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

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.1-1 Through 15.1-9

ML17046A565
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: ML17046A565 (9)

Text

85 80 75 70 65 t-ao ca -55 50 45 40 ' ' \ \ \ 1840 '. \ PSIA\ \ \ \ \ X 2000 PSJA \ \ // \ y \ "' \ \ \ \ \ \ ' \ ' \ \ \ \ \ \ ' ' \ \ ' \ \ \ \ \ ' \ \ \ ' \ \ \ ' \ \ \ \ \ \ \ \ \ \ \ ' O..rtemperature Delta T \ Trtp Lines (fncludklD Instrument Enors) At \ \ Indicated PressureS \ \ \ \ \ \ \ \ \ \ OYirpower Delta T Trip li'le Locus of Conditions VVhere .._. ........ _ ONBR** Safety Analysis Linl Far Thermal Design Flow OesQn Hot Chunel Factors Locus of Points VVhere Steam Generator Safety \latves Open \ 35 560 570 580 PSEG Nuclear, LLC 590 SALEM NUCLEAR GENERATING STAT ION \ ' ' \ \ \ \ \ 800 610 Tavg (*F) 620 630 640 650 R 18 A 1 26 2000 ev1s1on , 1pr1 ' Solem Nuclear Station ILLUSTRATION OF OVERT£ PERATURE AND OVERPOWER LT PROTECTION Updated FSAR Figure 15.1-1 CD 2000 PS£G Nucletr, llC. All Riljlts Reserved.

• ---*-*-**--****--------90 eo 70 j i .s 50 1 30 20 10 Dashpot 0 0 0.4 0.8 1.2 1.8 2 . 2.4 2.8 3.2 11me From Rod Release (Sec.) R 18 A 1 26 2000 eVlSlOn ' !Jlrl ' Solem Nuclear Generating Station PSEG Nuclear, LLC ROD POSITION VERSUS TIME ON REACTOR TRIP SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 15.1-2 CD 21:00 PSEG Noclecr. LLC. All Riljlts Reserved.

1.0 0.1 0.1 0.7 0.1 0.5 o.* 0.3 0.2 0.1 0 20 PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STATION 10 100 Rod Insertion (%) Rev1s1on 18, Apr1l 26, 2000 Solem Nuclear Generotinq_ Station NORMALIZED RCCA REACTIVITY WORTH VERSUS PERCENT INSERTION Updated FSAR Figure 15.1-3 CO 2000 P5[G Noc lefT. LLC. All R itJts Reserved. _

1.0 0.1 DASt-POT 0.1 0.7 i 0.8 .z: i 0.5 a: "i ,!:1j 0.4 18 i 0.3 0.2 0.1 0 o ... 0.1 1.2 1.1 2 2 .* 3.2 Tme Fn:m Rod Release (Sec.) R 18 A 1 26 2000 evision , tprl

• Salem Nuclear Generati'Vfr Station PSEG Nuclear, LLC NORMALIZED RCCA REACTI Y WORTH VERSUS TIME KTER REACTOR TRIP SALEM NUCLEAR GENERATING STATION Updated FSAA Figure 15.1-4 CO 200:J PS[G tiJclerr, LLC. All R i<Jlts Reserved.

--****-------------------*3,CX10 --------------------, *2.500 ..-.. -2t000 ....., I Da11P11t * ..z.ft Dill K -1,500 ... DI'C I I -1,000 -500 o 10 20 30 <<>> so eo 10 so 90 100 110 120 Power (%) Revision 18, April 26, 2000 PSEG Nuclear, LLC Solem Nuclear Generating Station INTEGRATED DOPPLER POWER COEFFICIENT USED IN ACCIDENT YSIS S,AJ...EM NUCLEAR GENERATING STATION Updated FSAR Figure 15.1-5 © 2lXXJ PS£G tU!ea-. LLC. All Reserved.

e "'V c fnCD >r-.... -mn z::D c< n-r-(') mm >m :Dr-m-1 ZXI m-:tJ(') >> -4Z zo C)C> (I)> -tfn !48 -3: 0-a Z> 0:: w )r; 0 0.. 2 < 1-oct 1-1-..c( )1:: --Cl) 1-1-oCl' )1:: i' a: c:: !!. 0 ! i .... "n:D :D-cl! JitO :DZ -c * ... !!' .... I .... I0°l 8 6 4 2 10-1 8 6 " 2 10-2 8 6 " 2 10-3 10-l 2 e FISSION PRODUCT O£CAY U-238 CAPTURf DfCAY TOTAL HEAT (WITH 4t q 6 8 10° 2 ll 6 8 101 2 ll 6 8 102 2 TIME AFTER SHUTDOWN (SECONDS) e q 6 8103 N+l PUBLIC SERVICE ELECTRiC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Updated FSAR FILM CLAD GAP Fuel Rod Cross Section REVISION I FEBRUARY 15,1917 Figure 15.1*7 THIS FIGURE HAS BEEN DELETED PSEG NUCLEAR L.L.C. SALEM GENERATING STATION SALEM UFSAR -REV 18 APRIL 26, 2000 . SHEET 1 OF 1 F15.1-8 THIS FIGURE HAS BEEN DELETED PSEG NUCLEAR L.L.C. SALEM GENERATING STATION SALEM UFSAR -REV 18 APRIL 26, 2000 SHEET 1 OF 1 F15.1-9