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

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.3-1 to 4.3-35

ML17046A339
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: ML17046A339 (36)

Text

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BEJBBBBD **BBBBBB ** BBElEJ KEY: VALUE REPRESENTS ASSEMBLY RELATIVE POWER REVISION 17 OCTOB:::R 16 1996 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Nonnalized Power Density Distribution At BOL, Unrodded Core, HFP, No Xenon {Typical) Updated FSAR Figure 4.3-3 H G F E 0 c B A *BDDDDDDD *BGDDDDDD **GGBDDDDD ,BBBBDDDD ,BBBBBDD ,BGBGBBD **BBBEJBB .. BBEJG KEY: VALUE REPRESENTS ASSEMBLY RELATIVE POWER PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION REVISION 17 OCTOBER 161998 Normalized Power Density Distribution Near BOL, Unrodded Core, HFP, Equilibrium Xenon (Typical) Updated FSAR Figure 4.3-4 H G F E 0 c B A *GDDDDDDD *GBDDDDDD **BBBDDDDD ,GGBBDDDD **BBGBBDD **BGGGBBD .. BGEJGEJB .. E1BE1B KEY: VALUE REPRESENTS ASSEMBLY RELATIVE POWER REVISION 17 OCTOBER 16 1998 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Normalized Power Density Distribution Near BOL, Group D Inserted, HFP, Equilibrium Xenon (Typical) Updated FSAR Figure 4.3*5 H G F E 0 c B A *EJDDDDDDD *BBDDDDDD **BBBDDDDD ,BElEIGDDDD **BGEJGGDD *3BGGGBBD **BBBEJBG **BBEJB KEY: VALUE REPRESENTS ASSEMBLY RELATIVE POWER PUBUC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION -REVISION 17 OCTOBER 16 1998 Nonnalized Power Density Distribution Near Middle of Life. Unrodded Core, HFP, Equilibrium Xenon {Typical) Updated FSAR Figure 4.3-6 H G F E D c B A *BDDDDDDD *BBDDDDDD **BBBDDDDD ,BEJBBDDDD **BBBBBDD **BBGBBBD **BGGGGB **BElGB KEY: VALUE REPRESENTS ASSEMBLY RELATIVE POWER REVISION 17 OCTOBER 161998 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Nonnalized Power Density DistribuOon Near End of Life, Unrodded Core, HFP, Equilibrium Xenon (Typical) Updated FSAR Figure 4.3*7 a: w 0 CL. 0 w N _, <( :i a: 0 z 2.0 .--------------------------1.5 1.0 0.5 0 0 10 20 P = POWER p = 1.0 0 = 0.1 AO =-8.81 D =FRACTIONAL INSERTION OF BANK 0 AO =AXIAL OFFSET 30 40 50 60 70 80 PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM 90 100 PUBLIC SERVICE ELECTRIC AND GAS COMPANY Typical Axial Power Shapes Ocurring at Beginning of Life SALEM NUCLEAR GENERATING STATION Updated FSAR Fig4.3-8 REVISION 17 OCTOBER 161998 a: w 5: c w 2.0 1.5 N 