Comments
Description
Transcript
ACRONYMS APPENDIX C.
APPENDIX C. ACRONYMS ABS ABWR AC ac ACI ACLCO ACM ACRS ACSR ADAMS ADG ADS AEA AFEM AFIP AFT AFU AHS AHU AISC AISI AL ALARA ALT ALWR AMS ANI ANS ANSI AOC AOE AOF AOO AOP AOSC AOV AP APE APLHGR APRM ARI ARM ARMS ARP ARS ART ARTNDT auxiliary boiler system Advanced Boiling Water Reactor availability control alternating current American Concrete Institute availability control limiting condition for operation availability controls manual Advisory Committee on Reactor Safeguards availability control surveillance requirement Agencywide Documents Access and Management System ancillary diesel generator automatic depressurization system Atomic Energy Act acoustic finite element model automatic fixed in-core probe as found tolerance air filtration unit auxiliary heat sink air-handling unit American Institute of Steel Construction American Iron and Steel Institute analytical limit as low as reasonably achievable as-left tolerance Advanced Light Water Reactor alarm management system authorized nuclear inspector American Nuclear Society American National Standards Institute present value of averted offsite property damage costs ($) present value of averted occupational exposure costs ($) allocation of functions anticipated operational occurrence abnormal operating procedure present value of averted onsite costs ($) air operated valve annulus pressurization present value of averted public exposure ($) Average Planar Linear Heat Generation Rate average power range monitor alternate rod insertion area radiation monitor area radiation monitoring system annunciator response procedure amplified response spectra adjusted reference temperature adjusted reference temperature nil ductility temperature C-1 ASA ASCE ASD ASHRAE ASME AST ASTM ATIP ATLM ATWS AV AWS B&PV B&W BDBA BDLB BISI BL BMP BNL BOC BOL BOP BOPCWS BPU BPVC BRR BTP BTU BV-1 BVZ BWR BWROG BWRVIP C/C C-I C-II CAM CAP CAR CARS CAS CASS CB CBGAVS CBVS CC-II CCF CCFP Acoustical Society of America American Society of Civil Engineers adjustable speed drive American Society of Heating Refrigerating and Air-Conditioning Engineers American Society of Mechanical Engineers alternative source term American Society of Testing and Materials automated traversing incore probe automated thermal limit monitor anticipated transient without scram allowable values American Welding Society Boiler and Pressure Vessel Babcock & Wilcox beyond design basis accident bottom drainline break bypassed or inoperable status indication bulletin basemat melt penetration Brookhaven National Laboratory beginning of cycle beginning of life balance of plant balance-of-plant chilled water subsystem bypass unit Boiler and Pressure Vessel Code baseline review record branch technical position British thermal unit Beaver Valley Unit 1 Black & Veatch Zachry boiling water reactor Boiling-Water Reactor Owners Group Boiling-Water Reactor Vessel and Internals Project cooling and cleanup Category I Category II continuous air monitor corrective action program corrective action request condenser air removal system central alarm station cast austenitic stainless steel control building control building general area heating ventilation and air conditioning subsystem control building heating ventilation and air conditioning system Capability Category 2 common-cause failure conditional containment failure probability C-2 CCI CCID CCIW CD CDA CDF CDI CDM CDS CET CEUS CF CFD CFP CFR CFS CFT CH CHF CHPB CHR CHUG CI CIB2 CIM CIRC CIS CISE CIV CJ CLAVS CLD CMAA CMF CMS CO COE COL COLA COLP COLR CONAVS COTS CPG CPI CPS core-concrete interaction core-concrete interactions-dry core-concrete interactions-wet confirmation density control, display, and alarm core damage frequency conceptual design information certified design material clean drain (non-radioactive) system containment event tree Central and Eastern United States chemistry factor computational fluid dynamics containment failure probability Code of Federal Regulations condensate and feedwater system channel functional test chugging critical heat flux Health Physics Branch, Division of Construction Inspection and Operational Programs containment heat removal an oscillatory dynamic loading confirmatory item Component Integrity, Performance and Testing Branch 2, Division of Engineering communication interface module circulating water system containment inerting system Ciencias de la Seguridas test facility containment isolation valve Chapman-Jouguet clean area heating, ventilation, and air conditioning subsystem containment load definition Crane