HFE human factors engineering HIS hydrogen igniter system human failure event hydrogen ignition subsystem HFED high-frequency envelope detection hydrogen ignition system HFEF hot fuel examination facility HrrC Hydraulic Institute test code HFEPRM human factors engineering program HJTC heated junction thermocouple review model HKG Hochtem liFIR G.m.b.H.peratur-Kernkraftwerk,(Germany) high-flux isotope reactor HFP hot full power HLB hot laboratory building liFPP humu. factors program plan HLC high-level cell HFR high-flux reactor HLCS high-level compaction station HERG human factors review group HLCV hot-leg check valve HFT hot functional testing HLHS heavy load handling system HG hydrogen gas HLIV h"t-leg isolation valve HGE hydraulic grade elevation HLLWT h:3a-level liquid waste tank HGMS high gradient magnetic separator HLNCC high-level neutron coincidence e unter HG/NG hydrogen gas / nitrogen gas HHLR HLO high-level override Horace Hardy Lestor Reactor HHS Health and liuman Services, U.S. HL&P Houston Lighting & Power Co.

Department of HLRW high-levcl radioactive waste HHSI high-head safety injection HLSW high-level solidified waste IIHW high-heat waste HLW high-levelliquid waste HI Hydraulic Institute high-level radioactive waste H&l harassment and intimidation high-level waste HIC hand indicator controller HLWC high-level waste calcination high-integrity container high-level waste concentrate HI-C high conversion-critical HLWD high-level waste distillate HLWF high-level waste feed H 52

I

• NFC (,01 l I,C T ION ( A ,Al@l4 VIA TIONS 4 l

l }{LWOG high-level liquid waste off-gas HPOF high-pressure oil fill HLWR high-level waste repository high pressure, oil filled HLWS high-level waste surge HPP health physics program l HM heavy metal hot processing plant l HMS Hanford Meteorology Survey HPPP Human Performance Program Plan hydrogen mixing system HPR high-pressure recirculation H&N Holmes and Narver, Inc. HPRR health physics research reactor HNL Holifield National Lt.boratory HPRS high-pressure recirculation system HNNP liaddam Neck Nuclear Plant HPS Hanford Plant standard HNP Haddam Neck Plant Health Physics Society Hartsville Nuclear Plant health physics station HNPF Hallam Nuclear Power Facility helium purification system HO hydraulic operator hydrogen purge system HOG head off-gas HPSI high-pressure safety injection HOO headquarters operations officer HPSIP high-pressure safety injection pump HOP HEDL (Hanford Engineering HPSP high-power set point Development Laboratory) overpower liPSW high-pressure service water HOTCE hot critical experiment liPSWS high-pressure service water system HOV hydraulic-operated valve liPT high-pressure turbine HP Edwin I. liatch Plant hot pipe tunnel hanger package HPU hydraulic power unit health physicist Hydro-Quebec (Canada)

HQ health physics HR hard rock high pressure Human Resources, Office of(NRC) high purity hydrogen recombiner liPC health physics center HRA human reliability analysis hot pipe chase HRB Hochtemperatur-Reaktorbau, HPCF high-pressure core flooder G.m.b.H. (Germany)

HPCI high-pressure coolant injection HRE homogeneous reactor experiment HPCIS high-pressure coolant injection HRIS human resources information system system HRM human resources management HPCS high-pressure core spray HRP Halden Reactor Project l l HPD high-power density HRPS hydrogen recombination and purge l l HPED Human Performance Event Database system i liPES human performance evaluation HRRM high-range radiation monitor i

system HRS heat rejection system HPFL high-performance fuels laboratory hydrogen recombination subsystem HPFP high-pressure fire protection HRT homogeneous reactor test HPI high-pressure injection HS hand switch HPIP Human Performance Investigation hot shop Process HSI human-system interface HPIS high-pressure injection system liSM horizontal storage module HPME high-pressuie melt ejection HSO hydrogen seal oil HPN health physics network lisp hot-shutdown panel 53 1

NHU GOl 1 [ 4 ilON Of ABBHE VIATlONS HSSC highly safety significant component HULP Hudson Light and Power Dept.

HSST heavy section steel technology HUT HEDL (Hanford Engineering IISW heat sink welding Development Laboratory) up I HSWA Hazardous and Solid Waste Amendments HUT holdup tank HSWil high solid waste header HV hand valve HTB hafnium test blade H&V heating and ventilation HTFFT heat transfer fluid flow HVAC heating, ventilation, and air ,

thermodynamics conditiomng l HVD heaters, vents, and drains HTGCR high-temperature gas-cooled reactor HTGR high-temperature gas-cooled reactor HVdc high-voltage direct current high-temperature gas reactor HVH hydrogen vent header l HTGR-CX high-temperature gas reactor critical HVSU heating and ventilating supply unit experiment HW heavy water IITIS heat transfer instrument system hot water llTL heat transfer loop hotwell llTLTR high-temperature lattice test reactor HWC hydrogen water chemistry HTM high trajectory missile HWCTR heavy-water components test reactor HTPC Hayward Tyler Pump Company HWGCR heavy-water-moderated, gas-cooled HTR llanford Test Reactor reactor high-temperature reactor HWH hot water heating liitachi Training Reactor (Japan) HWLC hotwell level control HTRDA High-Temperature Reactor HWLWCR heavy-water-moderated, boiling Development Associates light-water-cooled reactor HTRE heat transfer rea. tor experiment HWP heavy-water plant HTRI Heat Transfer Rt tearch Institute llWR heavy-water reactor HTS heat transfer system hot water return heat transport system HWS Hanford work specification HTSF high-temperature sodium facility Hanford work standard HTTP hypertext transfer protocol HWSF hazardous waste storage facility HTV half thickness value HWWVS hardened wetwall vent system H/U heatup HX heat exchange HU hydraulic unit heat exchanger HUGHES- HYPO high-power water-boiler reactor NEL Hughes Aircraft Company Nuclear HZP hot zero power Electronics Laboratory H 54

NRC COLLE CTION OF ABBREVIATIONS IA industry application ICA item control area insertion approval ICAP International Code Assessment instmment air Program I/A isolation amplifier ICAR interface control action request I&A identification and authentication ICAVP independent corrective action venf.ication program IAA interim access authon.zation ICB m

. formation collection budget IAC .

interim acceptance criterion /cn.tena IAD interface control board immediate action directive .

ICBWR improved cycle boiling-water reactor IAE instrumentation and electncal .

ICC madequate core cooling IAEA Intemational Atomic Energy Agency m

. formation collection coordinator IAEC israel Atomic Energy Commission IAG mcident analysis group Interstate Commerce Commission ICCDP incremental conditional core damage IAL immediate action letter probability IALL intermediate activity level liquid ICCGR international cyclic crack growth rate

[ system]

ICCU interchannel comparison unit IANEC Inter-American Nuclear Energy Commission ICCW in-containment chilled water IAP independent assessment program ICD interface control diagram integrated action plan interface control document Iowa Power interface control drawing IAPG Interagency Advanced Power Group ICE implicit continuous-fluid Eulerian IAPMO International Association of ICEA Insulated, Cable Engineers Plumbing and Mechanical Officials Association IAR irradiation-anneal-reirradiation ICES integrated civil engineering system IAS instrument air system ICI ice condenser instrumentation IASCC irradiation-assisted stress-corrosion in-c re instrumentation cracking ICODS Interagency Committee on Dam IAT information assessment team Safety IATI integrated assessment team ICONS Information Center on Nuclear inspection Standards IAW in accordance with ICP inert carrier process IB inner bremsstrahlung instrument calibration procedure IBA inner blanket assembly inventory control point intermediate break accident ICPP Idaho Chemical Processing Plant IBEW International Brotherhood of ICRA Interagency Committee on Electrical Workers Radiological Assistance IBJ Industrial Bank of Japan, Ltd. ICRI incomplete control rod insertion Instytut Baddn Jadrowych (Poland) ICRP International Commission on IBM Radiological Protection International Business Machines .

Corp. ICRS instrument calibration and recall IBSHR integral boiling and superheat reactor "Y" #* .

ICRU International Commission on IC andicating controller Radiation Units and Measurements Internuclear Co. ICS instrumentation and control system isolation condenser integrated control system I&C instrumentation and control intercommunication system 55

w NHC LOLLEC IKJN OF ABBHE VIATIONS l

iodine cleanup system IEAR Instituto de Energia Atomica Reactor ICSA in-core shim assembly (Brazil)

ICSD ionization chamber ... oke detector IEB IE (Office ofInspection and

. Enforcement) bulletm ICV mdependent construction verification .

. IEC International Electrotechn.ical ID inner diameter Commission inside diameter IED improvised explosive device inventory difference IEEE Institute of Electrical and Electronics IDA intrusion detection alarm Engineers IDAS intermediate dose assessment system IEG items evaluation group IDCA independent design and construction IELP Iowa Electric Light & Power Co.

assessment IEM interim examination and IDCOR Industry Degraded-Core Rulemaking maintenance Program IEMTF interim examination and IDCV independent design and construction maintenance training facility venfication IEN IE (Office of Inspection and IDEN Instituto de Engenharia Nuclear Enforcement) notice (Brazil) IEOTSG integral economizer once-through IDI independent design inspection steam generator integrated design inspection IES Illumination Engineering Society IDLH inunediate danger to life and health Institute of Environmental Sciences IDMS isotope dilution mass spectrometry irradiation effects simulation IDNS Illinois Depanment of Nuclear IESB iron-enriched synthetic basalt Safety IET initial engine test IDOT Illinois Department of Transportation IFA instrument fuel assembly i IDP Individual Development Plan (NRC IFIl invitation for bids l IDR Iindependent I" . .

design review IFBA integral fuel burnable absorber IFCA instrumentation to follow the course inspection discrepancy report of an accident interface data report IFCF integrated fuel cycle facility IDS interim decay storage IFCI integrated fuel-coolant interaction 1 intermediate decay storage IFE Institut for Energiteknikk (Norway) l isotope detection system IFI inspector followup item IDT integrated design team IFM intermediate flow mixing IDV independent design verification IFMIS integrated financial management IDVP independent design verification information system program Ipirr integrated fission product transport

!E industrial electronics IFR integral fast reactor initiating event IFTS irradiated fuel transfer station l Ins irradiated fuel transfer system of(pection NRC) and Enforcement, Office IG implementation guideline irradiation effect I&E "*E* ' #"*'"'

internally and externally IEA Instituto de Energia Atomica (Brazil)

^ " #'E'""" '"""'

. IGC Independent Government Cost International Energy Agency Estimate 1 IGLD International Great Lakes Datum l )

1 56

-__A

NHC Col L ECTION OF ABBREVIATIONS 1

IGRP inert gas receiving and processing integrated master IGR&P inert gas receiving and processing IMA independent management appraisal IGRPS inert gas receiving and processing IMARC integrated multiple assumptions and system release code IGSCC intergranular stress-corrosion IMAS impurity monitoring and analysis cracking system IGT instrument guide tube IMC incident management center IH integrated head Inspution Manual chapter IHSI induction heating stress improvement IMCO Inter-Government Maritime induction heat stress improvement Consultative Organization intermediate head safety injection IMECo Indiana & Michigan Electric IHTS intermediate heat transport system f mPany .

IMP instrument mamtenance procedure IHX intermediate heat exchanger IMPAC International Merchant Authorization IHXGV intermediate heat exchanger guard Card

. . IMPCo Indiana Michigan Power Company Ele tfica ei IMPEP Integrated Material Performance

. . Evaluation Program IIF internals indexing fixture IMPR Indiana & Michigan Power Co.

IIGE lowa-llhnois Gas and Electric Co.

. IMS in-core monitoring system IIP Incident Investigation Program ion mobih.ty spectrometer in-core instrument penetration IN information notice IIRC c t Investigation Review INB International Natrium-Brutreaktor-Bau, G.m.b.H. (Germany)

IIS in-core instrumentation system INC Idaho Nuclear Corporation integrated implementation schedule INCA in-core analysis / analyses IIT Ilhnois Institute of Technology inner neutron control assembly Incident Investigation Team INCB International Nuclear Credit Bank Indian Institute of Technology INCOT in-core test IKRD inverse kinetics rod drop IND investigational exemption of a new ILC intermediate level cell drug ILIP in-line instmment package INDE inservice nondestructive examination ILLW intermediate-level liquid waste INDEX integrated nuclear data exchange ILO Intemational Labour Organization INEC Idaho Nuclear Energy Commission ILPR Illinois Power Co. INEEL Idaho National Engineering and ILRT integrated leak rate test Environmental Laboratory (formerly l

integrated leak rate testing INEL)

ILSW intermediate-level solid waste INEL Idaho National Engineering Laboratory (now INEEL) i ILW intermediate-level waste Institute of Nuclear Energy Research INER I ILWC intermediate-level waste concentrate (Taiwan)

ILWD intermediate-level waste distillate INES international nuclear event scale ILWF intermediate-level waste feed INFCE International Nuclear Fuel Cycle ILWS intermediate-level waste storage Evaluation IM information management ININ Instituto Nacional de Investigaciones instrumentation and measurement Nucleares (Mexico) 57

i H M, U >l l I (, T l()N ()F AHHHf VI A T IONS INIS International Nuclear Information IPC integrated protection cabinet System Interjurisdictional Planning INITEC Empresa Nacional de Ingenierfa y Committee Tecnologfa, S.A. (Spain) IPCEA Insulated Power Cable Engineers INLA International Nuclear Law Association Association IPDD initial project design description INMM Institute of Nuclear Materials IPE individual plant examination Management .

Institute of Nuclear Power !ntegrated plant evaluanon INPO mdividual plant examination of Operations IPEEE extemal events INR immediate notification report IPF odine protection factor INRA International Nuclear Regulators Association IPliT in-process heat treatment INS Immigration and Naturalization IPIRG International Piping Integrity Service Research Group INSAG International Nuclear Safety IPL initial program load Advisory Group IPP independent power producer INSRP Interagency Nuclear Safety Review integrated plotting package Panel IPR initial pressure regulator INTER- IPRDS in-plant reliability data system ATOM International Atomreaktorbau, IPRN in-process rework notice G.m.b.ll. (Germany) .

IPS Indian Pom.t Station INTLO International Nuclear Technology Liaison Office interim pol. icy statement INX ion exchange investment protection subsystem 1/0 input / output Iowa Public Service Company IOAA Independent Offices Appropriation iron pipe size Act of 1952 IPSAR integrated plant safety assessment IOE industry operating experience report IOERS integrated operating experience IPSN Institute of Nuclear Safety and reportmg system Protection (France)

IORV inadvertently opened relief valve IPTS integrated pressurized thermal shock IOSRV inadvertent opening of a safety / relief IPyC inner pyrolytic carbon valve IR information request IP inspection procedure inspection report I&P inerting and preheating intermediate range IPA Intergovernmental Personnel Act IRA integrated review of assessment iterative performance assessment IRAC Interdepanmental Radio Advisory IPAC International Participants Advisory Comnuttee Conunittee (Institute of Nuclear IRACT incident response action coordination Power Operations) team IPAP integrated performance assessment IRAP Integrated Review of NRC process Assessment Processes integrated performance assessment Interagency Radiological Assistance program Plan IPAS Inspection Procedure Authority Interagency Radiological Assistance System Program IPB illustrated parts breakdown IRB inside reactor building l 58

NHC COL L f CTION OF Al3l3HEVI AT lONS' .

l Istituto Ricerche Breda, spa (Italy) indepe,ndent safety assessment or IRC incident response center analysis Indiana Regional Cancer (Center) Instrument Society of America j internal review committee integrated safety assessment IRE Institut National des Radio 616ments ISAF isotopic source adjustable fissometer (Belgium) ISAM indexed sequential access method IREP integrated reliability evaluation ISAP integrated safety assessment program program ISAS isotopic source assay system interim reliability evaluation ISCA Intersociety Committee on Methoas j program for Ambient Air Sampling IRFM integral reactor flow model ISCORS Interagency Steering Committee on IRG Interagency Review Group Radiation Standards l

IRM information resarces management ISCP intermediate sodium characterization l Information Resot.rces Management, Package

{

Office of(NRC) ISCT imponant-to-safety-criteria task intermediate-range monitor inner seal collar tool IRMP Independent Radiatien Monitoring ISD instructional system design j Program ISDF intern 6 ate rodium disposal facility l IRN item removal notice ISDN Integrated Services Digital Network IRP incident response plan ISE ion-selective electrode intermediate rotating plug ISEG independent safety engineering IRPA International Radiation Protection group Association (France) ISER integral systems experimental IRPI individual rod position indicator requirement l IRR Institute for Reactor Research ISFSF independent spent fuel storage (Switzerland) facility i Israeli Research Reactor ISFSI independent spent fuel storage IRRAS int rated reliability and risk installation anaYysis system ISG integrated scheduling group 1RS Incident Reporting System ISGMP integrated scheduling group manual Inquiry and Reponing System procedure Institut filr Reaktorsicherheit der ISGTR induced steam generator tube rupture Technischen Oberwachungs-Vereine, ISI inservice inspection e.V. (Germany) ISIS integrated safeguards information iodine removal system system IRSF interim radwaste storage facility ISITS integrated safety issues tracking IRSP inside recirculation spray pump system IRSR issue Resolution Status Report ISLH inservice leak and hydrostatic IRTS inspection report tracking system ISLOCA inte,rfacing-systems loss-of-coolant accident IRVH integrated reactor vessel head ISMES Istituto Sperimentale Modelli e IRWST in-containment refueling water Strutture (Italy) storage tank ISNF intermediate-energy standard neutron IS mdicating switch field information system ISO independent system operation l

ISA independent safety analysis independent system operator 59 1

NHL COI L F G1 ION OF ABBREVIATIONS .. l 1

)

International Standardization ITPOP independent, third-party oversight Organization program ISO /DWG isometric drawing ITR instrument test rig ISOO Information Security Oversight ITRI Industrial Technology Research Office Institute (Taiwan)

ISP industrial security plan ITRIA instrument tree removable instrument ISR intermediate sodium removal assembly ISSO Information System Security Officer ITS Idaho Test Station l IST inservice test unp rtant to safety inservice testing improved technical specification integral simulation test Inf rmation Technology Services 3 integral systems test inventory tracking system {

ISTS Improved Standard Technical IT/SP instrument tree / spool piece Specifications ITV intermediate test vessel ISV in situ verification IUPAC International Union of Pure and IT information technology Applied Chemistry information theory IUPAP International Union of Pure and

. Applied Physics instrument test . .

IV independent verification instrument tree IVHM in-vessel handling machine I&T inspection and test IVHM-EM in-vessel handling ITAAC inspection, test, analysis, and machine---engineering model acceptance criterion / criteria IVHX in-vessel heat exchanger ITAL Instituut voor Toepassing van Atoomenergie in de Landbouw IVIC Instituto Venezolano de (Netherlands) Investigaciones Cientificas (Venezuela)

IT&AP inspection test and analysis plan .

IVO Imatran Voima Osakeyhtio (Finland)

ITC Information Technology Council .

