ML17046A354

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Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.2-1 to 5.2-24
ML17046A354
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/30/2017
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17046A230 List: ... further results
References
LR-N17-0034
Download: ML17046A354 (24)
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Text

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  • Standard ASTM Tensile Test Material: 304 Stainless Steel Temperature: 600°F 20 Strain, %
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  • r-5. 0 Material: SA 376 Tp 316 Cross-section: Hollow.:_Circular r 4.s Hoop Stress: Collapse // -........:.'-..// "'-'< _____ $ 4. 0 S /S "' 0.0 s y S /S = Faulted Conditions "'" t-3. 5 s y Design Limit "\."\. 3.0
  • o.o Curves S /S ;; 0.2 s y ""-{/ 1/ I I L 2. s II II Emergency \\ I I L 2.0 Conditions , 1.5 1.0 0.5 l 0 -2.5 -1.5 -0.5 0 0.5 1.5 2.5 3.5 Stress from Axial Force I Yield Stress
  • -o c rtJtD l>C l(i mrtJ :S::m 5.0 z::O cS 4.5 Ci(i ! rm mm l>, ::Om G>Ci m-t 4.0 (/) (/) mn <!.) :::0)> 1-< l>z 3.5 ::!o (/) 2G> "'0 0)> rl rtlrtl <!.) -!Ci *r-C 3.0 )> 0 :>< ::!s: o 2)> z :;.-, 2.5 -< *r-C (/) <!.) c '&. H 2.0 -DO ,.. "' Q. (/) (/) <!.) 'TI Ci H rtJ 0 l.S )> 3 (/) ::0 't) ;:;:;* 0 Ci :::1 1.0 0 co I :::1 "' !!. ('b 0 "' :::1 :::1 0.5 ::o I 0 (1) . "' 0 ... o<g rtJ I>> "::rl 0 < :::1 -3.5 Ci >>en !2. c:-J>O iii" XIZ 'El -(CD "' ... $1' .... 1.0 co ..... S /S s y S /S s y
  • Material: SA 376 To 316 Cross-section: Hollow-Circular Hoop Stress: 0.00 S y Faulted Conditions / / / -2.5 S /S s y 0.0 S /S s y Emergency Conditions 0.2 '\_ r**/ -1.5 7--7-y-T--7 / 7 / 7-"7-;::77;* Normal or Upset Conditions I -0.5 0 0.5 Limit \ 1.5 Stress from Axial Force I Yield Stress
  • 5.0 4.5 Collapse '*. 0 3. 5 3.0 2.5 -2. 0 \ 1.5 1.0 0.5 0 2.s 3.5
  • *
  • PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION -, 8 & c @\ \ r---F G REVISION 6 15. 1987 Reactor Vessel Stress Analysis Areas Examined Updated FSAR Figure 5.2-4
  • *
  • A 0 (INLET) E (OUTLET) PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Updated FSAR B & C REVISION 6 FEBRUARY 15, 1987 Reactor Vessel Stress Analysis Details
  • Upper Figure 5.2*5
  • * * ,. -e --,... .--E F G NOTE: THE POINTS CIRCLED IN THE SKETCHES REPRESENT THE GENERAL LOCATION AND GEOMETRY OF THE AREAS OF DISCONTINUITY AND/OR STRESS CONCENTRATION. PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Updated FSAR REVISION 6 FEBRUARY 15, 1987 Reactor Vessel Stress Analysis Details
  • Lower Figure 5.2*6 r** ----.. _. -**-.. I I ! I i -l.s i I iii u ! Ill 'li;j l£j { I\ I I I \ ! I I ' I J I I I I I x.: : '" I . ' "'i I I I ,I f gJ PSEG Nuclear, LLC SALEM NUCLEAR GENERATING SJ ATJON Revision 24 May 11, 2009 Salem Nuclear GenerotinR Station PRIMARY #10 SECONDARY HYD OSTATIC TEST STRESS HISTORY FOR THE CENTER HOLE LOCATION AREVA NP Model 61!19T SG (UNIT 2 ONL Yl Uvdoted FSAR frqure 5.2-7 <D 11m FSIC !U:Iecr, m. Ail Rijtts R!s<<wed..
    • = '1:1 Ill 0 ...I ! I UJ tn I I l l I I } Q. !<II F I t I 0 0 0 '<t M {\) PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STATION 0 E I I= a 1j (I) G) 0 Revision 24 May 11, 2009 Salem Nuclear Station PUNT HEATUP .AND l AOING TR>>lSIENTS CWITH STEADY-STATE PLATEAU) STRESS H!STORY FOR THE HOT SIDE CENTER HOLE LOCATION AREVA NP Model 61/19T SG {UNIT 2 ONLY) Updated FSJR Figure 5.2*8 © 21DJ PiC Huctea. UC. All Rifrt$

