ML25094A183

SDAA - FSER Appendix C - Abbreviations

ML25094A183
Person / Time
Site:	05200050
Issue date:	05/22/2025
From:	Office of Nuclear Reactor Regulation
To:
References
Download: ML25094A183 (17)

Text

C-1 APPENDIX C - ABBREVIATIONS Aac Amps alternating current AAPS auxiliary ac power source ABS auxiliary boiler system AC acceptance criteria ac alternating current ACI American Concrete Institute ACRS Advisory Committee on Reactor Safeguards ADAMS Agencywide Documents Access and Management System AEA Atomic Energy Act AFT as-found tolerance AFU air filtration unit AFWS automatic auxiliary feedwater system AFWST auxiliary feedwater storage tank AHU air handling unit AIA Aircraft Impact Assessment AICC adiabatic isochoric with complete combustion AIL accident-induced leakage AISC American Institute of Steel Construction AISI American Iron and Steel Institute AL analytical limit ALARA as low as reasonably achievable ALI annual limits on intake ALT as-left tolerance AMS Aerospace Material Specification ANB Annex Building ANBVS Annex Building HVAC system ANL Argonne National Laboratory ALWR advanced light-water reactor ANS American Nuclear Society ANSI American National Standards Institute AO axial offset AOAS axial offset anomaly AOO anticipated operational occurrence AOV air-operated valve APL actuation and priority logic APRM average power range [neutron flux] monitor AQ-S as augmented quality Ar argon AR acoustic resonance ASAI application-specific action item ASCE American Society of Civil Engineers

C-2 ASHRAE American Society of Heating, Refrigerating, and Air-Conditioning Engineers ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials ATWS anticipated transient without scram AWS American Welding Society B

boron Ba Barium BACE boric acid corrosion evaluation BAS boron addition system BDBE beyond-design-basis event BDBEE beyond-design-basis external event BDG backup diesel generator BISI bypassed and inoperable status indication BL bulletin BOC beginning of cycle BIST built-in self-test BNL Brookhaven National Laboratory BPDS balance-of-plant drain system BPSS backup power supply system BPV Boiler and Pressure Vessel BPVC Boiler and Pressure Vessel Code BTP branch technical position BWR boiling-water reactor C

carbon C

Celsius cal/g calories per gram CARS condenser air removal system CAS compressed air system CB control building CBA cost-benefit analysis CBP computer-based procedures CCF common-cause failure CCFP conditional containment failure probability CCTV closed-circuit television system CDE core damage event CDF core damage frequency CDI conceptual design information CDST core damage source term CEAC control element assembly calculator CES containment evacuation system CET containment event tree CFD computational fluid dynamics

C-3 CFD containment flood and drain CFDS containment flooding and drain system cfm cubic feet per minute CFR Code of Federal Regulations CFT containment flange tool CFWS condensate and feedwater system CHF critical heat flux CHFR critical heat flux ratio CHRS containment heat removal system(s)

Ci/yr curies per year CILRT containment integrated leak rate test CIS containment isolation system CIV containment isolation valve CLD complex logic device CLL collapsed liquid level cm centimeter(s)

CM communication module cmh cubic meters per hour CMTR certified material test report CNTS containment system CNV containment vessel CNV containment volume CoF Coefficient of friction COL combined license COLR core operating limits report COMS communications systems ConOps concept of operations COT channel operational test CP construction permit CPC core protection calculator CPS condensate polishing system Cr-Mo chrome-molybdenum CRA control rod assembly CRAGT control rod assembly guide tube CRAM containment response analysis methodology CRB control building CRC cyclic redundancy check CRD control rod drive CRDM control rod drive mechanism CRDS control rod drive system CREATCS Control Room Emergency Air Temperature Control System CRE control room envelope CRHS control room habitability system CRVS control room heating, ventilation, and air conditioning system CRVS control room ventilation system

