ML18085A293

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Sample Piping Stress Analysis Calculations & Pipe Support Re-Evaluation
ML18085A293
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Site: Salem PSEG icon.png
Issue date: 08/17/1979
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{{#Wiki_filter:! *'*-\\-:":'.-'> i \\--~- r .~. ) -~ ___,_... :........ _ ,.. e REPORT ON SALEM GENERATING STATION NO. 1 UNIT SAMPLE PIPING STRESS ANALYSIS CALCULATIONS AND PIPE SUPPORT RE-EVALUATION August 17, 1979 Public Service Electric and Gas Company P79 71 39 o30'r\\ so1201

J ( In response to NRC Bulletin 79-07 and information required for interim operation, we enclose results of our re-evalua-tion efforts on 138 sample stress analysis calculaions on 15 safety related piping systems as identified in Attach-ment E of presentation on.June 19, 1979. As r~quested by you, we are also including in our response, answers to specific questions you have subseguently informed us to be resolved. We have reviewed 138 sample stress analysis calculations on safety related systems using the new 3D (SRSS) 3 dimensional square root sum of the squares method) for combining seismic loads. The results of this.evaluation are -based on this ciiteria. Our summary and conclusions are *tabulated in attachments identified as Tables 2.1 and 2.2 Appendix. We have concluded, based on this reanalysis effort that the plant as designed and built would not cause a hazard to the health and safety of the public. P79 71 42

..... *-... *-*;:--~ ****-'- "i --* *. -*-** --~*-*.. *.. -~ *---~~-.,...:............. -.....,_ ___ "'- *-- *-- *- *-*-**--* *--- --..J.-** --~-------* ******"'**-.-~'**'-** r:**.. ~ ( \\* '-- .. ~--.. - REPORT SUBMITTED TO NRC RESULTS OF RE-EVALUATION.EFFORTS SAMPLE STRESS ANALYSIS CALCULATIONS NO. 1 UNIT SALEM NUCLEAR GENERATING STATION TABLE OF CONTENTS

1.

SUMMARY

AND CONCLUSIONS 1.1 Pipe Stresses - Re-Evaluation 1.2 Pipe Supports - Re-Evaluation 1.3 Results of Sample Evluation. 1.4 Classification of Supports 1.4.1 Long Term Fix 1.4.2 Short Term Fix. 1.5 Modifications

2.

Tabulation of Stress Results 2.1 Stresss Re-evaluation Summary 2.2 Summary of Original Maximum Stress (DBE) Large and Small Pipe

3.

Results of Pipe Support Re-evaluation 3.1 Tabulation of Results 3.2 Pipe Support Structure, Weld and Bolt Sizing Criteria 3.3 Procedure for Evaluating Pipe Supports 3.4 Interface with IE Bulletin 79-02

4.

Nozzle and Penetration Loadings 4.1 Summary of, Results 4.2 Criteria for Acceptability P79 71 40

I (

s.

Primary Coolant Pressure Boundary Piping

6.

FSAR Pipe Break Reanalysis Efforts 6.1 Results of Reanalyses 6.2 Pipe Break Location and Criteria

7.

Seismic Reanalysis Methods 7.1 Comparison between Old/New Methods (Seismic Analysis) 7.2 Seismic Anchor Movements B. NRC Bulletin 79-02 8.1 Implementation and Response

9.

Safety Related Piping Not Analyzed by Computers 9.1 Techniques used lb. Verification of "As Built" Conditions

11. Computer Code Verification 11.l Submission and listings of Computer Programs 11.2 NRC Bench Work Problems 11.3 Code Verification P79 71 41

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1.

SUMMARY

AND CONCLUSIONS 1.1 Pipe Stresses There were a total of 138 sample Stress Analysis Calculations on safety related systems which were reanalyzed using 3D SRSS method as requested. The samples were selected using guidelines established in our QA Manual instruction QAI No. 7-5 dated 2-21-79 a copy of which was included in our pre-liminary submittal to the Staff of the NRC. A tabulation of stress results shown in Table 2.1 indicates the system, calculation number and com-pares the original combined stress (by the algebraic summation) to the new combined stress (by the 3D ( SRSS method). None of the 138 calculations were overstressed. The code followed was B31.l Power Piping, 1967. As stated in the FSAR, piping for Salem No. 1 Unit was designed in accordance with this code. The (Design Basis Earthquake DBE) was run against (Op~ratng Basis Earthquake OBE) stress limits. Any calculations that exceeded OBE limits were evaluated and checked to ensure our compliance with the Code. In 1975 the calculations using DBE were rerun as a result of the input from the as built conditions. P79 71 43 1

.....,. j

1.

SUMMARY

AND. CONCLUSIONS (Continued) Tabulation of original maximum stress and the ratio of allowable that the seismic contributes is shown in Table 2.2. 1.1 Pipe Stresses (Cont'd) The ratio of large bore stresses to their allowable is from a low of 1 percent to a max of 60 percent. The ratio of small bore is from a low of 1 percent to a max of 55 percent allowable. The maximum increase in combined allowable from the entire sample of 138 calculations was 17%. 1.2 Pipe Supports The 138 cajculations for large bore piping resulted ( in 743 piping supports to be reanalyzed. As these were to be completed within a reasonable time, we utilized the technical services of three Consult-ants; Stone & Webster, Bechtel and United Engineers and Constructors. Our ~n-house Engineering Depart-ment was also utilized in re-evaluating pipe supports. 1.3 Results of Sample Evaluation The results are summarized below a) Total No. of Supports 743 b) Total number of supports accepted based on new loads developed 647 c) Total supports exceeding design criteria 96 P79 71 44 2

( c_- .. -*..:...... ~* *-* ;*

1.

SUMMARY

AND CONCLUSIONS (Continued) 1.4 Classification of Supports The supports which exceed design criteria have been classified into the following two categories for the purpose of modifications to return the supports to the commited conditions: a) Long Term Fix b) Short Term Fix 1.4.1 Long Term Fix _ P79 71 45 These are supports that have loads exceeding the design criteria but maintain structural integrity of the system. However it is de-sirable to' have them modified. 1.4.2 Short Term Fix This applies to the_supports that have loads exceeding design criteria and cannot continue to perform their intended function under the emergency load conditions and therefore, require to be modified. Of the 96 supports that exceed design mar-gins,_ 40 are in the category of Long Term Fix and 56 require near term modification. The supports in this category are presently being corrected in the field since our plant is shut down for a refueling outage. 3

:-~---,-----------------,---,------

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1.

SUMMARY

AND CONCLUSIONS (Continued) 1.5 Modifications Mofifications of supports shall be implemented on a priority basis. The supports in the inaccess-ible areas, such as reactor containment shall have first prority. Generally the supports that require long and short term fixes are straps and guides which can be designated as acceptable after slight modification to the strap. These correc-tions can be made during the current outage and we are confident that these shall be finished before the unit is started up. c*.-, (_ P79 71 46 4

-~'** wl.-~ -*-.. --~ l*. f,_.._ __, --*-***----.....:..... __.... ___ *....__,_ ____ --- r*... \\ ( (

2.

TABULATION OF STRESS RESULTS 2.1 Stress Re-evaluation Summary (See Talbe 2.1 Large and Small Bore Pipe) These tabulations show the comparison between the new reanalyses results {based on 3D SRSS-summation) and the ori9inal analyses to determine the percentage of variation. The allowable stresses are based on DBE of B31Ql Code.

== Conclusion:== The result of re-analyses indicate that none of the pipe stresses exceed the allowables based on the new criteria required by the I&E Bulletin 79*07. 2.2 Summary of Original Maximum Stress - Large Bore Pipe ( Se e T Ab le 2

  • 2 )

We have tabulated the results based on DBE for Large and Small Bore Pipe. Also, the original stress and the percentage are identified, it con~ tributes towards total seismic stresses.

== Conclusion:== The seismic stresses do not exceed 60% of the allowables. We have included in our tabulation pipe sizes as required. P79 71 47 5

i i. \\. __

3.

RESULTS OF PIPE SUPPORT RE-EVALUATION We have re-evaluated 743 sample piping supports of the 15 systems involving 138 piping calculations. The percentage acceptable supports using new load values based on reanalyses is 87%. Of the 96 supports that exceed the design margins 7.5% Short term fix and shall be modified in the field. 3.1 Tabulation of Results a) Total support re-evaluated 743 b) Total supports acceptable (new loads) 647 c) Percentage acceptable 87 Supports requiring Short Term Fix 56 Supports requiring Long Term Fix 40 Percentage requiring Short Term Fix 3.2 Pipe Support Structure, Weld & Bolt Sizing Criteria 7.5 Design of pipe supports for Salem is in accor-dance with ANSI B31.1. Allowable stresses for pipe support material are taken from this code for all normal operation. Components used in pipe supports, (rods, u-bolts, clamps and bolts) are designed in accordance with ANSI B31.l and MSSP 58. Bolting of structural components associated with pipe supports are designed in accordance with AISC. P79 71 48 6

l

3.

RESULTS OF PIPE SUPPORT RE-EVALUATIONS 3.2 Pipe Support Structure, Weld & Bolt Sizing Criteria (Continued) Allowable stress is increased to a maximum value of 1.75 Sh for the maximum combined loadings this includes Design Basis Earth-quake. Welded connections are designed in accordance with 831.1. The maximum loading conditions do not allow stress levels to exceed 24.0 KSI for fillet welds. Results of piping stress reanalyses are used in the flexibility analyses and field ( evaluations, part of I&E Bulletin 79-02. Where flexibility analyses were performed prior to receiving the values resulting from calcula-tions for Bulletin 79-07 a reanalysis shall be performed with the new values where these may have exceed the original values. ( \\ P79 71 49 7

1 J f 0**. (

3.

RESULTS OF ALL PIPE SUPPORT RE-EVALUATIONS 3.3 Procedure for Evaluating Pipe Supports The procedure for evaluati~g pipe supports is included in this presentation. 3

  • 4 In t er face w i th I E Bu 11 et i n 7 9-,0 2 Our response to this Bulletin was submitted to your Staff on July 6, 1979, where we have stated that base plate flexibility analysis is in progress.

P79 71 50 8

-* ~- - 1 r:.~'. \\.. r** I

4.

NOZZLE AND PENETRATION LOADINGS 4.1 Summary of Results We have examined nozzle loadings on two (2) Auxiliary Feedwater Pumps and one (1) Contain-ment Spray Pump. The new forces and moments obtained from our reanalyses were included in our re-evaluation. Final results indicate no overstressed conditions. We are continuing this effort ~n the nozzles and penetrations that is included in the reanalysis. 4.2 Criteria for Acceptability Our criteria for acceptability were to examine the allowables loads given to us.from the equipment manufactuers. These allowables were checked against the new loads we calculated. If the forces/moments were within the manufacturers allowables the equipment nozzle was determined acceptable and no further re-evaluation was required. We have informed all the manufacturers that this process of re-examining the nozzle reactions is in progress. Should we come across an instance where nozzle loads are increased over original loads and exceed the manufacturers allowables he will be informed and asked to verify the ac-(: ceptability new loads P79 71 50 9

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s.

PRIMARY COOLANT PRESSURE BOUNDARY PIPING As stated in our initial response to I&E Bulletin 79-07, dated May 1, 1979, we informed the NRC that the Reactor Coolant Loop Piping was analyzed by Westinghouse for both DBE and OBE. In addition, the piping within the Reactor Coolant pressure boundary has been calculated by Westinghouse or re-analyzed by us. Therefore, the concerns of Bulletin 79-07 do not apply. See Westinghouse letter dated April 23, 1979, attached. P79 71 58 10

.. -* *--*-**-- **--*** -... *- -. -*****-*--___.............,_.........._ __. __, __ ~---**-- - I i, I p.: \\. ' (: (_

6.

