LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 1.6, List of Acronyms

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 1.6, List of Acronyms

ML17046A243
Person / Time
Site:	Salem
Issue date:	01/30/2017
From:	Public Service Enterprise Group
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17046A230	List: LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.8-1 Through 3.8-56 LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 6.3-1A Through 6.3-4 LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 9.1-1 Through 9.1-9 LR-N17-0034, Redacted Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 5.5-1 Through 5.5-7 LR-N17-0034, Redacted-Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.2, Nearby Industrial, Transportation, and Military Facilities LR-N17-0034, Redacted-Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 3.6, Figure 3.6-1 Through Figure 3.6-30 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 15.3A, Generic Small Break Analysis LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3.6A, Description of Backdraft Damper LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3.9A, Bolted Connections for Linear Component Support LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 7A, Program Element Descriptions Resulting from the Implementation of the May 6, 1983 Order LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 15, Figures 15.4-2 to 15.4-111 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 15, Section 15.5, Anticipated Transients Without Scram LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 17, Figures 17.2-1 to 17.2-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.2-1 to 4.2-25 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.3-1 to 4.3-35 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4-1 to 4.4-17 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4.1 to 4.4-66d LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.5-1 to 4.5-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Section 4.5, Reload Analyses LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 4.3.1 to 4.3-61 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 5.4.1 to 5.4-14 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.2-1 to 4.2-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.3-1 to 4.3-11 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.4-1 to 4.4-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.5-1 to 4.5-2 (Deleted) LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.1-1 to 5.1-13 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.2-1 to 5.2-24 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.1 to 5.1-8 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.2.1 to 5.2-75 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.3.1 to 5.3-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Table 5.1-1, System Design and Operating Parameters LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Tables 5.2-1 to 5.2-42 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 14.6-1 Through 14.6-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.1-1 Through 15.1-9 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.2-1 Through 15.2-46 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.3-1 Through 15.3-68 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.7.1 Through 3.7-13 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.9-1 Through 3.9-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3A-1 Through 3A-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 7.6-1 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 8.2-1 (Intentionally Deleted) and Figure 8.2-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.2-1 to 10.2-4 Intentionally Deleted LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.3-1A Sheets 1 Through 6 of 6 Intentionally Deleted to 10.3-3, Sheets 1 & 2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.4-1 Sheets 1 & 2 of 2, Intentionally Deleted to 10.4-19 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.2-1A Sheets 1 Through 5 of 5 to 11.2-1B Intentionally Deleted LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.3-1A & B, Sheets 1, 2 & 3 of 3, Intentionally Deleted. Refer to Plant Drawings 205240 & 205340 in Dcrms LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.4-1 to 11.4-9 ... further results
References
LR-N17-0034
Download: ML17046A243 (14)

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• 1.6 LIST OF ACRONYMS The following is an alphabetical listing of the most frequently used acronyms in this report. AEC AFST AFW AIF ALARA -ALP ALS AMSAC -ANS ANSI AO ASTM ATWS BIT BNWL BOL SGS-UFSAR Atomic Energy Commission Auxiliary Feedwater Storage Tank Auxiliary Feedwater Atomic Industrial Forum As Low as is Reasonably Achievable Actuation Logic Processor (AMSAC) Actuation Logic System (AMSAC) Actuation Mitigation System Actuation Circuitry American Nuclear Society American National Standards Institute Axial Offset American Society for Testing and Materials Anticipated Transient Without SCRAM Boron Injection Tank Battelle Northwest Laboratory Beginning-of-Life 1.6-1 Revision 10 July 22, 1990 BOP Balance-of-Plant BTP Branch Technical Position 1. 6-la SGS-UFSAR Revision 10 July 22, 1990 * * *

• SGS-UFSAR

• THIS PAGE INTENTIONALLY BLANK 1.6-lb Revision 10 July 22, 1990 BWR CAACS CAP CASP CCP CERC CFR CIS CPS CRDM CRS CSAS css eves CVTR cws DAS DBA DBE DCRDR SGS-UFSAR Boiling Water Reactor Control Area Air Conditioning System Chemical Analysis Panel Containment Air Sampling Panel Centrifugal Charging Pump coastal Engineering Research Center Code of Federal Regulations Containment Isolation System condensate Polishing System Control Rod Drive Mechanism control Room supervisor Containment Spray Actuation System Containment Spray System Chemical and Volume Control System Carolina-Virginia Tube Reactor Circulating Water System Data Acquisition System Design Basis Accident Design Basis Earthquake Detailed Control Room Design Review 1.6-2 Revision 16 January 31, 1998 DEPS OF DNB DNBR DOT djp DR!' OTT DVRPC E&CD EACS ECCS EOL EPD EPRI EPZ ESF FPS SGS-UFSAR Double-Ended Pump Suction Decontamination Factor Departure from Nucleate Boiling Departure from Nucleate Boiling Ratio Department of Transportation differential pressure Dose Reduction Factor Ductility Transition Temperature Delaware Valley Regional Planning COmmission Engineering and construction Department Emergency Air COnditioning system Emergency core Cooling System End-of-Life Electric Production Department Electrical Power Research Institute Emergency Planning Area Engineered Safety Features Fire Protection system 1.6-3 Revision 16 January 31, 1998 FSAR GDC GM GPM GWD GWS HED HEPA HFP HHW HP I&C ICE IEEE I/0 LCR LDP LP LPG SGS-UFSAR Final Safety Analysis Report General Design Criteria Geiger-Mueller Gallons Per Minute Gigawatt Day Gaseous Waste System Human Engineering Deficiency High-Efficiency Particulate Air Hot Full Power High-High Water High Pressure Instrumentation and Control Instrumentation Controls and Electrical Institute of Electrical and Electronics Engineers Input/Output License Change Request Lighting Distribution Panel Low Pressure Liquified Petroleum Gas 1.6-4 Revision 10 July 22, 1990 * * *