C-4 CS core support CSA core support assembly CSDRS certified seismic design response spectra CSDRS-HF CSDRS-high frequency CSF critical safety function CST condensate storage tank CTB calibration and testing bus CUF cumulative usage factor CVAP Comprehensive Vibration Assessment Program CVCS Chemical and Volume Control System CVCSI CVCS Isolation CWS circulating water system DAC derived air concentration DAC design acceptance criteria DBA design-basis accident DBAST Design Basis Analysis Source Term DBE design-basis event DBFFF design-basis failed fuel fraction DBPB design basis pipe break DBST design basis source term DBT design-basis threat DBT design basis tornado DC design certification dc direct current DCA design certification application DCD design control document DCS distributed control system DE dose equivalent DF decontamination factor DGB diesel generator building DHR decay heat removal DHRS decay heat removal system DI design implementation DID defense-in-depth (also refers to as D3)

DLF dynamic load factor DM direct method DNBR departure from nucleate boiling ratio DO dissolved oxygen DOD Department of Defense DOE Department of Energy DOT Department of Transportation DPR Division of Preparedness and Response D/Q deposition factor DR decay ratio

C-5 D-RAP design reliability assurance program DSRS design specific review standard DWO density wave oscillation DWS demineralized water system DWSI demineralized water system isolation DWST demineralized water storage tank DWT demineralized water treatment EAB exclusion area boundary EAF environmentally assisted fatigue ECCS emergency core cooling system EDAS NuScale augmented DC power system EDG emergency diesel generator EDNS (refers to NuScale) normal dc power system EDSS (refers to NuScale) highly reliable dc power system EDSS-C EDSS-common EFDS equipment and floor drain system EFPDS effective full power day EFPYs full-power years EHVS switchyard system (Chapter 8)

EIM equipment interface module ELVS electrical distribution system (Chapter 8)

EM evaluation model EMI electromagnetic interference EMVS electrical distribution system (Chapter 8)

ENDF Evaluated Nuclear Data File EOC end of cycle EOF emergency operations facility EOL End-of-life EOP emergency operating procedure EP emergency planning EPAs electrical penetration assemblies EPA Environmental Protection Agency EPRI Electric Power Research Institute EQ equipment qualification EQRF equipment qualification record file ERDS emergency response data system ERG emergency response guideline ERS equipment requirement specification ESF engineered safety feature ESFAS engineered safety features actuation system ESM extended subtraction method ESS-MS module specific ETAP Electrical Transient Analyzer Program E-W east-west

C-6 F

Fahrenheit FA function allocation FAC flow-accelerated corrosion FCU fan coil unit FE finite element FEA finite element analysis FEI fluid-elastic instability FEM finite element model FEMA failure modes and effects analysis Fen factor for environmental fatigue FFD fitness for duty F/G flutter and galloping FHA fire hazards analysis FHA fuel handling accident FHE fuel handling equipment FHM fuel handling machine FIRS foundation input response spectra FIV flow-induced vibration FMEA failure modes and effects analysis FN ferrite number FOAK first-of-a-kind FOS factor of safety FPGA field programmable gate array FPP fire protection program FPRA fire probabilistic risk assessment FPS fire protection system FQ flux hot channel factor FR Federal Register FRA functional requirements analysis FRA/FA functional requirements analysis and function allocation FRED EPRI Fuel Reliability Database FSAR final safety analysis report FSER final safety evaluation report FSI fluid structure interaction FSSD fire safe shutdown ft Feet or foot FTR final test report FWIV feedwater isolation valve FWLB feedwater line break FWPD feedwater pipe break FWRV feedwater regulating valve FWRV feedwater regulation valve FWS feedwater system g

grams

C-7 GAC Granulated Activated Charcoal GALE gaseous and liquid effluent GALL generic aging lessons learned GCB generator circuit breaker Gd2O3 gadolinium oxide GDC general design criterion/criteria GE General Electric GL generic letter GMRS ground motion response spectrum gph gallon per hour gpm gallons per minute GRWS gaseous radioactive waste system GSI generic safety issue GTG generic technical guidance GTS generic technical specification Gy/h grays per hour H2 hydrogen H-3 tritium hr hour HA hazard analysis HA human action HCSG helical coil SG HCSG helical coil steam generator HCW high-conductivity waste HDCI high duty core index HDPE high-density polyethylene HDR Heissdampf reactor HED human engineering discrepancy HELB high energy line break HEPA high-efficiency particulate air HF high frequency HFE human factors engineering HFEITS human factors engineering issues tracking system HFP hot full power HIC high integrity container HICR highly-integrated control roomshuman factors issue HIPS highly integrated protection system HIPS TR highly integrated protection system topical report HMI human machine interface HOV hydraulic operated valve HPS Health Physics Society HPU hydraulic power unit HRA human reliability analysis HSI human system interfaces