FSAR PIPE BREAK REANALYSES EFFORT Pipe break lines have been identified on piping diagrams for their respective systems. We have listed stress analysis calculation numbers ~nd identified if postulated pipe break locations have -changed. This effort is ongoing as the reanalysis is progressing. 6.1 Results of Reanalyses We have examined pipe break locations on Main Steam Piping and it was concluded that postulated pipe break locations did not change. 6.2 Pipe Break Location and Criteria The criteria for analysis of high Energy piping systems is addressed in Section 14.5.1.2 of the Salem FSAR. This was based on the recommendation of the reference 1 of Section 14.5 of the letter from A. Giambusso (AEC) to F. W. Schneider (PSE&G) dated December 18, 1972. It contained the attachment "General information required for consideration of the effects of a piping system break outside containment." P79 71 59 11

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  • --~-

-,_ --~ * - 0 ****** 6.2 Pipe Break Location and Criteria (Continued) This reference suggests criteria for location of postulated pipe breaks.

1.

At terminal points.

2.

At locations where stresses due to normal operational loadings associated with seismic event are in excess of.8(Sb+Sa) allowable stress.

3.

At a minimum of two intermediate locations between anchor points selected on a rea-sonable basis as necessary to provide pro-tection. Based on the above we are reviewing the new stress results. Additional pipe break protection provisions may be found necessary if the analysis per 79-07 indicates new stress levels on any intermediate location exceeding the .8(Sh+Sa) criteria. To date, our reanalysis shows none of the calculations have exceeded this limit.,. 12 P79 71 60

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7.

SEISMIC REANALYSIS METHODS The method that was used to reanalyze the safety related piping was response spectra model analysis. It also incorporates summing up individual responses by 3D SRSS load combinations. Valve mass eccentricities are accounted for appropriate stress intensification factors are considered. 7.1 Comparison Between Old/New Methods (Seismic Analysis) We have informed you that the old method was to add up algebraically X+Y ot Y+Z direction of earthquake responses. This was our commitment in the FSAR reference Q5.37. Our new reanalysis methods employ 3D SRSS combination for earthquake loadings ~x 2 + y 2 + z 2. 7.2 Seismic Anchor Movements This has been addressed in our FSAR reference Q5. 27-1. 13 P79 71 61

I \\.. :*. c:**:.

8.

- *--..... _. ____,:._....__,~ -~ !.*...:-......_:...... -- '*. -** NRC BULLETIN 79-02 As stated in our prelimina~y presentation to Staff on June 19, 1979, our intent is to check results of Bulletin I&E 79-07 if deemed necessary. 8.1 Implementation and Response A copy of PS~&G letter to NRC dated July 6, 1979 is attached herewith, indicates method used to implement requirements of I&E Bulletin 79-02. 14 P79 71 62

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9.
    • -***. *-*~-~~

,*~.,......... *.-..,'., SAFETY RELATED PIPING NOT ANALYZED BY COMPUTERS We have identified portions of safety related piping which employed techniques using standard beam theory. 9.1 Techniques Used Generally small bore piping at Salem Generating Station is seismically analyzed using standard verified computer programs as indicated in Item No. 11. However there are cases where small bore piping has been field run, and which has been calculated seismically using guidelines shown below. 9.1.l Seismic class I & II piping with operating temperature of 1300 F and below and pipe size 1-1/2" or smaller was calculated for seismie supports based on the following formula. f = 9 2.87,~ Ref: "Formulas for V ~ Stress & Strain" WL4 by Roark where f 30 cps to length. is assumed to be determine span 15 P79 71 63

~-***.. r* c* ___ :_ *-- *------------- __,, -----*--*------- ~----.

10.

VERIFICIATION OF "AS BUILT" We have included in our submittal to you on June 19, 1979 the procedure we used in identifying as built" conditions. To add further assurance and to comply with the requirements of this Bulletin, we field walked the sample safety related piping within the pressure boundary of the R. c. Loop and found -it in compliance with our isometric sketches. In addition, we agreed at our June 19 meeting to perform a stress walk by ourselves and by the NRC~ That sample walk has taken place in the inaccessible areas of the containment by the resident NRC inspector together with our Stress Engineer. The procedure that was followed was the same as pre-viously submitted to you. The results of these walks confirmed our previous assertions that the actual configuration conforms to the stress isometric drawings. 16 P79 71 64

Sl\\l,fo:M G~:N~;P,.~,NG STATION* Nil.

  • II T STJn:s*: lff-1:v..

l'ION SUMMAHY (~ 'l'Al3LE 2.1 I IJ I *11~'1 c-11r1q111.1l ll11q111.1l i:, 1111111111*<1 Nt!W New 1<.&l lu e..Jl Stress Al low.1hl l* Calculation St r** ~:; ~' Svetem No. 1'6 I l , I

  • 1 S!;

!it!ismic Combined ComlJLllc(I :; L l u:;s 11 I Stress Stress LO Allowdbl~ Stru21a . J_o~..i.1J_1-~- PSl PSI St r **~i!i

,.1*
.1111 c Cnml1u11*d

!;1 I': i I l'Sl /\\1 R.H.R. 267198. 2081:30 14" 313 3697 .177 525 3909 .187 267201

  • 20880 14 II 1888 5G 50

.271 2368 6130 .294 267201A

  • 23220

.260 1452 5927 .260 _ 3(i ___... ---~~-03 ___ - 5978 267202

  • 19800 8"

8736 15556 .786 9077 15897 .80 267203* 198Q_Q ___ .689 7759 13750 .690 _!?_'..'_ __ --- -- _ _7.f:>_?_Q _____ --~)_§:1~- --*- 267204 * .J.9.JiQQ __,_ - _U'.' ___________ 7_5Jl, ____ _ l.3.2J2. __ .* 0.]_Q_ 6956 14f.f.O _740 267204B* 23220 3/4" 1446 6316 .272 1718 6588 .284 267204C* 23220 3349 7306 .315 3546 9170 .395 2672040* 23220 ---

  • 240 1800 5549

.240. 1874 5b23 _3/_~_ 26720400* 23220 .200 1255 4867 .210 - 3 /4. ~--- --- -19_9-_? __ -- --4 7 Q~ -* - - 267204E* 23220 3/4" 1499 7126 .310 1747 7374 .320 267204F* 23220 __l(i_" --l--8 5_6__ __9_q_49__ --.390 11'1.9 9312 .400 267204G* 23220 .377 3257 8516 -367 _u~_:_ __ _ 3505. 8764 2672041-1* 23220 .330 5432 8137 _ 11)0 7596 3/4" 4891 267204J* 23220 .~lJ.~ ?710 77i:;q . ~ ~ i; _3L4_'~-- ~1_4}__ _ __ ]482 --- -- 267204K* 23220 ~~-* ---+-~1~4.5.1_ __ __ 53_u __ -- __._ 2.50 . 1 r::'lQ ~nnn ?CJ\\ ?f.7?Q.1L~_ _ 2.322.Q_ ____ _ _3/A'.~_:_- ._.J.9.4.6______ _6.0.56....___ _ _ *-26.0 ., n11 o c.., c..n .270 267204M** 23220 .300 5194 7033 .300 3(_~-*~- --- __ 5~1-~--- ,_J9_4_9_ -- -- 267204N

  • 23220

- *. 5.26. 1;'1h? 11"71"7 - t:;(} i:; 3/4" 5848

+-*-----.. - - -

122_Q~_ *-

  • Part of Sample Calculation l of 14

~vatem R.H.R. (cont'd) Stress Cal cu la tion No. 267204P

  • 2672040
  • 267229
  • 267229A
  • 267240AA*

267240BB* 267241

  • 267241A
  • 2672410
  • 267244A
  • 267247
  • 267248A
  • 267248B*

267248C

  • 267249*

267249B* 267251* 267253* 267253B* 5/\\1,EM GJ-:N1*:w-:-*"'-tH: STATION r*i* *.'

  • *'11 *r S'l'lh:ss RI-:-* LVI........ lllN

SUMMARY

Al low.ah le !it a t~!iH p:; I 23220 2_3220 __ 26640 c? S 17.e __ ]/ ."Ji 911 411 411 26640 23220 ----- 23220 21132 811 411 -~L 3/ 411 14 II Ila l'lllloll ~ ;,

  • a : an a '*

!.i t *.*. : * ~ i I':; I. 1302 .. ~-74 _ ----- 11256 8346 6522 5445 7846 20880 14 II 7967 23220 14 II 621 20880 12 II 11872 21132 11720 --~ ------- - ------- ~ 23410 20 II 7214 26748 12 II 150 26748 12 II 161 19800 6' I 13362 29232 II J4?Q ____ 19800 8' I 15581 19800 e* I 12407 23220 . 2' I 10213 111aq1n.1 I l~omh 1111 *ll !lt t'**:;s I'S I **-*- 5587 -~Q_4_~ - *-- 17924 11626 16969 13100 12390 14804 5496 17101 17360 9505 1563 7165 16691 10160 18849 17037 17528

1-----*--- -----*-

  • Part of Sample Calculation II I" I 'J l*tl,al -- ---

1'.t11nl*1nt*d New !il. l'l'SS Se.1.emic ,<. "I St r(iss /\\llowalJle PSI .240 1458 .088 469 .673 15705 .436 10263 .730 6459

  • a*---

.560 5522 .586 9168 .700 6752 .240 766 ~819 11701 >--*.820 13037 .406 5761 .060 111 .270 205 .843

  • 12954

~350 8227 .950 13696 .860 12221 .755 10096 New combined llJL!O "I Comhuwtl :;jLl"t*SS Stress Lu Al.lowall.lu PSI Struss - 5743 .250 2144 .090 22372 .840 13543 .508 16906 .730 13177 .570 13712 .650 13589 .650 5591 .24 16930 .811 18677 .880 11572 '.494 1600

  • .060 7209

.270 16283 .822 - 10899 .371 17488 .890 16851 .851 17411 .750 2 of 14

e.

l / I i i., I

a...--*- Svstem R.H.R. Ccont'dl REACTOR. COOLANT Stress Alluw.iule Calculation Slt:l~:i:i No. I'S l 267253C~-- 32544 267326* 23220 267405* 28080 - -- 2671261* 21132 ~---- 267l,.261B* 21780 - 2671264* 21132 2671265* 21132 2671289A-A 23220 2671290A-A 21780 *- - 2671293A'll 2178Q *- 26712958~ 21132 -- 267177* 28800 267208B 28800 267210 22671 267210A 22671 .~. S/\\l.t.:M Gt:Nl*:rt. ': ST/\\TlON Nll. I

  • 1 *r s1*1n:ss Rt:. l;V/\\l.ll/\\'l' I ON SUMM/\\RY lll"L*pn,11 II 1* 1q1 n.1 I S**1 :;11111*

C 11ml 1 l llC'd !jl l'l':i~i* s I 11*ss .. J~>l l'!i I 211 2368 3 633 . - --*-4" 11664 -~.9-~§.- l 3_ 11 .. 20.4) __... !) ..'.34J_.. 2" 2839 6 415 2" 1149 4 842 3/4" 324 2 809 074 3/4..:'._ -* -* __ -:17.4 ---- -. 3 3/4" 5817 7 798 858 3 I:!_" ___ _7 ~ ___ _ _ 5 1 11 3922 1 3699 3/4" 545 4 094 3 11 12272 3/4 11 6734. 12" 811 i.---*** 12 II 2201 1 1 4QQ!L_ 1027 5039 3 972 267210B 28800 3842 5 665 267210C ~~800 __ ----

_?_70. *---

.?L.4.~~---* --~-~-~--- ____ 2 267211 20484 74~§ __ 14 11 2800 ---+-- I j r I

  • 11 llol l -----

l:111t1l> 11\\l'd New New !it.1 f'H~i !iui.emic Combined IC.tl IU UI l:oml>inud Stres11

  • ~....

St. ress Stress to Allowable _/\\I Ju~~ l.JJ_ £.,! __ _ES! PSl Stress .112 1878 3143 .097 .562 13642 1517~

  • . 653.

-_ _. J,_9_0 lq47 5361 _1q1 .304 4615 8191 .388 .222 1668 5361 .246

e.