1.0 ..J <( :i: a: 0 z 0.5 0 0 10 P =POWER 0 = FRACTIONAL INSERTION OF BANK 0 AO =AXIAL OFFSET 20 30 40 50 60 70 80 PE'RCENT OF ACTIVE CORE HEIGHT FROM BOTTOM 90 100 PUBLIC SERVICE ELECTRIC AND GAS COMPANY Typical Axial Power Shapes Ocurring at Middle of Ufe SALEM NUCLEAR GENERATING STATION Updated FSAR Fig4.3-9 REVISION 17 OCTOBER 16 1998 a: w 0 2.0 1.5 1.0 _, c :E a: 0 z 0.5 0.0 0 10 P=POWER 0 = FRACTIONAL INSERTION OF BANK 0 A.O. = AXIAL OFFSET 20 30 40 50 60 70 80 PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM 90 100 PUBLIC SERVICE ELECTRIC AND GAS COMPANY Typical Axial Power Shapes Ocurring at End of Life SALEM NUCLEAR GENERATING STATION Updated FSAR Fig 4.3-10 REVISION 17 OCTOBER 16 1998 2.8 .....-------------------, 2.6 2.2 -CORE HEIGHT fQ LIMIT 01 2.40 6' 2.40 12' 2.22 1.6 1.4 1.2 1 0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (ft) PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION REVISION 17 OCTOBER 16 1998 Maximum Fa* Power ve Axial Height During Nonnal Operation Updated FSAR Figure 4.3-11 20 15 5 0 -50 (j) 0 -25 0 25 REVISION 17 OCTOBER 16 1998 PUBLIC SERVICE ELECTRIC AND GAS COMPANY Peak POW'el' Density During Control Rod Malfunction Overpower Transients SALEM NUCLEAR GENERATING STATION Updated FSAR Fig 4.3-12 20 15 10 5 25 0 Q) 0 25 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION REVISION 17 OCTOBER 16 1998 Peak Linear Power During Boration/Dilution Overpower Transients Updated FSAR Fig 4.3-13 0.759 o. 792 "* 3*" o.nu. I. 255 o.aoo 1.21.1.9 3.14"' -O.S" 1.229 I. 225 -0.3" I. 109 I. 077 '* 107 1.092 -0.2' '* \1. I. 202 -'* 170 -2. 7** 0.523 1.217 '* 22.1 o. s .. a 1.203 1.233 U..6"' I. '.o .. I. 229 I. 189 -3. J** I. 2 17 I. 221l 0.6-I. 229 I. 218 -o.:v I. 223 1.2S6 2.7r I, 229 1.220 -0.7" I. 217 I. 211 -o.s* I. 217 I. 210 -0.6. ..,...___ CALCULATED ..,..__ MEASURED ......,_ D I FF£REMCE PEAKING FACTORS 1.5 1.357 2.07 LOCATED AT M-8 SOUTH PUBLIC SERVICE ELECTRIC AND GAS COMPANY Comparison Beetween Calculated and Measured Relative Fuel Assembly Power Distribution SALEM NUCLEAR GENERATING STATION Updated FSAR .. Fig 4.3-14 REVISION 17 OCTOBER 16 1998 Q .... -"" """ "' X & ...... -.... "" -....... ... Cl Q za: ......... _,;az CIQ<C 0 N 0 --3AI1Y13H 1YIXl REVISION 17 OCTOBER 161998 PUBUC SERVICE ELECTRIC AND GAS COMPANY Comparison of Calculated and Measured Axial Shape SALEM NUCLEAR GENERATING STATION FSAR Fig 4.3-15 0 0 0 * *