Manufacturer's Association of America common mode failure containment monitoring system condensation oscillation cost of enhancement ($) combined license combined license application Operator Licensing and Human Performance Branch, Division of Construction Inspection and Operational Programs Core Operating Limits Report contaminated area ventilation system commercial off the shelf containment performance goal containment performance improvement condensate purification system C-3 CQVB Quality and Vendor Branch 2, Division of Construction Inspection and Operational Programs CR control room CRACS control room air conditioning systems CRB control rod block CRD control rod drive CRDA control rod drop accident CRDS control rod drive system CREFU control room emergency filtration unit CRGT control rod guide tube CRHA control room habitability area CRHAVS control room habitability area ventilation system CRHS control room habitability systems CS&TS condensate storage and transfer system CSDRS certified seismic design response spectra CSF critical safety function CSGB Steam Generator Tube Integrity and Chemical Engineering Branch, Division of Component Integrity CSI cesium iodide CST condensate storage tank CUF cumulative usage factor CV check valve CWS chilled water system D/Q deposition factors D-RAP design reliability assurance program D&S detect and suppress DAC design acceptance criteria DBA design basis accident design-basis event DBE DBT design basis threat DC design certification dc direct current design certification application DCA DCD design control document DCH direct containment heating DCIS distributed control and information system drywell cooling system DCS DDT deflagration-to-detonation transition DEG double-ended guillotine DF decontamination factor DG diesel generator DGCAIES diesel generator combustion air intake and exhaust system DGVS diesel generators heating, ventilation, and air conditioning subsystem DHR decay heat removal DICS diverse instrumentation and controls systems DL dead load DLF dynamic load factor DMW dissimilar metal welds DOE Department of Energy DOF degree of freedom C-4 DOI DOT DPL DPS DPV DQR DR DRF DSS DTLM DTM DW E-DCIS EAB EAC EB EBAS EBVS ECC ECCS EDG EEB EER EERVS EFDS EFPD EFPY EFU EGC EGCB EL EMB EMC EMI ENS EOF EOL EOP EP EPA EPG EPRI EQ EQD ERDS ERF ERICP ERIP ESBWR dedicated operator interface Department of Transportation design pressure limit diverse protection system depressurization valve dynamic qualification report decay ratio design record file detect and suppress solution digital trip logic module digital trip module drywell essential distributed control and information system exclusion area boundary emergency alternating current electrical building emergency bottled air breathing system electrical building heating, ventilation, and air conditioning system emergency core cooling emergency core cooling system emergency diesel generator Electrical Engineering Branch, Division of Engineering electric and electronic rooms electric and electronic rooms heating, ventilation, and air conditioning subsystem equipment and floor drain system effective full power day effective full power year emergency filter unit Exelon Generation Company Geoscience and Civil Engineering Branch, Division of Engineering elevation Engineering Mechanics Branch electromagnetic compatibility electromagnetic interference Emergency Notification System emergency operations facility end of life emergency operating procedure emergency planning Environmental Protection Agency emergency procedure guideline Electric Power Research Institute environmental qualification environmental qualification document Emergency Response Data System emergency response facility emergency rod insertion control panel emergency rod insertion panel economic simplified boiling water reactor C-5 ESF ESP EVE F F/D FA FAC FAPCS FAT FATT FB FBFPVS FBGAVS FBVS FCI FCISL FCM FCU FDA FE FEA FEM FEMA FHA FIRS FIV FM FMCRD FMEA FOAK FOAKE FOSTS FPE FPM FPP FPRA FPS FPWS FR FRA FRS FS FSAR FSER FSR FSWYD FTDC FTS FV FW engineered safety feature early site permit ex-vessel steam explosions Fahrenheit filter/demineralizer function allocation flow-accelerated corrosion fuel and auxiliary pools cooling system factory acceptance tests fracture appearance transition temperatures fuel building fuel building fuel pool area heating, ventilation, and air conditioning subsystem fuel building general area heating, ventilation, and air conditioning subsystem fuel building heating, ventilation, and air conditioning system fuel-coolant interaction fuel cladding