.133 334 2819 .133 .150 620 3220 .150 .340 6101 8082 .350 .269 781 5845 .268 .629 3070 12847 -590 .190 603 4152 .200 ~-486 13079 16490 .5'73 .383 7042 11783 .409 _.222 1039 SOR,::. _??.ll .175 2432 4203 .185 __ 1_9_7 __ -* 4453 6139 .213 c..._..i..0.8-9__ __ -626 ?C\\QA nQ ___

  • __ l2.5_

2892 7578 .37

Svatem REACTOR COOLANT (cont'd) SAFETY INJECT. Stress All11w.,111., Calcula lion !3 t l't~!i~i No. 1'8 l 267217* 28800 267217A 27000 ~--*--*-*--*--* - -* -* 267219* 28800 267221* 28800 267221A 28800 267221B 2 88_90 ----- 267225 28800 267325 23220 267325A __ _)_O 7 J-2_ __ 267327 2EHiQQ ___ 267328 24192 267239 30726 *-- 267240A 30726 267242* 28800 267242A* 28800 267246* 28800 267250 30_7_2-§ ___ 267250A* 30726 ---*- ~--*----. -- ~i/\\L,EM la*'~,TIN<i STA'l'IUN J..,

  • . lJN IT S'l'lll*:ss RE-L vni°.ll/\\'I' I <>N.SU MM/\\ HY I i 11.J I CJ1 I* p 11.ll or* 1 q 111.il c.. 111 Ii I I Wei

!;**1:.11111* Coml*11u*d

111 *S!i

!il I 1 1 ',!'t !i l I I'.!'i ~;

  • , It I y_1111~
    ; 17.1.*.

f*:; I w.1Lile 411 __ 3/4 11 411 411 ____ }l~.**-*. ~_L 4 ~*---- 2 II 111 111 -~II -- - l" 411 . 411 10 11 4652 14B5 87'JO 10011 13BOG 7130 2649 __ Q97.~ *---* 8469 3854 13537 14680 14858 8663 9771 4671. 14205 __ :Z.9:1Q_ --- _1_9-04!) __ _ 5917 10575 294 143 '17 51 516 301 339 201 462 --~ 557 . 437 8085 15454 . 503 775 7419 241 12151 16744 . 581 6" 7934 12860 . 447 ____ 6_'.~---* __ J:~)~-~--- _l.8~9-9_ -** -*---*' J>35 --~-*~---*-- ___ 9-.22_9 ____. _.+..1189 _______ _. 4.-6.2_ 411 11474 16767 . 546

  • Prlrr of Sample Calculation Nt!W

!.i*!J.emic 81 l"l!lHI P!il -- 8347 1670 10685 9338 11729 7413 5395 2837 8806 6348

  • 7276 t

12123 839 14788 11984 14061 _.9.9li 13112 ~- New Combined Stress PSI 12164 3977 15666 14007 '12781 8946 9390 4859 14339 14463 11934 17813 7483 19381 16022 l9qOfi l LI ~.d. 'l 18405 4 of 14 P'~ **-*----------... __ : i.(. J(.,al lu ul <.:umb111cd tilrt:s~ Lo Alluw.il.Jle Str~1111 - .422 .14*7 .544 .486 .444 .311 .326 .209 .467 .502 .493 .58 .244 .673 .556 .h<°ll Ll.t=.. 7 .599

'
  • i I*

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-~ SALEH Gt:NERJI,.--...,i STATION ~) Nil. I T . *~* STRESS RE-t;VALI.> ** a ION

SUMMARY

  • ---- -(ir-i;Tina-1 or 1*Jinal ori.lJindl Combined New New Stre11e Allowdl>le Sui:.;mic Comll1ned

~lrl!BS Se.Lamie Combined Natio ut Combined Stre** Calculation Struss SL ra?_~iS Struss % of Stress St re** to Allowable Sv*tem Ho. P61 Pine Size l'!i l _rs1 Allowable PSI PSI Str***. ----- SAFETY INJECT. 2671263 21132 411 621 4539 .215 729 4640 .22 (cont.d) 2671282 21132 2" 2895 5459 .258 4146 6710 .318 2671296A* 28800 211 9438 16364 .568 10358 17377 .603 S.G.F.W. 267171* 31500 14 11 3350 10305 .327 3267 10582 .336 ~ e r f 267171A 31500 14~--- _!_?_~ :!: ___ _ l.4_73~-- _!....468 1561 14673 .466 267172* 31500 14 11 5174 9961 .316 7415 12202 .387 ?67172A* 31500 14~*---- _.]738 10855 .345 7801 10918 .347 ' ?h7l 73* 31500 14 11 77_99 15129 .480 7911 15241 .484 I 267173A 31500 14 11 17988 21406 .680 18371 21789 .692 i------- 267174* 31500 14" 7456_ 12072 .383 7684 12300 .39 2671711.'A. 3lSOO 14 11 5673 12842 .408 51'60 12240 .389 COMPONENT COOL. 267196

  • 27000 611 1540 3401

.126 1529 3396 .126 267l96C

  • 27000 911 12540 15213

-563 1. 13883 l6'li:\\h .613 1: ?h7197

  • 27000 16 11

_li_l_8 ___ l:)QL17 .22 281C)0 F".~33 ?~I:\\ 267197C* 27000 16 11 8424 10297 .381 7544 9223 .342

  • ----- ---------r----

267198A

  • 27000 12" 693 29.45

.109 617 2869 .106 267198B

  • 27000 12 11 104 1842

.068 123 1861 .069 5 of 14

Stre** Allowable C.lculation Slross Sv*t** No. P61 f"nM-u. *N.. -ru:T,..nnT _ 267205A

  • 27000 Ccont.dl 2672070
  • 27000 267220A
  • 27000 267220B
  • 27000 7fl7fl10
  • 27onn
  • 267632
  • 27000 7fl7fl11:\\ *

?70(}(} 267639* 27000 267642

  • 27000 267950*

27000 267953

  • 27000 267954*

27000 2671103* 27000 2671107* 27000 ~F.RVTCF. WATER 267701* 24660 267706* 24660 267708* 24660 267720

  • 24660 SALF.M a*:Nl-~* *.:.:\\NG STATiON NO
  • j ' '** lJN l T STRESS RE-l~VALUATION

SUMMARY

Or i*1 tnal Ori*1indl Sc1:;m1c Cnml.J1ned St rc?:is Slrt!SS Pi.oe Size p:;J ..._ PSI 12 II 494 1998 12 11 873 2874 12 11 87 2732 12 11 10 1508 A II QOlQ 9Q?2 411 2482 ~O~L

  • -~---*-

--~*- _2~30 41n-:t 411 7671 13038 911 10979 16614 3 II 836 2082 3 II 2207 2893 411 .435 1161 611 761 2179 411 2352 3814 411 .d.7A. lQ7B 411 327 1523 3 II 248 )..-2.H.1 8" 622 2196 or-i"gTnal Cumliined New New K4t.i.o ot Stress Sei.. ic combined Combined Str*** 'JC, ut Stre11* Streaa to Allo-bl* Str*** Allowable PSI PSI .074 515 2019 .075 .106 915 2916 .108 .101 106 2751 .102 .056 11 1509 .056 .367 8959 QA62 .365 .151 2792 4094 .152 .1S9 2426 .d.?QQ _} 1:\\9 .483 9215 14582 .54 .615 11573 17208 .637 .077 1144 2390 .089 .107 2403 3089 .114 .06 507 1683 .062 .081 835 2253 .083 .141 2322 3800' .141 OB 551 ?nni; nR1 .062 341 lsi:;.1 _063 _QnR 2.Sl 1flRR n,;~ .089 623 2196 .089 6 of 14

!.~ SALEH.Gt:NERA'

  • STATION NO. I

-.,.,, T STRESS RE-1-:VALUAT lllN

SUMMARY

oriqinal or llJ 1 nal OrL*J i.ncll Cumhi.ned Stree11 Allowable S1!LW11ic l:omln n1!d St rt!SS CAlculation Slress 5L 1:1*ss Slrt!SS % of svatem No-P61 PiE!C ~iZ'?___ I'S l 1'51 !.-------- '-Allowable SERVICE WATER 267724* 24660 8" 961 2634 .107 (cont'd_\\ 267728* 24660 8 II 1231 2346 .095 267710 * ?4f,f,Q 8" _ _6_656 2977 .121 267730A*: 24660 4" 3930 4795 .194 --- ~--- 267731* 24660 6" 2196 4031 .163 267735

  • 24660 6"

1331 3924 .159 ?677'14 * ?Ll.~6n 10 11 513~ 7631 .309 267755* 24660 10 11 1686 4675 .19 267757* 24660 10 11 1068 2874 .117 ?f;77i;q * ?Ll.f;f;() 3 II 1675 4920 .2 ?~77 r:;ar. * ?4i::.i::.o 3 II 201 1275 .052 267760

  • 24660 10 11 2501 2904

.118 267761

  • 24660 10 11 762 2143

.087 267761A

  • 24660 10 11 373 1876

.076 267763

  • 24660 10 11 1586 3167

.128 267767

  • 24660 10 11 6478 8181

.332 AUX. F-w_ 267272

  • 27000 4"

5597 12'26.2 .454 ~--*- 267273A

  • 27000 4"

182 5760 213 New Sei**ic Strea11 PSI 952 1339 3246 3321 1771 2582 5094 2117 1440 2048 205 3211 992 384 1819 6419 6441 161 . /'f' New Combined HaLio of Streaa Combined Stte** to Allo~bl8 PSI Str*** *-*- 2812 .114 2345 .095 3567 .145 4186 .170 3606 .146 5096 .206 7643 .31 4847 .197 3003 .122 5285 .214 1279 .052 3614 .147 2373 .096 1944 .079 3400 .138 8122 .329 12187 .451 5779 .214 7 nf 14 i i* r

.~, SALEM GF'.Nf .. NG STATION N1~.. JNlT STRESS RE-EVALUATION

SUMMARY

~. i* Or [;jinal Or i*J indl Ori*JLOdl Coml>Lned New New Rdtio ot Stre*a Allowal..llu Seismic Coml..11ned Stress Seiaaic Colllbined Combined Str*** C.lculation Struss SL Ct~.ss Stress % of Streaa Str*** to Allowable Sv*teia Ho. PSI PinA Size P:ll PSI AU011oable PSI PSI Streaa AUX. F. w. 267274* 27000 411 3413 10029 .371 3357 9973 .369 (cont'd) 267274E* 27000 4" 9562 14658 .543 9920 15016 .556 2672770* 27000 411 1914 10426 .386 2142 10482 .388 CONTAINMENT SPRAY SYSTF.M 267251A* 22150 8 II 1368 .4877 .220 1429 4899 .221 267251B 24192 911 9727 14169 .586 10349 14791 .611 267251C 28026 8 II 8687 14122 .504 7737 13172 .470 1672'lln 28026 3/4 11 767 4G40 .166 780 4651 .166 ?.;7?i:;l R1r 7R026 3/4" 5552 8165 .291 -6168 8725 .311 267252F 28026 12 11 1489 3439 .123 1440 3573 .127 167252G 28026 2 II 343 2870 .102 355 2882 .103 ?i;72qO* 28026 12 II 2399 5138 .183 21:~8 4994 .178 267291* 26035 911 4509 10839 .416 4900 11230 .431 267291A 24192 911 16731 20251 .837 17825 21345. .882 267293 24192 0 II 3141 7404 .306 3951 7606 .314 267295* 28512 U" 13924 16761 .588 18731 21568 .756 ?67291:\\A 24192 a 11 1967 4376 .181 2506 4963 _20s 267251F 28026 3 II 12927 15261 .545 13421 15755 .562 -~-., -..., -.*.a...: -- 8 of 14

