ML19242A404

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Rept on Reanalysis of Safety-Related Piping Sys, Revision 3
ML19242A404
Person / Time
Site: Beaver Valley
Issue date: 07/03/1979
From:
STONE & WEBSTER ENGINEERING CORP.
To:
Shared Package
ML19225C630 List:
References
NUDOCS 7908010580
Download: ML19242A404 (52)
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Text

BEAVER VALLEY POWER STATION, UN1T 1 Revision 3 INSTRUCTIONS FOR ADDING REVISION 3 TO THE REPORT ON THE REANALYSIS OF SAFETY-RELATED PIPING SYSTEMS The following listing will serve as a checklist for entering the attached pages into the report.

The items listed in the " REMOVE" column should be removed from the report and replaced with the items in the " ENTER" column.

Vertical bars (change bars) have been placed in the outside margins of revised text pages and tables to show the location of any technical changes originating with this amendment.

Some pages bear a new amendment designation, but no change bars, because revisions on other pages in that section caused a text shift.

A few unrevised pages have been reprinted because they fall within a run of closely spaced revised pages.

No change bars are used on figures or on new sections, appendices, questions and responses, etc.

Change bars from previous amendments have been deleted on pages revised by this amendment.

The instruction sheet and cover letter should be filed at the beginning of the report.

REMOVE ENTER Title Page Title Page p 3-25 p 3-25 p 4-2 thru 4-3 p 4-2 thru 4-4 Table 4-1 (8 pages)

Table 4-1 (10 pages)

Table 4-2 (6 pages)

Table 4-2 ( 7 pages) p 5-1 thru 5-3 p 5-1 thru 5-2 Table 5-1 (6 pages)

Table 5-1 ( 7 pages)

Table 5-2 (1 page)

Table 5-2 (1 page)

Table 5-3 (1 page) p 6-2 p 6-2 p A-3 thru A-9 p A-3 thru A-12 p B-1 thru B-4 p B-1 thru B-3 Table B-1 (2 pages)

Table B-1 (1 page)

Table B-2 (2 pages)

Table B-2 (4 pages)

Table B-3 (4 pages) h l) b

+

79080105@p.

BEAVER VALLEY POWER STATION, UNIT 1 REPORT ON THE REANALYSIS OF SAFETY-RELATED PIPINC SYSTEMS FOR BEAVER VALLEY UNIT 1 DUQUESNE LIGHT COMPANY ORIGINAL - JUNE 15, 1979 REVISION 3 - JULY 27, 1979 Stone & Webster Engineering Corporation

,,, n Boston, Massachusetts I} }-) (g 1, / 4.

BEAVER VALLEY F0WER STATION, UNIT 1 Problem 270, the discharge from the CC heat exchangers has one support (H-56) out of 13 which has a local overstress in a lug of 78 percent.

A new support is being added to the piping system adjacent to this support to correct the condition.

The fuel pool cooling and purification system is presently isolated since there is no spent fuel being stored.

The quench and recirculation spray systems have been completely analyzed for DBE and water ha=mer loads using NUPIPE and are acceptable.

The CBE case vill be run in the long term.

3.

How have stress intensification factors been applied at branch connections during the reanalysis?

Response

Appropriate stress intensifications from 331.1 have been applied to the run pipe at reduced outlet branch connections.

Branches which are uncoupled have been evaluated for the effects of the movements of the run g

S :)(J lJ 3-25 Revision 3

BEAVER VALLEY PO'a*ER STATION, UNIT 1 Tield verified piping fabricator isometric drawings provide the basis for program inputs for the pipe stress reanalysis.

Additionally, in some cases, piping is analyzed utilizing amplified response spectra (ARS) that are developed using soil structure interaction techniques (SSI-ARS).

The resultant stresses and loads are used to evaluate piping, supports, nozzles, and penetrations.

ihese techniques are disc 2ss ed in Section 8.7.

Of the 121 SHOCK 2 problems, 116 have been reanalyzed; 115 are within allowable stress values, r7d one is presently overstressed.

Table 4-1 lists the problems including the peak stress values for the SHOCK 3 and NUPIPE pipe stress runs.

Stresses were computed by the SHOCK 3 or NUPIPE program using different mass models and in some cases different ARS than the original calculations.

More importantly, the reanalyses were based on field-verified, as-built conditions which in some cases differ significantly from the original design conditions.

For these reasons, the originally calculated stresses are not comparable to the new stresses.

The river water discharge line (Problem 122) in the turbine building has been found to have an overstress condition at two unreinforced branch connections 4-2 Revision 3 6)

BEAVER VALLEY POWER STATION, UNIT 1 where a stress intensification factor of 10.45 is used.

This line has been analyzed to this point because it provides the terminal anchor to end the problem.

The line is seismically supported and antlyzed; however, it is located in a non-seismic building and the consequences of a break at these points would not affect any safety-related piping, components, or equipment and would not result in the loss of function o s ay safety-related system or equipment.

f There is no possibility that any flooding that might occur in the turbine buildtr. can affect any safety-related areas.

Therefore, thia condition is considered acceptable for the short term and the branch coanections will be reinforced during the next refueling outage.

Table 4-2 summarizes the nozzles.and penetrations evaluated under the reanalysis p ogram. Of a total of 131 nozzles on problems vitain the scope of the interim effort, all have been evaluated and found to be acceptable.

The 14 nozzles in the quench and recirculation spray system have been accepted based on the DBE case only.

The fuel pool cooling and purification system has 10 nozzles which have not been reviewed at this time.

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4-3 Revision 3

BEAVER VALLEY PO'n'ER STATION, UNIT 1 The SHOCK 2 stress problems contained in the overall effort include 58 penetration connections, all of which have been evaluated and found to be acceptable.

Surmary During the period between the initial issue of this report and this revision, 40 additional problems have been rerun on NUPIPE using the SSI-ARS curve.

All of the above 40 problems have been reanalyzed and were found to be within allouable stress limits.

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4-4 Revision 3

BEAVER VALLEY POWER STATION, UNIT 1 TABLE 4-1 PIPE STRESS REEVALUATION

SUMMARY

System Allevable Reanalysis and Stress Maximum Reanalysis Problem No.

(esi)

Stress Method Reactor Coolant 653A 12.547 7.671 NUPIPE/SSI-ARS 18,820 8,189 653B 19.200 10.084 NUPIPE/SSI-ARS 28,800 10,575 653C 19.200 15.060 NUPIPE/SSI-ARS 28,800 17,244 833 1 8 17.220/19.200<

12.420828 NUPIPE/SSI-ARS 25,830/28,200 17,300 1200 19.200 12.690 NUPIPE/SSI-ARS 28,800 16,424 1201 19.200 9.711 NUPIPE/SSI-ARS 28,800 10,442 Safety Iniection 391A 10.000 15.425 SHOCK 3/SSI-ARS 28,620 18,228 2112 22.500 20.754 SHOCK 3 33,750 25,002 610 18.586 2.081 NUPIPE/SSI-ARS 27,878 2,328 613 21.100

,9.802 NUPIPE/SSI-ARS 31,770 14,336 615 19.500/20.280)

17.585 NUPIPE/SSI-ARS 29,250/30,400 16,069 15 17.340/19.200

I.214 SHOCK 3/SSI-ARS 26,010/28,800 8,123 9;6

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!i 1 of 10 Revision 3

BEAVER VALLEY PO'JER STATION, UNIT 1 TABLE 4-1 (Cont)

System Allowable Reanalysis and Stress Maximum Reanalysis Problen No.