. . IVP integrated verification plan isothermal temperature coefficient

. IVS in-vessel storage ITDP improved thermal design procedure IVSM in-vessel storage module ITF interstitial transfer facility IVTM in-vessel transfer machine ITFTRIA instrument tree flow and temperature . .

removal instrument assembly IWF andustrial waste filter ITI inspection / test instruction industrial waste filtration ion track instrument IWFS industrial waste filter system ITIP Industry Technical Information industrial waste filtration system Program IWGFR Intemational Working Group on Fast ITL Industrial Testing Laboratories Breeder Reactors ITM in-core temperature monitor IWRC iron wire rope core information technology management IWS/IT integrated work sequence / inspection ITMA irradiation test management activity ITMRA Information Technolo !n ustr al w ste tmatment system Management Reform ct ky IX ion exchanger ITMS in-core temperature monitoring IZ isolation zone system ITP initial test program 60

NRC COLLECTION OF ABBREVIATIONS

• JAllE John A.131ume and Associates, joint establishment experimental pile Engineers JEN Junta de Energia Nuclear (Spain)

JAEC Japan Atomic Energy Commission JEPIC Japan Electric Power Information JAEIP Japan Atomic Energy insurance Pool Center JAERI Japan Atomic Energy Research JET joint European torus Institute JETR Japan Engineering Test Reactor JAERO Japan Ato,mic Energy Relations JFNP Joseph M Farley Nuclear Plant Orgamzation JFNPP mes A. FitzPatrick Nuclear Power JAF James A. FitzPatrick Nuclear Power Plant "E " *"" "

JAFNPP James A. FitzPatrick Nuclear Power Plant JGCR Japan Gas-Cooled Reactor JAIF Japan Atomic Industrial Forum JHEP jomt human error probability JAJ J.A. Jones Co. JINR Joint Institute far Nuclear Research JANAP joint Army-Navy-Air Force J10 justification for interim operation publication JOFOC justification for other than full and JAPC Japan Atomic Power Co. open competition JARRP Japan Association for Radiation JOG Joint Owners Group Research on Polymers JPDR Japan Power Demonstration Reactor JCAE Joint Committee on Atomic Energy JPM job performance measure JCCCNRS Joint Coordinating Committee for JRR Japanese Research Reactor Civilian Nuclear Reactor Safety JSW Japan Steel Works, Ltd.

JCL job control language JTA job task analysis / analyses JCO justdication for continued operation JTG Joint Test Group JCP Joint Committee on Printing JUMA Joint Utility Management JCPL Jersey Central Power & Light Co. Assessment Group JCP&L Jersey Central Power & Light Co. JURIS justice retrieval and inquiry system JEA Jacksonville Electric Authority JEEP joint emergency evacuation plan 1

1 4

)

61 J !

)

i NHG Coll f C1 ION OF Al4M4E VIATIONS KAEA Kazakh Atomic Energy Agency KNFDI Korea Nuclear Fuel Development KAERI Korea Atomic Energy Research Institute Institute KNPP Kewaunee Nuclear Power Plant KAIF Korea Atomic Industrial Forum KNPS Kuosheng Nuclear Power Station KALC krypton absorption in liquid carbon (Taiwan) dioxide KNU Korean Nuclear Unit KANUPP Karachi Nuclear Power Plant KPDS key plant damage state (Pakistan) KRB Kernkraftwerk Gundremmingen KAPL Knolls Atomic Power Laboratory Betriebsgesellschaft (Germany)

K/As knowledge and abilities Kernkraftwerk RWE-Bayernwerk, Kernkraftwerk-Betriebsgesellschaft, G.m.b.H. (Germany)

KBG m.b.H. (Germany) KRR Kansai Research Reactor (Japan)

KBWP Keinkraftwerk Baden-Wuerttemberg KSAs knowledge, skills, and abilities Planungsgesellschaft (Germany) KSB Klein, Schanzlin and Becker KE Kaiser Engineers Aktiengesellschaft (Germany)

KEEPS Kodak Ektaprint Electronic KSF Karen Silkwood Fund Publishing System KSGE Kansas Gas & Electric Co.

Keff effective multiplication factor KSH Kernenergie-Gesellschaft KEMA Tot Keuring van Elektrotechnische Schleswig-Holstein, m.b.H.

Materialen, N.V. (Netherlands) (Germany)

KERMA kinetic energy released in material KSTR Kema Suspension Test Reactor KEWA Kernbrennstoff-Wiederaufarbeitungs (Netherlands)  ;

-Gesellschaft, m.b.H. (Germany) KTG Kerntechnische Gesellschaft im Deutschen Atomforum, e.V.

KEWB kinetic experiment on water boilers

( """*"Y KFKI K67ponti Fizakai Kutat6 Int 6zet (Hungary) KTl key techm. cal issue KGBS krypton gas bottling station KTS Kernte,chnische Sektio Schweizenschen Verem,n der igung fur KG&E Kansas Gas & Electne Atomenergie (Switzerland)

KKB Kernkraftwerk Brunsbuettel, KTU key technical uncertainty G.m.b.H. (Germany) Kernkraftwerk Graben, A.G.

KWG KKK Kernkraftwerk Krummel, G.m.b.H.

(Switzerland)

(Gennany) Kemkraftwerk Lingen, G.m.b.H.

KWL l KKL Kernkraftwerk Leibstadt, A.G. (Germany) l (Switzerland) . KWO Kernkraftwerk Obrigheim, G.m.b.H.

KKN Kernkraftwerk Niederaichbach, (Germany) i G.m.b.H. (Germany) Kernkraftwerk Sud, G.m.b.H.

KWS l l KKP Kernkraftwerk Phillipsburg, (Germany)

G.m.b.H. (Germany) Kraftwerk Union Aktiengesellschaft KWU KMC Kerr McGee Corp. (Germany) l 63 l

NHC COL L E CTION OF AHHREVIATIONS .

i LA licensing assistant LCR large component removal local alarm log count rate LACBWR ' . Crosse Boiling Water Reactor LCRE lithium-cooled reactor experiment LACE L dR,(light-water reactor) aerosol LCRM linear count rate meter contamment experiment LCS leakage collection system LAFM Los Alamos Fuel Model leakage control system LALL low activity level liquid [ system] level control system LAMPRE Los Alamos Molten Plutonium local control station Reactor Experiment LAN local area network dW g; ,, g ;gg; LAND League Against Nuclear Dangers  ;

LANL Los Alamos National Laboratory (formerly Los Alamos Scientific LCV level control valve Laboratory) local control valve LAPL Louisiana Power & Light Co. LCVIP licensee contractor vendor inspection LAPPES large power plant effluent study program LAPRE Los Alamos Power Reactor LD letdown Experiment lethal dose LAR license amendment request UD length to diameter licensing action report LDCC large-diameter component cask limited analytical review LDR load definition report local automatic regulation low dose rate LASL Los Alamos Scientific Laboratory UDRS level and density recorder switch (now LANL) LDS leak detection system LAW low-acid waste leakage detection system LAWB Los Aiamos Water Boiler LDST letdown storage tank LBB leak before break LE left end L.BE licensing-basis event I mit of error LBilS 'large-bore hydraulic snubber LEAC levelized energy adjustment clause LBL Lawrence Berkeley Laboratory LED light-emitting diode LBLOCA large-break loss-of-coolant accident LEFM linear elastic fracture mechanics LBP land-based plant LEID limit of error on inventory difference lumped burnable poison LEL large engineering loop LBPR lumped bumable poison rod lower electrical limit LBRB leak before risk of break LEMUF limit of error on material LC level controller unaccounted for local control LEO lasers and electro-optics locked closed LEP local emergency protection LCCC large-component cleaning cell LER licensee event report LCCV large-component cleaning vessel LERF large early release frequency LCHS large-component handling system LERO local emergency response LCL lower control limit organution LCM LOCA (loss-of-coolant accident) LERP large early release probability core melt LES limited early site LCO limiting condition for operation Louisiana Energy Services 65

NRC COOLECTION OF ABBREVIATIONS ..

[ .

I l

LESR limited early site review lower limit of detection LET linear energy transfer LLEA local law enforcement agency LEU license to export uranium LLFM low-level flux monitor low-erdched uranium LLHS light load handling system LFA lead Federal agency LLLWT low-level liquid waste tank LFBR liquid fluidized bed rer.ctor LLMPP liquid level monitor port plug LFBR-CX liquid fluidized bed reactor-critical LLNL Lawrence Livermore National experiment Laboratory LFDCP local fire detection cont.oi parvi LLRT local leak-rate tut LFL lower flammability limit LLRW low-level radioactive waste LFMS license fee management staff 1.LRWPAA Low-Level Radioactive Waste Policy LGR light-water-cooled, graphite. Amendments Act moderated reactor LLS low-level solid LGS Limerick Generating Station low-low set lower group Stop LLSV low-level storage vault LH low head LLSWV low-level solid-waste storage vault LHC Little Harbor Consultants, Inc. LLT liquid level transducer LHGR linear heat generation rate LLTR large-leak test rig LHM loop-handling machine LLW low-level radioactive waste LHR linear heat rate low-level waste LHS Latin Hypercube Sampling LLWBG low-level-waste burial ground loop-handling system LLWSV low-level-waste storage vault LHSI low-head safety injection LM labor management LHST laundry and hot shower tank local manual LI level indicator LMEC Liquid Metal Engineering Center LIC level indicating controller LMFBR liquid metal fast breeder reactor level indicator controller LMFR liquid metal fuel reactor loop insertion cell LMFRE liquid metal fuel reactor experiment LIFO last in, first out LMHX liquid metal heat exchanger LILCO Long Island Lighting Co. LMP licensing milestone plan LIM ligament instability model LMR liquid metal reactor lower inlet module LMS licensing management system LIMB liquid metal breeder LMTD logarithmic mean temperature LIMSW limit switch difference limit switch LNG liquefied natural gas LINAC linear accelerator liquid natural gas LIONS Licensing and Inspection Online LNGS Lacrosse Nuclear Generating Station System LNS liquid nitrogen system LIRS level indicator recording switch Londor. Nuclear Services LITR low-intensity test reactor LNT linear, no-threshold LIWB Livermore Water Boiler LNW loss of normal water LL liquid limit LN2 liquid nitrogen LLCS low-level compaction station LO lock open LLD low-level dose locked open 66

NHC COL LECTION OF ABBREVIATIONS '

lube oil LOVS loss-of-voltage signal LOA letter of agreement loss-of-voltage start line of assurance LP liquid penetrant LOBI loop blowdown investigation low pressure LOCA loss-of-coolant accident LPC loop preparation cask LOCE loss-of-coolant experiment LPCI low-pressure coolant injection LOCF loss of coolant flow low-pressure core injection LOCP loss-of-coolant protection LPCIS low-pressure coolant injection LOCV loss of condenser vacuum system LOF lack of fusion LPCS low-pressure core spray loss of feedwater LPD linear power density loss of flow local power density LOFA loss-of-feedwater accident LPDR local public document room loss-of-flow accident LPE loop preparation equipment LOFC loss of forced circulation LPG liquefied petroleum gas loss of forced cooling liquid petroleum gas  ;

loss-of-fluid test low-Pressure gas LOFT LPGS Liquid Pathway Generic Study LOFW loss of feedwater LOFWS loss of flow without scram LPHSW last pass heat sink welding LOHS loss of heat sink LPI low-power injection low-pressure injection LOHSWS loss of heat sink without scram loss ofignition LPIS low-pressure injection system LOI LP&L Louisiana Power & Light Co.

LOMF loss of main feedwater LPLNG low-pressure liquefied natural gas LOMFW loss of main feedwater loss of offsite power LPM licensing project manager LOOP LOP loss of offsite power LPMA loose-parts-monitor assembly LPMS loose-parts monitoring system loss of power LPNGP low-pressure noble gas processing LOPAR low parasitic fuel LPOL low-power operating license LOPI loss of pipe integrity LPR Lynchburg Pool Reactor LOPO low power LPRM local power range monitor LOPRA low-power reactor assembly tow-p wer range monitor LOPS loss-of-power start LPRS low-pressure recirculation system LOR lower oil reservoir LP&S low power and shutdown LORD licensing online retrieval data LPSI low-pressure safety injection LORDS licensing online retrieval data system LPSIP low-pressure safety injection pump LORT licensed operator requalification training LPSP low-power set point LOSP loss of offsite power LPSW iow-pressure service water loss of station power j LPT liquid penetrant testing loss of system pressure low-pressure turbine LOST lube oil storage tank LPTF low-power test facility LOU letter of understanding LPTR Livermore Pool Type Reactor limited official use LPZ low-population zone 67 1

NRC COL LECTION OF ABBREVIATIONS I LR level regulator LSR Lynchburg Source Reactor load reject LSRO limited senior reactor operator load rejection LSS Licensing Support System LRA locked-rotor accident LSSA Licensing Support System LRB licensing review basis / bases Administrator, Office of(NRC)

LRC level recorder controller LSSARP Licensin Support System Advisory

. Review I anel I Lewis Research Center . .

LSSC less safety sigmficant component l local recovery center . I LRED licensing reportable event

' * * # I "E". '#" # I"E "#"

determination LSSP latest scram set point i LRG license review group LSSS limiting safety system set point licensing review group limiting safety system setting i LRIA level removable instrument assembly LST large-scale test LRL Lawrence Radiation Laboratory LSTF large-scale test facility LRM lead reactor manufacturer LT leak testing logarithmic radiation monitor level transmitter LRP large rotating plug LTA lead test assembly LRPE licensee regulatory performance less than adequate evaluation low-temperature adsorber LRRP long-range research plan LTBT Limited Test Ban Treaty LRS level recording switch LTC linear translation case liquid radwaste system load tap changer LRSC License Renewal Steering LTD letdown Committee LTL lot truck load LRTS liquid radwaste treatment system LTM long-term maintenance LRVOS liner recombiner and vacuum lew. trajectory missile outgassing system LRW LTMD less than minimum detectable liquid radioactive waste LTNGP low-temperature noble gas process LRX large reactor critical experiment LTOP low-temperature overpressure LS level switch protection lighting system LTP licensing termination plan locked shut long-term program LSA low specific activity LTR lattice test reactor LSB last-stage blade licensing technical review LSCS LaSalle County Station Lockheed Training Reactor LSDF large sodium disposal facility LTS License Tracking System LSDP Lake Superior District Power Co. Licensing Tracking System LSFT loric system functional test or testing LTSF lid tank shielding facility LSI licensed supervising instructor LTSP long-term seismic program LSNM low strategic si nificance special LTV large test vessel nucle r materia LSP level set point LUWAS lowest unit with age significance

.. LUX-lower sequential permissiv ATOM Syndicat Luxembourgeois pour low steamlme pressure l'Industrie Nuctsaire (Luxembourg)

L 68

r NRC COLLECTION OF. ABBREVIA*flONS _ .

LV leaky valve LWCHW light-water-cooled, heavy-water-LVDT linear variable differential transducer moderated reactor linear variable differential LWGR light-water-cooled graphite-transformer moderated reactor linear variable displacement LWMS liquid waste management system transducer LWOP leave without pay linear voltage differential LWP liquid waste processing transformer LWPS liquid waste processing system LWA limited work authorization LWR light-water reactor LWBR light-water breeder reactor LWTS laundry waste treatment system l

69

NHC COLL E CTION OF ABBHEVIATlONS I l

l M/A manual or automatic MBP monobutyl phosphate MAA material access area MBq megabecquerel MAAC Mid-Atlantic Area Council MBR material balance report MAAP material access authorization MC main circulator Program main condenser modular accident analysis program major component MAC maintenance action card manual chapter (NRC) management advisory committee metal clad Management Analysis Co. Mitsubishi Corporation material accountmg MCA material control and accountability maximum allowable concentration maximum credible accident MACCT multiple assembly cooling cask test multichannel analyzer MAD maintenance assembly-disassembly MC&A material control and accounting MAELU Mutual Atomic Energy Liability MCAP Management Corrective Action Plan Underwriters MCB main control board MAG raagnetics .

MCC Matenals Characteri7ation Center MAI miscellaneous actuation instrumentation motor control center MAIN Mid-American Interpool Network movement control center MAIT matrix analysis of insider threat MCCB molded-case circuit breaker MAM management and administration MCES main condenser evacuation system mmual MCET materials, chemical, and MAN Maschinenfabrik environmental technology Augsberg-Nornberg, A.G. (Germany) MCHER minimum critical heat flux rate MAP maintenance action plan minimum critical heat flux ratio j maintenance assessment package MCI managed cost improvement methodology assessment program millicurie l MAPI Mitsubishi Atomic PowerIndustries, MCIG miscellaneous control and Inc. (Japan) instrumentation group j MAPLHGR maximum average planar linear MCIS materials compatibility in sodium heat , .neration rate MCLAMS measurement, control, LEID (limit of l maximum average planar linear error of the inventory difference) and heat-generation ratio MUF (material unaccounted for) ID t

MAR maintenance act'on request (inventory difference) simulation MARAD Maritime Administration MCOV maximum continuous operating

" 8" MARCA Mid-Continent Area Reliability .

Coordination Agreement MCPR maximum critical power ratio MARCH meltdown accident response minimum critical power ratio characteristic MCR main control room MASE microwave amplification by material certification report l stimulated emission MCRE main control room envelope MAT management advisory team MCREC main control room environmental MB mixed bed control MB-2 Model Boiler-Two MCRH main control room habitability MBA material balance area MCRHS main control room habitability MBO management by objective system 71 L

NHC CCXL EC TION OF ABBREVIATIONS l

l MCS main circulator subsystem MEl maintenance effectiveness indicator )

master control station maximally exposed individual Monte Carlo Sampling M EIS minimum electrical isolation scheme MCSS metallic core support structure MEL master equipment list MCV movable closure valve Mitsubishi Electric Corp. (Japan)

MD management directive MELB moderate-energy line break measured discard MELC moderate-energy lire crack MDA minimum detectable activity MEOD maximum extended operating MDAFWP motor-driven auxiliary feedwater domain pump MEPNS Ministry of Environmental MDB master database Protection and Nuclear Safety (Ukrame)

MDC maximum dependable capacity MEQ mechanical equipment qualification '

minimum detectable concentration MERIT mana ement evaluation and risk moderator density coefficient identification tree MDCT mechanical draft cooling tower MERITS methodically engineered, MDEFWP motor-driven emergency feedwater restructured, and improved technical pump specifications MDEP Maine Department of Environmental MERLIN Medium-Energy, Protection Light-Water-M oderated, Industrial MDF mechanical design flow Nuclear Reactor (United Kingdom)

MDHR mini-decay heat removal MES maintenance engineering services MDI Many Diverse Interests, Inc. MESA multielement skew angle MDL minimum detectable limit MESF minimum engineered safety feature MDM metal disintegration machining MESL maximum emergency service load modified diffusion method META-MDNBR minimum departure from nucleate FRAM M6tallurgie Fran9aise des Poudres, boiling ratio S.A. (France)

MDP master decommissioning plan MEU medium-enriched uranium MDR manufacturer's date report MeV million electron volts MDS megawatt demand setter MEWS Mixed Energy Waste Study MDU motion detection unit MF mound facility ME maintenance effectiveness MFB main feeder bus M&E material and equipment MFC master flow controller MEA maintenance engineering analysis MFCI molten fuel coolant interaction Materials Engineering Associates MFCS main feedwater control system MEAG Metropolitan Electric Authority of MFCV main feedwater control valve Georgia MFI minimum flow interlock MEC Mid American Energy Co. M FIS main feedwater isolation signal MECAS multienergy californium assay MFIV main feedwater isolation valve system MFL main feedwater line MEED Metropolitan Edison Co. master fuse list MEHC Mid American Energy Holdings Co. maximum foreseeable loss MEF median energy of fission MFLB main feedwater line break MEFV maintenance equipment floor valve MFLPD maximum fraction oflimiting power MEGAS multienergy gamma assay system density 72

MFP main feed power MHTGR modular high-temperature gas-cooled main feedwater pump reactor mixed fission product MHTS main heat transport system MFPG mixed fission products generator MI manual individual MFPT main feedwater pump turbine mineral insulated MFPTC main feed pump turbine condenser MIBK methyl isobutyl ketone MFRV main feedwater regulation valve MIC microbiologically induced corrosion MFS main feedwater system microbiologically influenced mobilization for survival

. . . MICDS movable in-core detector system MFT multiprogramming with a fixed . .

number of tasks MIDAS meteorological information and dose MFTA multiduct fuel test assembly "#9*" ' " .*#* #* .

meteorological information and dose MFV main feedwater valve assessment system maintenance floor valve MIDS movable instrument drive system MFW main feedwater M&IE meals and incidental expenses MFWCS main feedwater and condensate MIL material identification list

'Y #* material identification log MFWLB main feedwater line break

• • • *E * * "8 'YS**

• MFWRV main feedwater regulating valve MINET momentum integral network MFWV main feedwater valve MIP maintenance improvement program MG manual gmup master inspection plan m tor generator MIPS master inspection planning system M/G motor generator MIS mim m id w im p M-G motor generator management information system MGCR maritime gas cooled reactor MIST maximum isothermal system MGCR-CX mariti,me gas-cooled reactor-critical temperature

1. • Periment

. . minor isotopes safeguards technique MGDS mined geologic disposal system g;;9  ; ,;

MGEC Madison Gas & Electric Co.