SALEH GEN 1~ING STATION NO UNIT STRESS RE-J::VALUATION

SUMMARY

orTginal Origi.nal original Combined New New Ratio of Stre** Allowable Seismic Coml.Jined Stress Sei**ic Combined Combined Str*** Calculation Stress Stress Stress % of Stress Strea* to Allowable Svatea No. PSI Pi.,.. Size PSI PSI Allowable !?SI PSI su,.. MAIN STEAM 267130* 31500 30 11 3539 10192 .324 344q 10102 .321 267130A 31500 30 11 2803 9453 _3 3323 qg72 3]7 1* 267132A* 31500 32 11 10639 15313 .486 9718 14392 .457 267132B 2'7000 3 II 1875 6825 .253 2199 7149 .. 26c; 267132C 27000 3 II 7933 10799 _4 GlQh 17nt:.? AA7 267132M 31500 32 II 12973 18211 .578 15155 20393 .647 267133A 27000 311 4579 10659 _395 4796 l1nl7 _AnR 267133B 27000 3 II 6970 Q1~h 14R h0f..:'I R477 11 C\\ 267133C* 31500 32 11 10720 16112 .515 9912 15304 .486 2671330 31500 3 2 11 12323 17511 -556 14149 19337 .614 2671700 . 27000 l" 12362 14003 .519 12377 14018 .519 2671701 27000 l" 13616 16468 .61 15438 1R790 .. 677 2671703 27000 2 II 9338 12473 _467 7q3R 1 ?-:t?? AC\\t; e ~ 2671710 27000 211 12067 18643 -6QO 112Qt; 17Ci1R t;.4Q 2671713 27000 2 II sqns lt:.OAn _f\\?Q QA,?l , "7~0)1 t:.AA 2671419 27000 3 II 2869 7573 .28 3926 R107 10R 2671420 27000 2 II 558 3528 .131 i;.42 35?.4 111 2671421 27000 2 II 245 4616 . 1 71 1.l!.R A&;. 'H; , "7 'l 2671422 27000 3 II 3293 6996

  • 259 *-

11?.4 'Ja-Mh .. *283

  • Part of Sample Calculations 9 of 14

Stre** Calculation Svete* No. MAIN STEAM 2671423 (cont 1 d.) 2671424 2671425 2671426 2671427 2671428 2671429 2671430 2671740 2671741 2671742 2671743 2671744 2671745 2671746 2671747 267l49* 267149A

  • 267150LL Al low.ihl l~

St1*1!US 1'61 27000 --- 27000 27000 27_00_Q ____ 27000 ---- 27000 __ -- 27000 27000 27000 27000 SALEH Gt:Na::(~~.... c; STATION Nil.. .~I *r STRt:ss RE-l*:VALUATJON

SUMMARY

Or1q1n.sl or i 'Ii n.1 I SPl!iOll 1: L'on1l 11 n1*cl S l I I'~,:~ ~l 11*!;s y !.P~ __ s i. 7:~ _ I':; I -* _)*_:q _____ 211 168 4449 311 10679 13566 ---~_'._'__ 298 __ 4:4~7 __ .. ---311 -- - -~-9J ----.. _ __?4~_}.. ___ 2" 2974 6139 2 II -~~7 4723 -~*~- - -.. -99..6 -*-.... 3.7~_2.._ __ 2 II 413 4586 1 II 6730 11803 -- ---~-* >-*--- 111 9126 11866 27000 1 II 9451 13888 27000 2 II 8873 14864 27000 111 10504 16266 27000 111 13102 17320 27000 l" 6458 13353 27000 2 II 5606 8898

t---------*--

27000 611 6905 13888 27000 611 12630 16969 27000 l" 2954 5049 -,;r * *i (1i.i_l_ C11111h 1111*ct New

ii 1"*~59

!>tu*111ic ... of st Cl!811 _J\\_!_l_~~~-"-!L PSI .165 199 .... 504 12732 -~166 420 - -~-;2.Ql-2499 ."227 2629 .175 921 .14 __ ---2.29. .17 512 .437 6743 .439 9660 .514 10907 .551 12'023 .602 10398 .641 13638 .495 5089 .33 5296 .. ~_1_4 8954 .628 13056 .187 2916 Hew Combined KatJ.o ot Combined Str*** St re** to Allowable PSI Str*** 4451 .165 l4~~4r-' ,S27 4518 .167 5467 .202 5794 .215 4748 .176 3785 -14 4607 .171 13399 .496 12459 .461 15344 .568 16878 .625 16160 .599 17856 .661 11984 .444 8922

  • 3.1 14458

- !:i.1 i:; 173Q'i - h.d..d. 5011 .l81i. 10 of 14 i I + f ' I f t f t [ l ' 1* I ; ~ 'I

SALEM Gt:Nt.:r~c; STATION tm.. llT STRt-:ss RE-l*:VAl.*u**'r ltlN

SUMMARY

l1r' 1 *.ii"1i.1.i Or i'I 111cil Ori'! inc\\ I t:11ml 11111*d Stre** Allowc1hll! SI' I :;m I 1; l'.11ml11 n1*d

l11'69 Calculation Stn
ss Sl I ili

!il.1*t 1 !1S '.%. 11t' s *t

  • Ho P61

_r_~_s i_z.~. I':; I I':; 1 _A_!_l_Q~~ble

  • --** -- r-------* *--

MAIN STEAM 267150 27000 6" 11058 14013 .519 cont.d 267150A 27000 267150B 27000 267150C 27000 26715000 27000 267150EE 27000 267150FF 27000 267150GG 27000

  • ~~~~~~~~---........... i...=..~H!L 2 000 267150JJ 27000 CHILLED WATER 267150KK 27000 2671500 21060 2671501 21060 2671502*

22860 2671503 21060 2671505* 22860 2671506* 22860 2671507* 22860 6" l" l" l" 3_/4 11 l" l" - _3_L 4~*--. l" 3 II 4" 3 II 411 411 411 411

  • P~r~ n¥ R~mnlR Calculation 2240

_6_7]!!__ _!.251 _ _! p_~.84 -- ~,1_0790. - _.&399 7026 10390 .385 1419 4581 .170 708 4317 .160 _.74§ _:_ __ - -~~3_7 ___ .12 _!1~79 ___ _!_43.il_..531 1580 1838 _068 1747 4625 .171 2193 4977 .184 1301 4255 .202 7902 8379 .398 2996 6637 .* 29 170 1812 .086 3017 11800 .516 448 3526 -1'14 496 2352 .103 Hew New RAtio ot S111.*aic Coabined combined St1:*** Steese Stre*a to Allo-bl* P~I PSI Str*** 10005 12960 .48 2547 7085 .262 12596 12772 _473 7300 11550 .428 1211* 4379 .162 665 4274 .158* 1034 3482 -129 12974 l '14~R _i;72 lF..F..2 1920 .n71 1754 4632 .172 2182 4966 -lR4 1301 4255 .202 i : 12251 12721 . e.n4 ~. 3413 7054 .309 ~. 181 1813 .nR6 3293 12121 - s:;':ln ~Rl ~"f;? 1 l:.t:. 213" ~qql 17~ 11 of 14

SALEM Gf'.'. :. 'TING STATIQN

  • .,C\\

.. h UNlT STRESS RE-EVALUATION

SUMMARY

--0*,*1<Jin.i1 OricJinal Ori1J in.al combLned New New Ratio of Stre** AllowalJle Sc1sm1c Comhined Stress Sei.111aic Combined Combined Str*** calculation Strc!IS Str1!sa Slrcss

  • x. of St res*

Streaa to Allowable S"*t*.. Nn_ 1:'61 Pi.oe Size PSI PSI Allvwable PSI PSI Streea CHILLED WATER 2671508 21060 311 2986 4424 _210 3AQO c;12A - ']I:\\ l (cont.'d) 2671509 21060 3 II 4737 6320 .3 5154 6737 _32 2671510 21060 411 4388 5573 -265 4177 'i'il:\\7 _?1;4 267f512 21060 3_*~---* 1894 .2867 _ 1LL1 177n ?RLL "::t 1 "::t c; -.z. 2671513

  • 22860 3 II 1992 5025

.22 2016 5059 _771 2671514 21060 3 II 458

  • -~---

805 -038 c;q1 Q1Ll. _nA"::t 2671515 21060 3 II 483 2559 - 17, 4 ?f. ., c; 14 1., 2671516 21060 3 II 309 1282 .061 340 1328 .063 2671517 21060 411 1373 3320 .* 158 1639 3586 _17 2671518 21060 4" 2320 4766 . - 226 7.141 .47RQ 2671519 21060 l" 12.780 13343 .634 17039 17514 .832 2671520 21060 2" 320 1005 .048 435 1022 .049 2671521 21060 l" 7911 11564 .549 7979 12231 -581 2671522 21060 2 II 2697 3473 .165* 3504 l42Bn . ?n-:t 2671523 21060 2" 556 2682 .127 c;r; 1 l?~R? 1 ?R 2671524 21060 211 4365 9463 _AAQ .d "::t~ "::t .nA~i A An 2671525 21060 2" '660 2105 .1 868 2313 .110 c.v.c. 267357* 28800 3 II 792 5513 .191 Rl:\\1 c; c; "7 A 1 nA 12 of 14

1--. I' J*, (. ,( ( TABLE 2.2 Table 2.2 consists of the following:

1.
2.

18 Sheets of Summary of Original Maximum Seismic Stress (DBE) in Small Bore Calculation 9 Sheets of Summary of Original Maximum Seismic Stress (DBE) in Large Bore Calculation \\ c_: c (

SALEM GF.Nt:R/ ~ STATION / . "\\ ,c:-\\ NO. I IT STRESS RE-l*:VALUATHlN

SUMMARY

.. -- - -- --- -- ----- **----- (fr11j"(r\\.1"1 Ori..,inc1l Ora'f ind l Cumhi.ned New New Stre** Allowdhlc St? I :;m 1 i: Comlaanr.d !il rt~BB Se1.*111ic Colllbined Ratio of Combined Str*** calculation Strt?SS SL l"l'n!I Slrt*ss % of St rel!lll Stre1111 to Allowable 8v*t-HO-1'61 ..f.!E~_s !-~~ - I' ~i I Nil Allowable PSI PSI Stre** --*-*-- ~-----* >---* c.v.c. 267358* 28800 12 11 196 5089 .177 211 5104 .177 {cont'd) 267360B* 28800 3 II 1684 7828 .272 1701 7845 .272 -~------ --* 267362B 28800 3 II 4426 12253 .425 4375 12198 .424

    • -- ~------ ----**-

267375 28800 111 2139 5202 .181 2345 5283 .183 - --i------- 267375A 28800 111 13330 17418 .605 13972 18054 .627 I ' 267376* 28800 3 II _l_Q9] - _8_?67_ .297 4615 10175 .353 267381

  • 28800 3"

..__l4:4~1- _]J.R64 .62 l63A2 ]q74q .6A6 CONTROL AIR 2671550~* 22860 6 II 3080 4221 .185 2999 4140 .181 2671552

  • 22860 3 II 1586 4377

.191 1723 4536 .198 2671553

  • 22860 3 II 2461 4387

.192 2358 4284 .187 2671582

  • 22860 2 II 45f?8 5099

-223 4~0Q c;1 ?n - 2?.d 7671 c;Rs

  • 22860 3 II 215 ld.?2 06?"
d. c;):l

, c;.f;. ~ n~s:i DIESEL OIL AND S'T'AR'T' ATR 2671402,Nt 26035 3 II 827 1484 .057 807 1489 _ os;7 2671402B* 26035 3 II 409 1658 .064 s;A.? 1 f".nn _OkA 2671403A* 26035 2 II 142 1198 _._Q4f". , il ') ,, QJ:l nA.i=_ 2671406B

  • 26035 lJ.s II 4061 47"28

-182 4120 d.7A7 , Qil ,.... -. *-~ *-, ~ l~ of 14

SALEH Gf-:Nt:R/ *

  • r, STATION NO. I IT STJU;ss RE-1*:VALv1.i'ION

SUMMARY

Stre** Allow<1hlt! C.lculation Stru:rn S *tea No P61

  • -~:.i..:==-------i-....:.:=-.s..---+--- - ---*-

Y.!£~.s l!c~- 267143lr* 27000 311 S.G.B.D. -4~-----+----- - ------- 2671433A* 27000 - _ 1" *---* - 2671435*. 27000_ - 26 143