(esi)

Stress Method 1011 20.850 8.245 SHOCK 3/SSI-ARS 31,275 14,087 301 19.200 7.722 NUPIPE/SSI-ARS 28,800 8,712 213'a8 20.388

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  • 1 NUPIPE/SSI-ARE 30,582 5,

7 21138**

20.388 4.078 NUPIPE/SSI-ARS 30,582 4,443 Quench Sprav 211 22.500 1.807 SHOCK 3/SSI-ARS 33,750 2,653 212 22.500 10.445 SHOCK 3 33,750 11,639 228 22.500 12.149 SHOCK 3 33,750 16,589 229 22.500 11.810 SHOCK 3 33,750 15,987 23

'7'

'7*

NUPIPE 33,750 6,235 134

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NUPIPE 33,750 17,667 135

'F*

'F8 NUPIPE 33,750 37,452888 136

'7' NUPIPE 33,750 25,435 210

'r' NUPIPE 33,750 12,667 218

'7' NUPIPE 33,750 6,973 in

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2 of 10 Revision 3

BEAVER VALLEY PO'JER STATION, UNIT 1 TABLE 4-1 (Cont)

System Allevable Reanalyris and Stress Maximum Reanalysis Problem No.

(psi)

Stress Method 614

'F' NUPIPE 33,750 11,343

$ 7.l_

NUPIPE 617 57' 33,750 14,271 Recirculation Sprav 17

'F)

'F' NUPIPE 25,560 25,158 18

'r'

'F' NUPIPE 25,560 16,316

'78 NUPIPE 19

' F_L_

25,560 15,741 20

'F'

'F' NUPIPE 25,560 21,895 22

'F'

'F' NUPIPE 25,560 28,739'85 24

'78

'F' NUPIPE 25,560 16,298 25

'F8

'F' 4UPIPE 25,560 17,260 27

(?'

'F' NUPIPE 25,560 21,415 28

'78

'F' NUPIPE 25,560 14,696

'78 NUPIPE 29

'F'__

25,560 12,991 130

'F'

'F' NUPIPE 25,560 30,728'88 131

'F'

'F' NUPIPE 25,560 29,952'85 3 of 10 Revision 3

3EAVER VALLEY Pok'ER STATION, UNIT 1 TABLE 4-1 (Cont)

System Allowable Reanalysis and Stress Maximur Reanalysis Problea No.

(esi)

Stress _

Method 132

'75 NUPIPE 25,560 17,403 133 878 NUPIPE 25,560 24,337 611 NUPIPE 28,192 8,210 612 1.A.706 1.366 NUPIPE/SSI-ARS 28,193 1,434 Charging and Volume Control 100 18.660 15.220 SHOCK 3 27,990 15,463 102 18.w60 6.299 SHOCK 3/SSI-ARS 27,390 6,621 Residttal Heat Renoval 255A 17.940 5.075 NUPIPE/SSI-ARS 26,910 6,041 256 17.160 11.843 NUPIPE/SSI-ARS 25,740 15,063 14 17.940/19.200

O.740 SHCCK 3/SSI-ARS 26,910/28,800 10,376 3011 17.940 1.656 NUPIPE 26,910 18,148 9

4 of 10 Revision 3 v

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BEAVER VALLEY POWER cTATION, UNIT 1 TABLE 4-1 (Cont)

System Allowable Reanalysis and Stress Maxi;um Reanalysis Problem No.

(psi)

Stress Method 616 18.30C 8.498 NPPIPE/SSI-ARS 27,450 11,500 Component Cooling water 302 18.000 6.295 NtTIPE/SSI-ARS 27,000 10,271

'303 18.000 6.906 NUPIPE/SSI-ARS 27,000 10,377 304 18.000 7.836 NUPIPE/SSI-ARS 27,000 11,108 305 18.000 5.835 NUPIPE/SSI-ARS 27,000 8,330 306 18.000 4.246 NUPIPE/SSI-ARS 27,000 5,077 307 18.000 6.133 SHOCK 3/SSI-ARS 27,000 7,780 180E 18.000 7.554 NUPIPE/SSI-ARS 27,000 7,370 181E 18.000 7.516 NUPIPE/SSI-ARS 27,000 15,168 170C 18.000 4.539 NUPIPE/SSI-ARS 27,000 5,031 171 18.000 5.472 NUPIPE/SSI-ARS 27,000 5,667 172 18.000 8.319 NUPIPE/SSI-ARS 27,000 13,734 173D 18.000 5.107 NUPIPE/SSI-ARS 27,000 5,994 174D 18.000 3.036 NUPIPE/SSI-ARS j

g 27,000 4s115 5 of 10 Revision 3 5:;6 iBI

BEAVER VALLEY POWER STATION, UNIT 1 TABLE 4-1 (Cont)

System Allowable Reanalysis and Stress Maximum Reanalysis Probler No.

(psi)

Stress Method 175B 18.000 5.197 NUPIPE/SSI-ARS 27,000 5,414 176A 18.000 3.505 SHOCK 3/SSI-ARS 27,000 3,777 177 18.000 122]

SHOCK 3/SSI-ARS 27,000 13,707 178C 18.000 15.703 NUPIPE/SSI-ARS 27,000 15,797 179 13.000 2.081 NUPIPE/SSI-ARS 27,000 2,995 183 18,000 9.320 NUPIPE/SSI-ARS 27,000 11,336 184 18.000 10.l'1 NUPIPE/SSI-ARS 27,000 11,734 186A 18.000 15.703 NUPIPE/SSI-ARS 27,000 15,797 270A 18.000 15.703 NUPIPE/SSI-ARS 27,000 13,797 215 19.000 16.311 SHOCK 3 27,000 26,731 217 18.000 15.75152' NUPIPE/SSI-ARS 27,000 23,924 930 18.000 15.751 NUPIPE/SSI-ARS 27,000 23,924 931 18.000 15 211 NUPIPE/SSI-ARS 1

27,000 23,924 214 18.000 14.740 NUPIPE/SSI-ARS 27,000 25,774 6 of 10 Revision 3

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BEAVER VALLEY PO'a*ER STATION, UNIT 1 TABLE 4-1 (Cont)

System Allowable Reanalysis and Stress Maximum Reanalysis Problem No.

