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

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4-1 to 4.4-17

ML17046A343
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: ML17046A343 (21)

Text

3000 2500 AVEAAGE 2000 -.... 1500 * -""' ! .... ""' -_. 1000 '5 .... -----. ----------\__ SURFACE 500 0 2 * '

• 10 12 1* 16 18 20 Z2 LltitAR POWER {IUUFT) R 18 A l 26 2000 BVlSlOn I ' .?glem PSEG Nuclear, LLC PEAK FUEL AVERAGE AND SURFACE MPERATURES DURING FUEL ROD LIFETIME VS. LINEAR POWER FOR STANDARD SALEM NUCLEAR GENERATING STATION FUFL Updated FSAR Figure 4.4-1 CD 200J PS[G Nucle<r, llC. lll Ri\flts Reserved.

u: * -w a::. :;:) .... w D. :I w .... ..J w :;:) ..... 3000 ..-----------------------..., AVERAGE 2500 2000 1500 SURFACE 1000 500 __________ 0 2 4 8 PSEG Nuclear, LLC 8 10 12 14 16 18 20 22 LINEAR POWER (KWIFT) Rev1s10n 18, A nl 26, 2000 Solem Nuclear Generating Station PEAK FUEL AVERAGE AND SURFACE TEMPERATURES DURING FEUL ROD LIFETIME VS LINEAR POWER SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 4000 3500 -w. tt. ..... a: 3000 ::::>> .... <II( a: ..... a. ..... """' 2500 ..... z ..J a: w.; .... z 2000 w "' ..J ..... :;) ... 1500 1000 __ ._ __ 0 2 4 I I 10 12 tA 11 18 20 22 LINEAR POWER (kw/ttt R 18 A 1 26 2000 ev1s1on , 1pr1

• Solem Nuclear GenerotinRt Station PSEG Nuclear, LLC PEAK FUEL CENTERLINE TEMPERATU DURING FUEL ROD LIFETIME VS. LINEAR POWER FOR STANDARD FUEL SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 4.4-2 ({) 2(XX) PS£G lilcle<r. LLC. All Ri1!ts Res!rved.

3500 -.. * -:::::1 3000 ... ;I w m 2500 ! w ... z 2000 w CJ ..J w :::::1 "" 1500 1000

• 10 12 1.& 11 11 20 22 0 2 UNI!AFl POWER (KWIFT} R 18 A 1 26 2000 ev1s1on , -tprl ' Solem Nuclear Station PSEG Nuclear, LLC PEAK FUEL CENTERLINE TEMPERATU DURING FUEL ROD LIFETIME VS. LINEAR POWER FOR VANTAGE*5H FUEL SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 4.4*2A © 2000 PSEC Nocle<r. LLC. All Re&ned.

"'ft:D :D-e!! )>0 :DZ <G .... .9' i

• c: '8. I>> i ., (I) > :a .,. ?i ,.. * * "0 c: (1)1:0 >I"'" .-c; m(l) S:m z:a c:< n-.-n mm >m :al"" m-1 z:a m-:an >> -tZ zo C)Q (I)> -1(1) >0 s: o., Z];o 2 < -1 ::r ell ... 3 !. (') 0 co::s eng. *a -t ;r ::r -* ;: a l:!'. c: lo oN II>-:I c !'!\ I>> """n Sl 0 1600 ?000 liOI} 800 24.00 2800 noc ;: a a. TFMPERATURE {°C) .. 0

• *

• 0 a> ::; 0 .... Q <.:> "' z <0 ;; 0 w "" ...... 0 1.0 ci ::::: -<.!) z w -J 0 0 1,() a:: ci ....... 0 .z: 1-u ::7 ..:: 0::: 0 ..... ('P) ci 0 {Jo) OVl) PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Axial Variation of Average Clad Temperature for Rod Operating at 5.43 KW/FT Updated FSAR FIG. 4.4-4 REVISION I FEBRUARY 15, 1987

• ""' .... .... I Cl: = -= -... .,0 * -0 """ Cl: = .., ..

