ML17277A979

Forwards Response to Revised FSAR Question 110.42 Re Support Design Adequacy for Anchor Group 37,including Procedure 3900-76, MEB-50 Phase II Study, Per NRC 831012 Request & SER Confirmatory Issue 7

ML17277A979
Person / Time
Site:	Columbia
Issue date:	10/28/1983
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML17277A980	List: ML17277A979 ML17277A981
References
GO2-83-982, NUDOCS 8311080156
Download: ML17277A979 (12)

Text

n REGULATORY ORMATION DISTRIBUTION SY M (RIDS) p ACCESS~0, NBR;8311080156 DOC ~ DATE: 83/10/28 NOTARIZED; NO DOCKET FACIL:50-397 WPPSS Nuclear Projects Unit 2g Washington Public Powe 05000397 AUTH, NAME AUTHOR AFFILIATION SORENSENEG>C, Washington Public Power Supply System RECIP ~ NAME RECIPIENT AFFILIATION SCHWENCEREA, Licensing Branch 2

SUBJECT:

Forwards response to revised FSAR Question 110,42 re support design adequacy for archor Group 37 including Procedure 3900 76 >>MEB-50 Phase II Study'>> per NRC 831012 request SER Confir'matory Issue 7.

DISTRIBUTION CODE; BOO IS COPIES RECEIVED:LTR IRelated ENCL QCSIZE:

Correspondence TITLE: Licensing Submittal: PSAR/FSAR Amdts K NOTFS:

RECIPIENT COPIES RECIPIENT COPIES ID CODF/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR/DL/ADL 1 0 NRR LB2 BC 1 0 NRR L82 LA 1 0 AULUCKER ~ 01 1 1 INTERNAL; ELD/HOS2 1 0 IE FILE 1 1 IE/DEPER/EPB 36 3 3 IE/OEPER/IRB 35 1 1 IE/DEQA/QAB 21 1 1 NRR/DE/AEAB 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EHEB 1 1-NRR/DE/EQB 2 2 NRR/DE/GB 28 2 2 NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB, 24 1 1 NRR/DE/SGEB 25 1 NRR/DHFS/HFEB40 1 1 NRR/DHFS/LQB 32 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0 NRA/DS I/AEB 26 1 1 NRR/DS I/ASB 1 1 NRR/DS I/CPB 10 1 1 NRR/DSI/CSB 09 1 1 NRR/DSI/I CSB 16 1 1 NRR/DSI/h1ETB 12 1 1 NRR/DSI/PSB 19 NRR/DS I/RSB 23 RGNS 3 1

1 1

1 NRR FI RAB RM/DDAMI/MI 8 22 04 1,1 1

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0 EXTERNAL: ACRS 41 6 6 BNL(AMDTS ONLY) 1 1 DMB/DSS (AMDTS) 1 FEMA REP OIV 39 1 1 LPDR 03 1 1 NRC PDR 1 1 NSIC 02'TIS 05 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 53 ENCL 46

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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 October 28, 1983 G02-83-982 Docket No. 50-397 Director, Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

NUCLEAR PROJECT NO. 2 SUPPLY SYSTEM RESPONSE TO REVISED FSAR QUESTION 1'i0.42

Reference:

(a) Letter, A. Schwencer (NRC) to DW Mazur (SS),

dated October 12, 1983, subject, "Revised FSAR Question 110.42" (b) Letter, G02-83-584, GD Bouchey (SS) to A. Schwencer (NRC), dated June 30, 1983, subject, "Confirmatory Issue No. 7 - Component Supports" (c) Letter, G02-83-831, GC Sorensen (SS) to A. Schwencer (NRC), dated September 14, 1983, subject, "FSAR Question 110.42" The Washington Public Power Supply System hereby provides a reply to the revised FSAR Question 110.42 which was submitted as an attachment to reference (a) above. Our reply consists of this letter and two attach-ments. The initial FSAR Question 110.42 response was provided in Reference (c). The response to FSAR Question 110.40 was provided in Reference (b).