(esi)

Stress Methed River

'Ja t e r 1

18.000 10.801 SHOCK 3 27,000 13,759 30 18.000 4.830 NUPIPE/SSI-ARS 27,000 7.576 31 18.000 4.830 NUPIPE/SSI-ARS 27,000 7,576 32 18.000 5.363 NUPIPE/SSI-ARS 27,000 8,390 33 18.000 5.169 NUPIPE/SSI-ARS 27,000 8,241 140 18.000 13.758 SHOCK 3/SSI-ARS 27,000 16,349 384 18.000 6.156 SHOCK 3858 27,000 8,512 157 18.000 1.884 NUPIPE/SSI-ARS 27,000 2,011 158 18.000 1.976 NUPIPE/SSI-ARS 27,000 2,090 159'**

18.000 10.443 NUPIPE/SSI-ARS 27,000 17,277 128 18.000 10.760 NUPIPE/SST-ARS 27,000 12,562 127 18.000 13.384 NUPIPE/SSI-ARS 27,000 15,970 125 10.000 10.760 NUPIPE/SSI-ARS 27,000 12,562 124 18.000 13.384 NUPIPE/SSI-ARS 27,000 15,970 C, " {

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7 of 10 Revision 3

3Er/IR '! A~' ?! P07:.1 5 A! ION, F ! 1 TA3*_I i-1 (Cc -)

Syste:

A110Vahle Reanalysis and Stress Maximu Reanalysis Pr:ble-40.

(esi)

Stress Methed,

123 19.000 20.961 NUPIPE/SSI-ARS 27,C00 17,797 120 19.000 (78 NUP!PE/SSI-ARS 27,000 16,471 126 18.000 13.384 NUPIPE/SSI-ARS 27,000 15,970 21.6 19.000 6.047 NUPIPE/SSI-ARS 27,000 9,989 203 111222 12isi NUPIPE/SSI-ARS 27,000 4,189 2031 13.000 8.260 NUPIPE/SSI-ARS 27,000 9,699 152 19.00Q 4.950 NUPIPE/SSI-ARS 27,000 6,032 121 18.000 6.069 NUPIPE/SSI-ARS 27,000 8,354 122888 18.000 43.256 NUPIPE/SSI-ARS 27,000 62,608 165 18.000 4,95Q NUPIPE/SSI-ARS 27,000 6,032 652 10.000 1.231 NUPIPE/SSI-ARS 27,000 1,394 653 18.000 1.495 NUPIPE/SSI-ARS 27,000 1,b24 Main Sigam 658 22.500 10.248 SHOCK 3/SSI-ARS 33,750 12,025 6590 18.000

_f.977 SHCCK 3/SSI-ARS 27,000 11,105 8 of 10 Revision 3 r"/

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BEAVER VALLEY POWER STATION, UNIT 1 TABLE 4-1 (Cont)

System Allowable Reanalysis and Stress Maximum Reanalysis Problem No.

(esi)

Stress Method 101 18.000 112.911 SHOCK 3 27,000 18,277 639 22.500 10.544 SHOCK 3/SSI-ARS 33,750 12,570 660 22.500 11.121 SHOCK 3/SSI-ARS 33,750 13,304 3063 22.300 12.289 SHOCK 3 33,750 16,481 Teed Water 204 18.000 2.952 SHOCK 3 27,000 3,761 783 18.000 9.361 SHOCK 3/SSI-ARS 27,000 11,624 784 18.000 10.853 SHOCK 3/SSI-ARS 27,000 13,726 785 18,000 14 121 SHOCK 3 2

27,000 20,232 261 18,000 10.479 SHOCK 3/SSI-ARS 27,000 13,585 D*esel Generator Exhaust 651 12.960

1. 2 0 '.

NUPIPE/SSI-ARS 19,440 1,717 Notes:

SSI-ARS : Amplified response spectra developed using soils structure interaction techniques birc ses shown are Oeerational Basis Earthcuake (OBE) Stresses Design Basis Earthquake (DBE) Stresses

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TP304/IP316 allowables 9 of 10 R e visio n_. 3

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BEAVER VALLEY P0b'ER STATION, UNIT 1 TABLE 4-1 (Cont)

System Allowable Reanalysis and Stress Maximum Reanalysis Problem No.

_ frsi)

Stress Method

'88 After modification Are acceptable based on water hammer and OBE analysis using 2.4 For (88 the 1"ng term, this will be acceptable based on 1.8 SH SH

'"> Problems 213 and 2113 include S

+5

+S and S

+S

+S only.

DL LP OBEI DL LP DBEI

<s: Being rerun with SSI-ARS.

' cludes Problems 160 and 161.

<** Problem lav Evaluated for the DBE case only (S

+S

+S

).

'FS DL LP DBEI Overstress condition occurs in turbine building; considered acceptable for short term.

10 of 10 Revision 3 E, ', 6 i R, t

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BEAVER VALLEY POWER STATION, UNIT 1 TABLE 4-2 N0ZZLE AND PENETRATION

SUMMARY

No. Acceptable Total No.

After Pipe No. Requiring System /

of Nozzles /

Stress Re-Turther Re-Problen No.

Panetrations analysis Analysis Reactor Coolant 653A 6/0 6/0 0/0 6533 8/0 8/0 0/0 653C 8/0 8/0 0/0 833 & 8 4/0 4/0 0/0 1200 1/0 1/0 0/0 1201 0/0 0/0 0/0 Safety Iniection 391A 1/0 1/0 0/0 2112 0/0 0/0 0/0 610 2/2 2/2 0/0 613 0/0 0/0 0/0 615 2/3 2/3 0/0 15 1/0 1/0 0/0 1011 0/0 0/0 0/0 301 0/2 0/2 0/0 213 0/0 0/0 0/0 2113 0/0 0/0 0/0

,d/

5a6 1

1 of 7 Revision 3

SEAVER VALLEY POWER STATION, UNIT 1 TABLE 4-2 (Cont)

No. Acceptable Total No.

After Pipa No. Requiring System /

of Nozzles /

Strets Re-Further Re-Problen No.

Penetrations analycis Analvsis Ouench Serav 211 1/0 1/0 0/0 212 1/0 1/0 0/0 228 1/0 1/0 0/0 229 1/0 1/

0/0 23 0/0 0/0 0/0 134 0/0 0/0 0/0 135 0/1 0/1 0/0 136 0/1 0/1 0/0 210 1/0 1/0 0/0 218 1/0 1/0 0/0 614 0/1 0/1 0/0 617 0/1 0/1 0/0 Recirculation Sorav 17 2/0 2/0 0/0 18 2/0 2/0 0/0 19 2/0 2/0 0/0 20 2/0 2/0 0/0 22 0/0 0/0 0/0 24 0/0 0/0 0/0 25 0/0 0/0 0/0 27 1/0 1/0 0/0 2 of 7 Revision 3 cio I

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BEAVER VALLEY POWER STATION, UNIT 1 TABLE 4-2 (Cont)

No. Acceptable Total No.

After Pipe No. Requiring System /

of No::les/

Stress Re-Further Re-Problem No.

Penetrations analysis Analvcis 28 1/0 1/0 0/0 29 0/0 0/0 0/0 130 0/1 0/1 0/0 131 0/1 0/1 0/0 132 0/0 0/0 0/0 133 0/0 0/0 0, 0 611 2/2

./2 0/0 612 2/2 2/2 0/0 Charging &

Volume control 100 2/0 2/0 0/0 102 1/0 1/0 0/0 Residual Heat Renoval 255A 6/0 6/0 0/0 256 0/0 0/0 0/0 14 1/0 1/0 0/0 3011 0/0 0/0 0/0 616 0/1 0/1 0/0 Component Cooling Water 302 1/1 1/1 0/0 J

303 1/1 1/1 0/0 3 of 7 Revision 3 r

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BEAVER VALLEY POk 2 STATION, UNIT 1 7ABLE 4-2 (Cont)

No. Acceptable Total No.

