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

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.4-1 to 4.4-4

ML17046A342
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: ML17046A342 (6)

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• TABLE 4.4-1 REACTOR THERMAL AND HYDRAULIC DESIGN PARAMETERS Reactor Core Heat OUtput, MWt Reactor Core Heat Output, BTU/hr Heat Generated in Fuel System Pressure, Nominal psia System Pressure, Minimum Steady State psia coolant Flow Total Thermal Flow Rate, lb/hr Effective Flow Rate for Heat Transfer, lb/hr Effective Flow Area for Heat Transfer, ft2 Average Velocity Along Fuel Rods, ft/sec Average Mass Velocity, lb/hr-ft2 Coolant Temperature Nominal Inlet, deg-F Average Rise in Vessel, deg-F Average Rise in core, deg-F SGS-UFSAR 1 of 3 3459 11,806 X 106 97.4 2250 22U (STDP111only) 125.3 X 106 116.3 X 106 V-SH, V+ 51.3 RFA<2J Sl.l V-SH, V+ 14.1 RFA 14.2 V-SH,V+ 2.27 x 106 RFA 2.28 X 106 542.7 70.4 75.2 Revision 19 November 19, 2001 I I TABLE 4.4-1 (Cont.) Average in Core, deg-F Average in Vessel, deg-F Heat Transfer Active Heat Transfer Surface Area, ft2 Average Heat Flux, BTU/hr-ft2 Maximum Heat Flux, For normal operation, BTU/hr-ft2 Average Thermal Output, kW/ft Maximum Thermal Output, For normal operation, kW/ft Peak Linear Power for determination of protection setpoints, kW/ft Peak at Thermal Output Maximum for maximum Overpower Trip, deg-F Pressure Drop Across Core, psi Minimum DNBR at Normal Conditions Typical Flow Channel Thimble (Cold Wall) Flow Channel 2 of 3 SGS-UFSAR Full Full Full 582.4 577.9 59,700 192,470 461,930 (4) 5.52 13.3 (4) < 22.4 (S) <4700 core V-5H, V+ 22.2 (6) core core RFA with DFBN 24.7 (6) RFA with SDFBN 24.5 (9) V-5H,V+ 2.44 RFA 2.64 V-5H,V+ 2.32 RFA 2.62 Revision 28 May 22, 2015 TABLE 4.4-1 (Cont.) DNBR Correlation (7) DNBR Correlation Limit(7) DNBR Design Limit (B) Notes: l)Standard Thermal Design Procedure V-5H,V+ WRB-1 RFA WRB-2 WRB-1 1.17 WRB-2 1.17 WRB-1 1.24(RTDP(J) ,Typical) WRB-1 1.24(RTDP, Thimble) WRB-2 1.24(RTDP, Typical) WRB-2 1.22(RTDP, Thimble) 2)All Parameters for RFA include Intermediate Flow Mixing (IFM) grids 3)Revised Thermal Design Procedure 4)Associated with FQ limit of 2.40 5)See Section 4.3.2.2.6 6)Based on a best estimate reactor flow rate of 93,300 gpm/loop 7)See Section 4.4.2.3.1 8)See Section 4.4.1.1 9)Based on a best estimate reactor flow rate of 94,800 gpm/loop and a Tavg of 566.0 F. 3 of 3 SGS-UFSAR Revision 28 May 22, 2015 SGS-UFSAR TABLE 4.4-2 THERMAL-HYDRAULIC DESIGN PARAMETERS FOR ONE OF FOUR COOLANT LOOPS OUT OF SERVICE (This Table has been deleted) Revision 18 April 26, 2000

• Core Hot Subchannel

• SGS-UFSAR

• VOID FRACTIONS AT NOMINAL REACTOR CONDITIONS WITH DESIGN HOT CHANNEL FACTORS Average 0.24% 5.8% 1 of 1 Maximum 20.H Revision 19 November 19, 2001

• Power Reactor (MWt) Ginna 847 854 857 947 961 1091 1268 1284 1284 1287 1294 1295 Robinson 1427.0 1422.6 1529.0 2207.3 2213.9 SGS-UFSAR

• TABLE 4.4-4 COMPARISON OF THINC-IV AND THINC-1 PREDICTIONS WITH DATA FROM REPRESENTATIVE WESTINGHOUSE TWO AND THREE LOOP REACTORS a (oF) %Full Measured Inlet rms a (°F) Power Temp (°F) THINC-I THINC-IV 65.1 543.7 1.97 1.83 65.7 544.9 1.56 1.46 65.9 543.9 1.97 1.82 72.9 543.8 1.92 1. 74 74.0 543.7 1.97 1. 79 83.9 542.5 1. 73 1.54 97.5 542.0 2.35 2.11 98.8 240.2 2.69 2.47 98.9 541.0 2.42 2.17 99.0 544.4 2.26 1.97 99.5 540.8 2.20 1.91 99.6 542.0 2.10 1.83 65.1 548.0 1.85 1.88 64.9 549.4 1.39 1.39 88.0 550.0 2.35 2.34 100.7 534.0 2.41 2.41 101.0 533.8 2.52 2.44 1 of 1

• Improvement (°F) for THINC-IV over THINC-1 0.14 0.10 0.15 0.18 0.18 0.19 0.24 0.22 0.25 0.29 0.29 0.27 0.03 0.00 0.01 o.oo 0.08 Revision 6 February 15, 1987