MIT Massachusetts Institu:e of MGL Multiple Greek Lett,er(common- Technology cause failure analysis)

MITI Ministry of International Trade and MGVC manual governing valve control Industry (Japan)

MHA maximum hypothetical accident MITR Massachusetts Institute of MH-1A Mobile High Power Plant No. l A Technology Rector MHC mechanical-hydraulic control MKU Ma7 Lineen Uranium, Ltd.

MHD magnetohydrodynamics (Australia)

MHDC magnetohydrodynamic conversion ML manufacturing license MHFPR maximum h pothetical M L-1 Mobile Low Power Plant No. I fission-prod ct release MLD mean low-water datum / data MHI Mitsubishi Heavy Industries, Ltd. median lethal dose (Japan) MLHGR maximum linear heat generation rate MHNGS Marble Hiil Nuclear Generating maximum linear heat generation ratio Station MLO main lube oil MHP material handling procedur main loop pump MLP' MHS mechanical handling system 73

NHC COL LECTlON OF AHHHEVlATlONS I MLS Medilab Select (Belgium) MOU memorandum / memoranda of understanding multi-level secure MLSR Monthly Letter Status Report MOV metal oxide varister MLSV main loop shutoif valve motor-operated valve MLW mean low water MOVATS motor-operated valve analysis and test system MLWMS miscellaneous liquid waste management system hiOX mixed oxide MM mechanical maintenance MOXF mixed-oxide fuel modified Mercalli MP magnetic particle MME Mercantile Marine En ineering and maintenance procedure Graving Docks Co., N V. (Belgium) Midland Plant MMG motor-motor generator MPA multiplant action MMI man-machine interface multiplant activity modified Mercalli intensity MPAI maximum permissible annual intake MMIS man-machine interface system MPBB maximum permissible body burden MMP maintenance manual procedure MPC maximum permissible concentration MMPA Magnetic Material Producers Metals Properties Council Association Montana Power Co.

MMSA man-machine systems multi-purpose canister analysis / analyses MMWEC Massachusetts Municipal Wholesale

^ u PermissMe concentration

[a^ir Electric Co.

MPCW aximum permissible concentration MNCR material nonconformance report MNGP Monticello Nuclear Generating Plant MPD maximum permissible dose MNP maximum negative pressure MPE maximum permissible exposure MNPS Millstone Nuclear Power Station MPFF maintenance preventable functional MNS McGuire Nuclear Station failure i M&O management and organizational MPL master parts list MO mixed oxide maximum permissible level modulate open mechanical properties loop motor operator MP&L Mississippi Power & Light Co.

MOA memorandum / memoranda of MPO manufacturing production order agreement MPP maximum positive pressure l MOC middle of cycle M&PP materials and plant protection i minimum operable channel MPR mechanical pressure regulator MOD motor-operated disconnect MPRE medium-power reactor experiment MODE maximum organ dose equivalent MPRT multipurpose rail transport MODEM modulator-demodulator MPS manpower system MONAL mobile nondestructive assay mps meter per second laboratory

. MPS monitoring and protection system MOOS maintenance out of service MOP maintenance outline procedur MPSC hiair Public Senice Co.

MOR monthly operating report MFT magnetic particle testing MORT management oversight risk tree minimum Pressurization temperature MOTA materials open test assembly 74

NH'C COL L E C TION OF ABBREVIATIONS MPX multiplexer MSGTR multiple ster.m generator tube MQE materials and qualifications NPture engineering MSHA Mine Safety and Health mechanical quality engineering Administration MQS motion to quash subpoena MSICV main steam isolation check valve MR material requisition MSIP modified stabilization in place monitoring report MSIS main steam isolation signal morning report MSIV main steam isolation valve MRB Management Review Board MSIVLCS main steamline isolation valve

'#" 8 # "I*' 'YS #*

MRBI maintenance rule baseline inspection MRBT multirod burst test maximum still-water level MRC Medical Research Council (United Kingdom) mean sea level MREM millirem MSLA main steamline accident MRI material receiving instruction MSLB main steamline break MRMU mobile radiological measuring unit MSLD mass spectrometer leak detector MRO medical review officer MSLI main steamline isolation

~ MRP modification / rework package MSLIVSS main steamline isolation valve se Ung system MRPC motorized rotating pancake coil .

. .. MSLRDS main steamline rupture detection MRR material receivmg report system medical research reactor MSM master / slave manipulator MRS manipulator repair shop modified source multiplication manufacturer's record sheet MSNM special nuclear material of moderate monitored retrievable storage strategic significance MRSS main and reheat steam system MSPB Merit System Protection Board MS main steam MSR material status report manual sequential maximum steam rate j margin of safety moisture separator reheater l milestone molten salt reactor M/S maintenance / surveillance MSRE molten salt reactor experiment MSA management self-assessment MSRP Multiple System Responses Program )

material surveillance assembly MSRV main steam relief valve mechanical signature MSS main steam system analysis / analyses main support structure mines safety appliance management systems section MSAR mines safety appliance research Manufacturers Standardization MSB main steamline break Society of the Valve and Fittings multi-assembly sealed basket Industry MSBE molten salt breeder experiment mixed spectrum superheater MSBR molten salt breeder reactor m dified scram system MSCA mixed spectrum critical assembly MSSC more safety-significant component MSCI molten steel coolant interaction MSSCE mixed spectrum superheater critical experiment MS&FW main steam and feedwater MSSR mixed spectrum superheat reactor MSG modular steam generator 75 l l

1 U---__-- - __ -

NRC Col L SCIbiJ Of ABBilLVIATIONS I

main steam safety relief (valve) mean time to replacement MSSS main steam supply system MTU metric ton of uranium l

main steam support structure metric ton unit MSSV main steam safety valve module test unit main steam shutoff valve MU makeup MST main steam tunnel MUF material unaccounted for MSV mean square voltage MUG MOV Users Group MS&W maintenance shop and warehouse MU&P makeup and purification MT magnetic particle test MUR management update and retrieval magnetic particle testing mockup reactor material transfer MUSE Musicians United for Safe Energy materials test MUT makeup tank I melt through MUTN MOVATS Users Technical Notice MTBF mean time between failures MUX multiplexer MTC moderator temperature coefficient MVP mechanical vacuum pump multi-assembly transfer cask MVS multiple virtual storage M&TE measuring and test equipment MVSS multiple venture scrubbing system MTER multitest evaluation report MVT multiprogramming with a variable MTF mean time to failure numberof tasks MTG main turbine generator MW megawatt MT/G main turbine generator MWDC multiple weld data card MTI maintenance team inspection MWe megawatt electric mandatory team inspection MWHT miscellaneous waste holdup tank Mechanical Technology,Inc. MWO maintenance work order MTL materials test loop MWS makeup water system Mobiltherm light MWST makeup water storage tank MTOS magnetic tape operations system miscellaneous waste storage tank MTPF maximum total peaking factor MWt megawatt thermal MTR materials testing reactor MW-yr megawatt-year MTS main turbine system MYAP Maine Yankee Atomic Power Co.

module tracking system MYAPS Maine Yankee Atomic Power Station MTT microwave theory and techniques MZFR Mehrzweck Forschungsreaktor ,

(Germany)

MTTF mean time to failure MTTR mean time to repair 76

NHC COLLE C IlON Of Af3BHE VIAT ONS NA not applicable NAS-NRC National Academy of not available Sciene,es-National Research N/A not applicable NASE National Academies of Science NAA neutron activation analys. is/ analyses NASIRE National Association of State NAB nuclear assembly building Information Resource Executives NAC national agency check NASUCA National Association of State Utility Nuclear Assurance Corporation Consumer Advocates NACE National Association of Corrosion NAWAS national warning system Engineers NB nuclear blank NAD nuclear accident dosimetry nuclear boiler NAEC North Anna Environmental Coalition NBGEL New Bedford Gas and Edison Light NAESCO North Atlantic Energy Service Corp. Co.

NAFTA North American Free Trade NBL New Brunswick Laboratory Agreement NBP New Bmnswick Power (Canada)

NAGRA Nationale Genossenschaft for die NBR nuclear boiler rated dioaktiver Abfalle agrun NBS National Bureau of Standards (now

. National Institute of Standards and NAl sod.ium iodide Technology)

NAIG Nippon Atomic Industry Group Co., NBSR National Bureau of Standards Ltd. (Japan) Reactor NAN Nuclear Awareness Network NC neutron cc.~ -!iet NANT National Academy for Nuclear normally closi s Training

. . nuclear construction NAPA National Academy of Public Administration NCA neutron control assembly NAPCA NCAI Nat,ional Congress of American National /W Pollution Control Indians Administ ..ap NAPS North Amia Power Station NCBR near-commercial breeder reactor NAPSIC North American Power Systems NCC natural convection cooldown Interconnection Committee NCF no containment failure NAPUS nuclear auxiliary power unit system NCIG Nuclear Construction Issues Group NARA National Archives and Records (EPRI)

Administration NCP network control program NARADOom Natick Research and Development NCR nonconformance report Command nonconforming condition report NARM naturally occurring or . . notification-of-change report a eier tor-produced radioactiv NCRERP North Carolina Radiation Emergency "S*

NARUC National Association of Regulatory NCRP National Council on Radiation Utility Commissioners NAS National Academy of Sciences  !*

NCRP(M) National Committee on Radiation nonreactor assessment staff Protection and Measurements NASA National Ae,ronautics and Space NCRWS National Campaign for Radioactive Admmistration Waste Safety NASAP Nonproliferation Alternative NCS national communications system Systems Assessment Program g;g; 77

NHC CplLE CT K}N Of ABfmE VIATIONS I

l NCSA National Center for Supercomputing NEGEA New England Gas and Electric l Applications Association {

NCSAG Nuclear Cross Secthn Advisory NEI Nuclear Energy Institute (formerly l Group NUMARC and USCEA)

NCSCR North Carclir.a State College Reactor NEIL Nuclear Electric Insurance Limited NCSL National Conference of State NEJAC National Environmental Justice Legislatures Advisory Council I NCSS neu;ron control subsystem NELIA Nuclear Energy Liability Insurance NCSUR North Carolina State University Association Reactor NELPIA Nuclear Energy Liability Property NCV non-cited violation Insurance Association NCVP natural circulation verification NEMA National Electrical Manufacturers program Association ND negative dcciaration NENE Northeast Nuclear Energy Co.

normally dcerecgized NEO nuclear engineering and operations NDA no detectable activity NEP New England Plant nondestructive analysis NEPA National Environmental Policy Act nondestructive assay NEPCO New England Power Company NDC nuclear data committee NEPIA Nuclear Energy Property Insurance

.NDCT natural draft cooling tower NERA i onomic Research NDE nondestructive examination Associates, Inc.

NDHX natural draft heat exchanger NERC National Electric Reliability Council NDL nuclear data link National Environment Resource NDRC National Defense Research Council Council (United Kingdom)

NDT nil ductility temperature Nuclear Energy Research Centre nil ductility transition (Belgium) nondestructive testing NERHL Northeastern Radiological Health

. . Laboratory NDTT ml ductih.ty transition temperature NERP nuclear experience review program NE normally energized NERV nuclear emulsion recovery vehicle nuclear engineering NERVA nuclear engine for rocket vehicle NEA Northeast Energy Alh.ance application Nuclear Energy Agency (OECD) NESC National Electric Safety Code Nuclear Engineering Associates Nuclear Energy Software Center NEB Nuclear Energy Board (Ireland) NESCWS nonessential services chilled water NEC National Electrical Code system Nuclear Energy Center NESDIP Nestor Shielding and Dosimetry NECAP Nutmeg Electric Companies Atomic Improvement Program Project NESF normal engineered safety feature NECNP New England Coaliltion on Nuclear NESP National Environmental Studies Pollution Project NECO Nuclear Engineering Company NEST nuclear emergency search team NECSS Nuclear Energy Center Site Survey NETR Nuclear Engineering Test Reactor  !

NEDS nuclear employee data system NEU Northeastern Utilities (Company)

NEES New England Electric System NEUSSN Northeastern U.S. Seismic Network NEFC National Emergency Fire Center. NEUT Northeast Utilities N 78

__A

NHC col L1 C T ION OF ABHHL VIATIONS M -

NEVP Nevada Power Co. NiMo Niagara Mohawk Power Corp.

NEW Nuclear Energy Women NIOBE numericalintegration of the NEWS Nuclear Engineering Workstation Boltzmann equation Simulator NIOSH National Institute for Occupational NEWSTAR nuclear energy waste space Safety and Health (U.S. Public transportation and removal Health Service)

NF neutron flux NIPA not, ice ofinitiation of procurement NFC no further consequences NIPS N rthern Indiana Public Service Co.

NFCA nonfuel core array NIRA Nucleare traliana Reattori Avanzati, NFI Nuclear Fuel Industries, Ltd. (Japan) spa (Italy)

NFPA National Fire Protection Association NIRB Nuclear Insurance Rating Bureau NFRRC nuclear fuel recovery and receiving NIRL negligible individual risk level

1. 1. "I #

NIRMA Nuclear Information and Records NFS network file system Management Association,Inc.

Nuclear Fuel Services Co. NIRNS National Insti:ute for Research in NFSA new fuel storage area Nuclear Science (United Kingdom)

NG nitroglycerin NIRS Nationaii.atitute of Radiological noble gas Sciences (Japan)

NGA Nationale Gesellschaft fur F6rdemng Nuclear Information and Resource der Industriellen Atomtechnik Service (Switzerland) NIS Network Information Service NGE Nortn Georgia Electric Membership Nevada Inspection Service Corp. Newly Independent States NGF Natural Guard Fund nuclear instrumentation system NGN Next Generation Network NISCO Nuclear Inspection Services NGSF noble gas storage facility Company NHPA National Historic Preservation Act NISP National Industrial Security Program l NHY New Hampshire Yankee NISPOM National Industrial Security Program l NI never incorporated Operating Manual nuclear instmment NIST National Institute of Standards and Technology (formerl National nuclear instrumentation Bureau ofStandards nuclear island NJBPU New Jersey Board of Public Utilities l NIAC Nuclear Industry Assessment NJOAL New Jersey Office of Administrative Committee Law NuclearInsurance Association of NLI National Lead Industries Canada Nuclear Industries, Inc.

NIC Nuclear Industry Check Valve Group NMA National Mining Association Nuclear Industry Consortium (Belgium) NMAC Nuclear Maintenance Assistance Center (Electric Power Research NICWB nuclear island cooling water building Institute)

NIDA NationalInstitute on Drug Abuse NMCC Nuclear Material Control Center NIH National Institutes of Health (U.S. (Japan)

Public Health Service) NMDB nuclear maintenance database NII Nuclear Installations Inspectorate NMEC Northern Michigan Electric (United Kingdom) Cooperative, Inc.

NIM nuclear instmment module NMED nuclear material events database 79

NRC COLLE CTION OF ABBREVIATIONS NMIS nuclear materials information system NOL Naval Ordnance Laboratory nuclear materials inventory system normal operating loss NMMSS nuclear materials management and NON notice of nonconformance safeguards system NOP normal operating procedure NMP national meter programming NORCUS Northwest College and University Niagara Mohawk Power Corp. Association for Science NMPNS f;me Mile Point Nuclear Station NORM naturally occurring radioactive NMRG Nuclear Managers Review Group material NMS national measurement system NOS not otherwise specified neutron snonitoring system NOUE notice of unusual event NMSS notification of unusual event Nuclear Material Safeguards, Safetband Office of( RC) NOV notice of violation NMST new materials system test NOWUS normal operation with unscram NMT nuclear medicine technologist NP negative pressure NN nearest neighbor nuclear power nearest neighboring NPA nuclear plant analyzer NNC National Nuclear Corporation, Ltd. NPAR nuclear plant aging research (United Kingdom) NPC Nuclear Power Co.

NNCSC National Neutron Cross Section NPCA National Paint and Color Association mnuttee NNDC NPCC Northeast Power Coordinating National Nuclear Data Center Council NNEC National Nuclear Energy NPD national policy debate Commission (Brazil)

Nuclear Power Demonstration NNECO Northeast Nuclear Energy Co. (Canada)

NNESCO Nonheast Nuclear Energy Services NPDB nuclear plant data bank Co' NPDES National Pollutant Discharge NNI nonnuclear instrumentation Elimination System NNIE nonnuclear instrumentation system NPE nuclear plant engineering NNPA Nuclear Non-Proliferation Act of nuclear power experience 1978

. NPEC Nuclear Power Engineering NNPS Norco Nuclear Power Station Committee NNS nonnuclear safety NPEP Nuclear Plant Equipment NNSA National Nuclear Safety Procurement Working Group Administration (China) NPF nuclear power facility NNSDD Newpon News Shipbuilding and Dry NPG Nuclear Power Group, The (United  !

Dock Company Kingdom)

NNTP network news transfer protocol NPGS nuclear power generating station NNWSI Nevada Nuclear Waste Storage NPIS nuclear plant island structure nvesnganon NPO nuclear plant operator n rm Uy Pen NPP nuclear performance plan NOAA National Oceam.c and Atmospheric Administration nuclear power plant NOAC Nuclear Operations Analysis Center NPPD Nebraska Public Power District NOD notice of deviation NPR National Performance Review NOED notice of enforcement discretion new production reactor

{ NOI nonpower reactor notice of indication 80 i

, NHC COLL E CTION OF ABBREVIATIONS NPRCG Nuclear Public Relations Contact NRHE nonregenerative heat exchanger Group (Italy) NRHX nonregenerative heat exchanger NPRDS Nuclear Plant Reliability Data NRIM narrow resonance infinite mass System (INPO) i R earch Laboratory (United NPRF Northrop Pulse Radiation Facility hng NPS nominal pipe size NRPB National Radiological Protection i normal pressurizer spray Board l Nuclear Power Service NRR Naval Research Reactor 1 (Westinghouse) Nuclear Reactor Regulation, Office numerical plotting system of(NRC)

NPSH net positive suction head NRRO nuclear radiation-resistant oil NPSI Nuclear Power Service Incorporated NRT national response team NPSRA Nuclear-Powered Ship Research NRTS National Reactor Test Station Association (Japan) NRU National Reactor Universal NPSRS nuclear power safety reporting NRW nonradioactive waste system NRWV nonradioactive waste vent NIrr national pipe thread NRX National Research Reactor Nonproliferatmn Treaty

""#"' "E "* '#"' ' #* E#' **"I NI'TF nuclear proof test facility

. NS near side NPZ nickel-plated Zircaloy 4 nonseismic NQA nuclear quality assurance normally shut NQAA Nuclear Quality Assurance Agency

" .E NQAM nuclear quality assurance manual g NQAP nuclear quahty assurance plan

" " * '""E Nuclear Science Abstracts narrow resonance Nuclear Systems Associates nonconformance report NSAC Nuclear Safety Analysis Center ,

NRA Nuclear Regulatory Administration NSC National Security Council Nuclear Re (Ukraine) gulatory Authority net-section collapse naturally radioactive product net-suction collapse NRAP Nuclear Safety Concern NRB nonconformance review board ]

NSCR Nuclear Science Center Reactor NRC National Research Council NSCW nuclear service cooling water l Nuclear Regulatory Commission, U.S. NSDM national security decision l memorandum / memoranda NRCA nonradiologically controlled area NSEP National Security Emergency NRCAR NRC Acquisition Regulation

• E*'" "***

j NRCC National Research Council (Canada) .

mt t n Foundation Northern Rockies Cancer Center q n1 Nat onal Science Foundation NRDC National Resources Defense Council

"#'# ' ' " ' * "" "N "

NRDS Nuclear Rocket Development Station n ns dium fire protection NRE nuclear research emulsion NSHC no-significant-hazards consideration NREP National Reliability Evaluation NSHE no-significant-hazards evaluation Program neutron resonance escape probability NSI national security information l 81

NHC COLLECTION OF ABBREVIATIONS l

NSIAC Nuclear Strategic Issues Advisory NTIS National Technical Information l Committee (NEI) Service i NSIC Nuclear Safety Information Center NTOL near-term operating license (

NSIP Nuclear Safe Issues Program NTP National Toxicology Program NSLD No Seismic Limit Duration normal temperature and pressure NSMH Nuclear Systems Material Handbook nuclear test plant NSO nuclear station operate NTR nuclear test reactor NSOA nuclear safety operational nuclear testing reactor analysis / analyses NTS Nevada Test Site NSP Northern States Power Co. NTSB National Transportation Safety )

NSPP nuclear safety pilot plant Board NSPS nuclear safety protection system NU Northeast Utilities NSQAC Nuclear Supplier Quality Assurance NUBARG Nuclear Utility Backfitting and Committee Reform Group NSTC National Science and Technology NUC-Center LENOR Centrales Nucleares del Norte, S.A.