After Pipe No. Requiring System /

of Nozzles /

Stress Re-Turther Re-Problem No.

Penetrations ansivsis Analysis 304 1/1 1/1 0/0 305 1/1 1/1 0/0 306 0/1 0/1 0/0 307 0/1 0/1 0/0 L80E 2/0 2/0 0/0 7.81E 2/0 2/0 0/0

.'. 7 0C 3/0 3/0 0/0 171 6/0 6/0 0/0 172 0/0 0/0 0/0 173D 1/0 1/0 0/0 174D 1/0 1/0 0/0 1753 0/0 0/0 0/0 176A 0/0 0/0 0/0 177 1/0 1/0 0/0 179C 1/0 1/0 0/0 179 1/0 1/0 0/0 183 3/0 3/0 0/0 184 2/0 2/0 0/0 186A 0/0 0/0 0/0 270A 3/0 3/0 0/0 215 0/4 C/4 0/0 217 0/4 0/4 0/0

. (; rj 4 of 7 Revision 3 i

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BEAVER VALL2Y POWER STATION, UNIT 1 TABLE 4-2 (Cont)

No. Acceptable Total No.

After Pipe No. Requiring System /

of Nozzles /

Stress Re-Further Re-Preblem No.

Penetrationi analysis Analysis 930 0/1 0/1 0/0 931 0/1 0/1 0/0 214 0/1 0/1 0/0 River Water 1

4/4 4/4 0/0 30 1/1 1/1 0/0 31 1/1 1/1 0/0 32 1/1 1/1 0, 0 33 1/1 1/1 0/0 140 1/0 1/0 0/0 384 1/0 1/0 0/0 157 0/0 0/0 0/0 158 0/0 0/0 0/0 159 3/0 3/0 0/0 128 0/0 0/0 0/0 127 0/0 0/0 0/0 125 0/0 0/0 0/0 124 0/0 0/0 0/0 123 0/4 0/4 0/0 120 0/4 0/4 0/0 126 3/0 3/0 0/0

,fl 216 1/1 1/1 0/0 5 of 7 Revision 3

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SEAVER VALLEY POWER STATION, UNIT 1 TABLE 4-2 (Cont)

No. Acceptable Total No.

After Pipe No. Requiring System /

of Nozzles /

Stress Re-Turther Re-Proble9 No.

Penetrations analysis Analysis 203 3/0 3/0 0/0 2031 0/0 0/0 0/0 152 2/0 2/0 J/0 121 3/0 3/0 0/0 122 0/0 0/0 0/0 165 0/0 0/0 0/0 652 2/0 2/0 0/0 653 2/0 2/0 0/0 Main Steam 658 1/1 1/1 0/0 6590 0/0 0/0 0/0 101 0/0 0/0 0/0 659 1/1 1/1 0/0 660 1/1 1/1 0/0 3063 0/0 0/0 0/0 Teed-water 204 3/0 3/0 0/0 783 1/1 1/1 0/0 784 1/1 1/1 0/0 785 1/1 1/1 0/0 261 0/0 0/0 0/0 6 of 7 Fevision 3

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BEAVER VALLEY POWER STATION, UNIT 1 TABLE 4-2 (Cont)

No. Acceptable Total No.

After Pipe No. Requiring System /

of Nczzles/

Stress Re-Turther Re-Problem No.

Penetrations analysis Analysis Diesel Generator Exhaust 651 0/0 0/0 0/0 7 of 7 Revision 3 i Qj, i,;s'

BEAVER VALLEY PC*n'ER STATION, UNIT 1 SECTION 5 PIPE SUPPORT RESULTS Table 5-1 summarizes the pipe supports evaluated in tne reanalysis program.

There are 1060 pipe supports on lines within the interim reanalysis effort; of

these, 667 have ' Ween evaluated and found acceptable and 7 have been modified to be acceptable.

A support is considered acceptable if all the load components are lower in magnitude than those for which the support was originally designed.

If some load components are greater than the original design load components, the support is reanalyzed using the new loads.

Of the total 386 supports requiring reanalysis, 383 have been found to be acceptable based on DBEI+DL, 3 have not been accepted at this ime.

There is sufficient analytical information available for the remainin 3 supports to exercise engineering judgment in determining whether the inacceptable condition vill become acceptable.

1.

The use of one time load for snubbers 2.

Use of DBEI plus dead load 5-1 Revision 3

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?IR VALLEY POk'IR STATION, UNIT 1 If a support is unacceptable using any of the above apprcaches, a codification is re' ' ired.

Table 3-2 identifies those supports where acceptance is based on the future use of the options listed above.

Hardware modifications and additions are discussed in Section 6.

Support designs which are not in accordance with either of these criteria vill be suitably modified against the acceptance design criteria of Table 3-1 prior to interim plant operation.

Base plate design criteria and anchor bolt pullout and shear allowable loads are addressed in Section 3.

The seismic support loadings which vill be utiliced for the NF evaluation will be the result of either SH00K3 or NUPIPE evaluations using SSI-ARS.

Surmarv The pipe support reanalysis effort which took place between the original issue of this report and this revision includes accepting 377 supports; 190 based on DBEI+DL and 187 based on long-term criter a.

Also, one additional modification was necessary for the 14" RHR line off the reactor coolant loop and one additional support is required en the 24 inch header from the component cooling heat exchangers.

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ii 5-2 Revision 3

3EAVER VALLEY PO*-7R STATION, UNIT 1 e

TABLE 5-1 PIPE SUPPCRIS St.*,.ARY No. Presently 5

Total No.

Acceptable No. Acceptable Modifications Syster/

cf Based on for Interim or Additions Problem No.

Suceerts Reanalysis Oeeration _

Recrired Reactor Coolant 4

653A 2

2 0

0 N

6533 16 12 0

4 6530 8

8 0

0 83318 15 15 0

1 1200 18 15 3

0 1201 19 19 0

0 Safety Iniection 391A 11 11 0

0 2112 8

8 0

0 610 2

2 0

0 613 5

5 0

0 615825 11 6

5 0

15 11 8

3 0

1011 19 19 0

0 301

56 0

56 0

213 16 0

16 0

f.'l l3 16 0

16 0

l of 7 Revision 3 i~, 'y [3

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BEAVER VALLEY PO*4ER TATION, UNIT 1 TABLE 5-1 (Cont)

No. Presently Total No.

Acceptable No. Acceptable Modifications Syste:/

of Based on for Interi:

'or Additions Proble-A Suerorts

_ve ralysis _

Oeerati n J,uired Ouer.ch Forav 211 5

5 0

0 212 3

3 0

0 228 0

0 0

0 229 0

0 0

0 23 12 0

12 0

134 5

0 5

0 135 9

0 9

0 136 7

0 7

0 210 12 0

12 0

218 9

0 9

0 614 3

0 3

0 617 9

0 9

0 Recirculation Serav 17 3

0 3

0 18 4

0 2

0 19 4

0 4

0 20 4

0 4

0 22 9

0 9

0 24 9

0 9

0 25 9

0 9

0 27 12 0

12 0

2 of 7 Revision 3

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3EAVER VALLEY POWER STATION, UNIT 1 TABLE 5-1 (Cont)

No. Presently Total No.