• w -w.. = *Co.J 0'

• 1.2 t .o 0.8 0.6 o .* 0.2 0 0 / -23 0 ,,. fYPICAL CELL*UIIIFORM WALL I' fYPtCAL C£LL*UIIFOitM VALL 0 t** COLDWALL*IIOIIIJIIFGitM WALL Q ita" TYPICAL CELL*IIOIIUIIIf'OIM WALL 0.2 0., 0.6 0.8 '.o 4. CHF (PREDICTED) X 106 8TU/HR-FT2 1.2 PUBUC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION

• COMPARISON OF MEASURED TO PREDICTED 1 7 x 17 DNB DATA Updated FSAR Revlaion 11, July 22, 1991 Sheet 1 of 1 Fig. 4.4-SA

• { t.Z

• IC t.t E -1.0 i 0.8 ... io.a 5* E o.7 c : o.e .. c = 0.1

• loA !o.a .. ,. o.z .. .... ... z 0.1 .u s 0 0 0.1

• 0.2 + + * '\.

• II% OF DATA WIU. FALL ABOVE THIS UNE WITH IS% CONFIDENCE. 0.3 0.4 0.1 o.e 0.7 0.1 o.t 1.0 1.1 1.2 1.3 W"CHplto'J M!DICTED CRmCAL HEAT FLUX C8TUIHR*,.,Z, PUBUC SERVICE ELECTRIC AND GAS COMPANY SALEM Nucu:AR GENERATING STATION MEASURED VS PREDICTED CRmCAL HEAT FLUX* WR&-1 CORRELATION Updated FSAR Revision 11, July 22, 1991 Sheet1 of1 Fig. 4.4-SB 1.10

• 1/ 1.00 N t: 0.9(t I I -:I O.RO --... :I 0.70 _, .... .... c 0.60 * ... / I *7. / -.. v . 'J .... * " ,I-'-ts/95* a. 50 -. c 0.40 ! 0.30 0.20 .-C) 0.10 . ..., e ., v "' *951 of dltl .n fl11 1 bon this ltnt with 9U v confldenc:e. 0.00 l o.oo 0.10 0.20 0.30 0.40 0.50 0.60 0.10 0.80 0.90 1.00 .10 (QCHfll06)Pim. PUDlCTED CRITICAL HtAT n.ux (8TU/HR-fr2l R 18 A 1 26 2080 ev1s1on , iprl ' Salem Nuclear Generatint Station PSEG Nuclear, LLC MEASURED VS. PREDICTED CRITI PJ.. HEAT FLUX WRB-2 CORRELATION SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 4.4-5C CD l[XX) PSEG Nucle<r, LLC. All Ri1Jts Reserved.

• :1.1 Q) ", V'l ttl s::. .s:: Cl.. c.. I I ...-N co <..? X .z 0 ::r:; 0 u ..., ""' ""' <1.0 Cl. a.. ...... (/') en ...J * * <D t,O C'4 c..... 00

• I ) I N 0 <lO 0 0 0 0 0 ci :>01 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION

• 0 0 0 OOQ) 0 '2J or&> s'& oo> oo ro 0 I I :::r N 0 0 0 0 0 <lO 0 -r-0 !..0 0 -:::r 0 -(") -0 N -0 0 0 ..n

• 0 -Q) TDC vs Reynolds Number for 26" Grid Spacing Updated FSAR FIG. 4.4*6 REVISION 6 FEBRUARY 15, 1987

• I I G. 1.086 1.001 . 1--1.020 1.111 1.001 1.001 I 1.145 1.066 1.178 1.000 1.001 1.000 I 1.160 1.203 1.157 1.183 1.000 1.000 1.001 1.000 I 1.220 1.167 1.185 1.065