NSR neutron source reactor (Spain) non-safety-related NUCLIT Nucleare Italiana (Italy)

NSRA Nuclear Safety Research Association NUCPR nuclear procedure requirement (Japan) NUDE nuclear data evaluation NSRB Nuclear Safety Review Board NUDOCS Nuclear Documents System NSRG Nuclear Safety Review Group NUDOCS/

NSRL Nuclear Structure Research Laboratory AD Nuclear Documents System / Advanced Design NSRR nuclear safety research reactor NUFCOR Nuclear Fuels Corp. of South Africa l

NSRRC Nuclear Safety Research Review j Comnuttee NUGEQ Nuclear Utility Group on Equipment Qualification NSRS nuclear safety review staff NUGSBO Nuclear Utility Group on Station NSS ruclear steam system Blackout NSSM national security study NUHOMS Nutech Horizontal Modular Storage memorandum / memoranda NUMAC Nuclear Management and Control NSSS nuclear steam supply system nuclear steam system supplier NUMARC Council Nuclear (now Manakement EI) and Resou NSSS3 nuclear steam supply shutoff systein NUMEC Nuclear Materials and Equipment NSTF Nuclear Science and Technology Corp.

Facility NUMS nuclear materials security NSUM neutron shuffler uranium monitor NUPEC Nuclear Power Engineering NSW nuclear service water Corporation (Japan)

NSWMA National Solid Waste Management NUPlc Nuclear Procurement Issues Association Committee NSWS nuclear service water system NUPLEX Nuclear Utilities Plant Life NT neutron transmitter S NTCP

. . NURE national uranium resource evaluation near-term construction pernut NTE not to exceed NUREG NRC technical report designation

(_N_uclear R_egulatory Commission)

NTEU National Treasury Employees Union NUREG/BR NUREG brochure NTF nuclear test facility 82 E - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - -

NRC COLLECTION OF ABBREVIATIONS NUREGCP NUREG conference proceedings NWP Nuclear Waste Project NUREGCR NUREG contractor report NWPA Nuclear Waste Policy Act of 1982 NUREGOR NUREG grantee report NWPAA Nuclear Waste Policy Amendments NURFBIA NUREG international agreement Act of 1987 report NWR nuclear work request NUS Nuclear Utilities Service NWS National Weather Service NUSCO Northeast Utilities Service Company NWTRB Nuclear Waste Technical Review NUSMG Nuclear Utilities Software Board Management Group NYD New York mean tide data NUSS nuclear safety standard (International NYGAS New York Gas Group Atomic Energy Agency) NYPA New York Power Authority NUTAC Nuclear Utility Task Action NYPIRG New York Public Inter:st Research Committee Group NVH nitrogen vent header NYSADA New York State Atomic and Space NVLAP National Voluntary Laboratory Development Authority Accreditation Program NYSEG New York State Electric & Gas NW normal waste Corp.

NWC normal water chemistry NYSERDA New York State Energy Research NWCC neutron well coincidence counter and Development Authority NWL normal water leg i

i l

1 1

I l

83 1

NRC CO.LLECTION'OF ABB~REVIATIONS OA oil to air OCRE Ohio Citizens for Responsible operating authorization Energy OAB Orszdgos Atomenergia John Urban: OCRWM Office of Civilian Radioactive Waste Bizottssg (Hungary) Management OAC office allegation coordinator OD outside diameter OAD operational availability date ODCM offsite dose calculation manual OAI outside air intake ODCWT outer-diameter creeping wave techmque OAR operational assessment and readm.ess ODF onsite decontamination facility OARP operator accelerated retraining program ODSCC outer-diameter stress-corrosion OAS

1. '" "E Organization of Agreement States .

outside-diameter stress-corrosion OATP operational acceptance test cracking Procedure OE oceanic engineering OBA operating-basis accident Office of Enforcement (NRC)

OBE Office of Business Economics

. operating engineer operating-basis earthquake OBERS Office of Business Economics F## E# # ##"##

Research Service OEC Ohio Edison Co.

OBRA-90 Omnibus Budget Reconciliation Act OECD Organization for Economic I

l of 1990 Cooperation and Development OC Office of the Controller (NRC) OEDO Office of the Executive Director for Operations (NRC)

OEM original equipment manufacturer g

I OER operating event report OCA Office of Congressional Affairs operating experience review

! (NRC) l overcooling accident OERTS operational events repon tracking i OCAA Office of Commission Appellate 87*!#*

Adjudication (NRC) OFA optmuzed fuel assembly l

OCB oil collection basin OFPP Office of Federal Procurement Policy oil-operated circuit breaker .

i . . OFZS Dsterreichisches Forschungszentrum OCDE Orgam.sation de Coopa, ration et de Siebersdorf, G.m.b.H. (Austria)

D6veloppement Econonuques OG off-gas (France)

OCDRE Organic-Cooled Deuterium Reactor wners group Experiment (Canada) OGC Office of the General Counsel (NRC) j OCFO Office of the Chief Financial Officer OGE Office of Government Ethics 1 OGI off-gas isolation  !

OCl oxide control and indication l

OCIMS Operations Center Information OGR ORNL (Oak Ridge National Management System Laboratory) Graphite Reactor OCIO Office of the ChiefInformation OGS off-gas system Officer (NRC) OGST overthread guide sleeve tool i OCLC Online Computer Library Center, OGTB off-gas treatment building  !

. OH Ontario Hydro (Canada)  !

OCM Office of the Comm.ission (NRC)  :

OHER Office of Health and Environmental 1 OCNPP Oyster Creek Nuclear Power Plant Research (U.S. Department of OCR operational control record Energy) 85 O 1

i

NHC COLLECTION OF ABBREVIATIONS l

OHLH overhead heavy-load handling OOS out of sequence OHRS overflow heat removal system out of service OHST overhead storage tank OOSC onsite operations support center OHTCS outer head temper ture control OOSS operations officer support system )

system OP Off ce of Personnel (NRC) 01 Office ofInvestigations (NRC) oxygen pressure operatmg mstruction OPA Office of Public Affairs (NRC) I optical isolator operational performance assessment outstanding item OPAC online payment and collection OIC online instrument and control OPCTR Operations Center OlG Office of the Inspector General OPDRV operation with a potential for (NRC) draining the reactor vessel OIP Office of International Programs OPEC Organization of Petroleum Exporting (NRC) Countries operating internal pressure OPEN O anisation des Producteurs OITS open item tracking system dhnergie Nucl6 aire (France)

OJT on-the-job training OPERA out-of-pile expulsion and reentry OL operating license apparatus operating limit OPF Official Personnel File operator license OPFM outlet plenum feature model OLIP online instrument package OPL Omega Point Laboratories OLMCPR operating limit maximum critical OPM Office of Personnel Management power ratio OPPD Omaha Public Power District OLTS operator licensing tracking system OPR offsite procurement request OM operations manager open pool reactor oxide melt OPS Offshore Power Systems O/M oxygen to metal operational protection system O&M operation and maintenance overpressure protection system Operations and Maintenance overpressurization protection system Committee of ASME OPST out-of-pile systems test OMB Office of Management and Budget Ol'T optimization OMCA organic-moderated critical assembly OPX off-premise extension OMM operation and maintenance manual OPyC outer pyrolytic carbon OMR organic-moderated reactor operations quality assurance OQA O&MR operation and maintenance report operational quality assurance plan OQAP operations and maintenance reminder OR onsite representative OMRCA organic-moderated reactor critical operating reactor assembly OMRE organic-moderated reactor

^ . * "S*#'" Y experiment 0-RAP operational reliability assurance OMRR Ordnance Material Research Reactor E*E' .*

ONCA E outer neutron control assembly eah tional readiness assessment ONE Operations Notification and ORAU Oak Ridge Associated Universities Evaluation (form)

ORB outside reactor building ONS Oconee Nuclear Station ORC online reactivity computer 86

NOC COLL'ECTION OF ABBREVIATIONS i

1 l

operational review committee OSRC Offsite Review Committee operations review committee OSRE Operational Safeguards Response ORE occupational radiation exposure Evaluation ORFM outlet region feature model of#' rat,ional

1. "#** security response

ORGDP Oak Ridge Gaseous Diffusion Plant P#' " * '"E

• ORIC Oak Ridge Isochronous Cyclotron

1. "# "" *' " EY ORISE Oak Ridge Institute for Science and Education OSTI operational safety team inspection ORLA operating reactor licensing action OSTR Oregon State University TRIGA

• 'I #

ORNL Oak Ridge National Laboratory .

OSU Oregon State Um.versity ORO .

offsite response organization OSUR Ohio State University Reactor ORR operational readiness review OSVS Outlier Seismic Verification Sheet ORRR Oak Ridge Research Reactor T operating temperature ORRT operations readiness review team Peradonal tednology ORSORT Oak Ridge School of Reactor Technology OTA Office of Technology Assessment ORU Orange and Rockland Utilities, Inc. Pen test assembly OS operating system OTC once-through cooling i OSART operational safety assessment review OTIS once-through integral system team OTM overspeed trip mechanism OSC Office of Special Counsel OTR organic test reactor Oncology Services Corporation OTSG once-through steam generator operational support center OTSR once-through superheat reactor OSG operations support group OTrS operations training and technical OSHA Occupational Safety and Health Act services Occupational Safety and Health OUO official use only i Adnunistration (U.S. Department of OWCP Office of Workers' Compensation Labor) Programs

OSI open systems interconnection OWFN One White Flint North

OSIP operational support information OWP operations work procedure Pmgram OWR Omega West Reactor OSM optical storage media OWRR Office of Water Resources Research OSP Office of State Programs (NRC) OZD Offshore Zone of Deformation operational surveillance program l

l 87

NHC COLI ECTION OF ABBREVIATIONS PA performance assessment public affairs officer l

, personnel area PAP plant administrative procedure .

! pressure alann power ascension program i l Privacy Act PAPAS pin and pellet assay system f

protected area PAPUC Pennsylvania Public Utility public address Commission purge alarm PAR passive autocatalytic recombiner PAA primary auxiliary area Pennsylvania Advanced Reactor PAB preliminary as built Performance autocatalytic report l

primary auxiliary building Pool At6mico Portuguss (Portugal)

PABX private automatic branch exchange Protective action recommendation PAC Pilgrim Area Collaborative Purchasing approval request protection auxiliary cabinet PARD postaccident radioactivity depletion l public affairs coordinator PARR Pakistan Atomic Research Reactor PACC protected air-cooled condenser Postaccident radioactivity removal PACE plant acquisition and constmction PARV power-activated relief valve equipment power-actuated relief valve PACP Pacific Power Co. PAS Privacy Act statement PACV postaccident containment venting probabilistic analysis staff PAD performance analysis and design PASNY Power Authority of the State of New PADS Personnel Access Data System York plant alarm and display system PASS postaccident sampling system PAEC Pakistan Atomic Energy Commission PAT performance appraisal team Philippine Atomic Energy plutonium air transportable Commission preplaced aggregate technique PAG protective action guideline PATP power ascension testing program J PAHL pressure alarm, high limit power ascension test program PAHR postaccident heat removal PATRAM pac,kaging and transportation of PAIC public address intercommunications radioactive material system PAX private automatic exchange PAIP public affairs and information PB pipe break program proportional band PAL permissive action link PBAPS Peach Bottom Atomic Power Station personnel airlock PBE prompt burst excursion programmer assistance and liaison prompt burst experiment prototype application loop PBF power burst facility PAM postaccident monitoring PBI performance-based instruction PAMI postaccident, monitoring PBL pressure balance line

'"*****"I'"

{ PBNP Point Beach Nuclear Plant PAMS postaccident monitoring system PBR pebble bed reactor PANE People Against Nuclear Energy Plum Brook Reactor PANL plant annunciators list PBRE pebble bed reactor experiment PAO postulated abnormal occurrence PBRF Plum Brook Reactor Facility Privacy Act Officer PBS pressure boundary subsystem

89 l

Nf K, COM f C1K)N Of Af3f 4Hf VIATIONS i

l I

project breakdown structure PCIOMR preconditioning interim operating l PBTF pump bearing test facility management recommendation j PBX private branch exchange PCIS primary containment isolation i system PC personal computer pg  ; ;g; g 9

Pl ant computu I PCL permissible contamination limit E '"""#

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PCLDI prototype closed-loop development pressure controller installation '

Process computer PCLS prototype closed-loop system professional communication PCLT prototype closed-loop test Protective clothing PCM pending contractual matter Protective coatmg power cooling mismatch PCA pool critical assembly PCMI pellet / cladding mechanical primary control assembly interaction primary coolant activity PCN procedure change notice PCAM punched card accounting machine PCP post-construction permit PCAS primary central alarm station primary coolant pump PCB power circuit breaker process control program printed circuit board program control procedure PC&BS project controls and budget services PCPS pool cooling and purification system PCC plutonium concentrator concentrate PCPV primary containment purge valve primary component cooling PCR plant change request process chemistry cell procedure change request PCCGC prima containment combustible gas protective coating report contro PCRB personnel and control room building PCCS passive containment cooling system PCRDL primary control rod driveline PCCV precracked Charpy V-notch PCRDM primary control rod drive mechanism PCD plutonium conce:itrator distillate PCRM primary certified reference material power control device PCRS primary control rod system PCDC plutonium canister decontamination PCRV prestressed concrete reactor vessel cell PCS passive containment system PCDIS plant control, data, and instrumentation system plant computer system PCETF power conversion equipment test Pl ant control system facility power conversion system PCHRS passive containment heat removal pressure control system system primary coolant system primary containment hydrogen process computer system recombiner system PCI pellet / cladding interaction Process control sheet

. . . PCSG Pipe Crack Study Group personnel contamination incident PCT peak centerline temperature Prestressed Concrete Institute Peak cladding temperature primary containment isolation PCIE President's Council on Integrity and

• I 8 " *P*'"I"'*

Efficiency PCTF plant component test facih.ty PCIL plant computer input list PCTR physical constant test reactor 90

NIC C(M i l CIIOJ (d AHHHf VIATIONS .

PCV pressure control valve power distribution system pressurizer control valve predocketed special PD population density project decision schedule population distribution project descriptive summary project director PDT performance discharge test pump discharge PDTS permanently defueled technical PDA predocketed application Specification preliminary design acceptance PE power engineering preliminary design analysis project engmeer PEAP procurement engineering assessment 1.reliminary design approval l preliminary design assessment PECO hi adelphia Electric Co.

preliminary design authorization PDAS plant data acquisition system bcont min t Pn se ion PDB plant damage bin PEF potential enforcement finding l PDC predocketed construction PElS programmatic environmental impact preliminary design criterion / criteria statement principal design criterion / criteria PEL power electronics PDCO plant design control office PEMA Pennsylvania Emergency PDD Presidential Decision Directive Management Agency projected decision date PENELEC Pennsylvania Electric Company prospective decision date PEO patrol emergency officer PDES preliminary draft environmental plant equipment operator statement PEP performance enhancement program PDF plant design factor PEPCO Potomac Electric Power Co.

probability density function PEPR precision encoder and pattern project design flood recogmtion PDH&DS plant data handling and display PER problem event report system procurement evaluation request PDHS plutonium decontamination and hot PERMS process and effluent radiological shop momtonng system PDI Performance Demonstration PERMSS process and effluent radiological Initiative monitoring and sampling system PDIL power-dependent insertion limit PERT program evaluation and review PDL power distribution limit techmque PDMS postdefueling monitored storage program evaluation report technique PDP positive displacement pump PET performance evaluation team Process Development Pile permanent equipment transfer )

project definition phase PETA plutonium equipment transfer area PDR preliminary design report PETN pentaerythritol tetranitrate pressurized deuterium reactor PETS procedure for evaluating technical specifications public document room PE'ITE post-emergency tabletop exercise PDRP program data requirement plan Pu um e4u Pment Wann P PDS plant damage state PF partition factor plant data system g 91

Ni}C COL LF G flON OF ABBRL VIATIO Progressive Foundation pressurized heavy-water reactor proposed finding PI performance indicator protection factor physical inventory purge fan plasticity index PFCS primary flow control system position indication PFD process flow diagram pressure indicator PFDAS plant fire detection and alarm system process instrumentation PFE plenum fill experiment proportional integral PFES proposed final environmental purge isolation statement F&I piping and instrumentation PFG paper flow group PIA pressure indicator alarm Pi ping and filter gallery PIC pressure-indicating controller PFPCDS plant fire protection carbon dioxide pressurized ion chamber

"" "Y * #

• public information center PFPHS gnt fire protection Halon PICAN Prairie Island Coalition Against Nuclear Storage PFPS plant fire protection system PI&CS plant instrumentation and control PFPWS plant fire protection water subsystem system PFR Prototype Fast Reactor (United PID panial initial decision Kmgdom) .

Pii P ng and instrumentation diagram PFS peripheral fixed shim position indication device private fuel storage .

pmject ent ation PFSF private fuel storage facility .

PmPortional integral den.vative PG p.uticulate and gas P&ID piping and instrumentation diagram PGA peak ground acceleration PIPmg and instrumentation drawing PGCC power generation control complex Process and instrumentation diagram P&GD policy and guidance directive PIDS project identification sumnury PGDS pressurized gas distribution system PIE postirradiation examination PG&E Pacific Gas & Electric Co.

Postirradiation experiment PGG power generation group PIF pool irradiation facility PGP procedures generation package . .

problem identification form PGQ potentially generic question pressure-injected footing PGS plant gas system PIL Plant Issues List (now the Plant PHA pulse-height analyzer Issues Matrix)

PHERMEX pulsed high-energy radiographic PIM Plant Issues Matrix (formerly the machme-emitted x-ray Plant Issues List)

PHF plug-handling fixture PIMS pooled inventory management PHGA peak horizontal ground acceleration system PHR process heat reactor PIN piping interference notification PHS Public Health Service potential interference notification PHSPS preservation, handling, storage, PING particulate, iodine, and noble gas Packaging, and shipping PINGP Prairie Island Nuclear Generating PHTS primary heat transport system Plant PHWR pressurized heavy-water-moderated PINSTECH Pakistan Institute of Nuclear Science and -cooled reactor and Technology 92

1 PIO public information officer jl PLS precautions, limitations, and set PIOTA postirradiation open test assembly i Pomts proximity-instrumented open test PLT Princeton Large Torus assembly PM photomultiplier PIP Performance Indicator Program pressure multiplier performance improvement plan preventive maintenance performance improvement program program manager position indication probe project manager  ;

Probabilistic Risk Assessment (PRA) protective measure  !