Acceptable No. Acceptable Modifications System /

of Based on for Interim or Additions Problem No.

Supports Reanalysis Oeeration Rectired 28 6

0 6

0 29 22 0

22 0

130 2

0 2

0 131 2

0 2

0 132 2

0 2

0 133 35 0

35 0

611 6

0 6

0 612 0

0 0

0 Charrine Volume Control 100 9

9 O

O 102 8

8 0

0 Residual Heat Renoval 255A 8

4 4

0 256 6

6 0

0 14 15 15-0 0

3011 11 10 1

0 616 7

0 7

0 Concenent Cooline Water 302 23 23 0

0 303 23 23 0

0 304 33 33 0

0 3 of 7 Revision 3 iu' hj1

BEAVER VALLEY POWER STATION, UNIT 1 TABLE 5-1 (Cont)

No. Presently Total No.

Acceptable No. Acceptable Modifications Syste:/

of Based on for Interim or Additions Proble* No.

Suecorts Peanalvsis Operation

?ecuired 305 30 30 0

0 306 11 10 1

0 307 10 10 0

0 180E 5

5 0

0 181E 5

4 1

0 170C 17 16 1

0 171 15 11 4

0 172 13 12 1

0 173D 15 14 1

0 174D 20 16 4

0 175B 6

5 1

0 176A 5

5 0

0 177 9

9 0

0 1780 14 10 4

0 179 8

8 0

0 183 9

8 1

0 184 14 11 3

0 186A 6

3 3

0 270A 10 6

4 1

215 8

8 0

0 217 10 10 0

1 930 3

3 0

0 4 of 7 Revision 3

, j ')

O

'3 J

BEAVER VALLEY POWER STATION, UNIT 1 TABLE 5-1 (Cont)

No. Presently Total No.

Acceptable No. Acceptable Modifications System /

of Based on for Interim er Additions Preble= No.

Suceerts ceanalysis Operation Pecuired 931 2

2 0

0 214 5

5 0

0 River tJater 1

0 0

0 0

30 2

2 0

0 31 2

2 0

0 32 2

1 1

0 33 2

2 0

0 140 2

2 0

0 384 5

5 0

0 157 3

3 0

0 158 2

2 0

0 15?'**

8 8

0 0

128 1

0 1

0 127 10 6

0 125 12 12 0

0 124 13 13 0

0 123 15 12 0

3 120 11 5

6 0

126 7

7 0

0 216 2

2 0

0 203 16 13 1

0 5 of 7 Revision 3

(,

BEAVER VALLEY PC'n'IR STATION, UNIT 1 TABLE 5-1 (Cont)

No. Presently Total No.

Acceptable No. Acceptable Modifications Syste:/

of Based on for Interim or Additions Problem No.

Sueoorts Peanalveir creration

?eceired 2031 9

9 0

0 121 15 0

15 0

122 19 0

19 0

165 1

0 1

0 152 8

8 0

0 652888 1

0 1

0 653'88 2

0 2

0 Main steam 658 6

6 0

0 6590 3

3 0

0 101 4

4 0

0 659 2

2 0

0 660 7

7 0

0 3063 0

0 0

0 Feedvaier 204 15 15 0

0 783 9

9 0

0 784 6

6 0

0 785 3

0 0

261 6

6 0

0 Diesel Generator Exhaust 651 2

0 2

0 6 of 7 Revision 3 n ;s '

v,,,(,

La

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BEAVER VALLEY PO'n'ER STATION, UNIT 1 TABLE 5-1 (Cont)

NOTES:

Deleted.

ca> Problem 615 contains modifications (NPSH) scheduled for installation during the first refueling outage.

Therefore, it will only be analyzed for interin operation.

Problem 159 includes Problems 160 and 161.

      • Deleted.

88 Analyzed based on DBEI+DL only.

9 7 of 7 Revision 3 C

f.

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3EAVER VALLEY POWER STATION, UNIT 1 TABLE 5-2 ENGINEERING EVALUATION OF REMAINING SUPPORTS Problem Support No.

No.

Overstress Condition Pesolutien RIVER 'JATER SYSTEM 120 H307 Snubber Overloaded Will be Acceptable Based on DIEI+DL R6 Vertical Support Instelled/

Will be Acceptable Based Required Double Acting on DBEI+DL H306 Me=ber/ Weld Overstress/

Wil". be Acceptable Based 3 cit Pullout

,n DBEI+DL 1 of 1 Revision 3 i;'d -)

n-JJV

BEAVER VALLEY FOWER STATION, UNIT 1 Following reanalysis of Problem No. 833, an additional snubber was designed and will be installed to alleviate a pipe overstress occurring under upset (03E) and faulted (D3E) conditions.

Similarly, an additional snubber was designed and vill be installed in Problem No. 217 to alleviate a pipe overstress occurring under the same conditions.

Three supports in Problem No. 123 vill be modified, one to make the as-built condition agree with the original design, one to strengthen a =arginal original design, and one to alleviate an overstressed veld in the support resulting from seismic uplift forces.

Similarly, four supports in Problem No. 6533 vill be modified, three to make the as-built condition agree with the original design, and one to alleviate in overstressed member in the support resulting from seismic farces.

A new support is being added adjacent to an existing support in Problem No. 270 in order to relieve a local overstress in a lug.

6-2 Revision 3 r

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BEAVER VALLEY POWER STATION, UNIT 1 Probier.

FSAR 125 ten Line Numbgr No.

Fig. No.

6"-SI-29-1502-Q1 6"-SI-20-1502-01 6"-SI-19-1502-QL 6"-SI-32-1502-Q1 6"-5I-33-1502-Q1 6"-SI-40-153W-Q2 2113 6.3-1 6"-SI-44-153W-Q2 213 6.3-1 Quench Spray 12"-QS-2-153B-Q3 211 6.4-1 (QS) 12"-QS-1-1533-Q3 212 6.4-1 12"-QS-1-1533-Q3 228 6.4-1 12"-QS-2-153B-Q3 229 6.4-1 10"-QS-4-1533-Q3 614 6.4-1 10"-QS-3-1533-Q3 617 6.4-1 4"-QS-6-1533-Q3 210 6.4-1 10"-QS-4-1533-Q3 4"-QS-5-153B-Q3 218 6.4-1 10"-QS-3-1533-Q3 10"-QS-3-1533-Q3 134 6.4-1 10"-QS-3-1533-Q3 135 6.4-1 10"-QS-4-1533-Q3 31 6.4-1 10"-QS-3-153B-Q3 23 6.4-1 10"-QS-4-153B-Q3 8"-QS-22-1533-Q3 8"-QS-23-1533-Q3 Recirculation Spray 12"-RS-7-153A-Q2 612 6.4-1 (RS) 12"-RS-8-153A-Q2 12"-RS-5-153A-Q2 10"-RS-9-1533-Q2 611 6.4-1 4"-RS-14-1533-Q2 10"-RS-10-1533-Q2 4"-RS-15-1533-Q2 A-3 Revision 3

, s '-

'j s D C U a,

3EAVER VALLEY PC*n'IR STA!!ON, UNIT 1 Problem PSAR System line Nu-ber Nr.