• 0
• 0 \, 0 :x REACTOR I 0 REACTOR 't:J REACTOR 2
• REACTOR 5 e REACTOR 3 FQ 3.0 2. s 0 *
• i'. X 0 oo *50 -liO 30 -25 *20 10 -S 0 5 10 15 20 25 30 INCORE AXIAL OFFSET {r.} REVISION 17 OCTOBER 16 1998 PUBLIC SERVICE ELECTRIC AND GAS COMPANY Measured Values of Fa for Full Power Rod SALEM NUCLEAR GENERATING STATION Configuration Updated FSAR Fig 4.3-16 u.. 2.... E -1.5 8. !Z w (j u: -2.5 u.. w 8 -3 ::;) i Ji w .... ex: -4 8: 8 -4.5 . . .. .. -.. . ---* *
• BOL --EOL ------500 600 700 800 900 1000 FUEL TEMPERATURE (°F) 1100 1200 REVISION 17 OCTOBER 16 1998 Doppler Temperature Coefficient at BOLand EOL PUBLIC SERVICE ELECTRIC AND GAS COMPANY (Typical) SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 4.3-17

-... CD a. .... c CD e CD a. -E u a. z w -LL LL w 0 u lr: w 0 a. lr: w .J a. a. 0 0 12 . ::.---14 --16 . ' . . . 20 1--22 . . -24 / . ,.* -26 .. -28 0 ------------------....... "' ...... ---.. .. . . .. ... ---... , .. .. ,. .. ---... --. . . --. -. . . . . . . ' . . . . --.... -**-........ .. ........ ---. . . _ .... -'" . -. . / . . / . ' / ' I / . I / . / . . / . . / . 1 ---BOL -, . / . ******MOL . / -* *-EOL I . I I 10 20 30 40 50 60 70 80 90 100 POWER LEVEL (percent of full power) REVISION 17 OCTOBER 16 1998 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Doppler Power Coefficient

• BOL, MOL, EOL (Typical) Updated FSAR Figure 4.3-18 1',':\ 'C l c CD ! e 8. fd u. -200 -400 -600 --800 -1000 .. 0:: I 0:: w ..J A. A. 8 -1200 -1400 r-1--1600 -1800 0 * :!>,. \ *::-... .' \.'*' ... ' ' ' ' \ *. ' . . ' . '. ' \ . . ' . ' ' ' '* '. ' . ' . ' . ' \ . ' ' ' . ' ---BOL --.. **MOL -**-EOL . 10 20 30 . ' ' ' \. 40 . ' \. ' . 50 ' ' . ' ' ' ' ' . . 60 ' ' . ' ' ' ' ' ' ' . ' ' . . 70 ' ' ' . ' . . ' ' ' . . ' . *. . . ' 80 . ' ' ' ' . . ' . ' . . ' . . ' 90 ' ' . ' . . . . ' . . 100 POWER LEVEL (percent of full power) PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION REVISION 17 OCTOBER 16 1998 Doppler Power Defect
• BOL, MOL. EOL (Typical) Updated FSAR Figure 4.3-19 u::-0 e 8. 10 z I&J g LL. LL. I&J 0 -0 (.) ::1 i -:& I&J 1-a: I&J -20 ... Q 0 :& -===--..... -----....... ----. ---. -. . . ---=:::----.... . ---........ __ --., ......... -.. .. --2000ppm --1500ppm -* -1000 ppm --500ppm --Oppm ...... .. .. .. .. ' .. ' ' ...... \ ' .. \ ' .. .. ' ' \ .. ' \ ' .. \ .. '*' ' \ ' \ ' Jl: 0 100 200 300 400 500 600 MODERATOR TEMPERATURE (*f) PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION REVISION 17 OCTOBER 16 1998 Moderator Temperature Coemcient
• BOL (Typical) Updated FSAR Figure 4.3-20 u:-i u 0 a. z w y I.L I.L -10 0 w 0: ::::>> i -20 :IE w ..... 0! i w -30 c 0 :E .. .. * *
• 500 ppm, Unrodded ' --0 ppm, Unrodded --o ppm, Rodded 0 100 200 300 400 500 600 MODERATOR TEMPERATURE (°F) REVISION 17 OCTOBER 16 1998 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Moderator Temperature Coefficient-EOL (Typical) Updated FSAR Figure 4.3-21

-u.. 0 e u a. -.... z w 0 u:: u. w 0 0 w a::: :::J i w 11. :::& w .... a::: 0 .... w c 0 :E 5 . .,. .,..,. .,..,. ,..,. ..,.,. .. 0 """""-,. .. """"" ,. .,. ... ... """"" .. """"" .. .. """"" .. / """"" .. "" .. """"" .,. / ';,;"" "" .. ,. ., / .. ... ,. .. / ., -10 !-.. .. ., / ,. .. ., .. / ,. ., ., , / -15 .. .. 68 °F # .. / "' -350 °F .. .. -/ II' --.. 547 °F -20 / .. -.. 575 °F / , / -25 , ,/ 0 500 1 000 1500 2000 SOLUBLE BORON CONCENTRATION (ppm) REVISION 17 OCTOBER 161998 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Moderator Temperature Coefficient as a Function of Boron Concentration -BOL (Typical) Updated FSAR Figure 4.3-22 Li:' !L -10 E u CL -.... z w 0-15 ii: u.. w 0 (.) ::::. -20 i w a. :1 w .... -25 ct: UJ c 0 *30 :1 0 5000 10000 15000 BURNUP (MWD/MTU) 20000 REVISION 17 OCTOBER 16 1998 PUBLIC SERVlCE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Hot Full Power Moderator Temperature Coefficient vs Cycle Bumup (Typical) Updated FSAR Figure 4.3*23 10 ; -12 0 !-14 c CD Co) ;s -16 Q. -e 8.-18 -..... z Y:! -20 CJ LL: u. w -22 0 CJ m -24 Q. -26 _, :! 0-28 ..... 32 0 SOL --------------...,......... . .... ---* --.. -. . . .. ........ .. -*-.-1--1900PPM --1600PPM * *