  • 22860 __. -

2671441

  • 27000

__ l_'_' *- -* --- q"

  • ----------li-------+----*--

3" SPENT FUEL COOLING 267453B

  • 20880 11----------t-------t-------
  • ----------l------+-- ---- --
  • --- 6~' -** -

+------ ------- -- - - ---------

  • ----------+------.J------- *-------
  • ----------4------+-------- -*----* *-
  • Part of Sample Calculation Or i*1 i nal Oriqi.ndJ Se a sm a 1:

Coml11nf'd St r-l':;s Sl.n!ss l'~i I _ _J*?t __ 8109 123TI_ 8768 11523 5841 ~-*------,_ J..Q_J_:u__ __.l.22.3. - - _ _llB.L _ 5336 13931 - 4_~54 --*- _ _I~Q.L --* cir"i*l"1ii.11 Coml*aned New New Ratio of

l l"*!SS Se.a.8laiC Cotabin9d Combined Stre**

.., uf Stress St re** to Allowable I** Allowable P~I PSI Str*** ~---- .459 8263 12551 .465 .427 871'7 11.d..72 _4, i; i -~83 7626 1?117 _44q ____ 095 ?171 ?7~1 1, Q .~16 6908 14638 .542 .378 46QR 7<:}4.r:; _ 1R1 I e: 14 of 14

--~* --*

  • --~--

1(. It... -:.-~~-:-:----

  • .-.:.-**-*-*"'-***--~.. --. ----*-,----*.......... _._, ___.,~-~-'~.... *.******-

e *- TABLE 2.2 SALEM GENERATING STATION 0.s~RY OF ORIGINAL MAXIMUM SEIS:~c ~T:~~ (DBE) IN SMALJ., BORE cALcULATION Ratio of Stress Original Total Seismic Stresf: Calculation Pipe Seismic Allowable Ito Allowable System No. Size Stress Stress Stress Chemical & Volume Control 267229B 3/4 11 331 28890 .0115 267261A 2" 4218 29190 .1445 267476 1" 2643 29190 .0905 267478 1" 657 29190

  • 0225*

267479 l" 13615 29190 .4664 267484 2" 182 29190 ."0062 267485 2" 3385 29190 .1160 I 267488 l" 3573 29190 .1224 i ~ I 267497A 2" 3993 29190 .1368 ~(. 267499 l" 6370 29190 .2182 i '-..:.: 3/4" I 267500A 578 29574 .0195 ' j 267501 2" 10791 29190 .3697 267654 2" 6592 29190 .2454 ' I 267254 2" 11120 27128 .4099 267255 2" 9513 30204 .3150 267255BB 2" 2901 30204 .1623 267257A 3/4" 819 27774 .0295 267258A 3/4" 423 30204 .0140 267340 2" 4177 30204 .1383 267340B 3/4 11 - 353 27774 .00004 267343 2" 5495 30204 .1819 (" 267343B l" 2487 28800 .0864 267375 1" 2139 28800 .0743 267375A 1" 13336 28800 .4631

e* .. ---..... ***-~---* --- ---~---...... ---~--- ----. e (_ SALEM GENERATING STATION NO. 1 UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE} IN.SMALI,. BORE CALCULATION Ratio of**--- Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable svstem No. Size Stress Stress Stress Chemical Control 6c Volum~,. 267656 211 671 29790 .0230 (Continued) 267657 l" 1330 29790' .0458 267658 2" 6689 29790. .2292 267659 211 11404 29790' .3902 267660 2 II 6857 29790 .234g 267661 2 II 829 29790 .0284 267662 2 II 4192 29790 .1436 267663 2 II 2916-29790 .0999 (--.- 267664 2 11_ 4713

  • 29790

.1615 267665 211 2468 29790- - ~ 0845 267666 2 II 1299 29790. .0445 267667 211 4445 29790_ .1522 267668 2" 1334 29790. .0457 267673 l" 6895 29790. .2362 267674 2 II 463 29790 .0159 267676 2 II 5397 29790 .1849 267676A 111 336 29790 .0115 267676B l" 226 29790 .0077 267676C 2" 5856 29790. .2006 267680 2" 3866 29790 .1324 267683 2 II 909 29790* .0311 ~ 267690 2 II 7406 29790- .2537 267692 3/4 11 1169 29790 .0400 267923 2" 12930 2g790 .4430

________..__. -* '-** **~- ---.. ---*-*... ~-- (:- *-_.. :. SALEM GENERATING STATION .:":~* NO. 1 UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMAL4 BORE CALCULATION Ratio of Stress Original Total Seismic Stress. Calculation Pipe Seismic Allowable to Allowable Svstem No.* Size Stress Stress Stress I Chemical & Volume Control 267377 2" 7586 27128 .. 2785 267922A 1/2" 8237 29574 .2785 267924 3" 2597 29790 .0872 267655 1" 7163 28800 .2454 267248 E 2 II 2875 30728 .0936 267248F 2" 6974 32168 .2168 2672490 3/4" 267249J 3/4" 1442 29574 ~0488 2672530 3/4" 172 26910 .0064 2671168B 2" 4597 29574 .1554 267304A 1"

  • 4006 28512

.1405 267304B l" 3541 28512 .1242 267241CC l" 1002 28512 .0351 267241F 1" 1430 28512 .0501 267243CC l" 4190 28512 .1470 267245A 1-1/2" 7303 28800 .2536 267245B 1-1/2" 2944 28800 .1022 f( .4261 267245C 1-1/2" 12272. 28800 2671261A 1" 7'8 9 28800 .0274 '~~~_:_~~~~~_J.:__~2~67~1~2~6~2:___J__.:2~*-*~--L~9~5~3~0:..._~~~2~8~8-0_0~-*-~-=--*-3_3_09~-- ,~

**-"~-----~-*-

-- - -* - ~--"""--*.:~....;. "-----------------***--*- -~- -"------ --*---;.~_.... ____ ~ *----****--- ------ -------*--***--- SALEM GENERATING STATION c* *.. NO. 1 UNIT ~... jMMARY OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMALL BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress Safe~y_Injectio~- 2671263A 2" 3177 28800 _1103 (continued) 2671263B 2". 6283 28800 .2102 2671266 1" 9419 28800 .3270 2671266A 1" 292 28512 .0102 2671267 3/4 11 5172 28800 .1796 2671269 3/4" 11853 28800 .4116 2671270 3/4~' 3466 28800 .1203 2671271 1-1/2 11 7764 28800 .2696 2671272 3/4 11 6663 28800 .2314 -r 2671273 3/4" 3005 28800 .1043 2671274 3/4" 8364 28800 .2904 2671275 1" 2181 28800 .0757 2671276 3/4" 1352 28800 .0469 2671277 2" 438 28800 .0152 2671278 2" 1261 28800 .0043 2671279 2" 10681 28800 .3709 2671279A 2" 10949 28800 .3802 2671280 2" 2469 28800 .0857 2671281 l" 1919 28512 .0673 2671282 2" 2895 28800 .1005 2671283 3/4" 3916 28800 .1360 c* 2671284 3/4" 3181 28800 .1105 2671285 3/4" 7538 28800 .2617 2671286 1" 614 291..t<i* .0210*'

      • ~*~- -

. - **--... -._. ___,_,_ _ __;,... -*-~*... --~-----*--**----*--* -~-------**---. ------*----*-*--- -* ( /-_*, SALEM GENERATING STATION NO. 1 UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMALL BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress Safety Injection 2671286A 3/4 11 4947 30728 .1610 (continued} 2671287A l" 4612 29190 .1580 2671288 3/4" 7728 28800 .2683 2671289 l" 8531 28512 .2992 2671290 1" 9915 29190 .3397 2671291 3/4 11 5039 28800 .1750 2671291A 3/4 11 388 26910 .0144 2671292 3/4 11 5785 28800 .2009 -{',. 2671292A 3/4" 385 26910 .0143 2671293 3/4 11 10199 28800 .3541 2671294 l" 5828 28800 .1851 2671294A 3/4 11 230 30728 .0075 2671294AB 3/4 11 239 30728 .00775 2671295 3/4 11 3497 28800 .1214 2671295A 3/4 11 1011 28800 .0351 2671295AB 3/4 11 223 28800 _0077 2671295B 3/4 11 11053 28800 .3838 2671295C 3/4 11 7016 28800 .2436 26712950 3/4 11 9368 28800 .3253 2671296 3/4 11 6690 28800 .2323 2671296A l" 9438 28800 .. 3277 _( 2671297A 3/4 11 12645 28800 .4391 2671298 3/4 11 3744 -20000 .1300 2671299 3/4" 4061 28800 .1!1:1Q

( SALEM GENERATING STATION NO. 1 UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMALL BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress Safety. Iniection 2671300 3/4 11 5398 28800 .1874 (continued) 267 301 l" 5889 28412 .2065 267304 l" 562 28512 .0197 S.G.; Drains and Blowdown 2671461A 2" '1169 27000 .-0433 /.*":... 2671452 2 II 807 27000 .0299 r.* - - \\." Auxiliary Feedwater 2G7271CC 3/4 11 918 27000 .0340 267285A 2 II 5604 27000 .2075 267285B 2 II 2021 27000 .0748 I Component Cooling 267206A-l l" 8682 27000 .3216 267206A-2 1" 10189 27000 .3774 267206A-3 1" 1284 27000 .0476 267206B-l l" 4207 27000 .155*9 267206B-2 l" 4123 27000 .1527 µ* 267206B-3 l" 5668 27000 .2099 2671101-A 3/4 11 619 27000 .0229 2671104 3/4 11 544 27000 .0201

. *-~-----

  • i.,.

e.{ SALEM GENERATING STATION NO. 1 UNIT

SUMMARY

OF ORIGINAL MAXI.MUM SEISMIC STRESS (DBE) IN SMAL~ BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress Component Cooling ---.L 267206 211 184 27,000 .0068 (Continued) 267207A 111 203 27,000 .. 0075 267207B 111 201 27,000 .0074 267216 2 II 234 27,000 .0087 267216A 2 II 4777 27,000 .1769 267216B 2 II 1664 27,000 .0616 267216C 2 II 2006 27,000 .0743 267216D 2 II 1063 27,000 .0394 (-.*.*< 267216E 2 2365 . 27 I 000 .0876 ~. 267216F 2 II 1650 27,000 .0611 267216G 2 II 3565 27,000 .1320 267216J 211 343 27,000 .0127 267216K 2 II 2186 27,000 .0810 267216L 2 II 311 27,000 .0115 I 267216M 2 II 1742 27#000 .0645 267216N 2 II 166 27,000 .0061 267216P 2 II 395 27,000 .0146 267216Q 2 II 639 27,000 .0237 267216R 2 II 2360 27,000 .0874 267625 2 II 8474 27,000 .3139 2679~0 2 II 1588' 27,000 .0588 -c 267991 2" 740 27,000 .0274 267992 2" . 1061 27,000 .0393 2671105 211 1986 27,000 .0735 7

( .e SALEM GENERATING STATION

        • -----**---***---~-*------,..___---- -

NO. 1 UNIT \\)

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMAL~ BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable System No. Size Stress Stress Stress . qomwneni:;: cooling 2671107 2.. 2017 27,000 .0747 (Continued) 2671108 l" 7091 27,000 .2626 2671109 2" 8461 27,000 .3134 2671110 2 II 9916 27,000 .3673 267190CA l" 5087 27,000 .1884 267196A 2 II 1781 . 27,000 .0660 267196E l" 1203 27,000 .0445 26719GF

  • l" 6458 27,000

.2392 ('.*** 267196G l" 8751 27,000 .3241 I.. \\ -* 267196H l" 9690 27,000 .3589 267197E 211 5466 27,000 .2024 - 267197F 2 II 3110 27,000 .1152 267197G l" 10567 27,000 .3914 267197H l" 7247 27,000 .2684 i 267197J l" 1088 27,000 .0403 267205CA 2" 8433 27,000 .3123 267205CB l" 5790 27,000 .2144 267205D l" 14724 27,000 .5453 I 267205EA 2" 14974 27,000 .5546 267205EB 2 II 5119 27,000 .1896 267205EC l" 2558 27,000 .* 0947 -c*-* 267207H 211 1754 27,000 .0650 267207J l" 2279 27,000 .0844 267207K l" 4287 27,000 .1588 \\

~ --- - -* ----------... ~---"'---*--*- *---* -.-** ~ -

~
  • '**-** -,. ~.