C-8 HTP heat transfer plate HTPTM High Temperature Performance HVAC heating, ventilation, and air conditioning HWM hard-wired module Hz Hertz HZP hot zero power I

iodine I&C instrumentation and control IAB inadvertent actuation block IAEA International Atomic Energy Agency IAS instrument air system IASCC irradiation-assisted stress corrosion cracking ICC inadequate core cooling ICI in-core instrumentation ICIGT in core instrumentation guide tube ICIS in-core instrumentation system ICSBEP International Handbook of Evaluated Criticality Safety Benchmark Experiments IDDS interface design descriptions IE infrequent event IE inspection and enforcement IEEE Institute of Electrical and Electronic Engineers IFPRA internal flooding probabilistic risk assessment IGSCC intergranular stress-corrosion cracking IHAS identify important human action ILRT integrated leakage rate testing IN information notice in.

inch(es)

INL Idaho National Laboratory I/O input/output IODHRS inadvertent operation of the DHRS IP implementation plan IP inspection procedure iPWR integral pressurized-water reactor IRM information and records management IRPI individual rod position indicator system ISG interim staff guidance ISI inservice inspection ISLOCA interfacing system loss-of-coolant accident ISM independent support motion ISRS in-structure response spectra ISS in structure shock IST inservice testing ISV integrated system validation

C-9 ITA inspections, tests, and analyses ITAAC Inspections, tests, analyses, and acceptance criteria ITP initial test program IV&V independent verification and validation K

Kelvin KA knowledge and abilities kg/s kilograms per second km kilometer(s) kPa kilopascals KSA knowledge, skills, and abilities/aptitude ksf kilopound per square foot ksi kilopound per square inch kV kilovolt LAR large release frequency LBB leak-before-break lbm pound-mass lbs pounds lb/ft pounds per square-foot LCO limiting condition for operation LCS local control station LCW low-conductivity waste LFI leakage flow instability LHGR linear heat generation rate l/m liters per minute LLRT local leak-rate test LLRW low-level radioactive waste LOCA loss-of-coolant accident LOCV loss of condenser vacuum LOEL loss of external load LOFW limiting loss of feedwater LOOP loss-of-offsite power LPMS loose parts monitoring system LPSD low power shutdown operations LPZ low population zone LRF large release frequency LRWS liquid radioactive waste system LSSS limiting safety system setting LTOP low temperature overpressure protection LTSD long-term shutdown LTSP limiting trip setpoint LUHS loss of normal access to the normal heat sink LWA limited work authorization LWR light-water reactor

C-10 m

meter(s)

MACCS MELCOR Accident Consequence Code System MC Main condenser MCHFR minimum critical heat flux ratio MCNP Monte Carlo N-Particle Transport Code MCR main control room MCS module control system MG main generator MHS module heatup system MIB monitoring and indication bus MIP Measurement and Inspection Plan MIR module inspection rack MLA module lift adapter MLA module lifting adapter MLD master logic diagram mm millimeters MMAF multi-module adjustment factor MMBtu million British Thermal Units MOC middle of cycle MOV motor-operated valve MPa megapascals mph miles per hour MPS module protection system MPT main power transformer MR maintenance rule Mrem millirem MRP materials reliability program MRRS minimum required response spectrum m/s meters per second MS main steam MSLB main steam line break MSIBV main steam isolation bypass valves MSIV main steam isolation valve MSL main steam lines MSO multiple spurious operation MSPB main steam pipe break MSS main steam system MSSD minimum safe standoff distance MSSV main steam safety valve mSv milliSievert MTC moderator temperature coefficient MW megawatt MWS maintenance work station MWt megawatts thermal