• LPM *

• Loose Parts Monitoring Revision 10 July 22, 1990 THIS PAGE INTENTIONALLY BLANK 1. 6-4b SGS*UFSAR. Revision 10 July 22, 1990 * *

• LNG LOCA LOFT LSP LWS MCD MEL MEL MI MIG MMA MMI MOL MSIV MSL MSR MWD/ MTU NBS NBU NCO SGS-UFSAR Liquified Natural Gas Loss-of-Coolant Accident Loss of Fluid Test Liquid sampling Panel Liquid Waste System Minor Civil Division Master Equipment List (Section 17.2) Moderate Energy Lines Mechanical and Integrated Manual Inert Gas Manual Metal Arc Modified Mercalli Intensity Middle-of-Life Main Steam Isolation Valve Mean Sea Level Moisture Separator-Reheater Megawatt Days per Metric Ton of Uranium National Bureau of Standards Nuclear Business Unit Nuclear control Operators 1.6-5 Revision 16 January 31, 1998 NOT NEMA NFPA NIS NML NPSH I NOS NRB NRC NSR NSSS NWS OBE OD O&M ORNL OS OSHA OTG PASS SGS-UFSAR Nil Ductility Transition National Electric Manufacturers' Association National Fire Protection Association Nuclear Instrumentation System Nuclear Mutual Limited Net Positive Suction Head Nuclear Oversight Department Nuclear Review Board Nuclear Regulatory Commission Nuclear Safety Review Department Nuclear Steam Supplier System National Weather Service Operating Basis Earthquake Outside Diameter Operations and Maintenance Oak Ridge National Laboratories Operations Superintendent Occupational and Safety Health Act Operational Test Group Post Accident Sampling System 1.6-6 Revision 22 May 5, 2006 PLUS

• PMH POPS PORC PORV PRT PSAR PSD PSE&G PSSUG PVRC

• PWR QA RA RAMPS RCC RCS RCCA

• SGS-UFSAR Parcel Land Use System Probable Maximum Hurricane Pressurizer OVerpressure Protection System Preoperational Testing Review committee Power-Operated Relief Valve Pressurizer Relief Tank Preliminary Safety Analysis Report Public Service Datum Public service Electric & Gas Public Service Electric & Gas Startup Group* Pressure Vessel Research Committee Pressurized Water Reactor Quality Assurance Quality control Reduction Area Repair and Maintenance Procedure System Rod Cluster control Reactor Coolant Rod Cluster Control Assembly 1.6-7 Revision 6 February 15, 1987 RCFC RCS RCL RCP RCPB RCS REMP REP RG RBR RMS RMS RPS RSE RTD RVED RWST SBO SEC SER SGS-UFSAR Reactor Containment Fan Cooler Reactor coolant System Reactor Coolant Loop Reactor Coolant Pump Reactor Coolant Pressure Boundary Reactor COolant System Radiological Environmental Monitoring Program Radiation Exposure Permit Regulatory Guide Residual Heat Removal Radiation Monitoring System Root-Mean-square Reactor Protection System Reload Safety Evaluation Resistance Temperature Detector Reactor Vessel Examination Device Refueling Water Storage Tank Station Blackout Safeguards Equipment Control Safety Evaluation Report 1.6-8 Revision 15 June 12, 1996 * *

• SGB -: Steam Generator Blowdown

• SGS Salem Generating Station SIS Safety Injection System SMSA Standard Metropolitan Statistical Area SORC Station Operations Review Committee SPDS Safety Parameter Display System SRP Standard Review Plan SRSS Square-Root-of-the-Sum-of-the-Square SSE Safe Shutdown Earthquake

• SSG Salem Startup Group SSPS Solid State Protection System STA Shift Technical Advisor STGD Steam Turbine -Generator Division SWRI Southwest Research Institute sws Service Water System TDC Thermal Diffusion Coefficient TDH Total Dynamic Head TDS Total Dissolved Solid

• TLD Thermoluminescent Dosimeter 1.6-9 SGS-UFSAR Revision 6 February 15, 1987 TMI Three Mile Island T/MS Test/Maintenance System (AMSAC) TSC Technical Support Center UE&C United Engineers & Constructors UFSAR Updated Safety Analysis Report UPS Uninterruptible Power System USE Upper Shelf Energy UTG United Engineers and Constructors Test Group UTS Ultimate Tensile Stress VCT Volume Control Tank WDS Waste Disposal System w.g. water gage WILMAPCO

• Wilmington Metropolitan Area Planning Council WMID WOL SGS-UFSAR Wisconsin-Michigan Inspection Device Wedge Opening Loading 1. 6-10 Revision 10 July 22, 1990 * * *