'9 e c: SALEM GENERATING STATION NO. 1 UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS {DBE} IN SMALI,. BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable S~stem No. Size Stress Stress Stress Compo41_ent Cooling 267207L l" 3910 27,000 .1448 ~--* (Continued) 267207M l" 7161 27,000 .* 2652 267207N l-"'l/2 11 7549 27,000 .2796 267207P 1-1/2" 894 27,000 .0331 267207R 1-1/2 11 11744 27,000 .4350 - I I 2672075 1-1/2 11 4245 27,000 .1572 267214B 211 5042 27,000 .1867 267214C 111 2552 27,000 .0945 _/~: 267220E l" 2024 .27,000 .0750 ~* \\ ~-... 267983 3/4 11 644 27,000 .0238 267637 l" 1143 27,000 .0423 ~ 267639A 3/4 11 238 27,000 .0088 267985 211 3590 27,000 .1329 267643 2 II 9123 27,000 .3379 267645 3/4 11 3817 27,000 .1414 267647 3/4" 10510 27,000 .3893 267648 2 II 10119 27,000 .3748 267649 3/4" 6059 27,000 .2244 267951 3/4 11 1952 27,000 .0723 267952 2 II 3838 27,000 .1421 267957 3/4 11 912 27,000 .0338 ---c** 267961 2 II 3958 27.,000 .1466 267963 2 II 1726 27,000 .0640 267964 3/4 11 8804 27,000 .3261

r., SALEM GENERATING STATION ( NO. 1 UNIT _ *. MARY OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMAL~ BORE CALCULATION. Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable System No. Size Stress Stress Stress ! CompQnent Cooling 267965 3/4 11 6783 27,000 .2512 1 (Continue~) 267968 3/4 11 5390 27,000 .1996 i' 267969 3/4 11 6696 27,000 .2480 267970 3/4 11 6605 27,000 .2446 267971 3/4 11 8091 27,000 .2997 267972 2" 1449 27,000 .0537 I I 267973 2" 1590 27,000 .0589 i I 267974 2 II 1769 27,000 .0655 I i 267978 2 II 4807. 27,000 .1780 {*** 267979 3/4 11 1064 27,000 .0394 267979A 3/4 11 1589 27,000 .* 0588 267980 2 II 1604 27,000 .0594 267982 3/4 11 488 27,000 .0181 .. i -(......... Spent Fuel Cooling 267414 2" 6801 32166 - 2114 Sheet 10 of 18

    • *~~" -* **-:.:. I***- -*-~**---*~***--*-....,~-~*-**-*-........ --:0.....*--~-"'-***----*~- ----*-*******-._....... _ 1-~ -- :_., __....... -
  • .*.**-.*-;-,**"'"-*~:;~.-.-*** -....... :. _ _,,..., __._,. -* *:....~*-******-* -**---*-* - ----

SALEM GENERATING STATION NO. 1 UNIT (::-:.MARY OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMALJ., BORE CALCULATION 'Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress Control Air 2671560 211 829 27,000 .0307 2671561 2*11 1424 27,000 .0527 2671562 2" 1570 27,000 .0581 2671563 211 1075 27,000 .0398 2671564 2" 501 27,000 .0185 2671565 2" 702 27,000 .0260 2671566 2" 877 27,000 .0325 2671567 211 2723 27,000 .1008 2671568 211 4043 27,000 .1497 _]:'.?~'.;\\ 2671569 2 "* 2105 27,000 .0779 2671570 2 II 19.19 27,000 .0711 2671571 2 II 529 27,000 .0196 2671572 211 2133 27,000

  • 0790.

I 2671573 2" 1070 27,000 .0396 2671574 2 II 7366 27,000 .2728 I i 2671611' 2" 2144 27,000 .0794 2671612 2" 1541 27,000 .0571 I I 2671613 211 4197 27,000 .1554 I 2671614 2" 10372 27,000 .3841 I I I 2671615 2 II 12958 27,000 .4799 2671616 211 11575 27,000 .4287 2671617 2 II 4050 27,000 .1500 . I -c 2671618 2 II 3218 27,000 .1192 2671619 2" 10724 27,000 .3972 I Sheet 11 of 18

SALEM GENERATING STATION NO. 1 UNIT c** ~RY OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMALI,. BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress 9ontr9l ~~f 2671620 2 II Continue 525 27,000 .0194 2671621 211 3862 27,000 .1430 2671622 2 II 11140 27,000 .4126 2671623 211 1872 27,000 .0693 2671624 211

  • 3843 27,000

.1423 2671625 2 II 642 27,000 .0238 2671626 211 2369 27,000 .0877 2671629 2 II 1917 27,000 .0710 2671630 2 II 1447 27,000 .0536 ~~-~*-* 2671631 2 11_ 265 .27,000 .0098 2671632 2 II 909 27,000 .0337 2671583 2 II 2259 27,000 .0837 2671583A 2 II 1138 27,000 .0421 2671583B 2 II 5329 27,000 .1974 2671583C 2 II 971 27,000 .0360 2671583D 2 II 1855 27,000

  • 068.7 2671584 2 II 2849 27,000

.1055 2671587 211 1916 27,000 .0710 2671588 2 II 3728 27,000 .1381 2671589 211 575 27,000 .0213 2671590 2 II 904 27,000 .0335 2671591 2 II 1285 27,000 .0476 -c 2671592 2 II 417 27,000 .0154 2671593 211 2374 27,000 .0879 Sheet 12 of 18 I I i

JI : ~ SALEM GENERATING STATION NO. 1 UNIT {;:..,1ARY OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE} IN SMALI.i BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowa.ble to Allo.wable Svstem No. Size Stress Stress Stress Control Aiy lcontinued 2671594 2" 459 27,000 .0170 I I 2671595 2" 1167 27,000 .0432 2671596 2 II 186 27i000 .. 0069 2671597 2 II 216 27,000 .0080 2671598 2" 1228 27,000 .0455 2671599 211 2089 27,000 .0774 2671600 2" 756 27,000 .0280 2671601 , 2 II 327 27,000 .oi21 2671602 211 676 . 27 I 000 .0250 c:*:* 2671603 2 II. 657

  • 27 I 000

.0243 2671604 2 II 6073 27,000 .2249 2671605 . 2 II 737 27,000 .0273 i 2671606 2 II 495 27,000 .0183 I I 2671606A 2 II 6346 27,000 .2350 2671606B 211 1667 27,000 .0617 2671606C 2 II 4069 27,000 .1507 2671606D 211 1934 27,000 .0716 2671607 2 II 261 27,000 .0097 2671608 2" 478 27,000 .0177 2671551 2 II 362 27,000 .0134 2671609 2 II 4557 27,000 .1688 2671610 2 II 2334 27,000 .0864 -( 2671627 211 1303 27,,000 .0482 2671628 2 II 3999 27,000

  • .1481 I

Sheet 13 of 18

-*~ -.- ~. ~:..,--'........ *-**-* -~.. ~* l' l ~*. SALEM GENERATING STATION NO. 1 UNIT e _f_C'!.""lv'JMARY OF ORIGINAL MAXI.MUM SEISMIC STRESS (DBE) IN SMALI,. BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable vs tern No. Size Stress Stres-s Stress 1ontrQl Air Continued 2671628A 2 II 10340 27,000. .3829 2671628B 211 615 27,000 .0228 2671628C 211 3271 27,000 .1211 2671633 2 II 8900 27,000 .3296 2671634 2 II 4073 27,000 .1508 2671637 2 II 1143 27,000 .0423 2671639 2 II 1146 27,000 .0424 2671640 2 II 6819 27,000 .2525 2671641 2 II 6341 27,000 .2348 2671642 2 II 1438 27,000 .0532 -(*._ 2671643 2 II 12498 27,000 .4629 2671643A 2 II 3321 27,000 .1230 2671643B 2 II 3577 27,000 .1325 2671644 211 2202 27,000 .0815 Diesel Oil and Startinq Air 2671403A 211 142 27,000 .0053 2671403B 211 1036 27,000 .0384 2671403C 2 II 2776 27,000 .1028 2671403D 211 3126 27,000 .1158 2671403E 2" 2324 27,000 .0861 2671403F 2" 4347 27,000 .1610 2671404A 3/4 11 11997 27,000

  • .4443

( 2671404B 3/4 11 2545 27,000 .0943 2671405A 111 269 27,000 .0100 Sheet 14 of Jr,* I ' I ! i I I I I I I I I I \\ i i i

l I t SALEM GENERATING STATION NO. l UNIT _(c:~.~y OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMALI,. BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable ;to Allowable Svstem No. Size Stress Stress Stress Dieset Oil.& S~trtin~ Air - Continue 2671405B l" 10214* 27,000 .3783 2671406 3/4" 2105 27,000 .0780 2671406A 1-1/2" 5571 27,000 .2063 2671406B 1-1/2" 4061 27,000 .1504 2671406C 1-1/2 11 . 1514 27,000 .0561 26714060 3/4 11 10491 27,000 .3885 2671406E 3/4 11 1283 27,000 .0475 2671406F 3/4" 402 27,000 .0149 2671406G 3/4 11 135 27,000 .OQ50 2671406H 3/4 11 254 27,000 .0094 "i?*-*.,.. 2671408 2 II 198 27,000 .0073 2671408A 2" 502 27,000 .0186 2671408B l" 443 27,000 .0164 2671409 1-1/2" 4263 27,000 .1579 2671409B 1-1/2 11 3701 27,000 .1371 2671409DA 3/4 11 6109 27,000 .2263 2671410B l" 1283 27,000 .0475 2671410C 3/4" 1695 27,000 .0628 26714100 2 II 1212 27,000 .0449 2671410E 2" 377 27,000 .0140 2671410F 1-1/2 11 280 27,000 .0104 (. Tice Water 267747C 2" 690 24,750 .0278 2677470 3/4 11 4304 24,750 .17-39* Sheet 15 - of 18 l j i i

Jo

  • r J

I SALEM GENERATING ST.ATION NO. 1 UNIT

SUMMARY

OF ORIGINAL MAXI.MUM SEISMIC STRESS (DBE) IN SMAL~ BORE CALCULATION ( Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stres*s Stress Service Water 267747E 2 II 2102 24,660 .0852 f ~n,, r i,, 11~n) 267794F z.. 277. 24,660 .0112 267748C 111 1384 24,660 .0561 267748CA l" 3504 24,660 .1421 267748CB 111 12586 24,660 .5104 I 267749C 3/4 11 9360 24,660 .3795 267794G 2 ii 279 24,660 .0113 267749F 2 II 8452 24,660 .3427 267750B 2" 3579 24,660 .1451 267750EA 3/4 11 10209 24,660 .4140 (-... 267750G 2 II 1577 24,660 .0640 267750H 3/4 11 5442 24,660 .2207 267750J 3/4" 11218 24,660 .4549 267750K 3/4 11 12590 24,660 .5105 267750M 3/4" 4570 24,660 .1853 267794H 2" 199 24,660 .0081 267705 211 3301 24,660 .1339 267713A 211 2862 24,660 .1160 267709 1-1/2 II 10497 24,660 .4257 267710 1-1/2 11 5256 24,660 .2131 267712AA 1-1/2 11 2363 24,660 .0958 267712AB 2 II 6493 24, 660. .2633 ( 267712B 1-1/2" 4595 24,660 .1863 267712C 2 II 1232 24,660 .0499 Sheet 16 of 18 i I i