C-11 N

neutron N-16 Nitrogen-16 NDE nondestructive examination NDS nitrogen distribution system NDT nil ductility temperature NEI Nuclear Energy Institute NEMA National Electrical Manufacturers Association NFJC new fuel jib crane NFPA National Fire Protection Association NiCrFe Nickel-chromium-ion NIST NuScale Integral System Test Facility NMS neutron monitoring system NOPD normal operating pressure differential NPM nuclear power modules NPM NuScale Power Module NPP nuclear power plant NPS nominal pipe size NQA nuclear quality assurance NRC Nuclear Regulatory Commission NRELAP5 NuScale Reactor Excursion and Leak Analysis Program, Version 5 NRR Office of Nuclear Reactor Regulation N-S north-south NSIR Nuclear Security and Incident Response NSSS nuclear steam supply system NTSP nominal trip setpoint NuFuel NuScale fuel assembly NUMARC Nuclear Utilities Management and Resources Council NUSCALE NuScale Power, LLC O2 oxygen OBE operating-basis earthquake ODCM offsite dose calculation manual OER operating experience review OHLHS overhead heavy-load handling systems OI open items OL operating license OM Operation and Maintenance Code OPV Over-pressurization Vent ORE occupational radiation exposure ORIGEN Oak Ridge Isotope GENeration ORNL Oak Ridge National Laboratorys OSC operational support center OSHA Occupational Safety and Health Administration

C-12 OTT overtemperature T P&ID piping and instrumentation diagram Pa psia PA protected area PA postulated accident PAM Post-accident monitoring PASS post-accident sampling system PAT performance assessment testing pcm/s percent millirho per second PCP process control program PCS plant control system PCT peak cladding temperature PCUS pool cleanup system PDC principal design criterion PDILs power-dependent insertion limits PERMISS process and effluent radiation monitoring instrumentation and sampling system PGA peak ground acceleration PHT pressurizer heater trip PIRT phenomena identification and ranking table PIV pressure isolation valve PLDS pool leakage detection system PLS plant lighting system PMF probable maximum flood PMWP probable maximum winter precipitation PNNL Pacific Northwest National Laboratory POC proof of concept POS plant operating state POV power-operated valve ppm parts per million PPS plant protection system PRA probabilistic risk assessment PRHA pipe rupture hazards analysis P-STG plant specific technical guideline PSCIV primary system containment isolation valve PSCS pool surge control system psf pounds per square-foot PSI preservice inspection psi pounds per square inch psia pounds per square-inch absolute psig pound per square inch gauge PSS physical security system PSS process sampling system PST phase separator tanks

C-13 PST preservice testing PSWS potable and sanitary water system PTAC performance and test acceptance criteria PTLR pressure and temperature limits report P-T pressure-temperature PTS pressurized thermal shock PWR pressurized-water reactors PWS potable water system PWSCC primary water stress-corrosion cracking PZR pressurizer QA quality assurance QAP quality assurance program QAPD quality assurance program description QG quality group QHO quantitative health objective QMP quality management plan QPTR Quadrant Power Tilt Ratio rad/h radiation absorbed doses per hour RADTRAD RADionuclide Transport, Removal And Dose RAI request for additional information RAMP Radiation Protection Computer Code Analysis and Maintenance Program RAP reliability assurance program RBC reactor building crane RBVS reactor building heating ventilation and air conditioning system RBVS reactor building HVAC system RBVS reactor building ventilation system RBVS RXB ventilation system RCCW reactor component cooling water RCCWS reactor component cooling water system RCPB reactor coolant pressure boundary RCS reactor coolant system RCSB reactor coolant pressure boundary REA rod ejection accident rem roentgen equivalent man (a unit of radiation dose)

REMP radiological environmental monitoring program RETS radiological effluent technical specification RFFF realistic failed fuel fraction RFI radio frequency interference RFP reactor pool and refueling pool RFT reactor flange tool RFT reactor vessel flange tool RG regulatory guide