• 1.000 1.001 1.000 1.002 I 1.125 1.161 1.094 1.088 1.001 1.001 1.002 1.002 I I 1.028 1.028 0.994 0.980 1.002 1.002 1.002 1.002 0.720 0.785 0.667 0.566 0.999 0.999 0.998 0.997 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION

• KEY: -GIG 1.242 1.000 0.921 0.975 1.001 1.001 0.829 0.469 1.000 0.997 FOR RADIAL POWER DISTRIBUTION NEAR BEGINNING OF LIFE. HOT FULL POWER. EQUILIBRIUM XENON CALCULATED FN = 1.35 Normalized Radial Flow and Enthalpy Distribution at 4-Ft Elevation Updated FSAR FIG. 4.4-7 REVISION I FEBRUARY 15. 1987

• I 1.086 ---0.996 I 1.017 1.111 1.002 0.994 1.147 1.064 1.181 0.991 0.998 0.988 I 1.163 1.206 1.160 1.187 0.990 0.986 0.990 0.998 I 1.225 1.170 1.188 1.065 0.985 0.989 0.988 0.998

• I I 1.128 1.165 1.096 1.088 0.992 0.990 0.995 0.996 I I 1.027 1.028 0.993 0.978 1.000 1.000 1.003 1.004 I I 0.718 0.782 0.666 0.565 1.022 1.019 1.021 1.019 I J PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION

• KEY: --!-!-Doh/Doh !-GIG 1.246 0.981 0.921 0.971 1.009 1.006 0.825 0.471 1.018 1.018 FOR RADIAL POWER DISTRIBUTION NEAR BEGINNING OF LIFE, HOT FULL POWER, EOUI LIBRIUM* XENON N = CALCULATED F D.H 1.35 Normalized Radial Flow and Enthalpy Distribution at 8*Ft Elevation Updated FSAR FIG. 4.4-8 REVISION 6 FEBRUARY 15, 1987

• I I 1.087 -I-0.995 *I-I-I 1.017 1.112 0.999 0.993 I I 1.149 1.065 1.182 0.991 0.996 0.989 1.164 1.209 1.161 1.188 0.990 0.980 0.991 0.990 1.228 1.172 1.190 1.066

• 0.987 0.990 0.989 0.997 I 1.129 1.165 1.096 1.089 0.993 0.991 0.995 0.996 I I 1.026 1.027 0.991 0.976 1.000 1.000 1.002 1.003 I 0.714 0.779 0.663 0.563 1.016 1.013 1.019 1.025 I PUBLIC'SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION

• KEY: 1--I-.1h/.1h 1-GIG 1.247 0.987 0.919 0.969 1.005 1.003 0.823 0.472 1.011 1.030 FOR RADIAL POWER DISTRIBUTION NEAR BEGINNING OF LIFE, HOT FULL POWER, EQUILIBRIUM XENON N = CALCULATED F aH 1.35 Normalized Radial Flow and Enthalpy Distribution at 12-Ft Elevation (Unit 2) Updated FSAR FIG. 4.4-9 REVISION 6 FEBRUARY 15,1987

• *

• Jonnll3dW31 NO llY!l nns s -:v oo 3 3!!01V!l3dH31 Oln0i1 AdlVHlN3 :nne NO 0 I OA <.::> z: ...J 0 (X) -' ... <..> 0 -' z 0 ;:; ....... a:: z: 0 <.:) ..... a: ,_ % .... X '-' :r _. <...> a> "" "" .... ::> ..... a> Q ,_ ..... ::0:. -' ...... <D X ""' ;::; ;;;;) "" ... .... 0 ... z 0 X 0 a:: ::: ..... 1-Q :a .., ,_ > <...) ... Q _. ..... <l g:g 0 .... .... <I') :z: I ... :z: -:;( en :z: I :z: " X >-!.:::: ...J <( c-<..) :% < z: >-Q 0 X 0::: w ::z:: 1-PUBLIC SERVICE ELECTRIC AND GAS COMPANY Void Fraction vs Thermodynamic Quality H*HsAr/Hg"HSAT SALEM NUCLEAR GENERATING STATION Updated FSAR FIG. 4.4-10 REVISION& FEBRUARY 15.1987