r I i I I I d; c( Cl) .... I 0:: LIJ I . ., lia lT;l 1.!2 'a. !J!l ! I I ' r-0 "" PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STATION I ! Revision 24 May 11, 2009 em c ear enera rmq_ a 1on lARGE STEP LOAD DECREASES AND LOSS Of FLOW STRESS HISTORY OF THE HOT SIDE CENTER HOLE LOCATION AREVA NP Modei61/19T SG (UNIT 2 ONLY) doted FSAR Fi re 5.2-9 Secondary Lower Shell Support .... . PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STATION INSERT SAS-4 Divider Plate Revision 24 May 11, 2009 Sotem Nuclear Station PRIMMY NID SECONDARY BOUN Y COMPONENTS SHEll LOCATIONS Of STRESS INVESTIGATIONS AREVA NP Model 61/19T SG (UNIT 2) ONLY I lJPdated FSAR fiqure 5.2-10 ID 1C(l} PS[G IU:IIllr. UC. All R t ts

  • *
  • 3000 2800 2600 2400 2200 (!') ....... (f) 2000 a.. w 1800 a: :::> (f) en 1600 w a:: a.. 1400 a w 1-1200 <( (.) ..... a 1000 z ..... 800 600 400 200 0 CURVE APPLICABLE FOR HEATUP RATES UP TO 60 *F /HR., FOR THE SERVICE PERIOD UP TO 8 EFPY AND CONTAINS MARGINS OF 10 *F AND 60 PSIG FOR POSSIBLE INSTRUMENT ERRORS. CRITICALITY LIMIT 60 80 100 120 140 160 180 200 220 240 260 280 300 320 INDICATED TEMPERATURE ( *F) REVISION 6 FEBRUARY 15, 1987 PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION Reactor Coolant System*Heatup Limitations for First 8 E FPY of Operation Updated FSAR Figure 5.2*11
  • 2800 2600 2400 2200 2000 1800 1600 (!) -Ul
  • l&J
  • Q: 1200 ::::> Ul Ul 1000 0.. 0 w 8QO I-< (.) 0 600 z ..... 400 200 0 CURVE APPLICABLE FOR COOLDOWN RATES UP TO 60Cif"l1iR.,FOR THE SERVICE PERIOD UP TO 8 EFPY AND CONTAINS MARGINS 0 101=" AND 60 PSIG FOR POSSIBLE INSTRUMENT ERRORS. COOLOOWN RATE (0f/HR) 0 20 100 100 MATERIAL BASIS: CONTROLLING RV LOWER SHELL (ASSUMED COPPER. RTNOT ORIGINAL. 15Gf' AFTER 8 EFPY,I/4T,I31F I/4T. 90F 200 INDICATED TEMPERATURE ( REVISION 8 FEBRUARY 15, 1987 Reactor Coolant System Cool down Limitations for PUBLIC SERVICE ELECTRIC AND GAS COMPANY First 8 EFPY of Operation SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 5.2-12 280
  • *
  • THIS FIGURE HAS BEEN DELETED PSEG NUCLEAR L.L.C. SALEM GENERATING STATION SALEM UFSAR -REV 19 SHEET 1 OF 1 November 19, 2001 F5.2-13
  • *
  • Nozzle Weld Weld Vessel Intermediate Shell 32-5/811 Weld Lower Vessel Shell Thermal Shield Weld "Core" -:r --+ 0.030 Stainless Sheath Spacers Charpy Specimen -... ....._ ____ Weld REVISION 6 FEBRUARY 15, 1987 PUBLIC SERVICE ELECTRIC AND GAS COMPANY Typical Surveillance Capsule Elevation View SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 5.2-14
  • VESSEL *
  • PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION THERMAL SHIELD REVISION 6 FEBRUARY 15, 1987 Surveillance Capsule Plan View Updated FSAR Figure 5.2-15
  • * * \* 75 in. j_ 7.50 in. 4.50 in. T 1 65 in. Bore 8-3/8 in.diameter with 3 keyways NOTE: The plates are bolted together with the bolts aligned perpendicular to the planes of the plates. PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION REVISION 8 FEBRUARY 15, 1987 Reactor Coolant Pump Flywheel Updated FSAR Figure 5.2*16
  • * * "Q c: (I) CO J>l ,-m(') s:(l) m 24 z::O c:< (')-,n mm l>m ::o' m-1 22 20 Flywheel OD 75 in. z::o m-:::0(') )>l> -IZ 18 zo Ci)G'l (I))> -I (I) )>0 s: o"Q Z)> 16 ("") 0 ..-i 14 X Tangential stress vs Flywheel Radius z < -M (I] 12 1500 RPM -Overspeed . c (I] R II> ... "' 0.. (/) QJ 10 ... ... Cll .., (I) l> 8 :::0 -n < :: ::r 6 "' !!. ("') ::r II> ;;; 4 1200 RPM ;;;* .... 2 c:r "' (") < "' -n =* r::: .. <II "TI:D 0 :D-4 6 )>0 :DZ 8 14 18 34 20 16 26 28 22 24 30 12 32 10 Radius, in. 36 U1 -" P' i .....