integrity safety limit file control module fan cooling unit final design approval finite element finite element analysis finite element model Federal Emergency Management Agency fire hazards analysis foundation input response spectrum flow-induced vibration Factory Mutual fine motion control rod drive failure mode and effects analysis first-of-a-kind first-of-a-kind engineering fuel oil storage and transfer systems fire pump enclosure first principle model fire protection program fire probabilistic risk assessment fire protection system fire protection water system Federal Register functional requirements analysis floor response spectra full-scale final safety analysis report final safety evaluation report fuel storage rack fire in switchyard fault-tolerant digital controller fuel transfer system Fussell-Vesely feedwater C-6 FWCS FWIV FWL FWLB FWRB FWS FWSC FWTCS G GALL GDC GDCS GDCSP GDLB GE GEH GI GIST GL GMAW GMRS GSI GT GTAW GTS GW/MTU GWMS HA HAZ HCLPF HCU HCW HED HELB HELSA HEPA HF HFE HFEITS HIC HMR HP HPCF HPCI HPM HPCME HPNSS HPS HRA HRO feedwater control system feedwater isolation valve feedwater line feedwater line break feedwater runback firewater storage fire water service complex feedwater temperature control system acceleration of gravity generic aging lessons learned general design criterion gravity-driven cooling system gravity-driven cooling system pool gravity-driven cooling system line break General Electric General Electric – Hitachi Nuclear Energy generic issue gravity-driven integrated systems test generic letter gas metal arc welding ground motion response spectrum generic safety issue gamma thermometer gas tungsten arc welding generic technical specification gigawatts/metric ton of uranium gaseous waste management system human action heat-affected zone high confidence of low probability of failure hydraulic control unit high-conductivity waste human engineering discrepancy high-energy line break high-energy line separation analysis high-efficiency particulate air human factors human factors engineering human factors engineering issue tracking system high-integrity containers Hydrometeorological Reports high pressure high pressure core flooder high pressure coolant injection human performance monitoring high pressure core melt ejection high pressure nitrogen gas supply system Health Physics Society human reliability analysis high regulatory oversight C-7 HSI HSS HVAC HWCS I&C I/O IA IAS IASCC IBC IBF IC ICE2 ICEA ICGT ICHT ICLB ICMGT ICMH ICP ICS ICSB ID IE IEC IEEE IESNA IFTS IGSCC IICI ILRT IMCC IN INPO IORV IOT IP IPC IPE IPEEE ISA ISG ISI ISLOCA ISM ISO IST ISV ITA human-system interface high safety significance heating, ventilation, and air conditioning hydrogen water chemistry system instrumentation and control input/output instrument air instrument air system irradiation-assisted stress corrosion cracking International Building Code isolation bypass function isolation condenser Instrumentation, Controls and Electrical Engineering Branch 2, Division of Engineering Insulated Cable Engineers Association incore guide tube isolation condenser heat transfer isolation condenser line break incore monitor guide tube in-core monitor housing independent control platform isolation condenser system Instrumentation and Control Systems Branch, Division of Engineering identification infrequent event International Electrotechnical Commission Institute of Electrical and Electronic Engineers Illuminating Engineering Society of North America inclined fuel transfer system intergranular stress corrosion cracking inadvertent isolation condenser initiation integrated leak rate test induction motor controller cabinet information notice Institute of Nuclear Power Operations inadvertent opening of relief valves infrequent operational transients implementation plan isolation power center individual plant examination individual plant examination of external events Information, Systems, and Automation Society interim staff guidance inservice inspection intersystem loss-of-coolant accident independent support motion International Organization for Standardization inservice testing integrated system validation inspections tests and analyses C-8 ITAAC ITP JCWS KKM KWU L/D l/s LBB LBHS LCO LCS LCW LD&IS LDW LFCV LHGR LIA LLC LLHS LLW LOCA LOFWH LOOP LOPP LP LPCI LPCS LPRM LPZ LRF LRO LRS LRT LSFT LSSS LTR LTSP LVDT LWMS LWR MBTU MCC MCCI MCPR MCR MCRBP MCRP MDRFP MEB MFLPD Inspections, tests, analyses, and acceptance criteria initial test program jacket cooling water system Kashiwazaki Kariwa Kraftwerk Union Aktiengesellschaft length to