ML20129J898
| ML20129J898 | |
| Person / Time | |
|---|---|
| Site: | 05200045 |
| Issue date: | 05/08/2020 |
| From: | James Shea NRC/NRR/DNRL/NRLB |
| To: | |
| Shea J | |
| Shared Package | |
| ML20129J892 | List: |
| References | |
| Download: ML20129J898 (7) | |
Text
ABBREVIATIONS ac alternating current ABWR Advanced Boiling Water Reactor ACI American Concrete Institute ACIWA Alternating Current (ac) Independent Water Addition System ACS Atmospheric Control System ACRS Advisory Committee on Reactor Safeguards ADAMS Agencywide Documents Access and Management System AEA Atomic Energy Act AIA Aircraft Impact Assessment AISI American Iron and Steel Institute ALARA as low as reasonably achievable ANS American Nuclear Society ANSI American National Standards Institute AOO anticipated operational occurrence AOV air-operated valve AR annual reporting letters ASME American Society of Mechanical Engineers ASCE American Society of Civil Engineers ASCE/SEI American Society of Civil Engineers/Structural Engineering Institute ASTM American Society of Testing and Materials ATWS anticipated transient without scram BDBE beyond-design-basis event BE best estimate BL bulletin BPV Boiler and Pressure Vessel BPVC Boiler and Pressure Vessel Code BTP branch technical position Btu British thermal unit BWR boiling-water reactor BWROG BWR owners group C Celsius cc Cubic-centimeters C/B Control Building CDF core damage frequency CDI conceptual design information CENA central and eastern North America CFR Code of Federal Regulations cm centimeter(s)
COL combined license COPS containment overpressure protection system CP construction permit CR control room CRD control rod drive CRHA control room habitability area CST condensate storage tank I
CW circulating water DAC design acceptance criteria DAW dry active waste DB dry bulb DBA design-basis accident DBE design-basis event DBT design basis tornado DC design certification dc direct current DCA Design certification application DCD design control document DCR design certification rule DG diesel generator DLF dynamic load factors DNB departure from nucleate boiling DW-WW drywell-wetwell EAB exclusion area boundary EAC emergency alternating current EAL emergency action level ECCS emergency core cooling system EDG emergency diesel generator ELAP extended loss of alternating current power EMDG extensive damage mitigation guideline EMI electromagnetic interference EMS essential multiplexing system ENS emergency notification system EOC emergency operations center EOF emergency operations facility EOL end of life EOP emergency operating procedure EP emergency planning EP Emergency Preparedness EPA Environmental Protection Agency EPG emergency procedure guideline EPIP Emergency Plan Implementing Procedure EPRI Electric Power Research Institute EPZ emergency planning zone EQ environmental qualification ER environmental report ERDS emergency response data system ERF emergency response facility ERO emergency response organization ESBWR economic simplified boiling-water reactor ESF engineered safety feature ESP early site permit ETS emergency telecommunications system II
F Fahrenheit FB fuel building FEIS Final Environmental Impact Statement FEMA Federal Emergency Management Agency FERC Federal Energy Regulatory Commission FHA fire hazards analysis FLEX diverse and flexible coping strategy FP fire protection FPC fuel pool cooling and cleanup FPS fire protection system FR Federal Register FS factor of safety FSAR final safety analysis report FSER final safety evaluation report Ft feet/foot FWLB feedwater line break GDC general design criterion/criteria GE General Electric GEH General Electric - Hitachi (Nuclear Energy)
GENE General Electric Nuclear Energy (original ABWR applicant)
GI generic issue GL generic letter GMRS ground motion response spectrum gpm gallons per minute GSI generic safety issue GWMS gaseous waste management system hr hour HCLPF high confidence of low probability of failure HCU hydraulic control unit HEPA high-efficiency particulate air HF high frequency HFE human factors engineering HVAC heating, ventilation, and air conditioning HWL high water level Hz Hertz HX heat exchanger I&C instrumentation and control IBC International Building Code IDLH immediate danger to life and health IE inspection and enforcement IEEE Institute of Electrical and Electronic Engineers IN information notice in. inch(es)
IOZ inorganic zinc ISFSI independent spent fuel storage installation ISG interim staff guidance III
ISI inservice inspection ISRS in-structure response spectra IST inservice testing ITAAC Inspections, tests, analyses, and acceptance criteria ITP initial test program JLD Japan lesson-learned project directorate km kilometer(s) kPa kilopascals kV kilovolt LAN local area network LB lower-bound lb/ft2 pounds per square-foot LCO limiting condition for operation LF low frequency LLRW low-level radioactive waste LOCA loss-of-coolant accident LOLA loss of large area LOOP loss-of-offsite power LOPP loss of preferred power LPFL low pressure core flooder LPZ low population zone LR lower-range LTR licensing topical report LWMS liquid waste management system LWR light water reactor m meter(s)
M&TE measuring and test equipment MBDBE mitigation of beyond design basis events MBDBE-rule 10 CFR 50.155 Mitigation of beyond-design-basis events.