Implementation Plan PMA personnel management analyst problem investigation plan plastic moderated assembly prototypic inlet piping PMC programmable machine controller PIPPAP pile fo,r producing power and Project Management Corporation PI "I *"*

protective measures coordinator PIR Petrolite Irradiation Reactor PME process and manufacturing plant internal report engineering problem identification report PMF probable maximum flood problem investigation report PMH probable maximum hurricane PIRG Public Interest Research Group PMI plant manager instmetion PIRR pipe inspection round robin PMIS plant monitoring and information PIRT phenomena identification and system ranking table precision mechanisms in sodium PIS pressure-indicating switch PML pro'aable maximum loss process instrumentation system PMM pedestal-mounted manipulator PISA Project Integrated Safety Assessment PMNP platform-mounted nuclear plant PISC Program for the Inspection of Steel PMOG plutonium maintenance and Components operating gallery PIV pressure-indicating valve PMP preoperational monitoring program pressure isolation valve preventive maintenance procedure PIXIE proton-induced x-ray emission jrobable maximum precipitation PL panel left program mu.ual procedure piping load PMR )lar a modification request plastic limit project manager report public law PMS performance measurement system PLATR Pawling lattice test rig plant monitoring system PLBR prototype large breeder reactor primary makeup system PLC power-line carrier probable maximum surge PLCEA part-length control element assembly program management staff PLCEDM part-length control element drive PMT photomultiplier tube mechamsm postmamtenance testing PLEX plant life extension PMU plant makeup PLOCAP post-loss-of-coolant-accident protection PMW probable maximum wind PLR policy and labor relations PMWP probable maximum winter precipitation 93

J NHC.COI 1. E f; TION OF AHHHE VIATIDNS PMY professional man-year PORACC principle of radiation and l contamination control j PN plant normal preliminary notification PORC plant operations review committee l

PNA pulsed neutron activation PORV pilot-operated relief valve PNE peaceful nuclear explosion Power-operated relief valve PNET Peaceful Nuclear Explosion Treaty POS plant operating system PNL Pacific Northwest Laboratory plant operational state i PNNL Pacific Northwest National Point of sale Laboratory POSA preliminary operating safety PNO preliminary notification of analysis / analyses occurrence POTC Power Operations Training Center PNPP Palisades Nuclear Power Plant PP primary pressure Perry Nuclear Power Plant PPA plutonium preparation area PNR Pittsburgh Naval Reactors Office power plant attendant PNS prelirninary notification of safeguard Princeton-Pennsylvania Proton PNSRC plant nuclear safety review Accelerator committee probabilistic performance assessment PNWL Pacific Northwest Laboratory PPC Pennsylvania Power Co.

PO project officer plutonium process cell purchase order plutonium product cell POA provisional operating authorization pore pressure cell POAH point of adding heat PPDD preliminary project design POD point of discharge desenption probability of detection PPDI plant process display instrumentation PWR (pressurized-water reactor) PPDIL pre-power-dependent insertion limit oxide decontamination PPE personnel program effectiveness PODCI probability of detection and correct PPFR plutonium product filter room interpretation PPG policy and planning guidance POF probability of failure PPH primary pump house POG piping and operating gallery PPIS plant protection and instrumentation POGE Portland General Electric Co. system POGO Project on Government Oversight PP&L Pennsylvania Power & Light Co.

POIS prototype online instrument system PPL Plasma Physics Laboratory POL possession-only license plutonium product loadout provisional operating license priority placement list POM position modulator ppm part per million POP peak overpressure PPM procedure preparation manual proof of principle PPMIP plant performance and management POPR prototype organic power reactor improvement program POPS pressurizer overpressure protection PPNM physical protection of nuclear system matenals POQAP plant operational quality assurance PPP point-to-point protocol procedure portable plotting package POR plant operations review PPPG policy, planning, and program plutonium organic recycle guidance 94

i l l l C TIONL OF AHHHE VI A TIONS ,

PPR plant performance review pump room exhaust air cleanup PPS plant protecticn system system plant proteriive system PRF penetration room filtration plutonium product storage PRG procedure review group primary power system PRHR. passive residual 1 at removal pps pulu per second PRHRHX passive residual heat removal heat exchanger PPSAS program planning and status assessment system PRISIM plant risk status information management PPSP power plant siting program Power reactor inherently safe module PPSPS plutonium product shipping preparation station PRL postulated rupture location PPSV plutonium product storage vault PRM personal radiation monitor PQAD plant quality assurance director petition for'mlemaking PQAM project quality assurance manager power range monitor .

PQAP project quality assurance plan Process radiation monitor PQR procedure qualification record Program review model PR Philippine Reactor Proposal for rulemaking plant recovery PRMS process radiation monitoring system power range PRNC Puerto Rico Nuclear Center press release PROM programmable read-only memory pressure recorder PROS Professional Reactor Operator b CI*IY procurement request PRR Pawling Research Reactor proposed rule Philippines Research Reactor PRA Paperwork Reduction Act of 1995 Pressure nse rate plutonium recycle acid Puerto Rico Reactor probabilistic risk analysis / analyses PRRWS public risk reduction worksheet probabilistic risk assessment PRS pressure response spectrum / spectra PRAF robabilistic risk assessment fundamentals process radiation sampler PRATTP probabilistic risk assessment PRSC plutonium rework sample cell technology transfer program PRT pressurized relief tank PRB plant review board prompt relief trip procedure review board PRTR plutonium recycle test reactor PRBSG pseudo-random binary sequeace PRTS pressurizer relief tank system generator PRV pressure relief valve PRC piping review committee PRVS penetration room ventilation system Planning Research Corp. PRWRA Puerto Rico Water Resources plutonium rework cell Authority pressure recorder controller PS Pilgrim Station PRCF plutonium recycle critical facility policy statement PRD potentially reportable deficiency power supply PRDC Power Reactor Development Co. pressure switch PRE processing prefabrication experiment pressurizer surge PREACS penetration room exhaust air cleanup PSA personnel and service area system 95

- 1

NHC COLL ECTION OF ABBREVIATIONS i

plant-specific action PSOK Public Service Co. of Oklahoma probabilistic safety analysis / analyses PSP physical security plan probabilistic safety assessment primary sodium pump PSAR preliminary safety analysis report PSPGV primary sodium pump guard vessel PSARV pressurized safety and relief valve PSPL Puget Sound Power and Light Co.

PSB personnel services building PSQ personnel security questionnaire plant service building PSR Pennsylvania State University PSC plant safety committee Research Reactor plutonium stripping concentrate peripheral shim rod Public Service Commission permanent side reflector Public Service Co. of Colorado plant status report PSCD plutonium stripping concentration primary system relief distillate procurement status report PSCS plant supervisory control subsystem PSR&D primary sodium removal and PSD power spectral density decontammation power spectrum density . PSRM post-scram reactivity monitor PSDAR post-shutdown decommissioning PSS primary sampling system activities report probabilistic safety study PSDD prelimin,ary system design process sampling system description PSSA preclosure systems safety PSDF power spectrum density function analysis / analyses PSE pressurized subcritical exjyeriment PSSAR preliminary standard safety analysis PSE&C power supply engineering;and report construction PSSP primary sodium sampling package Public Service Electric & Gas Co. PSSPS primary, sodium storage and PSER preapplication safety evaluation processmg system report PST pressure suppression, tank PSF performance shaping factor primary surge tank personnel security file PSTF pressure suppression test facility plutonium stripper feed proximity sensor test facility poolside facility pump seal test facility PSH pressure switch, high PSTG plant-specific technical guidelines PSHA probabilistic seismic hazard PSU Publication Sales Unit assessment PSUR Pennsylvania State University PSI preservice inspection Reactor prioritization of safety issues PSV pressurizer safety valve

( PSID preliminary safety information PSW plant service water document PSWG l p.' ant-specific writers guide 1

PSIN Public Service Co. of Indiana, Inc.

PSWS potable and sanitary water system PSMD Public Service of Maryland M' penetrant test PSMS plant safety monitoring system penetrant testing PSNH Public Service Co. of New periodic test Hampshire PSNM Peri di testing

! Public Service Co. of New Mexico PSNP Pebble Springs Nuclear Plant Phototransistor pool temperature 96

bO NRC COU f (, TION OF ABBHEVIATle%

preoperationel test PUP peak underpressure l

preoperational testing plutonium utilization program l pressure an.d temperature PUR Purdue University Reactor pressure transmitter PURPA Public Utilities Regulatory Policy P/r pressure and temperature Act of 1978 PTC passive thermal control PUSPATI Pusat Penyelidikan Atom Tun Ismail post-turnover change py " "f "

i NE pan-time equivalent l physics test exceptiora E'* ""'# ""' **

! NFG E# ""'* * ***'

Probabilistic Risk Assessment (PRA) PVC Training Focus Group polyvmyl chloride l

i NI pipe test insert PVHA probabilistic volcanic hazard anessment plugging temperature indicator Penetration valve leakage contml PTL Pittst"rgh Testing Laboratory PVNGS Palo Verde Nuclear Generating NLR pressure-temperature limits report Station i PTM plant temporary modification PVORT pump and valve operability review l NP peak to peak team l

preoperational test program PVRC Pressure Vessel Research Committee proximity test plug PVS plant vent stack NR performance trend report pressure vessel simulation pool test reactor PVT 1 piping and valve test insert pool training reactor PV&V preliminary verift ation and pressure tube reactor validation programmer troable report PW potable water P&W Pratt and Whitney proof test reactor PTS pressurized thermal shock PWG principal working group (NEA)

PTSE pressurized thermal shock PWHA plutonium waste-handling area experiment PWHT postweld heat treatment MSF pressurized thermal shock facility PWR pipe whip restraint PT/SP pressure tube-to-spool piece pressurized-water reactor NSR pressure tube superheat reactor PWROG Pressurized-Water Reactor Owners NSTF pressurized thermal shock test Gmup facility PWS potable water system PUA plant-unique analysis / analyses PWSCC primary water stress-corrosion crackmg PUAAG plant-unique analysis-applications guide PWST protected water storage tank Pub.L. Public Law PyC pyrolytic carbon PUC Public Utility Commission PZR pressurizer PUD paired uranium detectors PZR LCS pressurizer level control system public utility district PZR PCS pressurizer pressure control system j PULSTAR pulsed training assembled reactor 97

NHC col l: F C IlON I ABHl4 VIAIlONS - ,

QA quality assurance QG quality group QAA quality assurance audit QHO qualitative health objective QAC quality assurance checklist quantitative health objective quality assurance criterion / criteria QHR quality history record QAI quality assurance instruction QIT quality improvement team QAIP quality assurance inspection QLR quick-look report procedure qualification maintenance program QMP QAIRG quality assurance installation review quality management program group QO quick opening QAM quality assurance manual QOBV quick-opening blowdown valve QA&O quahty assurance and operations PM pliyNa- w QAP quality assurance procedure Q,,T quadrant power tilt quality assurance program Q,,TR quadrant power tilt ratio QAPI quality assurance program index QR quality revalidation QAPP quality assurance program plan g g, QA/QC quality assurance / quality control QSC quality systems certificate QAR quality assurance requirement QSL qua:ity suppliers list quality assurance representative gp y; , 9 QC quality control QSPDS qualified safety parameter display QCI quality control instruction system QCIP quality control inspection procedure QSR quarterly statistical repon QCIR quality control inspection report QSTF quarter-scale test facility QCP quality control procedure QTC Quality Technology Co.

QCS Quad-Cities Station QTP quality test plan QDO quantitative design objective QV quality verification QDPS qualified display processing system QVFI quality verification functional QE quality engineer inspection QF quality factor QVI quality verification inspection l

quality form 99

NHC LOl LECllON Of AHHid VIATK)NS .

RA reduction of area remote acquisition station regional administrator RASCAL Radiological Assessment System for Robotics and Automation Council Consequence Analysis R/A reliability / availability RAT radiological assessment team RAB reactor auxiliary building radiological assistance team RABNVS reactor auxiliary building normal reserve auxiliary transformer ventilation system RATI readiness assessment team inspection RABSRVS reactor auxiliary building switchgear restart assessment team inspection room ventilation system RAW risk assessment worth RABV reflood assist bypass valve RB reactor building RAC radiological assessment coordinator RBA radial blanket assembly regional assistance committee RBAL reprocessing building analytical report of abnormal condition laboratory RACES Radio Amateur Civil Emergency RBC reactor building cooling Service RBCCW reactor building closed-cooling water RACS rod action control system RBCLCW reactor building closed-loop cooling l rad radiation absorbed dose water l RAD rapid access data RBCLCWS reactor building closed-loop cooling RADCON radiologic control water system RADS radiation and dosimetry service RBCR reprocessing building control room RAI request for additional information RBCS reactor building cooling system RAIP requester's approval in principle RBCU reactor building cooling unit  ;

RAM radioactive material RBCW reactor building cooling water

]

random access memory RBE relative biological effectiveness  !

reliability, availability, and RBEDT reactor building equipment drain l maintainability tank RAMI reliability, availability, RBESI reactor building exhaust system maintainability, and inspection isolation RAMS regulatory activities manpower RBFC reactor building fan cooler system RBHS reactor building heating system RANNP Research Applied to National Needs RBM rod-block monitor Program RBOF receiving basin for offsite fuel RAOC relaxed axial offset control RBP reactor building protection l RAP radiological assistance plan RBPVS reactor building purge ventilation I reliability assurance plan system l remedial action program RBS reactor building spray l restart action plan River Bend Station RAPS radioactive argon processing system RBSI reactor building spray injection RAI*TUS rapid thorium-uranium system RBSR reactor building spray recirculation RAREF radiation and repair engineering reactor building spreading room facility reprocessing building spreading RARP reliability assessment research room program RBTL reactor building truck lock RAS reactor analysis and safety RBVI reactor building ventilation isolation recirculation actuation signal 101 l

I

Nf uJ (1 A M (;110N f AfhHf VIATIONS 1 1

RBVPRM reactor building vent process RCPB reactor coolant pressure boundary )

radiation momtor RCPS reactor coolant pump system RC reactor cavity RCRA Resources Conservation and reactor coolant Recovery Act recording controller RCS reactor coolant system rigid confinement R&CS radiological and chemical support RCA Radiation Control Agency RCSI reactor coolant system integrity radiological controlled area RCSIL rapid communication service reactor coolant activity information letter roct cause analysis RCSS reactor core subsystera RCAP root cause analysis program RCT response coordination team l RCB reactor containment building rework / completion tag RCBHT reactor coolant bleed holdup tank RC&T radiation control and test RCTS reactor coolant treatment system RCBT reactor coolant bleed tank RCC Radiochemical Centre Ltd. (U.K.)

RCTWS railroad car and truck wash station reactor cavity cooling RCV radiation control valve reactor closed-cooling RCW raw cooling water rod cluster control reactor cooling water RCCA rod cluster control assembly recirculating cooling water RCCS reactor cavity cooling system RD random driver RCDT reactor coolant drain tank receipt day RCE reactor compatibility experiment requirements documect RCEP Radiological Contingency and restricted data Emergency Plan R&D research and development RCFC reactor containment fan cooler RDA rod drop accident RCG radioactivity concentration guide RDAT remote data acquisition terminal recommended concentration guide RDAU remote data acquisition unit RCGM reactor cover gas monitor RDDM reactor deck development mockup RCIC reactor core isolation coolant RDH radioactive drain header i reactor core isolation cooling RDO regional duty officer f RCICS reactor core isolation cooling system RDOS real-time disk operating system RCIS rod control and information system RDP reactor development program RCL reactor coolant loop RDS reactor depressurization system RCLC reactor coolant letdown cooler RDSD reliability design support document RCLVS radiation chemistry laboratory RDT reactor development and technology ventilation subsystem reactor drain tank RCM reliability-centered maintenance RE radiation equipment Response Coordination Manual rare earth RCMU reactor coolant makeup right end RCN Reactor Centrum Nederland REA radiologic engineering assessment (Netherlands) .

recycle acid RCP radiological control program

. rod ejection accident reactor charactenzation program Rural Electrification Administration reactor coolant pump 102 l

NRC COL L ECTION Of ABhHE VIATIONS-REAC Radiological Emergency Assistance RES INSP resident inspector Center (Oak Ridge Tennessee) RESAR reference safety analysis report REBA relativistic electron beam accelerator RESC reactor subcriticality REC radiant energy conversion RESL Radiological and Environmental RECC radiological effluent control Sciences Laboratory c mnutment RETS radiological efnuent technical RECHAR recombiner charcoal adsorber specification RECS radiologi, cal emergency radiological environmental technical commumcations system specification RECW reactor enclosure cooling water REVAB relief valve augmented bypass REETS radiological effluent and REW recycle water environmental technical specification RF radiofrequency REHR reactor heat removal release factor REI request for engineering investigation reply finding REIC Radiation Effects Information Center RFA Regulatory Flexibility Act REIRS Radiation Exposure and Information removable fuel assembly Reporting System .

RFC recirculation How control REL radiation evaluation loop request f r c mrnents reactor equipment limited RFCS recirculation flow control system REM realistic evaluation model RFI radio frequency interference rem roentgen equivalent man request for infonnation REM-

. RFIC request for information or ODCM radiological effluent, monitoring and clarification offsite dose calculation manual RFN remote filter niche REMP radiolog,ical environmental monitonng program RFO refuelin8 outa8e REP radiological emergency plan RFP reactor feed pump resonance escape probability request for procurement rep roentgen equivalent physical request for proposal RER radiation effects reactor reversed field pinch radioactive effluent release Rocky Flats Plant regulatory effectiveness review RFPA request for procurement action l representative for experiment review RFFT reactor feed pump turbine risk evaluation report RFQ request for quotation RERC radiological emergency response RFT revisable format text coordmation RFW reactor feedwater RERO radiological emergency response RFX reversed field experiment l operation RG regulated gallery RERP radiol,ogical emergency response regulatory guide planning RERS rea or enclosure recirculation R &E Ro es e Gas Electric Corp.

RERTR reduced enrichment for research and RGM radiogas monitor 1 test reactors RGR rare-gas recovery {

RES Nuclear Regulatory Research, Office RH relative humidity of(NRC) RHC reactor head cooling i

l 103

NRC COLLECTION OF AMBHEVIATlONS l

RHR residual heat removal receiving inspection plan RHRP residual heat removal pump RIPBR risk-informed, performance-based residual heat removal system regulation RHRS RIPS radioisotope power supply RHRSW residual heat removal service water RIR radiological incident report RHT recycle holdup tank RHTS reactor heat transport system receipt inspection report risk increase ratio RHX regenerative heat exchanger radiation indicator RIRP Regulatory Issue Resolution Plan RI reactor island RIS reporting identification symbol reservoir-induced seismicity Region 1-King of Prussia, Pennsylvania (NRC) RISC reduced instruction set computer resident inspector RISS reactor internals subsystem resonance integral RITS regulatory information tracking R&l removal and installation system resource information tracking system RIA reactivity-initiated accident reactivity insertion accident RIV reactor isolation valve regulatory impact analysis or Region IV-Arlington, Texas (NRC) analyses RJE remote job entry removable instrument assembly RKS Raadet foer Kaernkraftsaekerhet RIAEC Rhode Island Atomic Energy (Sweden)

Commission RL reactor licensing RIB recruitment, incentives, and benefits refracted longitudinal RICO Racketeering Influenced and Corrupt RLE review-level earthquake Organizations Act RLM residual load method RIDR receipt inspection data report RLO Records Liaison Officer RIDS receiving inspection data status RLOP reactor licensing operating procedure regulatory information distribution RLR radioactive lighting rod system RM radiation monitor RIE Replacement item Evaluation radiation monitoring RIENA Rassegra Internazionale Elettr6nica Nucleare ed Aerospaziale (Italy) radiometric monitor RIF reduction in force reactor manufacturer RIG risk-based inspection guide remote manual RII receiving inspection instmetion rulemaking Region II-Atlanta, Georgia (NRC) RMAAS reactivity monitoring and alarm RIIC rotary inertia included case 878'#*

RMBCS Rocky Mountain Bank Card System Rlll Region III-Lisle, Illinois (NRC)

RMC Radiation Management Corporation RIL research information letter rem te manual control RIM relative importance measure RM&C reactor monitoring and control RIMS regional input-output modeling system RMCS reactor makeup control system RINA Registro Italiano Navale (Italy) reactor manual control system RIOPR Rhode Island Open Pool Reactor RME reasonable maximum exposure RIOT remote input-output terminal RMF reactivity measurement facility RIP reactor internal pump RMI reflective metallic insulation i

R 104

• E NRC COLL ECTION OF ABBREVtAT' IONS RMIEP risk me,thodology integration and RPAO regional public affairs officer evaluation program RPAS reactor protection actuating signal RMP risk management plan RPB reactor pressure boundary RMRM radioactive materials reference RPC manual Radiation Policy Council RMS Radiation Protection Committee radiation monitoring systeni radiological monitoring system ** '# P""* * ##"

rod pattern controller regulatory manpower system mtadng pancake con remote manual switch RMW reactor makeup water ' P *" '"I RMWS reactor makeup water storage '**P""''^"*'"*

RPCS reactor plant control system RMWST reactor makeup water storage tank RMWT reactor makeup water tank 3 '*'P"" I II * '

te ctor plant ignu des. "E * *' 'Y' #* l reactor makeup water transfer . ,

. . . RPDF radiation protection design feature f RNA nbonucleic acid RPE radiation protection engineer RNB research nuclear battery resource planning and evaluation return to nucleate boiling regi n pe ng factor RNDT reference nil ductility temperature right panel front RNWP reduced notch worth procedure RO RPG radiation protection guide reactor operator report pmgram generator regional office .