diameter ratio liters per second leak before-break large-bore hydraulic snubbers limiting condition for operation local control station low conductivity waste leak detection and isolation system lower drywell low flow control valve linear heat generation rate load interpolation algorithm limited liability company light-load handling system low level waste loss-of-coolant accident loss of feedwater heating loss-of-offsite power loss of preferred power low pressure low pressure coolant injection low-pressure core spray local power range monitor low population zone large release frequency low regulatory oversight liquid radwaste system leak rate test logic system function test limiting safety system setting licensing topical report limiting and trip setpoints linear variable differential transformer liquid waste management system light water reactor one million BTU motor control center molten core-coolant interaction maximum critical power ratio main control room main control room back panel main control room panel system motor-driven reactor feed pump modified energy balance maximum fraction of limiting power density C-9 MGL MJ MLHGR MMIS MOD MOV MP MPa MRBM MS MSIS MSIV MSIVF MSIVLCS MSL MSLB MSLI MSR MSS MT MTCS MUX MW MWR MWS N/A N-DCIS N-S NA NB NBS NCIG ND NDE NE-DCIS NEI NEMA NEP NFPA NGI NICWS NMS NOAA NPHS NPP NPS NPSH NRC NRHX NRS multiple Greek letter megajoules maximum linear heat generation rate man-machine interface system motor operated disconnect motor operated valve medium power megapascals multichannel rod block monitor main steam main steam isolation system main steam isolation valve main steam isolation valve closure with flux scram main steam isolation valve leakage control system main steamline main steamline break main steam line isolation moisture separator reheater main steam system magnetic particle main turbine control system multiplexer megawatt metal water reaction makeup water system not applicable nonsafety-related distributed control and information system north-south not acceptable nuclear boiler nuclear boiler system Nuclear Construction Issue Group normal distribution nondestructive examination nonessential distributed control and information system Nuclear Energy Institute National Electrical Manufacturers Association nonexceedance probability National Fire Protection Association new generic issue nuclear island chilled water system neutron monitoring system National Oceanic and Atmospheric Administration normal power heat sink nuclear power plant nominal pipe size net positive suction head Nuclear Regulatory Commission nonregenerative heat exchanger not risk-significant C-10 NS NSAC NSR NSSS NTSP NTSPF NUMARC NWL NWS O&M OBCV OBE OCS ODCM OEM OER OGS OHLHS OIS OLD OLMCPR OLP OLU OPDRV OPRM ORNL OSC P&ID P/T PA PA/PL PABX PAM PAR PARS PAS PASS PBLE PBRS pC PCC PCCS PCD PCF PCP PCT PDA PDM PFRA PG nonseismic Nuclear Safety Analysis Center non-safety-related nuclear steam supply system nominal trip setpoints final nominal trip setpoint Nuclear Utilities Management and Resources Council normal water level National Weather Service operation and maintenance overboard control valve operating-basis earthquake operational condition sampling offsite dose calculation manual original equipment manufacturer operating experience review offgas system overhead heavy-load handling system oxygen injection system output logic device operating limit minimum critical power ratio online procedure output logic unit operation with potential to drain the reactor vessel oscillation power range monitor Oak Ridge National Laboratory operational support center piping and instrumentation diagram pressure/temperature protected area plant page/party-line private automatic branch exchange postaccident monitoring passive autocatalytic recombiner passive autocatalytic recombiner system plant automation system postaccident sampling stations plant-based load evaluation performance-based seismic response spectrum pico coulombs passive containment cooling passive containment cooling system plant configuration database plant computer functions process control program peak cladding temperature piping dynamic analysis project design manual plant-level functional requirements analysis power generation C-11 PGA PH PID PIP PIRT PIV PL PLC PMC PMF PMP PMWP POS POV PPS PRA PRMS PRNM PS PSB PSD PSI PSS PSTF PSW PSWS PT PTLR PUMA PWR Q-DCIS QA QAP QAPD QG QMS R/A RACS RAI RAP RAPI RAT RAW RB RBCC RBV RBVS RC&IS RCBS RCC peak ground acceleration precipitation hardening proportional, integral, derivative plant investment protection phenomena