• 1300 PPM -* 900PPM -* 600PPM , ...... .,._300PPM * <<
• 0 PPM , , , * , X ,. 20 . -.. -*---___ _,. --*----, ,. .. 40 .. -**--*-----,-' , . -...... ., .X .. '"X *
• EOL 60 80 100 POWER LEVEL (percent of full power) REVISION 17 OCTOBER 161998 Total Power Coefficient* BOL, EOL (Typical) PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 4.3-24

-200 -400 -600 --800 E u a. -t--1000 0 w u. -1200 w Q a: w -1400 a.. -1600 -J .c .... 0 -1800 .... -2000 -2200 -2400 -2600 0 t---1900 PPM --1600PPM * *

• 1300 PPM -... 900PPM -* 600PPM J......j-JOQPPM * <<
• 0 PPM 20 40 60 80 100 POWER LEVEL (percent of full power) REVISION 17 OCTOBER 16 1998 Total Power Defect* SOL, EOL (Typical) PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 4.3-25 18 18 KV \fj 9 & [g 'fl [9 \fj 0 0 [9 0 & K;) 'J 0 & 0 f0 0 9-(g '¢1 6 9 kS> 9 <8> 0 0 NUM8ER OF FUNCTION ROO CbUSTE AS SHUTDOWN BANK SA 8 SHUTDOWN SANK sa 8 SHUTDOWN BANK Sc*5o 4&4 CONTROL BANK A 8 CONTROL BANk 8 4 CONTROL BANK c 8 REVISION 17 CONTROL SANK 0 9 OCTOBER 161998 PUBLIC SERVICE ELECTRIC AND GAS COMPANY Rod Cluster Control Assembly Pattern -Unit 1 SALEM NUCLEAR GENERATING STATION Updated FSAR Fig 4.3-26A

!0 0 r*j!l t. ., IY'cl* u.,:.,t @ w 15} @ (5} ,, .. L .. 5) I& & 10 * & IW (j) K!) *) w & lf" *) 6 151 0 . ' ls.RJ @ <D rf.1 I (!61 . . ,,..., .. 1 ..... ew;*1* * *ww .... 1ft1h1CIP" I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I IHIItMwl ..-* . ...,, .... ' mii'IOJIII liriiK

• c .. Chll& Uilrl 1111 1 CtaliJI6L ...... &. I CatiiiCL *w (i) * (!)
• _ _j Rev1s10n 22, May 5, 2006 PSEG Nuclear, LLC Solem Nuclear Generat'1ng Station ROD CLUSTER CONTROL ASSEMBLY PATTERN -UNIT 2 SALEM NUCLEAR GENERATING STAT ION Updated FSAR Figure 4J-26B © 2000 PS£G llC. All Rights Reserved.