TOPHEAO LOWER HIAtl A lNG PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STATION &2 replacmsnt RVOHe are 'made1roma . toroll'lg. 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 I I I I I I I I I I I I I I _ _j Rev!Slon 22, May 5, 2006 Salem Nuclear Generating Station REACTOR PRESSURE VESSEL ASSEMBLY Updated FSAR Figure 5.2-18 © 2000 PS£G Nucleor, LLC. All Reserved.

  • * * -CORE ----..u. Nozzle Shel 1 8-042 2-Intermediate Shell 82402-2* 2 9-042 B240 3-... 3-042 Lower Shell 82403 -3 10-042 270° 180° -042C 3-042C NOTE: Relative to the midplane of the active core, the circumferential weld 8-042 is about 91.511 above the core r:tidplane and eire. welds 9-042 and 10-042 are 16.7" and 123.2" below the core oidplane respectively. PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION REVISION 7 JULY 22, 1987 Identification and Location of Beltline Region Material for the Salem Unit No. 1 Reactor Vessel Updated FSAR FIG. 5.2*19
  • *
  • Nozzle Shell 8-442 90° 84712-2 2-442A Intermediate 180° Shell B4712 CORE 84712-3 270° 9-442 90° 3-442A 84713-3 oo 180° Lower Shell 84713-1 84713-2 10-442 Relative to the nidplane of the active core, the weld 8-442 is about 92.1" above the core midplane and eire. weld! 9-442 and 10-442 are 16.7 and 123.2" below che core respectively. PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION REVISION 7 JULY 22, 1987 Identification and Location of Beltline Region Material for the Salem Unit No. 2 Reactor Vessel Updated FSAR FIG. 5.2-20 SALEM UNIT 1
  • SALEM UNIT :i .
  • REVISION 7
  • JUlY 22, 1987 PUBLIC SERVICE ELECTRIC AND GAS COMPANY Arrangement of Surveillance Capsules in the SALEM NUCLEAR GENERATING STATION Reactor Pressure Vessel Updated FSAR FIG. 5.2*21 1 PSEG Nuclear, LLC 'l'Htlf CAST UAD .
  • 3 Rev1s10n 18, Aprll 26, 2000 Solem Nuclear Generotin8 Station TUBSHEET AND SHELL J NCTIONS IMPORTANT STRESS LOCATIONS UNIT 1 MODEL FSG SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 5.2-22 © 2000 PSE:G Nucl e<r
  • llC. All R,!Jlts PSEG Nuclear, LLC 5! = EA 'iJ -= = --= g = Iii i I Iii I c *c *lr J. w = -§ 3 Rev1s10n 18, Apr1l 26, Salem Nuclear Generatin-(k Station SECONDAAY SHELL ftND ftNSITION CONE IMPORT ftNT LOCATIONS UNIT 1 MODEL FSG SALEM NUCLEAR GENERATING STATION Updated FSAR Fi9ure 5.2-23 CD 2000 PSEG NLCiet:r. llC. All R1¢ts RflSII"ved.

*---------.--------1---------* I n.v 'Olaed.'lllDd.o& wn* CI'Dil I I FIGURE 5 2-24 Tub481 Xaportant Stre** Locationa -On1t 1 tw\odJ.t F Et:, 8VlSlOn , 'tprl R 18 A 1 26, 2000 PSEG Nuclear, LLC Salem Nuclear Generating Station TUBES, IMPORT ANT STRESS LOCATIONS UNIT 1 MODEL FSG SALEM NUCLEAR GENERATING STATION Updated FSAR Figure 5.2-24 CD 200.l PSEG lUI eo-. tlC. All Res<<ved.}}

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