identification and ranking table pressure isolation valve primary local membrane stress programmable logic controller performance monitoring and control probable maximum flood probable maximum precipitation probable maximum winter precipitation plant operational state power-operated valve preferred power supply probabilistic risk assessment process radiation monitoring system power range neutron monitor pool swell Power Systems Branch, Division of Safety Systems power spectra density preservice inspection process sampling system pressure suppression test facility plant service water plant service water system liquid penetrant pressure and temperature limits report Purdue University Meteorological Association pressurized water reactor safety-related distributed control and information system quality assurance quality assurance program quality assurance program description quality group quality management system reliability/availability rod action control subsystem request for additional information reliability assurance program rod action and position information reserve auxiliary transformer risk achievement worth reactor building rod brake controller cabinet reactor building vibration reactor building heating ventilation and air conditioning system rod control and information system refueling cavity bellows seal remote communication cabinet C-12 RCCV RCCW RCCWS RCIC RCPB RCS RCSLD REMP REPAVS RES RETS RFI RFP RG RH RHEB RHR RHX RIP RIS RMS RMU ROAAM RPS RPT RPV RPVSB RRPS RRS RSA RSAC RSB RSPC RSS RSW RT RTD RTIF RTNDT RTNSS RTP RTS RV RVMSP RW RWB RWCR RWCRVS RWCU reinforced concrete containment vessel reactor closed-cooling water reactor component cooling water system reactor core isolation cooling reactor coolant pressure boundary reactor coolant system reactor coolant system leakage detection radiological environmental monitoring program refueling and pool area heating ventilation and air conditioning subsystem Office of Nuclear Regulatory Research radiological effluent technical specification radio frequency interference reactor feed pump regulatory guide relative humidity Hydrological Engineering Branch, Division of Site and Environmental Reviews residual heat removal system regenerative heat exchanger reactor internal pump regulatory issue summary radiation monitoring subsystem remote multiplexing unit risk-oriented accident analysis methodology reactor protection system recirculation pump trip reactor pressure vessel reactor pressure vessel support bracket reference rod pull sequence required response spectra reactor shield annulus Siting and Accident Consequences Branch, Division of Site and Environmental Reviews Reactor Systems Branch, Division of Safety Systems rod server processing channel remote shutdown system reactor shield wall radiographic testing resistance temperature detector reactor trip and isolation function reference temperature nil ductility temperature regulatory treatment of non-safety systems rated thermal power reactor trip system reactor vessel reactor vessel materials surveillance program radwaste radwaste building radwaste control room radwaste control room heating, ventilation, and air conditioning subsystem reactor water cleanup C-13 RWDS RWE RWGA RWGAVS RWM RWMS RWVS S&T SA SACF SAD SAM SAMA SAMDA SAMG SAR SAS SAT SAW SB SB&PC SBO SBWR SC SCC SCG SCMP SCP SCRAM SCRRI SDC SDG SDGLS SDGSAS SDM SDOE SDP SDS SDV SE SER SERG SFAT SFP SFPCS SFRA SGI SGTR SI SInstP radioactive waste drain systems rod withdrawal error radwaste general area radwaste general area heating, ventilation, and air conditioning subsystem rod worth minimizer radioactive waste management system radwaste heating, ventilation, and air conditioning system shell & tube service air single active component failure software architecture descriptions startup administrative manual severe accident mitigation alternatives severe accident mitigation design alternatives severe accident management guideline safety analysis report service air system site acceptance test submerged arc welding service building steam bypass and pressure control station blackout simplified boiling-water reactor structure and component stress corrosion cracking startup coordinating group software configuration management plan setpoint control program prompt reactor trip selected control rod run in shutdown cooling standby diesel generator standby diesel generator lubrication system standby diesel generator starting air system shutdown margin secure development and operational environment software development plan system design specification scram discharge volume safety