712. Ne.

10"-RS-1-1533-Q2 27 6.4-1 4"-RS-28-1533 4"-RS-27-1533 10"-RS-1-1533-Q2 20 6.4-1 12"-RS-3-1533-Q2 10"-RS-2-1533-Q2 28 6.4-1 10"-RS-2-1533-Q2 18 6.4-1 12"-RS-4-1533-Q2 10"-RS-25-1533-Q2 131 6.4-1 10"-RS-26-1533-Q2 130 6.4-1 10"-RS-25-1533-02 19 6.4-1 12"-RS-ll-1533-Q2 10"-RS-26-153B-Q2 17 6.4-1 12"-RS-12-1533-Q2 12"-RS-3-1533-Q2 133 6.4-1 12"-RS-4-1533-Q2 25 6.4-1 12"-RS-11-1533-Q2 24 6.4-1 12"-RS-12-1533-Q2 29 6.4-1 12"-RS-12-1533-Q2 132 6.4-1 8"-RS-21-153B-Q2 22 6.4-1 8"-RS-22-1533-Q2 8' -RS-2 3-15 3 3-Q2 E '-RS-2 4-1533 -Q 2 Charging and Volume o "-CH-6 3 - 15 3'.'-Q 2 100 9.1-1 Control 6"-CH-67-153W-Q2 (CH) 8"-CH-15-153W-Q2 8"-CH-15-153W-Q2 102 6"-CH-68-153W-Q2 Residual Heat Removal 12"-RH-6-602-Q2 255A 9.3-1 (RH) 12"-RH-9-602-Q2 12"-RH-12-602-Q2 10"-RH-4-602-Q2 10"-RH-5-602-Q2 A-4 Revision 3 nD:

E' i (J dUU

BEAVER VALLEY POb'ER STAT!ON, UNIT 1 Probler.

FSAR System Line Nu-ber

'i c.

Fiz. No.

10"-RH-7-602-Q2 10"-RH-8-602-Q2 10"-RH-10-602-Q2 10"-RH-19-602-Q2 12"-RH-9-602-Q2 256 9.3-1 12"-RH-12-602-Q2 10"-RH-16-602-Q2 10"-RH-17-602-Q2 6"-RH-20-602-Q2 3"-RM-13-602-Q2 10"-RH-16-602-Q2 3011 9.3-1 14"-RM-t-1502-Q1 653B 4-1,9.3-1 14"-RH-2-602-Q2 14"-RH-18-602-Q2 10"-RH-24-1502-Q1 653C 6.3-2 10"-RH-23-1502-Q2 14 9.3-1, 6.3-2 6"-RH-14-152-Q2 616 9.3-1 Component Cooling 18"-CC-ll8-151-Q3 302 9.4-4 18"-CC-116-151-Q3 303 9.4-4 18"-CC-ll4-151-Q3 304 9.4-4 18"-CC-130-151-Q3 305 9.4-4 8"-CC-255-151-Q3 306 9.4-3 8"-CC-256-151-Q3 8"-CC-257-151-Q3 6"-CC-261-151-03 8"-CC-476-151-Q3 6"-CC-258-151-Q3 307 9.4-3 6"-CC-265-151-Q3 8"-CC-259-151-Q3 8"-CC-260-151-Q3 8"-CC-517-151-Q3 6"-CC-519-151-Q3 215 9.4-4 24"-CC-125-151-Q3 18"-CC-489-151-Q2 18"-CC-490-151-Q2 A-5 Revision 3

^ ~7 f

i 2

/

3EAVER VALLEY PO*JER STACION, UNIT 1 Prchle TSAR lf Systen Line Nu-ber 40.

Tiz. No, 18"-CC-529-151-Q3 18"-CC-530-151-Q3 6"-CC-488-151-Q2 6"-CC-526-151-Q3 4"-CC-487-151-Q3 4"-CC-525-151-Q2 3"-CC-486-151-Q3 3"-CC-523-151-Q2 I"-CC-485-151-Q2 2"-CC-524-151-Q3 24"-CC-266-151-Q3 6"-CC-518-151-Q3 24"-CC-112-151-Q3 217 9.4-3, 24"-CC-113-151-Q3 9.4-4 6'*-CC-510- 151 -Q 3 9.4-3, 6"-CC-511-151-Q3 9.4-4 6"-CC-512-151-Q3 6"-CC-482-151-Q3 18"-CC-483-151-Q3 18"-CC-484 151 -

18"-CC-527 x.

18"-CC-528-151-Q3 8"-CC-517-151-Q2 214 9.4-3 6"-CC-481-151-Q2 930 9.4-4 6"-CC-511-151-Q3 6"-CC-480-151-Q2 931 9.4-4 6"-CC-510-151-Q3 10"-CC-20-151-Q3 172 9.4-1, 9.412 8"-CC-81-151 173D 8"-CC-469-151-Q3 6"-CC-82-151 8"-CC-65-151 174D 8"-CC-468-151-Q3 6"-CC-55-151 8"-CC-58-151-Q3 1753 9.4-1, 9.4-2 Kevision r3 A-6 7U LUU J.;

BEAVER VALLEY POWER STATION, UNIT 1 Problem TSAR System Line Number 40.

Fic. No.

10"-CC-320-151-Q3 176A 9.4-1 3"-CC-323-151-Q3 6"-CC-470-151-Q3 6"-CC-83-151 12"-CC-46-151-Q3 177 9.4-3 8"-CC-61-151 8"-CC-465-151-Q3 6"-CC-65-151 6"-CC-92-151-Q3 14"-CC-45-151-Q3 178C 9.4-1, 12"-CC-46-151-Q3 9.4-2 10"-CC-48-151-Q3 8"-CC-8-151-Q3 8"-CC-51-151-Q3 8"-CC-466-151-Q3 8"-CC-80-151 6"-CC-84-lil 6"-CC-23-151 179 9.4-2 4"-CC-26-151 8"-CC-51-151-Q3 180E 9.4-2 6"-CC-53-151-Q3' 6"-CC-56-151-Q3 8"-CC-58-151-Q3 181E 9.4-2 6"-CC-54-151-Q3 6"-CC-60-151-Q3 8"-CC-19-151-Q3 183 9.4-2 6"-CC-34-131 6"-CC-42-141-Q3 6"-CC-515-151-03 5"-CC-38-151-Q3 4"-CC-27-151 8"-CC-35-151-Q3 184 9.4-2 6"-CC-41-151-Q3 3"-CC-37-151-Q3 8"-CC-6-151-Q3 186A 9.4-1, 8"-CC-8-151-Q3 9.4-2 6"-CC-513-151-Q3 A-7 Revision 3 1('f

~~ '

/v

3EAVER VALLEY POWER STACION, UNIT 1 Proble:

TSAR Systen Line Nu-ber

'; a.

Tie. No.