RPI relative position indication remain open .. .

rod position indicator reponable occurrence .

. . RPIS rod pos. .ition indication system restriction onf. ice .

rod position information system ROD RPM radiation protection manager release order directive . . .

RPO radiation protection officer ROI region ofinterest RPP radiation protection plan ROM read only memory RPPS r : actor plant and process sampling ROP record of purchase RPS .adiation protection supervisor ROS requisition on stores Reactor Program System ROSA Rig of Safety Assessment

'#"# ' P"* " # #"'

ROSENERGO-

. regulatory performance summaiy ATOM Nuclear Power Utility (Russia)

. RPST reaction products separator tank ROSPA nsk-based operational safety performance assessment RI*T radiation Protection technician ROW requisition on warehouse reactor for physical and technical right of way recirculation pump trip RP radiation protection RPV reactor pressure vessel reactor pool RPVI reactor pressure vessel ictegrity reactor press w RPVRI reactor, pressure vessel reflective insulation re ctor pmpct R&QA reliability and quality assurance regulatory position RQD rock-quality designation miease p int RR receiving report RPAM regional public affairs manager 105

NHC COLLI C1K)N OF AHf$HE VIATIONS review report RSCW Research Reactor, State College of review request Washington RRA Radiation Research Associates,Inc. RSD relative standard deviation risk-reduction analysis / analyses responsible system designer RRC radiation recorder controller RSE reserve shutdown equipment reactor recirculation cooling RSEP Robinson Steam Electric Plant RRD retendering receipt day RSH resin sluice header R&RE radiation and repair engineering RSHX recirculation spray heat exchanger RRG regulatory response group RSI reactor siting index regulatory review group RSIC Radiation Shielding Information Center research review group RSK Reaktorsicherheitskommission RRI resident reactor mspector (Germany)

RRP reactor recirculation pump RSLO regional State liaison officer reactor refueling plug RSNGS Rancho Seco Nuclear Generating RRPI relative rod position indication Station rotary relative position indicator RSO radiation safety officer RRR Raleigh Research Reactor reactor system outline RRRC Regulatory Requirements Review RSP reactivity surveillance procedure Committee remote shutdown panel RRS reactor recirculation system rotating shield plug reactor refueling system RSPE recruitment, staffing, and position reactor regulating system evaluation required response spectrum / spectra RSR radiological safety review resin regeneration subsystem reactor safety research RRTF Regulatory Reform Task Force reference safety report RRW risk reduction worth remote shutdown room RS radiation source RSS reactor safety study reactor safeguards reactor shutdown system reactor safety recirculation spray system reactor system relay setting sheet recirculation spray remote shutdown system reference section reserve shutdown system RSA remote shutdown area RSSF retrievable surface storage facility RSAO Regional State Agreements Officer RSSMAP Reactor Safety Study Methodology RSARR Republic of South Africa Research A PPlication Program Reactor RSST reserve station service transformer RSB reactor service building RSW raw service water RSC radiation safety committee remote shutdown workstation reactor safety coordinator RT radiographic test reactor site criterion / criteria reactor trip RSCE reserve shutdown control equipment reference temperature RSCM reserve shutdown control material RTB reactor trip breaker RSCS reactor seqtience control system RTC regional training center rod sequence control system removable top closure 106

F ABisHEVIATIONS .

1 RTCB reactor trip circuit breaker RVLM reactor vessel level monitoring j run to cladding breach RVOS relief / safety valve, open system RTD resistance temperature detector RVRLIS reactor vessel refueling level resistance temperature device indication system Roent en Technische Dienst B.V. RVS reactor vessel system )

(Netherlands) RVSS reactor vessel support structure I RTDP reactor technology development plan RVUH reactor vessel upper head revised thermal design procedure RW raw water RTE relocation tabletop exercise Ringsdorff-Werke, G.m.b.H. '

residual total elongation (Germany)

RTG radioactive thermoelectric generator river water 3 radioisotope thermoelectric generator RWA radwaste area l

RTGB reactor turbine generator board RWB rod withdrawal block RTL radioisotope transport loop RWC reactor water cleanup RTM reactor trip module RWCS reactor water cleanup system regulatory technical RWCU reactor water cleanup j memorandum / memoranda RWDS radwaste disposal system Response Technical Manual RWE Rheinisch-Westfulisches RTndt reference temperature nil ductility Elektrizitutswerk, A.G.(Germany)

RTNSS regulatory treatment of nonsafety rod withdrawal error systems RWL reactor water level RTO reactor trip override rod withdrawal limiter RTP rated thermal power RWM rod worth minimizer restart test program RWN room work notification RTS reactor trip system RWP radiation work permit refueling water transfer and storage radwaste work permit RTSS reactor trip switchgear system RWPC radwaste process cell R'IT reference transition temperature RWPH river water pump house RTV room temperature vulcanizing RWR radioactive waste reduction R&U repairs and utilities RWS radwaste system RV Reactor Venezolano (Venezuela) raw water system reactor vessel RWSF radwaste solidification facility release valve RWSP refueling water storage pool relief valve RWSS radwaste sample station RVC reactor volume control RWST refueling water storage tank remote valve control RWT radiation worker training j l RVDP relief valve discharge piping refueling water tank l RVHVS reactor vessel head vent system RWTA river water treatment area l RVID Reactor Vessel Integrity Database RWTS regenerant waste treatment RVIS reactor vessel instrumentation system subsystem l

l RVLIS reactor vessel level instrumentation RWV radioactive waste vent system RY reactor-year l 1

l 1

l l

107 p -

SA safety analysis / analyses SAMDA severe accident mitigation design safety assessment alternative service air SAMG severe accident management guidelines system administrator SAMIS structural analysis and matrix S/A subassembly inversion system S&A surveillance and accountability SAN standard address number SAAEB South African Atomic Energy Board SAP Severe Accident Program SAC Systems Automation Corp. Special Access Program SACF single active component failure startup administrative procedure SAD safety analysis diagmrn synthetic aperture program safety assurance diagram SAPHIRE Systems Analysis Program for systems, assistant director Hands-on Integrated Reliability SADE superheat advanced demonstration Evaluation experiment SAPL Seacoast Antipollution League SAE site area emergency SAPS Shippingpoit Atomic Power Station Society of Automotive Engineers SAQV safet as,sessment and quality SAFDL specified acceptable fuel design limit ven ication SAFE safe SAR safety analysis report evalbuards ation automated facility SARA severe accident risk assessment Society for the Advancement of systems analysis and risk assessment Fission Energy SAREF safety research experiment facility SAFO Swedish Atomic Forum SARP Severe Accident Reduction Program SAFR sodium advanced fast reactor Severe Accident Research Plan SAFT synthetic aperture focusing technique Severe Accident Research Program SAG senior advisory group SARRP Severe Accident Risk Reduction SAGSI Standing Advisory Group on Program Safeguards Implementation SART site access refresher training SAI Science Applications,Inc. SAS safety assessment system SAIC Science Applications Intemational secondary alarm station Corp. (formerly Science Applications, Inc.) secunty agency study SAID safety analysis input data service air system SAIG~ Societh di Architettura Industrials station air system per Gli Impiantidi Generazione de SASA severe accident sequence Energia, spa (Italy) analysis / analyses SAL service advisory letter SAT site access training SALE safeguards analytical laboratory spray additive tank evaluation startup auxiliary transformer SALP systematic assessment oflicensee station auxiliary transformer performance SAM seismic anchor motion '#' .# "" EE" ' '" " " E SATNUC Societe pour l' Applications stabilized assay meter Techniques dans le Domaine de substitute alloy material l'Energie Nucl6 aire (France)

SAMA Scientific Apparatus Makers SAVC structural assembly verification card Association SAVS safeguards area ventilation system SAW steam, air, water 109

' o NHC col l E CTIONpf AWBHEVIATION5 _

submerged arc weld SCBR steam-cooled breeder reactor submerged are welding SCC shutdown cooling circulator SAYG sign-as-you-go specialized common carrier SBA Small Business Administration stres:.-corrosion cracking SBACS shield building air cleanup system SCCS secondary chemical control system SBAECS shield building air exhaust cleanup shutdown cooling circulator i system subsystem SBC steam bypass control sodium chemistry control system SBCC steam bubble collapse induced standby core cooling system SBCR Small Business and Civil Rights, SCD severe core damage Office of(NRC) significant construction deficiency  ;

SBCS steam bypass control system SCDAP severe core damage analysis package 1 SBFAS shield building air filtration actuation SCDWMR steam-cooled deuteriated system water-moderated reactor SBFU stuck breaker failure unit SCE saturated calonwi electrode SBGT standby gas treatment situation-caused error SBGTS standby gas treatment system Southern California Edison Co.

SBIR Small Business Innovative Research SCEAR Scientific Committee on the Effects SBK Schnell-B re ter-Kernkraftwerksgesell of Atomic Radiation schaft, m.b.H. (Germany) SCEG South Carolina Electric & Gas Co.

SBLC standby liquid control SCE&G South Carolina Electric & Gas Co.

SBLOCA small-break loss-of-coolant accident SCEL small-component evaluation loop SBO station blackout SCEW system component evaluation SBOC superheated blowdown outside worksheet contamment SCF SNAP critical facility SBR Soviet Breeder Reactor sodium cleaning facility SBREFA Small Business Regulatory SCFBR Enforcement Fairness Act steam-cooled fast breeder reactor scfh standard cubic foot / feet per hour SBVS shield building ventilation system scfm sta e ef et per m note SBWR simplified boiling-water reactor SCFS secondary containment fill station SC safety class secondary confinement SCGA sodium-cooled graphite assembly SCHE shutdown cooling heat exchanger site characterization SCHES shutdown cooling heat exchanger site contingency subsystem speed controller SCHS small-component handling system surveillance comph,ance SCI secondary containment isolation SCA secondary control assembly SCIV secondary containment isolation simulated core assembly valve single-channel analyzer SCK Studiecentrum voor Kernenergie site characterization (Belgium) analysis / analyses SCM simulated core mockup small component autoclave simulated core model sneak circuit analysis / analyses steam condensing mode SCAT spray chemical addition tank SCN software change notice SCBA self-contained breathing apparatus specification change notice S 110

v NRC cot.l.ECTION OF ABBREVIATIONS .

1 1

SCO senior control (room) operator SCTL small components test loop l SCOA sample cave operating area SCUMRA Soci6te Centrale de l' Uranium et des SCORE Standing Committee on Regulatory Min 6raux et M6taux Radioactifs l Effectiveness (France)

SCOTTR supercritical once-through tube SCV steel containment vessel I

reactor systems completion verification l l SCP security control point SCVI special construction verification I site characterization plan inspection l

SCPPCS secondary containment purge and SCWE safety-conscious work environment pressure control system SCWHE shutdown cooling water heat SCR selenium control rectifier exchanger significant condition report SCWR supercritical water reactor silicon-controlled rectifier SCWS shutdown cooling water system site characteri ation report SD scram discharge I

site characteraation review shakedown sodium-cocied reactor shutdown software change request standard deviation SCRB Senior Contract Review Board standard drawing SCRD secondary control rod driveline standards development SCRDM secondary control rod drive station directive mechanism supply duct SCRE shift control room engineer system description SCRM secondary certified reference S/D shutdown material SDA standard design approval l SCRO senior control room operator startup detector assembly ,

SCRS secondary control rod system supplier data approval l

SCRWC Sierra Club Radioactive Waste SDABFOS standby diesel and auxiliary boiler Campaign fuel oil system

)

SCS secondary coolant system SDBCS steam dump bypass control system shutdown cooling system shield design code SDC j sodium characterization system shutdown cooling Soil Conservation Service (U.S. standard design certification Department of Agneulture) structural design criterion / criteria SCSHX shutdown cooling system heat SDCAIES standby diesel combustion air intake and exhaust system shutdown cooling system heat SDCC small-diameter component cask SCSI Southern Company Services, Inc. SDCS shutdown cooling system SCSIN Service Central de SQrdt6 des SDD system design description Installations Nucl6aires (France) SDECS standby diesel engine cooling system SCSS Sequence Coding and Search System SDEM Soci6te d' Enterprise de Montages SCST spray chemical storage tank (France)

SCTA secondary container transfer area SDESS standby diesel engine starting system SCTF slab core test facility SDF spillway design flood sodium chemical technology facility SDG standby diesel generator SCTI sodium component test installation SDGE San Diego Gas & Electric Co.

111 w _ __ - _____ - _ _ _ _ _ _ _ _ _ _ _ .

NHC COL L ECTION OF ABBREVIATIONS '

SDH side drill hole SEASET separate effects and systems effects SDHR shutdown decay heat removal test SDHX shutdown heat exchanger SECC Safe Energy Communication Council SDIP surveillance dosimetry improvement SECHT scoping emergency cooling heat program transfer SDLC synchronous data link control SECOM Safe Energy Coalition of Michigan system development and life cycle SECY Secretary of the Commission, Office SDLCM system development and life cycle of the(NRC) management SEDSS Sandia Environmental Decision SDLOS standby diesel lubricating oil system SD/LP SEE IN S r ifi an nt Evaluation and shutdown and low power Information Network SDM shutdown margin SEE-IN significant event evaluation-SDMF surveillance dosimetry measurement information notice facility SEEN Syndicat d' Etudes de l'Energie SDMP Site Decommissioning Management hucleaire (Belgium)

Plan SEFOR Southwest Experimental Fast Oxide SDOF single d.. , ce of freedom Reactor SDP setdown pool SEFR shielding experiment facility reactor SDR security design report SELNI Societh Elettronucleare Italiana significant deficiency report (Italy)

SNAP Developmental Reactor SELO Societh Elettronica Lombarda (Italy) supplier deviation request SEM scanning electron microscope SDS sanitary drainage system SEMO Soci6t6, Belgo-Frangaise,d'Energie Nucl6 aire Mosane (Belgium) shutdown sequencer SEN Si nificant Event Notification steam dump system (INPO) submerged demineralized system SENA Soci6ts d'Energie Nucidaire SDSP site director standard practice Franco-Belge des Ardennes (France)

SDV scram discharge volume SENN Societh Elettronucleare Nazionale steam dump valve (Italy)

SDVIV scram discharge volume instrument SENTA Soci6t6 dEtudes Nucl6aires et de volume Techniques Avanc6es(France)

SE safety evaluation SEO side entry orifice shift engineer SEP safety enhancement program significant event (NRC performance s te emergency plan indicator) source evaluation panel subcritical experiment standby electric power SEA Science and Engineering Associates, Systematic Evaluation Program Inc. SER safety evaluation report Susquehanna Environmental Sandia Engineering Reactor Advocates SEAONC

1. "'"# " ##E "

ineers Association of .

Northern Cal Enffornia Structural significant event report SEAR safety evaluati on audit report SNAP Experimental Reactor SEAS Strategic Environmental Assessment Staff Evaluation Report Systems SERB State Environmental Review Board S 112 l

l

1 NRC col;LECTION OF ABBREVIATIONS -

SERC Southeastern Electric Reliability spent fuel pool Council SFPAVS spent fuel pool area ventilation SERF Sandia Engineering Reactor Facility system special environmental SFPC spent fuel pool cooling radiometallurgy facility SFPCCS spent fuel pool cooling and cleanup SERG steam explosion review group system SERR semiannual effluent release report SFPCPS spent, fuel pool cooling and SERS safety evaluation report supplement punf cation system SES safety evaluation supplement SFPCS spent fuel pool cooling system Senior Executive Service SFPO Spent Fuel Project Office (NRC) steam electric station SFR startup field report SET Special Evaluation Team SFRCS steam and feedwater rupture control system systems effects test

. SFRP Societs Franqaise de Radioprotection SETF SNAP Expenmental Test Facility (France)

SETS standard environmental technical SFR&TA system function review and task specification analysis standardized environmental technical SFS startup feedwater system specification steam and feedwater system SETU Societ6 d' Etudes et de Travaux pour SFSP spent fuel storage pool i l' Uranium (France)

SEUSSN Southeastern United States Seismic SFTA spent fuel transportation accident Network SFTT spent fuel transfer tube SEWS Screening Evaluation Work Sheet SG safety guide SF source factor steam generator spent fuel S/G steam generator SFA single-failure analysis / analyses SGAE Studiengesellschaft fur Atomenergie, spent fuel assembly m.b.H. ( Austria) standard fuel assembly SGAHRS steam g'enerator auxiliary heat safety features actuation signal

'# * "" 'YS #

• SFAS

. SGAS steam generator available s.ignal SFBI spent fuel build.mg isolation SGB steam generator blowdown SF&C standard format and content

• *

• E#"##" " "E SF&CG standard format and content I guidance SGBD steam generator blowdown SFCR storage facility control room SGBPS steam generator blowdown processmg system SFCS secondary flow control system SGBS steam generator blowdown system spent fuel cooling systern SNAP Generalized Critical Facility SGCF SFCSR starage facility cable spreadm.g room SGD steam generator dryout SFD severe fuel damage SGDSM steam generator degradation-specific SFDP safety functions determination management P' E'"* SGE Soci6t6 Gendrale d' Enterprises SFDST severe fuel damage scop.mg test (France)

SFEN Soci6t6 Frangaise d'Energie SGEF steam generator examination facility Nucleaire (France) SGER safeguards evaluation report SFIV startup feedwater isolation valve SGFP steam generator feedwater pump SFP spent fuel pit steam generator group project SGGP 113

\

NHC COL i ECTION OF ABBHE VIATIONS )

SGHWR steam-generating heavy-water reactor Enforcement Development I

SGI Safeguards Information S/HNP Skagit/Hanford Nuclear Project Silicon Graphics International SHNPP Shearon Harris Nuclear Power Plant SGIP Steam Generator Integrity Program SHPO State Historic Preservation Officer SGIS safeguards initiation signal SHRS shutdown heat removal system SGLIC steam generator level SHTL small heat-transfer loop instrumentation cabinet SI safety injection SGML standard generalized markup security inspector language special instruction SGMSR steam generator maximum steam rate SGN Societ6 de G6me Nucl6 aire (France) surveillance m.spection SGOG Steam Generators Owners Group SGR self-generation reactor

. . systeme mternational (d' unit 6s) sodium-graphite reactor (International System of Units)

SGS Salem Generating Station SIAS safety injection actuation signal segmented gamma scanner SIC standard industrial classification steam generator subsystem Standard Industrial Code steam generator system SICN Soci6td Industrielle de Combustible subgrid scale Nucl6 aire (France)

S/GS steam generator system SICS safety injection control systera SGSA steam generator subassembly SID sodium ionization detector SGSV steam generator safety valve SI/EB safety injection / emergency boration SGTF steam generator test facility SIET Societh Informazioni Es SGTIP Steam Generator Tube Integrity Termoidruliche (Italy) perienze Program SIG special inquiry group SGTR steam generator test rig SIGEN Societh Impianti Generazione steam generator tube rupture Energia Nucleare, spa (Italy)

SGTS standby gas treatment system SIHP Sargent Industries, Huntington Park SGV steam generator vessel SIL service information letter SGWLC steam generator water level control SIM service information