evaluation safety evaluation report Steam Explosions Review Group system factory acceptance test spent fuel pool spent fuel pool cooling system system functional requirements analysis safeguards information steam generator tube rupture International System of Units software installation plan C-14 SIntP SIP SIS SIT SIU SJAE SL SLC SLCS SLMCPR SMA SMACNA SMP SMPM SMT SOC SOMP SOP SP SPC SPCS SPDS SPLB SPTM SQA SQAP SQAPM SR SREC SRI SRM SRNM SRO SRP SRS SRSB SRSS SRV SRVD SS SSAM SSC SSE SSI SSLC SSP SST STP STRAP software integration plan software installation plan structural integrity shutdown structural integrity test signal interface unit steam jet-air ejector safety limit standby liquid control standby liquid control system safety limit minimum critical power ratio seismic margins analysis Sheet Metal and Air Conditioning Contractors’ National Association software management plan software management program manual scale model test state of charge software operations and maintenance plan software operations plan suppression pool suppression pool cooling suppression pool cooling system safety parameter display system Plant Systems Branch, Division of Safety Systems suppression pool temperature monitoring software quality assurance software quality assurance plan software quality assurance program manual surveillance requirement standard radiological effluent controls select rod insert staff requirements memorandum startup range neutron monitor senior reactor operator Standard Review Plan software requirements specifications Reactor Systems, Nuclear Performance and Code Review Branch, Division of Safety Systems and Risk Assessment square root of the sum of the squares safety relief valve safety relief valve discharge specific subscale seismic anchor movement structures, systems, and components safe-shutdown earthquake soil-structure interaction safety system logic control software safety plan shear stress transport software test plan scram time recording and analysis panel C-15 STrngP STRP STS SV SVT SVVP SWMS T-AT T-H T&M TA TAF TAP TASS TB TBAS TBCE TBDRE TBE TBLOE TBS TBV TBVS TCCWS TCV TEDE TEMA TER TG TGCS TGSS TI TID TIP TLU TMI TMSS TR TS TSC TSCVS TSFA TSL TSM TSTF TSV UAT UCL UDW UHS software training plan scram time recording panel standard technical specifications safety valve software validation test software verification and validation plan solid waste management system transient without negative reactivity insertion thermal-hydraulics test and maintenance task analysis top of active fuel task action plan turbine auxiliary steam system turbine building turbine building air supply turbine building compartment exhaust turbine building decontamination room exhaust turbine building exhaust turbine building lube oil area exhaust turbine bypass system turbine bypass valve turbine building heating, ventilation, and air conditioning system turbine component cooling water system turbine control valve total effective dose equivalent Tubular Exchanger Manufacturers Association technical evaluation report turbine generator turbine generator control system turbine gland seal system temporary instruction technical information document traversing in-core probe trip logic unit Three Mile Island turbine main steam system topical report technical specifications technical support center technical support center heating, ventilation, and air conditioning subsystem top of the stored fuel assemblies technical specification leakage technical specifications monitor Technical Specifications Task Force turbine stop valve unit auxiliary transformer upper confidence limit upper drywell ultimate heat sink C-16 UL UPS URD URI URS US USE USI USM USNRC UT V&V VAC VB VBIF VBIV VDC VDU VFTP VHRA VLA VLC VLU VPF VRLA VS VT VW WBGT WDP WG WNP-2 WRC WW ZIS ZPA Underwriter's Laboratories uninterruptible power supplies utility requirements document unresolved item ultimate rupture strength United States upper-shelf energy unresolved safety issue uniform support motion United States Nuclear Regulatory Commission ultrasonic verification and validation volts alternating current vacuum breaker vacuum breaker isolation function vacuum breaker isolation valve volts direct current video display unit ventilation filter testing program very high radiation area vented lead acid vent line clearing voter logic unit vane passing frequency valve-regulated lead-acid ventilation stack vertical vent wall wet bulb globe temperature wide display panel water gauge Washington Nuclear Plant Unit 2 Welding Research Council wetwell zinc injection system zero period acceleration C-17