24"-CC-5-151-Q3 270 9.4-1 24"-CC-ll2-151-Q3 18"-CC-4-151-Q3 18"-CC-105-151-Q3 18"-CC-109-151-Q3 21"-CC-22-151-Q3 170C 9.4-1 24"-CC-266-151-03 18"-CC-101-151-Q3 18"-CC-102-151-Q3 18"-CC-106-151-Q3 8"-CC-469-151-Q3 24"-CC-2-151-Q3 171 9.4-1 18"-CC-1-151-Q3 18"-CC-3-151-Q3 18"-CC-103-151-Q3 18"-CC-104-151-Q3 18"-CC-107-151-Q3 18"-CC-108-151-Q3 8"-CC-321-151-Q3 10"-CC-321-151-Q3 Chilled Water 8"-CW-8-151 216 9.4-3 (CW) 8"-CW-9-151 214 9.4-3 River Water 6"-WR-117-151-Q3 203 10.3-5 (WR) 14"-WR-64-151-Q2 30 9.9-1A 14"-WR-82-151-Q2 31 9.9-1A 14"-WR-89-151-Q2 32 9.9-1A 14"-UR-87-151-Q2 33 9.9-1A 8"-WR-228-151-Q3 140 9.9-1A 8"-WR-229-151-Q3 8"-WR-230-151 8"-WR-231-151 8"-WR-234-151-Q3 214 9.4-3 A-8 Revision 3

r. ; (~

h ) rf3

[ld

BEAVER VALLEY FOWER STATION, UNI! 1 Frchle FSAR Systen Line Number No.

Fin. No.

14"-WR-63-151-02 1

9.9-1A 14"-WR-65-151-Q2 14"-WR-86-151-Q2 14"-WR-88-151-Q2 14"-WR-25-151-Q3 120 9.9-1A 14"-WR-26-151-Q3 14"-WR-27-151-Q3 14"-WR-28-1..-Q3 24"-WR-29-151-Q3 14"-WR-21-151-Q3 123 9.9-1A 14"-WR-22-151-Q3 14"-WR-23-151-Q3 14"-WR-24-151-Q3 24"-WR-19-151-Q3 24"-WR-20-151-Q3 24"-WR-19-151-Q3 124 9.9-1A 24"-WR-187-151-Q3 24"-WR-20-151-Q3 125 9.9-1A 24"-WR-186-151-Q3 24"-WR-7-151-Q3 126 9.9-1A 24"-WR-8-151-Q3 24"-WR-9-151-Q3 18"-WR-11-151-Q3 18"-WR-12-151-Q3 18"-WR-13-151-Q3 24"-WR-19-151-Q3 127 9.9-1A 24"-WR-20-151-Q3 128 9.9-1A 24"-WR-99-151-Q3 157 9.9-1A 24"-WR-100-151-Q3 158 9.9-1A,B 20"-WR-1-151-Q3 159

9.9-1A,B 20"-WR-2-151-Q3 20"-UR-3-151-Q3 20"-WR-4-151-Q3 20"-WR-5-151-Q3 20"-WR-6-151-03 24"-WR-99-151-Q3 24"-WR-100-151-Q3 18"-WR-154-151-Q3 12"-WR-177-151-Q3 A-9 Revision 3

') ; b dI

BEAVER VALLEY POWER STATION, UNIT 1 Problem PSAR System Eine Nu-b;I No.

Ti2. No.

8"-WR-227-151 216 9.4-3, 9.9-1A 30"-UR-171-151-Q3 152 9.9-1B 30"-UR-172-151-Q3 30"-WR-175-151-Q3 10"-SWW-14-151-Q3 165'28 9.9-1B 10"-SWW-1-121 18"-WR-14-151-Q3 121 9.9-1A 18"-WR-15-151-Q3 18"-WR-16-151-Q3 30"-WR-17-151-Q3 122 9.9-1A 6"-WR-155-151-Q3 384 9.9-1B 6"-WR-214-151-Q3 652 RM-53A 6"-WR-215-151-Q3 653 RM-53A Main Steam 3"-SDHV-1-601-Q2 101 10.3-1 (MS) 3"-SDHV-2-601-Q2 3"-SDMV-3-601-Q2 4"-SDHV-4-601-Q2 32"-SHP-56-601-Q2 658 10.3-1 32"-SHP-57-601-Q2 659 10.3-1 32"-SHP-38-601-Q2 660 10.3-1 4"-SHP-19-601-Q2 6590 10.3-1 4"-SHP-20-601-Q2 4"-SHP-21-601-Q2 6"-SAE-1-601 6"-SAE-2-601 6"-SAE-3-601 32"-SHP-56-601-Q2 3063 10.3-1 32"-SMP-57-601-Q2 32"-SHP-38-601-Q2 32"-SHP-22-601-Q2 32"-SHP-23-601-Q2 32"-SHP-24-601-Q2 10"-SSVD-1-601 10"-SSVD-2-601 10"-SSVD-3-601

-9 10"-SSVD-4-601 A-10 Revision 3 C'b h.

[,

BEAVER VALLEY POWER STATION, UN!! 1 Problem TSAR SY9te9 Line Numba-Nr.

F12 No.

10"-SSVD-5-601 10"-SSVD-6-601 10"-SSVD-7-601 10"-SSVD-8-601 10"-SSVD-9-601 10"-SSVD-10-601 10"-SSVD-ll-601 10"-SSVD-12-601 10"-SSVD-13-601 10"-SSVD-14-601 10"-SSVD-15-601 Main and Auxiliary 4"-WAPD-3-601-Q3 204 10.3-5 Feedvater (FW) 4"-WAPD-4-601-Q3 4"-WAPD-5-601-Qs 4"-WAPD-6-601-Q3 6"- W' AP D-1-6 01-Q 3 6"-WAPD-2-601-Q3 16"-WFPD-22-601-Q2 783 10.3-5 16"-WTPD-24-601-Q2 784 10.3-5 16"-WTPD-23-601-Q2 785 10.3-5 16"-WFPD-9-601-Q2 0261 10.3-5 16"-W/PD-13-601-Q2 16"-WFFD-17-601-Q2 6"-WD-23-151-Q3 203 10.3-5 6"-WD-24-151-Q3 6"-WD-25-151-Q3 6"-UD-26-151-Q3 4"-WD-27-151-Q3 4"-WD-41-151-Q3 8"-WD-22-151-Q3 2031 10.3-5 6"-WD-25-151-Q3 6"-WD-26-151-Q3 Diesel Generator 22"-OL-55-151-Q3 651 RM-53A Exhaust (OL)

NOTES:

Problems 160 and 161 are included within the scope of the reanalysis effort for problem 159.

A-ll Revision 3 ki a O d

3

3EAVER VALLEY PO**ER STA!!ON, UNIT 1

'2' Problem 165 has been analy:ed on NUPIPE as part of the Beaver Valley Unit 2 stress analysis effort.

These lines are identified on the flev diagrams included in Appendix C.

In addition to the problems referenced above, a numbe: cf other computer analyses were also performed for Beaver Valley - Unit 1, uring the SHOCK 2 code.

These have been excluded frem the scope of the reanal'/ sis for interim startup and are discussed in Appeadix 3.

A-12 Revision 3 C

i

' - D 2;r

BEAVER VALLEY PC'a*ER STATION, UNIT 1

.s APPENDIX B PROBLEMS TO BE REANALYZED IN THE LONG TERM The problems described in Tables 3-1 and B-2 are the remaining problems run on SHOOK 2, five of which are within the scope of the long term effort.

These ptoblems are identified on the flow diagrams included in Appendix D.

1.

Other safety systens Table B-1 identifies the SHOCK 2 problems that are within the scope of the long-term reanalysis effort; these lines are not required for safe shutdown.