• 1. * '" "**#*'^"^

SHA sodium hydroxide addition SIMEA Societh Italiana Meridionales Energia solid homogeneous assembly Atomica (Italy)

SHAA sealed head access area SIMS safety issues management system SHADE shielded hot-air drum evaporator SIN Schweizerisches Institut fur SHARE systems for heat and radiation energy Nuklearforschung (Switzerland)

SHE semihomogeneous experiment SINB Southern Interstate Nuclear Board standard hydrogen electrode SINET Shared Information Network SHEAC Safety, Health, and Environmental SIO Societh per l'Industria dell'Ossigeno e Appraisal Committee de Altri Gas (Italy)

SHEEC Shearon Harris Energy and SIPAO simulator for postaccident operation Environmental Center SIPI Scientists Institute for Public SHF storage-handling facility Information SHI Sumitorno Heavy Industries Ltd. SIR safeguards implementation report Oapan) safe integral reactor SHMED State Hazardous Materials 114

. Niw ( ( >l I I ( i u m f Ahlld vl A n()NS safety issue resolution SLMCPR safety limit for minimum critical l

self-initiated review Power submarine intermediate reactor SLO single-loop operation SIRMO senior information resource State liaison officer management official SLP St. Lucie Plant SIRW safety injection and refueling water SLPS State and local program support SIRWT safety injection and refueling water SLSF sodium-loop safety facility tank SLTC seismic loading for temporary SIS safety injection signal condition safety injection system SLSV shutdown-loop shutoff valve site integrated schedule SLUC standard level user charge Special Inspection Services SLWMS secondary liquid waste management SISBO self-induced station blackout system l SISI surveillance and inservice inspection SM shift manager SIT safety injection tank stationary medium safety injection transmitter SMA shielded metal are Servizio Italiano di Taratura (Italy) SMACNA Sheet Metal and Air Conditioning Contractors' National Association socialimplications of technology SMARY senior management assessment of structural integrity test readmess team SITP site inspection and test procedure SMAW shielded metal arc weld SJAE steamjet air ejector shielded metal arc welding SJWCP skid jacket water cooling pump submerged metal are welding SKA Studienkommission fur Atomenergie SMBDB structural margin beyond design (Switzerland) basis SKI Swedish Nuclear Power Inspectorate SMC segmented maintenance cask SL safety limit seismic methodology chain section leader systems, man, and cybernetics j stationary low SMM seismic margins method S&L Sargent & Lundy Engineers senior management meeting SLAC Stanford Linear Accelerator Center subcooling margin monitor SLB status light box SMP simulator modification package j steamline break SMR shield mockup reactor SLC standby liquid control solid moderated reactor State liaison coordinator system modification request SLCRS supplemental leakage collection and SMS special monitoring system release system SMSA standard metropolitan statinical area supplementary leak collection and release systern SMTI sodium mechanisms test installation standby liquid control system SMTP simple mail transfer protocol j SLCS shutdown logic diagram MUD Sacramento Municipal Utility l

SLD District I SLF seismic load factor serial number '

S/N SLI steamline isolation SNAME Society of Naval Architects and SLIP serial line Internet protocol Marine Engineers SLIV steamline isolation valve 115 l

1

NHC COL.L.E CTION OF ABUf W \/lA T4ONS ,

SNAP safeguards network analysis SOE sequence of events Procedure SOER safety operational event report shielded neutron assay probe significant operating event report Struthers Nuclear and Process Co. significant operating experience systems for nuclear auxiliary power report SNC Sierra Nuclear Corp. SOICS summary ofinstallation control SNE Sociedad Nuclear Espa5ola (Spain) status SNEC Saxton Nuclear Experimental Corp. SOL senior operator license subgroup on nuclear export SOM shift operations manager coordination SONGS San Onofre Nuclear Generating SNERP Saxton Nuclear Experimental Station Reactor Project SONOPCO Southern Nuclear Operating SNG synthetic natural gas Company S'NGS Sa'em Nuclaar Generating Station SOP standard operating procedure SNI Societh Nucleare Italiana (Italy) stepoff pad Sandia National Laboratories Supervisory Orientation Program SNM Society for Nuclear Medicine SOPI system, operational performance inspection special nuclear material SOPR Spanish Open Pool Reactor SNOC Southern Nuclear Operating Company SOPREN Soc.ieth Progettazione Reattori SNP Nucleari, spa (Italy)

Sequoyah Nuclear Power Plant SOR static O-ring Skagit Nuclear Power Project SNPS Seabrook Nuclear Power Station '# "." * .

E## ' "" '# ## # "" ##

Shoreham Nuclear Power Station SORIN *Societ

" '. "h Ricerche impianti Nucleari SNR slow neutron reactor (Italy) supplier nonconformance report SORV stuck-open relief valve SNRC Soreg Nuclear Research Center SORX Security Organization Response SNS Seabrook Nuclear Station Exercise spallation neutron source SOS shift operations supervisor SNUPPS standardized nuclear unit power SOV solenoid-operated valve plant system SOW statement of work SO Siemens Dsterreich (Austria) SP sampling point status officer security procedure supervising operator set point SOA statement of account special project SOC Statements of Consideration special purpose SOCCS summary of component control suppression pool status SOCIA surveillance procedure Soci6t6 pour l'Industrie Atomique (France; SPACS sodium purification and SOD characterization system shallow outside diameter SPAHR simulation package for assessing

, Societe d' Etudes pour l'Obtention du health risks  !

Deuterium (France)

SPAR simplified plant analysis risk SODERN Socist6 d' Etudes et Realizations Nucleaires (France) SPB Security Policy Board S ,,e

l NRC COL L ECTION OF ABBHE VIATIONS .

I

{

SPC Siemens Power Corporation Surry Power Station l

(formerly Exxon Nuclear) SPSC Southwestern Public Service Co.

standby pressure control SP/SC shield plug / support cylinder I stored program controller SPSS l shield plug storage station suppression pool coolmg SW satellite pulse technique SPCED system for physical control of energy special purpose test I distribution standard penetration test l SPCP statistical process control program SMF sodium pump test facihty SPCU suppression pool cleanup SPDES State Pollutant Discharge SPVC

• !#8*E'******"I simulated pressure vessel capsule Elimination System SPDS safety parameter display system SPVR storage process vent room SPEEDI system for prediction of SPX superheat power experiment environmental emergency dose SQR seismic qualification report mformation supplier quality representative SPER Security Plan Evaluation Report seismic qualification review SQRS SPERT special power excursion reactor test summary {

SPES Simulatore per Esperienze di SQRT seismic qualification review team Sicurezza (Italy) [ Simulator for Seismic Qualification User's Group I Safety Expenmental Analysis] SQUG .

Seismi Qualification Utility Group Simuluzione PWR per Esperienze di Sicurezza (Italy) SR safety related SPF site population factor safety rod standard project flood source range

! SPGD self-powered gamma detector summary report l SP/HD spool piece head support reaction SPI site population index surveillance requirement SPIAM sodium purity in-line analytical S/R safety relief module shipper-receiver SPIN Societh SRA senior resident analyst (Italy) per Imprese Nucleare, spa SRB safety review board SPIP Safety and Performance SRBT single-rod burst test Improvement Program SRC ience Research Council (United SPMC Seabrook CommumPlan ties for the Massachusetts shutdown reactor cooling SPMS suppression pool makeup system Spares receiving checklist SPND self-powered neutron detector SRCAS safety-related control air system SPOC system preoperability checklist SRCC safety-related control circuit SPOUT system peripheral output utility SRCI safety-related control and SPR Sandia Pulsed Reactor instrumentauon SPRF Sandia Pulsed Reactor Facility SRD self-reading dosimeter SPS safety protection subsystem shipper-receiver difference secondary plant system SR&D sodium removal and decontamination standard project storm SRDA sodium removal development Summit Power Station apparatus supplementary protection system SRDC safety-related design condition 117 S

nia, (J n l I e in D F nnnni VInin >Ns SRDI safety-related display SRU Soci6t6 de Raffinage d' Uranium instrumentation (France)

SRE safety-related equipment SRV safety / relief valve sodium reactor experiment S/RV safety / relief valve SREC standard radiological effluent control SRVDL safety / relief valve discharge line SRFM source range flux monitor S/RVDL safety / relief valve discharge line source range flux monitoring SRVL safety-related vendor list SRGS St. Rosalie Generating Station SRVO safety relief valve open SRH switchyard relay house SR/VO safety relief valve open .

SRHC shutdown reactor head cooling SRWS solid radioactive waste system I SRI senior resident inspector SS safe shutdown l i

Stanford Research Institute sample sink SRIAER Scientific Research Institute for sample station Atomic Energy Reactors (U.S.S.R.) sampling system SRIC senior res,ident inspector for shift supervisor constriction SRL Savannah River Laboratory 8**'"[*IY site suitabih.ty SRM source range monitor S uthern Services,Inc.

staff requirements memorandum / memoranda special source standard reference material Speed sensor startup range monitor stainless steel SRN specification revision notice Susquehanna Station SRO senior reactor operator systems specialist specification release order SSA safety system, actuation (NRC SROA safety-related operator action Performance indicator)

SSAB site-specific advisory board SROS send / receive from the opposite side SSAR site safety analysis report SRP Savannah River Plant standard safety analysis report small radioactive particle AS sman sample assay system small rotating plug SSAT safety significance assessment team Standard Review Plan SSB Source Selection Board SRP-LR standard review plan-license renewal Strategic Steering Board SRRC Standing Results Review Committee SSC short segmented cask SRS sodium removal station simulated surveillance capsule sodium removal system Southern Services Company solid radwaste system stmeture, system, and component SRSS send / receive from the same side super system code square root of the sum of the squares SSCA spray system compressed air SRST spent resin storage tank SSCC Solid-State Circuits Council SRT special review team SSCCS solid-state component control system spent resin tank SSCR spectral shift control reactor SG Soci6t6 de Recherches Techniques et SS&D sealed source & device Industrielles (France) SSD system specification document S 118

1 l

x e

NHC COL LECTION OF ABBHEVtATIONS SSDR Sealed Source and Device SSR seal steam regulator Nationwide Registry secondary system relief SSE saie-shutdown earthquake separate superheater reactor SSEB Southern States Energy Board site suitability report South of Scotland Electricity Board site suitability review SSEI Safety System Engineering specification status report In5Pection

. SSRAP Senior Seismic Review and Advisory SSER site safety evaluation repoit Panel supplemental safety evaluation report SSRCR suggested State regulations for the supplement to safety evaluation control of radiation report SSRM safety system readiness monitor SSES Susquehanna Steam Electric Station SSRT slow strain rate test SSF safe-shutdown facility SSS safe-shutdown system safety system, failure (NRC secondary sampling system performance indicator) sensitized stainless steel service storage facility shield and seismic support standby shutdown facility

. shift support supervisor SSFI safety systems functional inspection special safeguards study SSI safe-shutdown impoundment special safety safeguard soil-stmeture interaction standby shutdown system steady-state irradiation

. SSST site suitability source term SSK Strahlenschutzkommission (Germany) SST secondary surge tank SSLC siting source term safetylrelated contro system logic and station service transformer SSLPS solid-state logic protection system SStr steady-state / transient SSMRP seismic safety margins research SSTP Super SARA Test Program prograrn SSTR solid-state track recorder SSNM strategic special nuclear material SSW salt service water SSNPP small-size nuclear power plant standby service water SSO System Security Officer SSWP station service water pump SSOMI safety s,ystems outage modification SSWS standby service water system inspection station service water system SSORA security system operational recording and analysis / analyses ST site team SSP sodium sampling package source term l

staff site position special test I static sodium pot speed transmitter SSPB Swedish State Power Board STA Science and Technology Agency SSPC Steel Structure Painting Council N"E"") .

. shift technical advisor SSPI safety system performance indicator STAR Sandia National Laboratories SSPM safety system performance monitor 1 Transient Axial Relocation l SSPS solid-state protection system shield test air reactor l SSPWR small-size pressurized-water reactor space thermionic auxiliary reactor SSQE safety system quality evaluation STC sound transmission coefficient j 119 1

I

NRC COLLECTION OF. ABBREVIATIONS -

STCL source-term control loop SU/SD startup and shutdown .

STCP source-term code package SUT startup transformer (

l STE shield test experiment SV safety valve i shift technical engineer Sv sievert special test exception solenoid valve system test engineer stop valve ST&E security test and evaluation SVA single-valve first-actuation STEC South Texas Electric Cooperative, SVBC simulated void box capsule Inc. SVHHC St. Vincent Hospital and Health STEP safety test engineering program Center j source-term experiments project SW service water STF safety test facility Struthers Wells Corp.

shield test facility S&W Stone and Webster Engineering shielded test facility Corp.

STH simplified time history SWA startup work authorization STI special team inspection SWAT subjective workload assessment techmque surveillance test interval SWBP sidewall bearing pressure STIF short-term irradiation facility

. SWBS solid waste barrel storage STIR shield test and irradiation reactor

. SWC solid waste cask special technical issue report surge withstand capability STL site team leader SWCP secondary water chemistry program STP short-temi program SWCS salt water cooling system shutdown transfer panel SWDS steam and water dump system South Texas Project

. SWEC Stone and Webster Engineering special technical publication Corp.

staff technical position SWESSAR Stone and Webster Standard Safety standard temperature and pressure Analysis Report surveillance test procedure SWET simulated water entry test system test procedure SWGR switchgear STPF shield test pool facility SWGTS steam and waste gas treatment STPM simulated thermal power monitor system STR submarine thermal reactor SWIS service water intake structure STRESS stmetural engineering system solver SWISS sustained water interactions with stainless steel STRIDE standard reactor island design

. SWM Serber-Wilson method STS Standard Technical Specification SWMS solid waste management system STV small test vessel SWO stop-work order S/U startup SWP service water pump SUFWS startup feedwater system

• • E SUNY State University of New York solid waste process."E ing SUPO super power

. special work permit SUPS stat.ic uninterruptible power supply SWPP Southwest Power Pool SUR startup rate SWPS solid waste processing system SUS startup system SWR service water reservoir 120

NRC COLLECTION OF sodium-water reaction SWU separate work unit steam / water reservoir separative work unit submarine water reactor SX solvent extraction swr 1 Southwest Research Institute SXF solvent extraction feed SWRPRS sodium-water reaction pressure relief SYCA Syndicat d' Etude des Centra s subsystem Atomiques (Belgium)

SWS service water system SYRFA Soci6t6 de Systame Frangaise pour solid waste system les R6acteurs Avanc6es (France)

SWSR solid waste shipping room SZW Ministry of Social Affairs and Employment (Netherlands)

SWTS secondary waste treatment system l

l

[

l 121 S

[

NRC COLLECTION OF ARHH[?VIA I M S ..

TA Technical Associates TBEA training benefits and employee transfer aisle assistance T&A time and attendance TBESI turbine building exhaust system isolation TAAG technical assessment and advisory group TBM tunnel-boring machine TAC task action commitment TBP tributyl phosphate technical assignment control TBS turbine bypass system technical assistance contract TBSCCW turbine building secondary closed

. coolmg water TACF temporary alteration control forni TBSW turbine building service water TACS techmcal assignment control system TBV turbine block valve test assembly conditioning station turbine building ventilation TADOT trip actuating device operational test TBYMS Technical Bases for Yucca Mountain TAEC Thailand Atomic Energy Standards

"* " * *I "

TC temperature controller TAF top of active fuel g

,7 TAG techmcal advisory group T/C thermocouple test assembly grapple TCA thermal critical assembly TAIC Tokyo Atomic Industrial Consonium .

TCC Transducer Controls Corporation TAL transporter air lock TCCC time current characteristic curve TAML Taunton Mumcipal Lighting Plant TC/LD thermocouple / lead detector echnical assistance management TCM technical committee meeting TAP task action plan TCP/IP transmission control

. protocol /Internet protocol test analysis package TCS telephone conference summary thermal analyzer prograrn temporary conditioning station TAPD test and analysis program description turbine control system TAPM technical assistance project manager TCV temperature control valve TAPMG technical assistance prograrn management group turbine control valve TAPSS technical assistance programs TD theoretical density support system time delay TAR technical assistance request transfer dolly test analysis report turbine driven TARGET thermal advanc,ed gas-cooled reactor TDAFP turbine-driven auxiliary feed pump exploiting thorium TDAFW turbine-driven auxiliary feedwater TASC Technical Activity Steering TDAFWP turbine-driven auxiliary feedwater Committee pump TAUF test assembly unloading fixture TDC thermal diffusion coefficient TAVS turbine area ventilation system TDCR test deficiency change request TAWC Tennessee-American Water Co. TDD test design description TB total body .

TDEFWP turbine-driven emergency feedwater turbine building pump TB&A Theodore Barry and Associates TDF task deletion form TBCCW turbine building closed cooling water thermal design flow TBD to be determined TDH Texas Department of Health 123

NHC COL L E CTION OF ABBREVIATIONS total developed head TFANP Task Force Against Nuclear total dynamic head Pollution Transamerica Delaval, Inc. TFC thermal fatigue crack TDI turbine disk integrity TFE thermionic fuel element TDIOG Transamerica DeLaval, Inc., Owners thin film evaporator Group TFM Treasury Financial Manual TDM time division multiplex TFS turbine first stage TDMC Technical Data Management Center TFTR tokamak fusion test reactor (Oak Ridge National Laboratory) TG turbine generator TDN technology development need T/G turbine generator TDP turbine-driven pump TGB turbine generator building TDR technical data repoit TGEP turbine generator emergency power test deficiency report TGIS toxic gas isolation system time domain reflectometry TGLM task group lung model

TDS time delay switch TGS turbine generator system total dissolved solids TGSCC TE temperature element transkranular crack ng stress-corrosion test exception TGSS turbine gland sealing system thermal expansion TGV turbine governor valve transient event T/H thermal and hydraulic T/E thermoelectric THCS temperature of hot-channel sodium TEAR training evaluation audit repon THD total harmonic distortion TEC Technology for Energy Corp. THERP technique for human error rate total estimated cost prediction TECHNIC- THL top of heated length ATOME Soci6t6 Technique pour l'Energie THM time history model Atomique (France) THPO Tribal Historic Preservation Officer TECO Toledo Edison Company THTF thermal hydraulic test facility TECRO Taipei Economic and Cultural THTR thorium high-temperature reactor Representative Office (Taiwan) TI temperature indicator TEDE total effective dose equivalent

) TEFC totally enclosed fan cooled temporary instruction test instruction TEG thermoelectric generator transport index TEM transmission electron microscope TIA task interface agreement TEMA Tubular Exchanger Manufacturers TIBB Tecnomasio Italiano Brown Boveri, Association spa (Italy)

TEMAC Top Event Matrix Analysis Code TIC Technical Information Center TENR technologically enhanced naturally temperature-indicating controller TENRAP tec no o scally enhanced naturally techm."##' ."

cal report designation for the radioactive product TEP Tyrone Energy Park ^ ' " " "#'EY ""***'"

TER technical evaluation report I '"' . ". #8'."I#

TIF task imtiation force techn.ical exchange report . .. .