C-14 RHR residual heat removal RIS regulatory issue summary RITSTF Risk-Informed TSTF RMS root mean square RO reactor operator RPCS reactor pool cooling system RPI rod position indication RPS reactor protection system RPV reactor pressure vessel RRS required response spectrum RRV reactor recirculation valve RSR results summary report RSS remote shutdown station RSV reactor safety valves RTB reactor trip breaker RTF reactor flange tool RTM requirement traceability matrix RTNDT reference temperature nil ductility temperature RTNSS regulatory treatment of non-safety systems RTP rated thermal power RTS reactor trip system RV reactor vessel RVI reactor vessel internal RVV reactor vent valve RWB radwaste building RWBVS RWB HVAC system RWDS radioactive waste drain system RWS radioactive waste building RXB reactor building s

second SA situation awareness SAFDL specified acceptable fuel design limit SAM seismic anchor motion SAPHIRE Systems Analysis Programs for Hands-on Integrated Reliability Evaluations SAR safety analysis report SAS service air system SASSI system for analysis of soil-structure interaction SAT site acceptance test SBAC smooth bounding analysis curve SBEDS single degree of freedom blast design spreadsheet SBM scheduling and bypass module SBO station blackout

C-15 SBT scenario-based testing SC-1 Seismic Category I SCALE Standardized Computer Analyses for Licensing Evaluation SCC stress corrosion cracking SCWS site cooling water system SBM safety data bus SDA standard design approval SDAA standard design approval application SDD software design description SDIS safety display and indication system SDIS safety display and information system SDM shutdown margin SMA seismic margins analysis SDOE secure development and operational environment SE safety evaluation SEI Structural Engineering Institute SER safety evaluation report SFC single failure criterion SFCP Surveillance Frequency Control Program SFDP Safety Function Determination Program SFM safety function module SFP spent fuel pool SFPC spent fuel pool cooling SG safety group SG steam generator SGI safeguards information SGIFR steam generator tube inlet flow restrictor SGS steam generator system SGTF steam generator tube failure SGTR SG tube rupture SGTR steam generator tube rupture SI International System SIL software integrity level SL safety limit SLB steam line break SM shift manager SMA seismic margin analysis SMACNA Sheet Metal and Air Conditioning Contractors National Association SME subject matter expert SMR small modular reactor SNAP Symbolic Nuclear Analysis Package SOARCA State-of-the-Art Reactor Consequence Analyses SOC sampling of operational condition SOV solenoid-operated valve SP setpoint program SPDS safety parameter display system SPND self-powered neutron detectors

C-16 SPV staffing plan validation SR surveillance requirement S&Q staffing and qualifications SRM staff requirements memorandum SRWS solid radioactive waste system SRO senior reactor operator SRP Standard Review Plan SRS software requirements specification SRSS square-root-sum-of-square SRST spent resin storage tank SRST spent resin storage tanks SSC structure, system, and component SSCIV secondary system containment isolation valve SSE safe-shutdown earthquake SSI secondary system isolation SSI soil-structure interaction SSSI structure-soil-structure interaction Std Standard STS standard technical specifications Sv sievert SVM scheduling and voting module TA task analysis TADOT TRIP ACTUATING DEVICE OPERATIONAL TEST TASCS thermal stratification, cycling, and striping TB turbulent buffeting TBS turbine bypass system TBVS turbine building ventilation system Tc technetium TCV turbine control valve TEDE total effective dose equivalent TeR technical report TF transfer function TGB turbine generator building TGS turbine generator system TGSS turbine gland seal system TH thermal-hydraulic TID total integrated dose TIHA treatment of important human actions TLX task load index TMI Three Mile Island TNT Trinitrotoluene TOM top of module TP typical TR technical report

C-17 TRACE TRAC/RELAP Advanced Computational Engine TRITON Time-dependent Operation for Neutronic depletion TRS test response spectrum TRU Transuranic TS technical specifications TSC technical support center TSS top support structure TSTF Technical Specifications Task Force TSV turbine stop valve TT thermally treated TT turbine trip UAT unit auxiliary transformer UFC Uniform Facility Code UHS ultimate heat sink UL Underwriters Laboratories UO2 uranium dioxide URA upper riser assembly URD Utility Requirements Document URS uniform response spectrum US United States USE upper shelf energy USNRC United States Nuclear Regulatory Commission USM uniform support motion V

volt VBS vehicle barrier system V/H vertical to horizontal VHRA very high radiation area VLA vented lead-acid VRLA valve-regulated lead-acid VS vortex shedding VT visual testing V&V verification & validation WRC Welding Research Council WSW wet solid waste Wt%

weight percent Xe xenon

/Q atmospheric dispersion factor ZOI zone of influence ZPA zero period acceleration