• *

• 0 ..... 0 .., ..... "" ... :::> <> .,. .... "" ... ..... -' 0 0 .:!0 'A 19W3SSV 1 V' ..... "" ..... ,_ -' co :::!: .... "' "' ..... ... ""' :::> 0 ..... .... < ""'""' = ..... Q = .......... ::o -' .., :z :z X -< <!t r ..., -z Q ... ..... -"" ..,. 0::0: ..... 0 u ._, 0 0') 0 (lQ 0 "" 2 >< -;::) 1-co a:: L.I.J 0... >-...J a=> :::£ w (I') (I') <t PUBLIC SERVICE ELECTRIC AND GAS COMPANY PWR Natural Circulation Test SALEM NUCLEAR GENERATING STATION Updated FSAR FIG.4.4-11 REVISION I FEBRUARY 15, 1987

• *

• 0 .... a:: w 0 Q. . .,. .

• LO 0) 8i I ..... 0) "' C") Cl() oO en 0) igJLZ LO !"CQO LO LO Ln CD ........ a:: w 0 en ,... 0 .... ;!! <'i C") (¥) (¥) m 0 ..... Cl() Cl() = en Q. z ., .. ::;,0' ..... en 0 C") "'t "'t LO LO 0 a:: z z w ODO<lOt> c:J w ...J Cl() (I) C'! .... .... s i .t! 'ii ""': E .. . 0 ..5. ....

• a: w .... Q. > ...I al :E w (1.) (1.) 0 <( w > <( = ...I 0 w a: 0 w a:: ::> ..... (1.) 0 <( w ::E o-* c.o 0 t> LO "'t N 0 N ,.ci I ' ( w '3 J. -d '3 l.)' 03UnS'V'3W-3UnJ.VU3dW3J. J.IX3 A 18W3SS'V' 03.101031-Jd PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Comparison of a Representative W Two-Loop Reactor lncore Thermocouple Measurements with Updated FSAR THINC-nz Predictions FIG. 4.4-12 REVISION 6 FEBRUARY 15, 1987

• *

• C::i ...... 0 . . 0 :II: OD<l Ot> -l 0 0 0 D N 1 [><] D 0 <Je ::I" * -0 0 LU N -J O< *:::E -0:: 0 z :Jo '(W'3l_d'jl) 'SA 1IX3 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Comparison of a Representative W Three-loop Reactor lncore Thermocouple Measurements Updated FSAR With THINC* DlPredictions FIG. 4.4-13 REVISION 6 FEBRUARY 15, 1987

• *

• 90 80 -L.L.. 0 .. I.U "" a:: A I.U A a:: 0 :::::. 1-0 << a:: A I.U a.. 1-RUN 70 LEGEHD: 0 Q MEASURE!> ATHINC*IV 60 r I 0 10 20 30 SUBCHAHi1.t:.l POWER OEHS I TY, 106 BTU/HR-FT3 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Hanford Subchannel Temperature Data Comparison With THINC-Ill Updated FSAR FIG. 4.4-14 REVISIONS FEBRUARY 15,1987

-n:D ID!2 :lD-c!e ,.o :lDZ <* .. "' ! * "'0 c (l)al )>I"" .... -mn z:O c< o-.-o mm l>m , .... m-t z;,:, m-,n )>l> -tZ ;zo C)C> c:nl> .... (I) )>0 -tO -3: 0"'0 Z)> z < :z: Ill :I :a a. '1:1 en Ill s: a* g 0 .. :I ;:; :e -* ... g, ::r-1 .... til :z:3 _, z!!l "a iii 0 a 1111. ...... 0 UJ (/) 111.0 120 0:::100 UJ 0::: 0::: U.J Q.. :::E: w 1-80 0 UJ ex: ;::::) (/) ""' w X 60 '10 '10 * , , ,. , , , , , 60 80 100 120 PREDICTED TEMPER.HURE RISE, °F 1'10