TES Teledyne Engineering Services 124

Niu3 J)1Ii( l h >N I AHHid VIA TIONS TIG tungsten inert gas nuclear engineering TIP tactical improvement package TNP Trojan Nuclear Plant transient in-core probe TNPG The Nuclear Power Group (United traveling in-core probe Kingdom) traversing in-core probe TNT trinitrotoluene TIRGAI.EX Technical Integration Review Group TOED Toledo Edison Co.

for Aging and Life Extension TOL temporary operating license TIS temperature-indicating switch thermal overload TL task leader TOP thermal overload protection test load transient overpower truck lock TOPO trioctylphosphine oxide TLA thin layer activation TOPR Taiwan Open-Pool Reactor TLAA time-limited aging analysis TOS torque overload switch TLD thermoluminescence dosimeter TOSS transient and/or steady state TLEC Texas-Louisiana Electric TP technical position Cooperative test pressure TLLM temperature and liquid level monitor test procedure TLO turbine lube oil test program TLOFW total loss of feedwater TPA total-system performance assessment TLOS turbine lube oil system TP-BAR tritium-producing bumable absorber TLOST turbine lube oil storage tank rod TLP top load pad TPC Taiwan Power Company top load plane TPCDF total plant core damage frequency TLTA two-loop test apparatus TPD test procedure deviation TLTM third-level thermal margin TPF total peaking factor TLV threshhold limit value TPFL two-phase flow loop TLX task load index TPM thermal power monitor TM technical manual TPPEP Turkey Point Performance temperature monitor Enforcement Program TMBDB thermal margin beyond design basis TPS Turkey Point Station TMD transient mass distribution TPSS turbine plant sampling system TMH trolley-mounted hoist TFTF two-phase test facility TMI Three Mile Island TQM total quality management TMI-l Three Mile Island Unit 1 T&QP Training and Qualification Plan TMI-2 Three Mile Island Unit 2 TR technical review TMIA Three Mile Island Alert,Inc. temperature recorder TMI-AP Three Mile Island Action Plan topical report TMINS Three Mile Island Nuclear Station tritium recovery TMIPO Three Mile Island Program Office Turkish Reactor TM/LP thermal margin / low pressure TRA tubular reactor assembly TMPA Texas Municipal Power Agency TRAP trip reduction and assessment TMR Teledyne Materials Research TRB est rev ew b ard TNA thermal neutron activation TRC technical review committee TNE TUEC (Texas Utilities Electric Co.)

125

1 NHC COLLECTlON OF ABBREVIATIONS ,

The Radiochemical Centre (United TSIR technical specifications Kingdom) interpretation report TRE total rare earths TSM temporary station modification TREAT transient reactor test TSMD technical services mechanical drafting TRIA temperature-removable instrument assembly TSMDA test section meltdown accident TRIGA training reactor and isotopes TSO time-sharing option production, General Atomics TSOP Technical Specifications TRIM targeted regulatory improvement Optimization Program TRIP transient response implementing TSP Telecommunications Service Priority procedure trisodium phosphate TRM Technical Requirements Manual tube support plate TRR test and research reactor TSPA-VA total system perfomiance Thailand Research Reactor assessment-viability assessment TRRT test results review team TSPM technical surveillance thermal reactor safety countermeasure TRS TSPS tube support plate sleeve TRT technical review team TSR thermal shock rig TRTR training, research, and test reactor total stress range TRU transuranic tower shielding reactor transuranium TSRG Technical Specifications Review TRUWIP Transuranic Waste Immobilization Group Program TSSC Toxic Substances Strategy TRX two-region physics critical Committee experiment TSV turbine stop ve2ve TS technical specification test specification TSW turbine service water treatment system TT temperature transmitter TSA tube support assembly test temperature turbine trip TSABC technical services as-built coordinator TTA thenoyltrifluoroacetone TSAR topical safety analysis report TTBT Threshold Test Ban Treaty TSC technical support center TTC Technical Training Center test shipping cask test transfer cask TSCA Toxic Substances Control Act Transportation Technology Center TSCC Technical Support Coordinating TTE thermal transient equipment Committee TTF transient time flowmeter TSCF task schedule change form TTFM transit time flowmeter TSDR technical services design review TTHE thermal transient histogram TSF tower shield facility equivalent tower shielding facility TTP technolagy transfer program TSG technical support guidelines test tratisfer port TSH temperature switch, high TTQAP teletherapy treatment quality TSI Thermal Sciences Inc. assurr.nce program TSIP Technical Specifications TTR the: mal test reactor improvement Program time to repair T 126 f

__ . )

NRC COLLfCTION OF ABBREVIATIONS l

TTS telecommunications tracking system TV&D test, vent, and drain time-temperature sensitization TVG time-variable gain TTV tenth thickness value TVO Teollisuuden Voima Osakeyhtio TTWB turbine trip with bypass (Finland)

TTY teletypewriter TVR Tennessee Valley region TU Texas Utilities Co. TWC Texas Water Commission TUEC Texas Utilities Electric Co. TWCA Teledyne Wah Chang Albany TUFCDF Thorium-Uranium Fuel Cycle TWFN Two White Flint North Development Facility TWG test working group TUS Texas Utilities Services Inc. TWRS tank waste remediation system TUSI Texas t';ilities Services Inc. TWX teletypewriter exchange service

! TUV Technischer Oberwachungsverein, TZM tantalun , zirconium, molybdenum

! e.V. (Germany) l TVA Tennessee Valley Authority l

l l

l l

I l

127

1 NHC COLLECTION OF ABBREVIATIONS 1

i 1

UA unsafe actioa UHTREX ultrahigh temperature reactor 4 UAP uranyl ammonium phosphate experiment UAT unit auxiliary transformer UHV ultrahigh voltage i UBAEC Union of Burma Atomic Energy UI United Illuminating Co.

Centre UIS upper internals structure UBC Uniform Building Code UlSJM upper internals structure jacking UCL upper control limit mechanism UCLA University of California, Los U.K. United Kingdom Angeles UKAEA United Kingdom Atomic Energy UCLR University of Califomia, Lawrence Authority Radiation Laboratory UKNR University of Kansas Nuclear UCNI unclassified controlled nuclear Reactor information UL Underwriters I glaboratories, Inc.

UCO uranium oxicarbide fuel upper level UCS Union of Concerned Scientists ULD unit load demand UDI Utility Data Institute UMRR University of Missouri Research UDRPS ultrasonic data recording and Reactor processing system UMTR University of Maryland Teaching UDS ultimate damage state Reactor UDT underwater demolition team UMTRA uranium mill tailings remedial action UE Union Electric Co. UMTRAP Uranium Mill Tailings Remedial UEC United Engineers and Constructors, UMTRCA U niu hii ailings Radiation ntml Act UE&C United Engineers and Constructors, Inc. UN uranyl nitrate

. UEF upper end fitting UNC United Nuclear Corp.

UEL upper electrical limit UND uranyl nitrate distillate UF urea-formaldehyde UNE Union Electric Co.

UFCS uranium hexafluoride chemical feed UNH uranyl nitrate hexahydrate station UNHC uranyl nitrate hexahydrate cell UFFC ultrasonic ferroelectrics and UNI United Nuclear Industries, Inc.

frequency control UNIPEDE International Union of Producers and UFL upper flammability limit Distributors of Electrical Energy UFM unified fracture mechanics UNIT United Illuminating Co.

UFR uranium hexafluoride recovery room UNPOC Utility Nuclear Power Oversight UFSAR updated final safety analysis report Committee UFTR University of Florida Teaching UNSCEAR United Nations Scientific Committee Reactor n the Effects of Atomic Radiation UGS upper group stop UNWMG Utility Nuclear Waste Management Group upper guide structure UO unit operator UHF ultrahigh frequency UOGF uranium off-gas filter UHI upper-head injection

. UOP unit operating procedure UHN uranyl hexahydrate mtrate UOR upper oil reservoir UHS ultimate heat aink UPI upper plenum injection ultrahigh speed UPL uranium product loadout l 129

NHC COL.LECTION OF ABBREVIATIONS Utah Power & Light Co. USEC U.S. Enrichment Corporation UPM universal permissive module USGS U.S. Geological Survey UPPS ultimate plant protection system USI unresolved safety issue UPR uranium production reactor USNDC U.S. Nuclear Data Committee UPS uninterrupted power supply USNRC U.S. Nuclear Regulatory utiinterruptible power supply Commission uninterruptible power system USP upper sequential permissive UPTF Upper Plenum Test Facility USPHS U.S. Public Health Service (Germany) USQ unreviewed safety question UlrrPS upper plenum thermal protection USQD unresolved, safety question structure determination UR user requirement USRP updated standard review plan URA Universities Research Association UST United States Testing Co.

uranium recycle acid USWB U.S. Weather Bureau URAEP University of Rochester Atomic UT ultrasonic test Energy Project ultrasonic testing URC ultrasonic resin cleaner universal time URD underground residential distribution U/Th uranium-to-thorium ratio Utility Requirements Document UT/ISI ultrasonic inservice inspection URFO uranium recovery field office UTM universal transverse Mercator uranium recovery field officer UTP upper tie plate URG unit review group UTR university training reactor URI unresolved item UTRR University of Teheran Research URL Uniform Resource Locator Reactor URS ultimate rupture strength UTS upper tube sheet URTC Ukrainian Radiation Training Center UU tSimate user USA upper-shelf analysis / analyses UUCP Unix-to-Unix copy program USAEC U.S. Atomic Energy Commission UV undervoltage USAR updated safety analysis report UVAR University of Virginia Reactor USAS United States of Amerin standards UVR undervoltage relay USASI United States of America Standards University of Virginia Reactor Institute UVSC uranium ventilation senibber cell USBR U.S. Bureau of Reclamation UVTA undervoltage trip attachment U.S.C. U.S. Code UWRR University of Wyoming Research USCEA U.S. Council for Energy Awareness Reactor (now NEI) UWTR University of Washington Training USCG U.S. Coast Guard Reactor Utility Safety Classification Group UXO unexploded ordnance USC&GS U.S. Coast and Geodetic Survey UZ unsaturated zone USDA U.S. Department of Agnculture USE upper-shelf energy 130

, NHC COkLEC1 ION OF ABBHEVIATIOy v% volume percent VHES Vitro Hanford Engineering Service VA viability assessment VHF very high frequency vital area VHP vessel head penetration Vac volts altemating current VHPT variable high-power trip VAK Versuchsatomkraftwerk Kahl VHTR very high temperature reactor (Germany) VI vent isolation VAN value-added network VIA value-impact analysis / analyses VANS vehicular alert and notification VIMS Virginia Institute of Marine Science

'Y'I'*

VIRG Vessel Integrity Review Group VAPORE valve and pressure operating related .

experiments VISA vessel integrity simulation analysis VAR volt amperes reactive VIV variable inlet vane VAT Vulnerability Assessment Team VNSP vacant nozzle shield plug VBMR ventilation barrier machine room VOG vessel off-gas VBWR Vallecitos Boiling Water Reactor VOT valve opening time VC vaporizer concentrate VOTA vibration open test assembly VCC ventilated concrete cask VOTES valve operation test and evaluation VCD vendor-certified drawing VCLF VP i W. Vo# A PM - Vo@

vertical cask-lifting fixture Electric Generating Plant VCM vinyl chloride monomer vent-clearing pressure VCT volume control tank VPI valve position indication VDA video graphics adapter vapor phase inhibitor VDC ventilation duct chase VQAR vendor quality assurance Vdc volts dire;t current representative VDEW Vereinigung Deutscher VR volume reduction Elektrizitutswerke (Germany) VRS vacuum relief system VD/OS vacuum distillation / overflow sampler volume reduction system VDS vacuum defueling system VS vapor suppression VDTUV Vereinigung der Technischen vendor specific Oberwachun (Germany) gs-Vereine, e.V. vessel system VDU video display unit virtual storage VE Vitro Engineering VSC ventilated storage cask VEC vertical electrical chase VSE vessel steam explosion VEPCO Virginia Electric and Power Co. VSLO valve stem leakoff VESIAC Vela Seismic Information and VSNS Virgil C. Summer Nuclear Station Analysis Center VSR Vallecitos Superheat Reactor VESR Vallecitos Experimental Superheat vertical slice review Reactor VSS vessel support subsystem VF vaporizer feed VST valve set point tolerance VFD variable frequency drive VT vehicular technology VFTP ventilation filter testing program VTC video teleconferencing VGCH vent gas collection header VTEC Vermont Electric Cooperative, Inc.

VGES variable geometry experimental VTEP Vermont Electric Power Co., Inc.

system .

VTO vital to operations 131

g' NHC COLLECTION OF ABBREVI,ATIONS ,

VTT Valtion Teknillinen Tutkimuskeskus VWI visual weld inspection (Finland) v sual weld inspector V&V verification and validation VWO valve wide open VWAC visual weld acceptance VYGS Vermont Yankee Generating Station criterion / criteria VemYa MuPpu VYNP VWE vanadium wire equilibration Corp.

VWED vanadium wire equilibration device 132

NHC COLLECTION OF ABBREVIATIONS l

W Westinghouse Electric Corp. WEC Westinghouse Electric Corporation w% weight percent Wolverine Electric Cooperative WAGR Windscale Advanced Gas-Cooled WECAN Westinghouse Electric computer Reactor (United Kingdom) analysis / analyses E AL Westinghouse-Astronuclear WECST waste evaporator condensate storage Laboratory tank V/AMS Work Action Management System WECT waste evaporator condensate tank WAN wide-area network WEP water-extended polyester WANO World Association of Nuclear weld evaluation project Operators WEPC Wisconsin Electric Power Co.

WAPA wet annular poison assembly WEPCO Nisconsin Electric Power Co.

WAPD Westinghouse Atomic Power WESF waste encapsulation storage facility

-WESI S stems WAPPA waste package performance Westinghouse Energky fVNI International (former assessment Nuclear)

W-ARD Westi,nghouse Advanced Reactors WESPAC Westchester People's Action Division Coalition WASI workforce analysis, systems, and WFMC welding filler material control WFML weld filler metal log WB whole body WG waste gas WBEP . Watts Bar Engineering Project

• #'E""E" WBNP Watts Bar Nuclear Plant WBNPP Watts Bar Nuclear Performance Plan WGDS

• • 1. E*$*E'#**I waste gas disposal system WBNS water-boiler neutron source WBPP *** # E * ' Y ""

Watts Bar Program Plan

• containment and isolation WBP'r Watts Bar Program Team trategy WBS work breakdown structure WGS waste gas system WC weather condition Waterford Generating Station WCA whole-core accident WH weekly highlight WCAP Westin house Commercial Atomic WHC Westinghouse Hanford Company

• " '#E

-WHEDL Westinghouse-Hanford WCF waste-calcinating facility Environmental Development WCFO Walnut Creek Field Office Laboratory WCGS Wolf Creek Generating Station WHO World Health Organization WCL

_ Westinghouse Canada Limited WHT waste holdup tank WCNOC Wolf Creek Nuclear Operating Corp. WIEB Western Interstate Energy Board WCS waste compaction station WlEP Wisconsin Electric Power Co.

WD waste disposal WINB Western Interstate Nuclear Board withdrawn WIPP waste isolation pilot plant WDC waste disposal cask WIR weekly information report weld data card WISE World Information Service on WDS waste disposal system Energy WDT water distribution test WISHA Washington Industrial Safety and Health Act WDTRS Westinghouse deyelop, ment test requirement specification WISP workload information and schedulin8 program 133

NI{C (:OllpC TION OF AltHREVIATIONS WITS Washington Interagency WPSC Wisconsin Public Service Corp.

Telecommunications System water quality certification WQC work item tracking system WR Whiteshell Reactor (Canada)

WLM working-level month wide range WMEC Western Massachusetts Electric Co. work request WMM wall-mounted manipulator WRAP water reactor analysis program WMNS William B. McGuire Nuclear Station WRC Welding Research Council WMO World Meteorological Organization WRGM wide-range gas monitor WMPC Wisconsin Michigan Power Co. WRM wide-range monitor WMS waste management system working reference material work management system W-RM Westinghouse-Reactor WMT waste management tank Manufacturer W

_NES Westinghouse nuclear energy system WRNMS wide-range neutron monitoring WNFM World Nuclear Fuel Market system WNP Washington Nuclear Project WRRR Walter Reed Research Reactor WNT waste neutralization tank WRSR water reactor safety research waste neutralizing tank WRT with respect to WNYNRC Western New York Nuclear WS warm shop Research Center WSA work situation approach WO work order WSCC Western Systems Coordinating

-WOFA Westinghouse optimized fuel Council assembly WSCS was,te solidification and compaction WOG Westinghouse Owners Group station WOR weld overlay repair WSD working stress design WP warm pipe WSF waste shipping facility welding procedure WSMF welded-steel moment-resisting frame welding project WSUOPR Washington State University Open-Pool Reactor work package g ;g g; ,

work procedure WPB WTF waste treatment facility waste processing building WTP water treatment plant WPBCWS waste processmg building chilled water system WTR Westinghouse Test Reactor WPC Werner and Pfleiderer Corp. WVN water vapor nitrogen WPCB Waste Processing Control Board WVOG wet vessel off-p WPLC Wisconsin Power & Light Co. WW well water WPPSS Washington Public Power Supply WWPC Washington Water Power Co.

System WWS waste water system WPQR welding procedure qualification well water system record WWTF waste water treatment facility WPS warm prestressing WWW World Wide Web waste processing system weldinF Procedure specification 134

NHC COLLECTION OF ABBREVIATIONS -

XLPE cross-linked polyethylene XRF explosion release factor XR export reactor x-ray fluorescence i

135

YAE Yankee Atomic Electric Co. YNHH Yale-New Haven Hospital YAEC Yankee Atomic Electric Co. YNPS Yankee Nuclear Power Station l YATA York Area Transportation Authority YCNP Yellow Creek Nuclear Plant 137

NHC COL.l f C TlON f AHHHf VIAll( >N:,

ZEA zero energy assembly ZIP zone improvement plan ZEEP Zero Energy Experimental Pile ZNP Zion Nuclear Plant (Canada) ZPA zero period acceleration ZEPHYR zero energy fast reactor ZPMB zero power mode bypass ZES zero energy system ZPPR zero power plutonium reactor ZETA Zero Energy Thermonuclear ZPR zero power reactor Apparatus (United Kmgdom)

ZPRF zero power reactor facility zero energy thermonuclear assembly ZPSS Zion Probabilistic Safety Study ZETR Zero Energy Thermal Reactor (United Kingdom) ZTO zero time outage ZEUS Zero Energy Uranium System ZWOK zirconium-water oxidation kinetics (United Kingdom)

ZGS zero gradient synchrotron 139

NAC FORM 335 U S. NUCLEAR REGULATORY COMMIStsON 1. REPOR1 NUMBER (2-09) (As.igried by NRC Add Vbl.. Supp.. Rev.,

NHCM 1102, and Addendum Nurnbers. # any) 32m. 32o2 BIBUOGRAPHIC DATA SHEET (s  %,ruaion. on u t.ver ) NUREG-0544, Rev. 4 2 TITLE AND SUBTi1LE 3 DATE REPORI PUBLISHED j NRC Collection of Abbreviations l l July 1998

4. FIN OR OhANT NUMBER 3 AtJTrivhv.>s 0. TYPE OF REPOH1 Compiler: Technical Publications Section ,, ,,,,gg goy,,,, (,,,,,,,, g,,,,,

8. Pt RFORMING nHGANilAllON - NAME AND ADDRESS (If NRC. provide Dnnsson, Office or Region, U.S. Nuclear Regulatory Comtru.sson, and massing address. W cortracsor, provide name and mailing address )

Information Management Division Office of the Chief Information Officer U.S. Nuclear Regulatory Commission Washington, DC 20555-(XX)1 9 SPONSOHANu ORGAN!ZATION - NAME AND ADDRESS (if NRC. type

• dame as above", # oontrador, provide NRC Division, Office or Region, U S. Nuc6 ear Regulatory Oornmissson, and maihng addrees )

Same as 8 above.

10. SUPPLEMt;NTARY NOTES

11. ABSTRACT (200 words or less)

This collection of abbreviations in common use in the nuclear industry and regulatory community was compiled from Nuclear Regulatory Commission (NRC) and nuclear industry sources. It was published to assist agency authors, readers, and stakeholder in identifying abbreviations for the numerous organizational, scientific, and engineering terms that appear in NRC printed and electronic information. The compilation is descriptive rather than prescriptive. No one abbreviation is recommended to the exclusion of another because the same abbreviation may with equal validity apply to two or more terms.

in .<rY wCRosrsCReTORS noi ord. or on,a ine, un a i.i r aren.r. .n iocating u r.po,i) is ^=tABiuTv STATsueNT Unlimited

. . 14 SECURITYCLASSIFICATION abbreviations g,,

acronyms initialisms Unclassified

(""8 R8Po")

nuclear terms nuclear phrases Unclassified nuclear facilities S NUMBER OHAGES nuclear organizations YPRICE NRC FORM 335 (2-89)

On recycled paper Federal Recycling Program

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