MBtu one million BTU MC&A material control and accounting MCR main control room MCWB mean coincident wet-bulb MEI maximally exposed individual mi mile(s)
MJ megajoules MOV motor-operated valve MPa megapascals MPaG megapascals gauge MPT main power transformer mph miles per hour MR maintenance rule Mrem millirem MSLB main steam-line break MSO multiple spurious operations IV
MW megawatt N2 nitrogen gas NACE National Association of Corrosion Engineers NCDC National Climatic Data Center NCS nuclear criticality safety NDE nondestructive examination NDT nil ductility temperature NEI Nuclear Energy Institute NFPA National Fire Protection Association NFSV new fuel storage vault NOAA National Oceanic and Atmospheric Administration NOC Nuclear Operations Center NPSH net positive suction head NQA nuclear quality assurance NRC Nuclear Regulatory Commission NRCS Natural Resources Conservation Service NRO Office of New Reactors NRR Office of Nuclear Reactor Regulation NS non-seismic NTTF Fukushima Near-Term Task Force NUREG Publications by the NRC staff NWS National Weather Service OBE operating-basis earthquake ODCM offsite dose calculation manual OE Owner's Engineer OEM original equipment manufacturer OGS offgas system OM Operation and Maintenance Code OPC open phase condition ORE occupational radiation exposure ORO offsite response organization OSC operational support center P&ID piping and instrumentation diagram P/T pressure/temperature PA protected area PAG Protective Action Guide PAM post-accident monitoring PAR protective action recommendation PAS post-accident sampling PASS post-accident sampling system PAT power ascension test PMF probable maximum flood PMH probable maximum hurricane POV power-operated valve ppb parts per billion PRA probabilistic risk assessment V
PRMS process radiation monitoring 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 QA quality assurance QAP quality assurance program QAPD quality assurance program description RAI request for additional information RAP reliability assurance program RAT reserve auxiliary transformer (alternate power source)
RB reactor building RCIC reactor core isolation cooling system RCPB reactor coolant pressure boundary RCS reactor coolant system rem roentgen equivalent man (a unit of radiation dose)
RG regulatory guide RHR residual heat removal system RIS regulatory issue summary RMU remote multiplexing units RMS radiation monitoring system RP radiation protection RPP Radiation Protection Program RPV reactor pressure vessel RSS remote shutdown panel RTNSS regulatory treatment of non-safety systems RV reactor vessel RVSP reactor vessel (materials) surveillance program RWB radwaste building RWCU reactor water cleanup RWCS reactor water cleanup systems RWMS radioactive waste management systems s second SAT systems approach to training S/B service building SBO station blackout SCC stress corrosion cracking SDC shutdown cooling SDG standby diesel generator SDM shutdown margin SE safety evaluation SEC Securities and Exchange Commission SER safety evaluation report SFP spent fuel pool SFPC spent fuel pool cooling VI
SGI safeguards information SLC standby liquid control SLCS standby liquid control system SPCS suppression pool clean-up system SR surveillance requirement SRI select rod insert SRM staff requirements memorandum SRO senior reactor operator SRP Standard Review Plan SRVs reactor safety relief valves SSC structure, system, and component SSCs structures, systems and components SSE safe-shutdown earthquake Std Standard STP South Texas Project STS standard technical specifications SUNSI Sensitive Unclassified Non-Safeguards Information Sv Sievert SWMS solid waste management system TAF top of active fuel T/B turbine building TCCWS turbine component cooling water system TEDE total effective dose equivalent TCD thermal conductivity degradation TLD thermoluminescent dosimeter TMI Three Mile Island TR technical report TS technical specifications TSC technical support center UAT unit auxiliary transformer UHS ultimate heat sink UPC unbalanced phase condition UPS uninterruptible power supply URG utility resolution guidance US United States USI unresolved safety issues USACE U.S. Army Corps of Engineers USCG United Sates Coast Guard USGS United States Geological Survey USI unresolved safety issue USNRC United States Nuclear Regulatory Commission V&V verification and validation V volt Vac volt alternating current Vdc volt direct current VII