ML21090A189

Enclosure 4 - Acronyms and Definitions

ML21090A189
Person / Time
Site:	Callaway
Issue date:	03/31/2021
From:	Ameren Missouri, Union Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML21090A184	List: ML21090A185 ML21090A186 ML21090A187 ML21090A188 ML21090A189
References
GL-04-002, GSI-191, ULNRC-06526
Download: ML21090A189 (4)

Text

ULNRC-06526 Enclosure 4 Acronyms and Definitions

ULNRC-06526 Enclosure 4 Page 1 of 3 Acronyms and Definitions ADAMS Agencywide Documents Access and Management System AISC American Institute of Steel Construction ALARA as low as reasonably achievable ALOOH aluminum oxy-hydroxide ANSI American National Standards Institute ASME American Society of Mechanical Engineers BDBEE Beyond Design Basis External Event BWR boiling-water reactor CAC containment air cooler CAD computer-aided design CASA Grande Containment Accident Stochastic Analysis GSI-191 Resolution and Evaluation CCP centrifugal charging pump CCW component cooling water CDF core damage frequency CEC Callaway Energy Center CFD computational fluid dynamics CFR Code of Federal Regulations CHRS containment heat removal system COMS cold overpressure mitigation system CSAS containment spray actuation signal CSHL clean screen head loss CSS containment spray system CtCS containment cooling system CVCS chemical and volume control system D diameter DBA design-basis accident DEGB double-ended guillotine break DEHLG double-ended hot leg guillotine DEPSG double-ended pump suction guillotine DID defense-in-depth DP differential pressure ECCS emergency core cooling system EDG emergency diesel generator EOP emergency operating procedure(s)

EPRI Electric Power Research Institute ERG Emergency Response Guideline ERPIP Emergency Response Plan Implementing Procedure ESF Engineered Safety Feature FA fuel assembly FDL full debris load FSAR Final Safety Analysis Report GDC general design criterion/criteria GL Generic Letter

ULNRC-06526 Enclosure 4 Page 2 of 3 GR Guidance Report GSI Generic Safety Issue HCS hydrogen control system HELB high-energy line break HHSI high-head safety injection HPCIS High-pressure Coolant Injection System HVAC heating, ventilation, and air conditioning ID inside diameter IOZ inorganic zinc ISI in-service inspection LAR License Amendment Request LBLOCA large-break LOCA LCO limiting condition for operation LDFG low-density Fiberglass LERF large early-release frequency LOCA loss-of-coolant accident LOOP loss of offsite power MAAP Modular Accident Analysis Program MBLOCA medium-break LOCA MSLB main steam-line break NEI Nuclear Energy Institute NPSH net positive suction head NRC Nuclear Regulatory Commission OBE operating basis earthquake OD outer diameter OEM original equipment manufacturer OQAM Operating Quality Assurance Manual OQAP Operating Quality Assurance Program PRA probabilistic risk assessment PRT pressurizer relief tank PWR pressurized-water reactor PWROG Pressurized Water Reactor Owners Group PWSCC primary water stress corrosion cracking QA quality assurance RAI request for additional information RCCA rod cluster control assembly RCFC reactor containment fan cooler subsystem RCDT reactor coolant drain tank RCP reactor coolant pump RCS reactor coolant system RG Regulatory Guide RHR residual heat removal RHRS residual heat removal system RI risk-informed RMI reflective metal insulation

ULNRC-06526 Enclosure 4 Page 3 of 3 RoverD Risk over Deterministic RPV reactor pressure vessel RVLIS reactor vessel level instrumentation system RWST refueling water storage tank SAMG Severe Accident Mitigation Guideline SAR Safety Analysis Report SBLOCA small-break LOCA SE Safety Evaluation SECY Secretary of the Commission, Office of the (NRC)

SER Safety Evaluation Report SFDP Safety Function Determination Program SG steam generator SI safety injection SIS safety injection system safety injection signal SM safety margin SRM Staff Requirements Memorandum/Memoranda SR surveillance requirement SSC structures, systems and components SSE safe shutdown earthquake STP South Texas Project STPNOC South Texas Project Nuclear Operating Company TB thin bed T-H thermal-hydraulic TKE turbulent kinetic energy TS Technical Specification(s)

TSC Technical Support Center TSP trisodium phosphate dodeca-hydrate TSTF Technical Specification Task Force WCAP Westinghouse Commercial Atomic Power ZOI zone of influence CDF change in core damage frequency LERF change in large early release frequency