LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 9.2-1 Through 9.2-5

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 9.2-1 Through 9.2-5

ML17046A461
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: ML17046A461 (6)

Text

TABLE 9.2-1 SERVICE WATER SYSTEM FLOWS AND HEAT LOADS (PER UNIT) {7) Jlo!;le ot: OJ2!!&:Ation Normal Blackout Injection Recirculation Start-up Normal Shu:t!lown No Agcidgnt lbaSfl f:hase No. of pumps required 4 4 3 2(4) 2(4) 3(6) El!ii!!! &:il!imL'ISI fo, S§,ViCf!!, gl!l'l Service Water Intake 1,230 1,230 1,115 1,000 1,000 1,115 Turbine Services 15,184 26,084 3,737 0 0 0 Nuclear Services 14.200 12.453 3J..!liil7(2l Total Flow (5) 40,144 41,514 28,634 13,453 11,137 32,142 E§t;!.mated Heat Loads, 6 Btu/hr x 10 Turbine Services 67.24 114.14 17.00 0 0 0 Nuclear Services 77.45 78.74 325!27C3l 39.44 .2..1L.2 536.82 Total Estimated Heat Load 144.69 192.88 342.27 39.44 271.9 536.82 Notes: (l) Remove one of two component cooling heat exchangers from service prior to feeding service water to second Turbine Auxiliaries Cooling System heat exchanger. (2) Westinghouse transmittal PSE-94-568 defines a minimum flow of 8,000 gpm at 90°F for one CCHX in service. (3) First four hours following shutdown. (4) Assume only two diesel generators running. (5) At service water temperature of 90°F. (6) LOCA + LOOP -Maximum safeguards condition (7) The flows listed in this table are based upon the design flows associated with the equipment and components required for various plant operating modes. The actual flows available for these plant operating modes may vary from the above flows and are documented in the Service Water System calculations. 1 of 1 SGS-UFSAR Revision 16 January 31, 1998

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• TABLE 9.2-2 COMPONENT COOLING SYSTEM CODE REQUIREMENTS Component Cooling Heat Exchangers (Shell/Tube Type) Component Cooling Heat Exchangers (Plate Type) Component Cooling Surge Tank Component Cooling Loop Piping Component Cooling Valves (l)Used for design ASME Sect VIII ASME Sect II I Class 3 ASME Sect VIII ANSI B31. 1. 0 (1) ANSI B31. 7 (2) (2)For piping not supplied by the NSSS supplier, material inspection, fabrication, and quality control conform to ANSI B31.7. Where not possible to comply with ANSI 831.7, the requirements of ASME 111-1971, which incorporated ANSI B31.7, were adhered to

• 1 of 1 SGS-UFSAR Revision 6 February 15, 1987 TABLE 9. 2-3 COMPONENT COOLING SYSTEM FLOW REQUIREMENTS -ONE UNIT Residual heat exchangers Reactor coolant pumps Seal water heat exchanger Sample heat exchangers (both units) Letdown heat exchanger Spent fuel pool heat exchanger Residual heat removal pumps Safety injection pumps Charging pump (Reciprocating) Charging pumps (Centrifugal) Waste evap package Boric acid evap package Waste gas compressors Excess letdown heat exchanger TOTAL Number of pumps required Number of pumps in service Number of pumps installed Pump capacity (ea) -4,600 gpm(8) Pump head 200 ft TDH(8) (gpm) Normal 760 (min) 210 308 (max) 1,000 ( 4) 3,000 ( 4) 20 20 100 ( 7) 28 (max) 780 (5) 1,896 (5) 85 ( 6) 230 (5) 8,437 2 2 3 (1) The data is for each component cooling loop (2) This load is only for loop B ( 9) Loss of Coolant Accident (Recirculation Phase) (1) 4,000 10 10 100 (2) (7) 14 (max) (9) 4,134 (3) 1 1 (3) Loop A total is 4034 gpm and for loop B total is 4134 gmp (4) Varies with heat load (5) May be out of service (6) Maximum flow for two waste gas compressors heat exchangers. Components in service may vary with load. (7) Varies with CCW temperature and/or CC heat load. May be throttled. (8) Design Point. Not maximum value. (9) Component Cooling Flow to 21 and 22 Centrifugal Charging Pumps eliminated. 1 of 1 SGS-UFSAR Revision 27 November 25, 2013 Quantity Type TABLE 9.2-4 COMPONENT COOLING SYSTEM COMPONENT DESIGN DATA 3 Horizontal Rated capacity, gpm (Design Point) Rated head, ft H2o(Design Point) 4600 200 pressure, Design Available NPSH, ft Material (1) 150 200 25 Carbon steel Component Cooling Heat Exchangers (Shell and Tube Type) Number Design heat transfer, Btu/hr Design pressure, psig Design temperature, OF Design flow rate, lb/hr Design inlet temperature, OF Design outlet temperature, OF 150 200 3.41 X 106 113.0 100.0 2 44.2 X 106 180 200 4.99 X 106(1) 90 99.3 Fouling Factor, 0.0005 0.00091 (11 & 21 CCHXs) 0.00097 (22 CCHX) Fluid Material SGS-UFSAR Component cooling *water Carbon steel 1 of 2 Service Water Titanium Revision 26 May 21, 2012

\ Number heat transfer, Btu/hr Fouling factor (total), TABLE 9.2-4 (Cont) 1 (2) 44.2 X 106 0.001 Component Cooling Water Side Service Water Side Design pressure, psig temperature, OF Design flow rate, lb/hr inlet ' OF Design outlet , OF Material Number Type pressure: Internal, psig External, psig Design temperature, °F Normal operating pressure, psig Total volume, gal Normal water volume, Fluid Material 150 200 3.41 X 106 113.0 100.0 Titanium 1 180 200 4.99 X 106(1) 90.0 99.3 Titanium Horizontal, with divider 100 Vacuum breaker provided 200 Atmospheric 2000 1000 Component Carbon Steel water (1) Westinghouse transmittal PSE-94-568 defines a minimum flow of 8000 gpm 6 (4.00 x 10 lbs for accident conditions. (2) Unit 1 has one shell and tube-type and one plate-type heat Unit 2 has two shell and tube-type heat exchangers. 2 of 2 SGS-UFSAR Revision 26 May 21, 2012

1. 2. 3. 4. 5. 6.

• Component Component cooling water pumps Component cooling water pumps Component cooling water pumps Component cooling water pump Component cooling heat exchanger Component cooling heat exchanger vent or drain valve SGS-UFSAR *

• TABLE 9.2-5 COMPONENT COOLING SYSTEM -MALFUNCTION ANALYSIS Malfunction Rupture of pump casing Pump fails to start Manual valve on a pump suction line closed Stop valve on discharge line closed or check valve sticks closed Tube or shell rupture Left open Comments and Consequences The casing and shell are designed for exceeds maximum operating conditions. protected against credible missiles. credible. 150 psi and 200°F which Pump is inspectable and Rupture is not considered One operating pump will supply sufficient flow. Redundancy is sufficient to provide ample flow for any condition. This will be prevented by prestartup and operational checks. Further, during normal operation, each pump will be checked on a periodic basis which would show that a valve was closed. Stop valve will be checked open by prestartup and operational checks. The stop valve and the check valve will be checked by periodic operation of the pumps during normal operation. Rupture is considered incredible because of low operating pressures. This will be prevented by prestartup and operational checks. During normal operation such a situation would be readily assessed by observation of level in the component cooling surge tank. 1 of 1 Revision 6 February 15, 1987