50 -Q.. """ "0 .... V) -z u A. -= 30 ..... a: Q Q a: ...... 20 -c .... z ...., a: ...., "'-"'-10 Q 0 0 50 100 ISO STEPS WITHDRAWN 200 250 REVISION 17 OCTOBER 16 1998 Accidental Simultaneous Withdrawal of 2 Control PUBLIC SERVICE ELECTRIC AND GAS COMPANY Banks EOL. HZP, Banks 0 & 8 Moving in the Same Plane SALEM NUCLEAR GENERATING STATION Updated FSAR Fig4.3-27 -z -z 0 .... en 2 160 ISO 130 120 110 100 90 80 70 60 50 30 20 10 0 .2 *" .6 .8 1.0 1.2 1." 1.6 1.8 2.0 2.2 2.1+ 2.6 TIME OF TRAVEL (SECONDS} REVISION 17 OCTOBER 16 1998 PUBLJC SERVICE ELECTRIC AND GAS COMPANY Design Trip Curve SALEM NUCLEAR GENERATING STATION Updated FSAR Fig 4.3-28 1.0 ::1: ..... IS -,... ..... -> -.... u .eo c = ..... N ..... I o .. OI\ao \ 10 "' r----.... 10 ROD Jos IT f&. (P!ltcENf I NSe:frED) 28 1 0 0 REVISION 17 OCTOBER 16 1998 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Normalized Rod Worth vs Percent Insertion All Rode But One Updated FSAR Figure 4.3-29 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION "' .... c *---' -"' 7'--. 0 0 -:> ** .... C> 0 c -= ' f c-... ::;; -I Cl .... Oc,:,ro. -= .. C 0 N,...... -::: .f'l't N ... _ REVISION 17 OCTOBER 16 1998 Axial Offset vs Time -PWR Core With a 12-Ft height and 121 Assemblies Updated FSAR Fig 4.3-30 10 "t't 8 -::1" 1-6 K c 0::: " 0 c g. 2 N 1-0 z:: c 0::: 0 c -2 ::::1 o-....., -" u z: w a:::: w -6 .... .... 0 l--8 ....J ....... ....... -10 :z: c a:::: :l Ill -16

• 0 * * * * * * * " ST.l81LITY IMO£X: -0.076 (HM.-I j RCC E *ll 8 12 16 20 2" 28 32 36 168 S2 56 60 6" HOURS AFTER WITHORAWAL OF RCC E-1 I REVISION 17 OCTOBER 161998 -* -XY Xenon Test Thermocouple Response PUBLIC SERVICE ELECTRIC AND GAS COMPANY Quadrant Tilt Difference vs Time SALEM NUCLEAR GENERATING STATION Updated FSAR Flg 4.3-31 I -!=> 0 0 0 -§ I e 8 DOPPLER COEFF I C I EMT { pcm/' p ) I I I w .c !=> ? ? 0 0 0 I "" ? 0 C>o n,...,=n .. ,. Q 0 ,... .,
• z (""')-0--= or: "" ::.:> --0 ... :: r"'\ ,.---0 -"' % .., -.::: "' "" ..... . ,.., -0 0 ;; "" -2 l t I 1 i t I 0'> <= 0 C' 2 h.) ""' C"' = 0 c (5 8 8 8 8 § IHTEGRAL DEFECT (pcm) I Cl'l ? 0 REVISION 17 OCTOBER 161998 Calculated and Measured Doppler Defect and PUBLIC SERVICE ELECTRIC AND GAS COMPANY Coefficients at BOL,Two Loop Plant, 121 Assemblies SALEM NUCLEAR GENERATING STATION 12-Ft Core Updated FSAR FIG.4.3-32 1200 1000 800 &. Q. I3CI <...> 600 200 CALCULAI£0 / 0 0 2000 6000 8000 I 0000 12000 I 16000 18000 BURMUP. t.ftiO /MTU PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION REVISION 17 OCTOBER 16 1998 Comparison of Calculated and Measured Boron Concentration for 2-Loop Plant, 121 Assemblies, 12*Ft Core Updated FSAR Fig 4.3*33 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION 0 0 ..r> = :::l )-0 0 -<1:1 Q <"') l Q.. :::l &! 8 :::l ,..... N REVISION 17 OCTOBER 161998 Comparison of Calculated and Measured C8 2-Loop with 121 Assemblies, 12-Ft Core Updated FSAR Fig 4.3-34

= ..... =: ; .,. .. 'i Hdd *SJ PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION 0 :c _. ; ...., -' ... u 0 0 0 c 0 ("'3 0 0 0 N 0 0 0 8 8 8 c:J') §;:) Q § i . "a.. ;:) IDcr::l 8 0 t.rl 0 0 0 :'1' 0 8 <"") g N § 0 REVISION 17 OCTOBER 161998 Comparison of Calculated and Measured C *3-Loop with 157 Assemblies, 12-Ft Core 8 Updated FSAR Fig 4.3.35}}