• PRfSSUR£ 20 ill r S I A f*IASS I LOw RflO 01 Am I fR ' ') o. !>-z. 2"( lu0ts/mll ROIJ PI TCII ltlAJ£0 UNGrti HlAT rLUX OISJRI6Ul10N INCtHS IN(HfS 811 INCHES INHrR ROO: OUrFR ROO 1.2011: 1.0 TC-THERMOCOUPLE LOCAIION

• R P N M L K J H G FED C B A i 0 [!] 0 0 [!] 0 9 [!] 0 [!] 0 0 0 [!] 0 [!] 0 0 [!] [!] 0 0 0 0 0 [!] [!] [!] [!] 0 0 0 0 0 [!] 0 9 [!] [!] [!] [!] [!] 0 0 mi [!] [!] 0 [!] 0 [!] 0 9 0 0 [!] [!] [!] [!] 0 0 [!] e 0 [!] 9 0 [!] [!] [!] 0 IC!J 0 9 0 [!] [!] 0 [!] [!] 0 [!] 0 [Q) THERMOCOUPLE LOCATION ******* __ ** __ ** 58 (!] INCORE DETECTOR LOCATION __ ** _ ******* 58 (Q] FLOW MIXING DEVICE LOCATION *..*..... 52 2 0 3 4 [!] 5 [!] 6 [!] 0 7 0 [!] B [!] q 1121 0 11 0 12 9 13 14 15 THERE ARE 58 LOCATIONS DESIGNATED AS THERMOCOUPLE AND INCORE DETECTOR LOCATIONS. THE MINUMUM NUMBER. OF FLUX THIMBLES AND THERMOCOUPLES IN USE, AS WELL AS THE MIIMUM NUMBER PER QUADRANT, IS CONTROLLED *ay THE TECHNlCAL SPECIFICATIONS. PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STATION Solem Nuclear Generatin_g_ Station DISTRIBUTION OF INCORE INSTRUMENTATION UNIT 1 Updated FSAR Figure 4.4-16

• R P N M L K J H G FE 0 C B A I 0 j' 0 ' [!] [!] 0 0 [!] [!] ' 0 e 0 [!] 0 0 ' 0 (!] 0 [!] 0 [!] 0 [!] 0 0 0 0 [!] 0 [!] 0 0 0 [!] 0 0 [!] 0 [!] [!] [!] 0 [!] 0 [!] 0 0 [!] 0 [!] 0 [!] 0 0 0 0 [!] 0 [!] e 0 [!] [!] 0 0 0 [!] 0 [!] [!] [!] 0 [!] 0 e 0 [!] [!] iO [!] [!] 0 [!] 0 (Q] THERMOCOUPLE LOCATION *************** 58 (!] INCORE DETECTOR LOCATION *******.**** 58 (Q]FLOW MIXING DEVICE LOCATION ********. 58 2 0 0 3 4 [!] 0 5 [!] 6 [!] 7 0 [!] 0 e 0 10 0 11 0 12 0 [!] 13 14 15 THERE ARE 58 LOCATIONS DESIGNATED AS THERMOCOUPLE AND INCORE DETECTOR LOCATIONS. THE MINIMUM NUMBER, OF FLUX . THIMBLES AND THERMOCOUPLES IN USE, AS WELL AS THE MINIMUM NUMBER PER QUADRANT IS CONtROLLED BY THE TECHNICAL SPECIFICATIONS. PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STAT ION ReV1s10n Dec. 6, Salem Nuclear Generotil)g Station DISTRIBUTION OF INCORE INSTRUMENT AT ION UNIT 2 Updated FSAR Figure 4.4-17