.... * -**-**.__,............ ~ ~......, -*. _,.*.,___.,-:;...~---*,, ___.; _________ -

        • ~- 4*----~----::~.. - **--*--....... _* -......... '***' --

~. -. e e SALEM GENERATING STATION NO. 1 UNIT ~lrMMARY OF ORIGINAL MAXIMUM SEISMIC STRESS {DBE} IN SMALL BORE CALCULATION Ratio-of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress Service water 2677120 2" 1736 24,660 .0704 (C!nnt-i nu""n) 267714B 2" 1672 24,660 .0678 267716 1-1/2 11 2703 24,660 .1096 267738 2 II '1764 24,660 .0715 267738A 2 II 10576 24,660 .4289 267738B 2 II 6309 24,660 .2558 267738C 211 1633 24,660 .0662 267739 2 II 638 24,660 .0259 267739A 211 3624 24,660 .1469 267739B 211 1729 24,660 .0701 ( 267740 1-1/2 11 906. 24,660 .0367 267741 1-1/2 11 7248 24,660 .2939 267742 1-1/2 11 1236 24,660 .0501 267743 2" 506 24,660 .0205 267744 2". 704 24,660 .0285 267744A 2" 124 24,660 .0050 267745 1-1/2 11 1544 24,660 .0626 267746 1-1/2 11 1377 24,660 .0558 267747A 1-1/2 11

  • 772 24,660

.0313 267747AA 1-1/2 11 4401 24,660 .1785 267791 211 620 24,660 .0251 267791A 2" 148 . 24, 660 .0060 -1: 267792 211 2164 24,660 .0877 267792A 2 II 329 24,660 .0133 Sheetl7 of 18

SALEM GENERATING STATION NO. l lJNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN SMALL BORE CALCULATION ( -1 Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable System No. Size Stress Stress Stress ~ervice wafer Continued 267793 2" 2634 24,660 .0168 267733B 2" 10806 24660 .4382 .267733C 2" 9492 24&60 .3849 267794A 211 532 24,660 .0216 I 267794B 2" 915 24,660 .0371 2677940 2 II 5238 24,660 .2124 267795A 2 II 1022 246660 .0414 267795B 2 II 370 24,660 .0150 267796 2 II 276 24,660 .0112 267798 2 II 378 24,660 .0153

  • -i 267794CC 2 II 1102 24,660

.-044 7 I 267794DD 2 II 2348 24,660 .0952 267794DA 2 II 1436 24,660 .0582 ( Sheet 18 of 1-8

TABLE 2. 2 51'..LE."1 GENERATING STATION s{~:*:; :~RY OF ORIGINAL MAXIMUM SEIS:~c ~T:~~ (DBE) IN LARGE BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable

vs tern No.

Size Stress Stress Stress I SERVICE WATER 267749E 411 8865 21,060 .4209 267733A 4u 9467 21,060 .4495 267747F 411 3346 21,060 .1589 267702 411 286 21,060 .0136 267703 411 996 21,060 .0473 I 267704 311 3385 21,060 .1607 267707 411 167 21,060 .0079 267711 411 1641 21,060 .077°9 (. . -~:: I 267712 411 4280

  • 21, 060

.2032 267715 311 2294 21,060 .1089 I 267717 411 1709 21,060 .0812 267718 20 11 9800 21,060 .4653 267719 411 2347 21,060. .1114 267721 411 442 21,060 .0210 267722 411 1084 21,060 .0515 267723 411 677 21,060 .0321 267725 20 11 4850 21,060 .2303 267726 911 318 24,750 .0128 267726A 411 2701 21,_06.Q .12Sl.. j 267727 911 2755 24,750 .1113 I 267727A 411 1427 21,060 .0678 I --(~-* 267728A 411 196 21,..0GQ * .0093 267729. 8" 2089 21,060 .0992 Sheet 1 of 9

-~.. *--* -**-*--'-**--'--~-...:~..._...;_...__~-* *--'--"~"-------* *--'**--*.. -~*-* - *'-----*- *--* -

c.

-~ e e SALEM GENER.?.. TING STATION NO. 1 UNIT Su)'.11"-z..RY OF ORIGINAL MAXIMUM SEISMIC STRESS {DBE) IN LARGE BORE CALCu"LA TI ON ~- Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable No. Size Stress Stress - Stress

vs tern
rvice Water 267729A 8"

272 24,750 .0110 ~!"'IT\\ t-i., n or'l' 267729B 411 2203 24,750 .0890 267732 6" 1015 I 21,060 I .* 04fa2 267732A 4" 8908 21,060 .4230 267733 6" 5220 21,060 .2479 267734 611 1083 24,750 .0438 I 267734A 411 170 2lg060 00081 267736 6" 607 21,060 .0288 267737 6" 6555 21,060 .3113 267737A 4 II 11027 21,060 .5236 (. 267751 10 11 4096 21,060 .1945. \\ -- 267752 10" 1517 21,060 .0720 267753 10 11 1979 21,060 00940 267756 10 11 3569 21,060 .1695 267761A 3 II 373 21,060 .0177 267762 3 II 5576 21,060 .2648 I 267762A 3 II 3474 21,060 .1650 267764 10 11 2087 21,060 .0991 267765 10 II 4144 21,060 .. 1968 267766 ion 6383 21,060 .3031 I 267768 10 11 8021 21,060 .3809 267769 10" 1376 21,060 .0653 .1651 I _( 267770 10 11 3478 21,060 j I l Sheet 2 of 9 ~--

  • ~~_.: _________ ;..,,._...., ___________._:.~ ----~.. ___,, ____,___... ~........... ______.,__, __ _

-~---~-'-***'***-**-- *-**-**---~-------~--""*~.. -~-.. -~*-***- SALEM GENERATING STATION NO. 1 UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN LARGE BORE CALCULATION * -( Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress Service Water 267771 10 11 6567 21,060 .3118 <continued) 267772 10 11 4870 21,060 -

  • 2312 267773 ion 4264 21,060

.2025 267774 10 11 972 21,060 .0462 267775 10 11 3952 21,060 .1877 267777 10 11 929 21,060 .0441 267778 10 11 1202 21,060 .0571 267779 ion 769 21,060 .0365 267780 10" 3235 21,060 .1536 267780A 10 11 560 21,060 .0266 7":* 267781A 10 11 680 21,060 .0323 267782 10 11 1104 21,060 .0524 267782A 16 11 1535 21,060 .0729 267783 3 II 868 21,060 .0412 267784 4" 2199 21,060 .1044 267785 6" 5561 21,060 .2641 267786 411 1319 21,060 .0626 267787 4" 1959 21,060 .0930 267788 411 8369 21,060 .3974 267789 411 1333 21,060 .0633 Control Air 2671645 3 II 149 27,000 .0056 ~'**. 2671586 3" 1686 27,000 .0624 Sheet 3 of 9 I I

. - - ---.... ~~-- -*---"---~-............ ________ _.,__,.__, ___,~_ ---**-*-*-'- -- ---.

    • -~'
  • ~* -....

"1 e SALEM GENERATING STATION. c* NO. 1-UNIT OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE} IN LARGE BORE CALCULATION ... M.MARY Ratio of* Stress Original Total* Seismic Stress Calculation Pipe Seismic Allowable to Allowable _Sys~em No. Size Stress Stress Stress Steam Gen. Drains and Blowdown 2671433 3" 2285 27,000 .0846 2671443 3" 7632 27,000 .2827 2671451B 3" 3454 27,000 .1279 2671451C 3" 6209 27,000 .2300 2671452B 3 II 4907 27,.000 .1817 2671452C 3" 1354 27,000 .0501 I 2671453 3 II 5696 27,000 .2110 I i Component Coolinq 267l90CP 16 11 61~9 27.000 ??7'1 ( 267196CA 4" 442 27.000 .0164 267196CB 4" 779 27.000 .0289 267196D 10 11 13611 27,000 .5041 267197A 12 11 3629 27,000 .1344 - 267197B 3" 11240 27,000 .4163 267197D 6" 14934 27,000 .5531 267198C 12" 341 27,000 .0126 267205B 12" 169 27,000 .0063 267205C 12" 340 27,000 .0126 267205C-i 16 11 1018 27,000 .0377 267205C-2 16 11 2899 27,000 .1074 I i i 267205E

  • 12 11 1956 27,000

.-0724 i -( 267205F 12" 6263 27,000 .2320 ' I I 267207C 12 11 2623 27,000 .0971 I I 267207F 3 II 6263 27,000 .2320 i I Sheet 4 of 9

-~-------....-.:.......,_.... -------*-"***---**-----~-. *--.. *-**

  • ~--.-:.. _ ~-.. **---*-****......

- : - :_ -;** :::.::... ~*~:.:.::~ :*.:;*.'.::. :. : :.. *.:.......... _...._,.. _ ~ ('.'*.*,, SALEM GENERATING STATION NO. 2 UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN LARGE BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress Component Cooling {cont. 1 d) 267207G ':! II Qli:.? ')/ {'\\()() ~~Q~ 267214 611 8':! 10 ?7.000 ~nA" 267214A 3 II 5679 27.000 -210~ 267220 12 11 128 27.000 .0047 267220C 12 11 449 27.000 .0166 267220D 611 7901 27.000 .2926 267237 611 10585 27.000 .3920 267238 611 13471 27.000 .4989 _(. 267626 411 10700 25,290 .4231 . '-.c.:. 267626A 411 8223 27,000 .3046 267627 411 4254 27,000 .1576 267631 611 1800 27,000 .0667 267633 . 411 4896 27,000 .1813 267634 311 6058 27,000 .2244 I 267636 6" 7448 27,000 .2759 267640 311 5999 27,000 .2222 267646 311 12813 27,000 .4746 267955 311 2982 27,000 .1104 267956 411 3124 27,000 .1157 267958 311 175 27,000 .0065 267959 311 3862 27,000 .1430 ( 267960 3 II 2418 27.,000 ~0896 267962 311 6135 27.000 ~2272 267966 3 II 8028 ? 7 (')(')()

  • -- I..,

,_ --**\\'.**....... '......_ _________.,_, ___________,_~,--~------------.---~----*-.. - ---- ~. --- *- *: ----~-_,,._, ____ **-*'""*-*** ('-* SALEM GENERATING STATION J. NO. UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE} IN LARGE BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress

!omponent Cooling

{cont.d) - 267967 3 II 9149 27.000 .3389 267975 3 II 4828 27.000 .1788 267976 3" 5295 27,000 .1961 267977 3" 3674 27,000 .1361 267981 3" 2462 27r000 .0912 267984 3" 203 27,000 .0075 267986 311 2378 27,000 .0881 267987 3" 3493 27,000 .1293 267988 3" 192 -27,000 .0071 267989 3" 12149 .27,000 .4500 267993 6" 681 27,000 .0252 267994 3" 4046 27,000 .1499 267995 311 5518 27,000 .2044 267996 311 6466 27,000 .2395 I 267997 3 II 783 27,000 .0290 267998 ' 611 7810 27,000 .2893 267999 6" 1218 27,000 .0451 2671000 311 2378 27,000 .0881 2671101 311 4371 27,000 .1619 2671102 311 2847 27,000 .1054. -z*_ and SI 267240 4" 9456 30,728 .3077 267241B 10 11 9157 24,192 .3785 267241C 10 11 9454 28,512 .3316

~-~-

---~~_, ____._..... ~....-t~--------*-~-*-*-4.._ *.* r_,.** _

    • __:.~,---~* Mo.****~.*******-"'"""*** **~**

.~..: ~- _ _._...... __ c. ~-

11...