2.

Hand Calculations Table B-2 identifies SHOCK 2 problems that are not within the scope of the long-term reanalysis effort; these SHCCK 2 runs are only check calculations of manual hand calculations.

They are identified here only to show the scope of the original SHOCK 2 effort.

B-1 Revision 3

/

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BEAVER VALLEY PC'n'ER STATION, UNIT 1 3.

sueerseded calculations The following SHOCK 2 runs have been superseded by a problem presently within the interim and long term reanalysis effort.

Superseded New Problem SMOCK 2 Run Nurber 122A 122 312 840 657 785 916 217 1012 391 2110 341B 6230 310 4.

Seismically Suceerted Nen-O Lines The following lines are not safety related but have been seismically supported as designated by an "E" in the line designation table.

2"-CV-1-154 2"-SHPD-5-601 3-2 Revision 3 T, ' {.

].b

EEW7IR VALLEY F0k'IR STATION, UNIT 1 2"-SHFL-6-601 2"-SHFD-7-601 2"-SHFD-8-601 1/4-SS-163-N9 1/4-SS-173-N9 1/4-SS-174-N9 3-3 Revision 3 q) 7

., I)

L: I u,

, ~.

BEAVER VALLEY POWER STATION, UNIT 1 TABLE B-1 SAFETY SYSTEMS TO BE ANALYZED IN THE LONG TERM Problem TSAR System Line Nurber No.

Fic. No.

Tuel Fool Cooling 6"-TC-4-152-Q3 104 9.5-1 8 Purification System 6"-TC-5-152-Q3 (TC) 6"-TC-6-152-Q3 6"-TC-8-152-Q3 105E 9.5-1 6"-TC-9-152-Q3 10"-FC-1-152-Q3 198B 9.5-1 6"-FC-2-152-Q3 6"-TC-31-152-03 4"-TC-10-152 107 9.5-1 4"-TC-11-152 6"-TC-14-152 6"-TC-17-152 6"-TC-32-152 River Water 30"-WR-175-151-Q3 153 9.9-1B (WR) 1 of 1 Revision 3 C*t C i ()

,a

- Iu

BEAVER VALLEY PCWER STATION, UNIT 1 TABLE B-2 HAND CALCULATIONS CHECKID BY SHOCK 2 Problem Systen Line N"nber No.

High Pressure Steam 3"-SHP-26-601-Q2 3043 (SHP) 3"-SEP-31-601-Q2 Steam Generator Auxiliary 3"-WAPD-13-601-Q3 207 Peedvater Pu=p Discharge (WAPD) 3"-WAPD-ll-601-Q3 208 Generator Water Blowdown 3"-WOCB-8-601-02

309, (WGCB) 3"-WCCB-12-601-Q2
3017, 6220,
2002, 2018, 6216 3"-WCCB-4-601-Q2 310 3"-WGCB-4-601-Q2 3100 Fuel Pool Cooling and 6"-FC-12-152-02 301 Purification System (FC) 6 '-FC-17-152-Q2 655C Charging and Volume 3"-CH-125-1503-Q2
911, Control System (CH)
260, 3001 2"-CH-97-1502-Q1 200 2"-CH-141-1503-Q1 220 2"-CH-100-1502-Q2 230 2"-CH-186-152-Q2 2"-CH-1-1502-Q1 240 2"-CH-96-1502-Q1 250 2"-CH-23-1502-Q1 300 2"-CH-143-1502-Q1 350 2"-CH-149-1502-Q1 2"-CH-145-602-Q1 2"-CF-2-602-Q1 2"-CH-3-602-Q1 1 of 4 Revision 3

-!/

5. ~~ I,

/

BEAVER VALLEY FC"ER STACION, UN2T 1 CABLE 3-2 (Cent)

F cblem System Eine Nu-ber No.

2"-CH-4-602-QL 2"-CH-146-152-Q3 3/4"-CH-ll5-1502-Q2 380 2"-CH-2-602-Q2 702 2"-CH-148-602-Q2 703 3"-CH-106-153W-Q2

901, 3135 3"-CH-107-153W-Q2 3135 3"-CH-108-153W-Q2
704, 3135 3"-CH-110-153W-Q2
704, 3"-CH-111-153W-Q2 3057 3"-CH-114-152W-Q2
3129, 3044 4"-CH-14-153W-Q2 3057 3"-CH-6-153W-Q2 3122 3"-CH-226-153W-Q2 3"-CH-13-153W-Q2 3125 4"-CH-72-1503-Q2 3131 4"-CH-76-1503-Q2 3"-CH-71-1503-02 3"-CH-75-1503-Q2 3"-CH-80-1503-Q2 3"-CH-69-1503-Q2 3031 3"-CH-70-1503-Q2 3"-CH-73-1503-Q2 3"-CH-74-1503-Q2 4"-CH-72-1503-Q2 4"-CH-76-1503-02 3"-CH-125-1503-Q1 3035 Safety Injection (SI) 3"-SI-81-1503-OltQ2
900, 3004 3"-SI-140-1503-Q1
902, 3004 2 of 4 Revision 3 u

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BEAVER VALLEY POWER STATION, UNIT 1 TABLE B-2 (Cent)

Problem systen Line Nunig4 N o.. __

6"-SI-34-1502-Q1 3006 6"-SI-74-1502-Q1 3"-SI-60-1503-Q2 3124 3"-SI-57-1503-QltQ2 900 3"-SI-130-1503-Q18Q2

313, 902 3"-SI-134-1503-Q2 922 3"-SI-81-1503-Q2 31'.0 3"-SI-56-1503-Q3 3052 3"-SI-60-1503-Q3 3"-SI-133-1503-Q3 4"-SI-75-1503-Q3 3"-SI-134-1503-Q1 3"-SI-31-153W-Q2 3127 3"-SI-145-153W-02 3"-SI-35-152-Q3 965 Residual Heat Re= oval 6"-RM-14-152-Q2 3012 System (RH)

Reactor Coolant (RC) 3"-RC-13-1502-QL 6530 3"-RC-23-1502-Q1 3"-RC-33-1502-Q1 3"-RC-160-153W-Q2 2"-RC-54-1502-Q1 220 3"-RC-160-153V 917 4"-RC-112-152-Q3 360 3"-RC-150-153W 917 3"-RC-160-153W-Q2 3021 Component Cooling (CC) 6"-CC-512-151-Q3 914 4"-CC-487-151-Q2 913 3 of 4 Revision 3 g -- (

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3EAVER VALLEY FCL*ER SCA!!ON, UN27 L TA3LE 3-2 (Cont) 9 Proble:

System Line Nu-ber N' o.

4"-CC-525-151-Q3 3"-CO-235-151-Q3 921 3"-CO-486-151-Q2 3"-CO-523-151-Q3 Diesel Generator 011 Line 3"-OL-46-151-Q3 650 (OL)

Primary Grade Water 3"-PG-5-152 917 (PG)

Quench Spray 2"-QS-29-152 315X (QS) 6"-QS-30-1533-03 840 6"-QS-31-1533-Q3 6"-QS-16-152 139 4"-05-8-152 3413 Neutron Shield Tank 6"-:: S L 15 2-Q 3 312 Cooling (NSL)

G 4 of 4 Revision 3

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