j e e G.*{;;~.':~ SALEM GENERATING STATION NO. 2 UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS {DBE} IN LARGE BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable Svstem No. Size Stress Stress Stress RHR and SI 267241E 4" 9027 28.800 .3134 267243 10 11 11904 28.512 .4174 267243A 911 9429 26.910 .3504 I 267243B 911. 1504 28,800 .0522 267244 10" 13214 24,192 .5462 267244B 8" 6819 28,800 .2368 267244BB 8" 12975 28,800 .4505 267248D 3 II 4693 28,350 .1655 __(*: 267249E 311 385

  • 27,342

.0141 ~-- 267249F 3 II 589 27,342 .0215 267249G 311 5990 27,342 .2191 267253A 911 11980 28,860 .5241 Aux. Feedwater 267271A 12 11 1375 27 onn nc::na I 267271BB 10" 55nc; 27.000 ?n<a 267271CA 911 12496 27.000 -46?R 267271D 10 11 1927 27.000 .0714 267271E 10 11 7364 27,000 .2727 267271F 411 280 27,000 .0104 267272A 411 246 27,000 .0091 267272AA 4" 141 27,000 .0052 ( 267272E 411 2425 27,000 .0898 267273 411 3522 27,000 .1304 267273AA 411 453 27,000 .0168

--~-J-*~-----~-~---*-._ -.. -... -~ *-----~------~------.~----'---. **- ---------- -**-*** SALEM GENERATING STATION NO. 2 UNIT SUMY.ARY OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN LARGE BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable System No. Size Stress Stress Stress Aux. Feedwater 267273B 411 427 27,000 .0158 (continued) / 267273C 6 II 2028 27,000 .0755 267273D 411 1961 27,000 .0726 267274A 4" 206 27,000 .0076. 267274C 411 206 27,000 .0076 2672740 411 1849 27,000 .0685 267274G 4 II 4862 27,000 ,.1801 267~74F 411 5762 27,000 .2131 _J-:* 267275 6" 7735

  • 27, 000

.2865 267275A 411 5658 22,950 .2465 267276 4" 7575 27,000 .2806 267278 4" 10990 27,000 .4070 267281 3 II 1647 27,000 .0670 267284 3 II 1491 27,000 .0552 l 267285 3" 1321 27,000 .0489 c.v.c. 267224 3" 262 30.204 ()()R7 267224A 3" 5952 30,204 .1971 267224AB 3" 1291 30,204 .0427 267227A 4" 7822 25,290 .3093 267227G 4" 9190 25,290 .3634 -c* 267229 8" 14171 24,525 .5778 267229A 8" 8346 24,525 .3403 2672300 311 11702 30,204 .3874

    • -*-'-**-~,.*---

.........-.(:: *" --..

    • ~

-* -*-..... ***** *-*---~---**. ******-*-~- **-- -*---*---- ~-- ( SALEM GENERATING STATION NO. l UNIT

SUMMARY

OF ORIGINAL MAXIMUM SEISMIC STRESS (DBE) IN LARGE BORE CALCULATION Ratio of Stress Original Total Seismic Stress Calculation Pipe Seismic Allowable to Allowable System No. Size Stress Stress Stress c.v.c. 267231D 3" 2687 30,204 .089 (continued) 267250AA 4" 9512 30.,728 .3096 267257 4" 9374 27,774 .3378 267258 3" 2124 30,204 .0703 267264A 4" 10596 30,728 .3448 267264AA 3" 2554 30,204 .0846 267269 4" 10384 23,580 .4404 267340A 4" 8205 23,580 .3480 _( 267361 4" 10664 25,290 .4217 267361B 3" 11172 27,128 .4118 267379 3" 5535 24,525 .2257 I 267380 3 II 2293 23,220 .0988 267670 3" 1080 25,290 .0427 267671 4" 403 25,290 .0159 267679 4" 938 23,580 .0398 267922 4" 8237 24,525 .3359 267925 4" 3117 25,290 .1272 267926 4" 2213 25,290 .0875 267927 3" 11~9 25,290 .0446 267928 4" 291 25,290 .0115 267946 3" 14849 24,525 .6055 ( 267948A 4" 1031 25,290 .0408 t r

( 9Sl 05

  • PUBLIC SERVICE ELECTRIC AND GAS COMPANY ENGINEERING AND CONSTRUCTION DEPARTMENT "Procedure for evaluating Pipe Support Capabilities at Salem Nuclear Generating Station.

(.

1.

Procedure for evaluating Pipe Support Capabilities Salem Nuclear Generating Station. SCOPE The sc~~e of this procedure is to re-evaluate the safety related pipe capability to carry the new seismic loads developed to meet the criteria of NRC Bulletin* I&E 79-07. Three dimensional seismic analysis of the piping systems at Salem Nuclear Generating Station are being performed ~sing 3D SRSS (square root sum of the squares) techniques for summation of modal effects. Safety related systems covered within the scope of this Bulletin are listed in Attachment A. *

2.

PURPOSE

3.

The purpose of this evaluation is to determine the capability of existing pipe supports for these safety related systems. ~ New seismic loads are to be combined with thermal and dead wei~ht to complete the re-analysis. GENERAL INFORMATION 3.1 Springs supports and rod hangers shall not be evaluated using this procedure. 3.2 Equipment nozzles shall be evaluated separately using manufacturer's allowable forces and moments. 3.3 Combined calculations shall be c~ecked using tabu-lated load sheets as provided by Stress Engineering on F6rm 79-07-01 Rev 2 (see attachment B) 3.4 The forces and moments specified on the stress load sheets are.reactions. Reverse this sign when evaluating pipe supports. The combined loading is identified in Item #11 and includes the new forces and moments developed as a result of reanalyses. 9Sl 06

( ~-- ( \\:. c**.

3.

.e GENERAL INFORMATION (Cont'd) 3.5 Structural steel provided to support piping shall be evaluated. Building steel shown on structural drawing shall not be included in this evaluation. 3.6 Pipe support evaluation shall include attachments to concrete, including all concrete embedments, anchor bolts and concrete anchors. (Anchor Bolts to be addressed separately in response to NRC Bulletin I&E 79-02). 3.7 Anchors loads must be combined from each. side of the anchor. 3.8 Loads on pipe support structural steel shall. only be considered for support evaluation.

4.

STRESS LOAD SHEETS (FORM 79-07-01 REV 2 ATTACHMENT B) Tabulated forces and moments on each support point for safety related systems as listed on attachment (A). Static, seismic and combined loads are computed separately for each support point and support capability is determined using combined loads which is identified as Item 11 (on Attachment B) on the Stress Load Sheets. The method for combining loads is as follows: 4.1 Item l and 2 are added algebraically. 4.2 Item 8 is SRSS summation for items 3, 4 & 5 and shall be +. 4.3 Item 11 is the summation of items 8 and 9. 9Sl 07 j

(~ c-

s.

PROCEDURE FOR SUPPORT EVALUATION 5.1 Stress load sheets (Form 79-07-01 Rev 2)-obtained from piping reanalyses shall be used in evaluating the load capabilities of pipe supports.

Load com-binations with corresponding allowable stress limits for acceptance criteria are shown on Attachment c. 5.2 The support which fails to meet the above, shall be identified on the individual support calcula-tion. 5.3 Failed supports shall be completely reanalyzed and a recommendation for the fix shall be made on the calculation cover sheet.

6.

ASSUMPTIONS 6.1 Assume E60XX Electrode for all weld calculations, unless specifically noted otherwise. 6.2 All base plates shall be assumed to be rigid. All loads shall be taken up to the base plate including the weld of the support to the base plates. 6.3 Local stresses must be considered when evaluating pipe supports.

7.

UNACCEPTABLE SUPPORTS All supports that have loads exceeding the design criteria shall be classified as unacceptable supports and based on.structural integrity fall into the following two categories. 9Sl 08

( (" '~- c*- ____:. __,_~ -~~---<!-~~-........ ~.......,-~~ ~----...'--'-~**-'-"-~--~-* ---**-----; ~.:... ~ -"-*- -~---- ~~ *--- ~-, --- 7.1 LONG TERM FIX These are supports that have loads exceeding the design criteria but maintain structural integrity of the system. However it is desirable to have them modified. 7.2 SHORT TERM FIX This applies to the supports that have loads exceeding design criteria and cannot continue to perform their intended function under the emergency load conditions and therefore, require to be modified.

8.

REFERENCES 8.1 PSE&G Standard. Allowable stresses (See Attach-ment C)

  • 8.2 NRC Bulletin IE 79-07 "Seismic Analysis of Safety Related Piping Systems".

8.3 ANSI B31.l, AISC and ASME Section III. 9Sl 09

--~----------------------:--------- -- Attachment A List of safety related systems:

l.

Reactor Coolant System

2.

Safety Injection System

3.

Steam Generator Feed System

4.

Component Cooling System

5.

Service W~ter - Nuclear System

6.

Auxiliary Feedwater System

7.

Containment Spray

8.

Main Steam System

9.

Chilled Water System

10.

Chemical and Volume Control System ~~. Control Air System

12.

Diesel Gen. Starting Air and Fuel System

13.

Steam Generator Slowdown System

14.

Spent Fuel Cooling System

15.

Residual Heat Removal System ( 9Sl 10

r~-, .e ~ttachment B SALEM GENERATING STATION UNIT NO RE-EVALUATION OF SAFETY RELATED SUPPORTS NRC BULLETIN #79-07 SYSTEM: ---------------CALC. # -------------- JOINT#--------- HANGER # ----------------- SUPPORT TYPE

E LOAD Fx Fy Fz Mx My

-Mz Lr.I LBS. LBS. LBS. IN-LBS. IN-LBS. IN-LBS. u I

  • DEADWEIGHT I-<

I-UI z *THERMAL 3

  • SEISMIC X 4
  • SEISMIC Y s
  • SEISMIC Z

~ LI.I Ul 6

  • SEISMIC (X+Y) 7
  • _SEISMJC (Y+ZJ 30 SRSS 8

.Jx2 +y2 +z2 TRANSIENT Cl DEADWEIGHT z 9 AND THERMAL c c( 0 ' .J D.W. +TH.+ c 10 (X+Y) OR (Y+Z) LI.I z m ~

  • D.W. +TH.+

0 11 SRSS (8) u NOTE:

  • TAKEN FROM PRINTOUT DATED THE FORCES ANO MOMENTS GIVEN ARE REACTIONS.

D.W. STRESS=-----------.PSI PRESSURE STRESS---'-----.PSI GENERAL STRESS MAX. SEISMIC STRESS ___________.PSI ANCHOR ADJOINING CAL.C. # ----------- DESIGNER WILL USE INFORMATION FROM ITEM #11 INFORMATION TRANSMITTED TO DESIGNER ON -------------------------- PREPARED BY:------------------ DA TE ---------- ACCEPTED 0 __:CHECKED BY: ---......,.:================:_:D:_-A:_T_:__:E_.:._-:-:-:-=:-:-=-=-=-=-=-=-=-=-=-=-=-=-- REJECTED 0 I I !

JI, (* ( \\. ATTACHMENT C DESIGN CRITERIA (ALLOWABLE STRESSES) SUPPORT COMPONENTS LOADING COMBINATION Integral Trunions, Ears, Shoes* Lugs, Rings & Skirts, etc. Non-Integral a) Catalog Hanger Components b) PSE&G Standard Pipe Hanger Components. c) Structural Steel & Components Not Covered by Subsection NF (See Note 1) d) Welds: Normal Sh. (B.31-1) Catalog Allowable PSE&G "Standard" Sh ( B. '31-1) AISC i) Integral Components O.BSh(B.31-1) (Interface) ii) Integral Components 0.8Sh (Elsewhere) Non-Integral Components in (a) & (b) iii) Structural Steel & AISC Components in (c) above NOTES: Emergency l.75Sh* l.75Sh* l.33x AISC l.2Sh** l.5Sh** 1.33 AISC**

  • Components within jurisdictional boundaries of Section III, Subsection NF, ASME Boiler and Pressure Vessel Code.
    • EGOXX Unless otherwise specified or noted on drawings.

9Sl 15

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