If you have any questions or desire further information, please contact P. L. Powell, Manager, WNP-2 Licensing.

Very truly yours,

~G. C. Sorensen, Acting Manager Nuclear Safety and Regulatory Program GCS:PWH:ch 831028 3i1080isb 05000397 PDR ADOCK PDR Attachments: (1) Response (2) Supporting Calculation No. 8.16.5037,"

pages 1-26, 70-80 cc: Mr. R. Auluck - NRC Mr. W. S. Chin - BPA Mr. A. D. Toth - NRC Resident Inspector

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Attachment 1 Page 1 of 3

, Revised FSAR uestion 110.42 I

"The applicant is requested to perform an assessment of its support design adequacy for 'the anchor group 37 of Reference 2. Specifically, the appli-cant should provide the final results of its assessment in detail to;!demon-strate compliance with the staff position described in Mechanical Engineering Branch SER Confirmatory Issue No. 7."

Su 1 S stem Res onse Anchor group 37 contains two (2) nozzles and 84 large bore supports including six (6) anchors. In addition to the two nozzles, 24 of these supports and the six anchors are thermally rigid. Our response to FSAR guestions 110.40 and the original FSAR guestion 110.42 provided summary Phase I load data on anchor group 37 support directions which, by observation, could not accept normal thermal loads in the faulted combination. Those loads have been refined as discussed in the response to FSAR guestion 110.43. The results of the Phase II effort have been compared to previously calculated support capacity in the following tabulation:

Previous Calculated Phase II Support Capacity Hanger Data Point Faulted Load (Less Than Number Number Combination ( ) Code:Allowables RHR-600 1329 Fx 4097 6577

-602 1252 Fy (Support loads were incorporated into RHR-601 since Phase I)

-601 1252 Fy 6421 12670

-601 1250 Fz 6872 18647

-605 1314 Fx 4133 9224

-358 1020 Fx 5884 12646

-366 4140 Fy 6220 11808

-368 2250 Fz 8250 11701

-267 213 Fx 4117 5737

-268 2102 Fx 2221 7308

-278 6202 Fx 3992 10532

-365 1220 Fx 6928 14436

-408 1245 Fx 3073 5929

-409 246 Fx 1692 3685

-409 246 Fz 3330 4906

-353 1034 Fx 4447 7647

-352 1034 Fz 12182 13882

-249 1345 Fx 6247 9583

-249 1345 Fy 3057 6982

-593 1992 Fx 4294 5139

"-594 990 Fz 3809 4465

-597 988 Fx 7630 6635 (1)

-582 1850 Fx 2224 4674

-583 1855 Fz 2140 4537

-266 1215 Fx 4723 11166

-606 1325 Fz 3986 5745 RCIC-116 121 Fx 2362 8693

-116 121 Fy 740 2647

-117 127 Fy 2295 8100

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Attachment 1 Page 2 of 3 Phase II Previous Calculated Anchor Anchor Data Point Faulted Load Capacity (Less than Number Number Combination Code Allowables RHR-975N 188 Fx 3644 5196 188 Fy 11604 11156 188 Fz 3515 4797 188 Mx 22925 30262 188 My 6340 4417 188 Mz 23920 39549 RC IC-912N 118 Fx 3070 4378 118 Fy 1917 2319 118 Fz 3970 4565 118 Mx 10671 16087 118 My 21576 31909 118 Mz 7461 5596 RHR-958N 3520 Fx 17109 25053 3520 Fy 10660 9555 3520 Fz 4536 5523 3520 Mx 28165 37564 3520 My 20732 23812 3520 Mz 75892 96828 RHR-238 201 Fx 4981 5702 201 Fy 13288 8935 201 Fz 8849 6869 201 Mx 55599 51494 201 My 7631 11636 201 Mz 37257 39761 RHR-970N(' ;431 Fx (':) (3) 7619 gl) 431 Fy ~"26653 431 Fz 3506 431 Mx 34530 431 My 10717 431 Mz 69833 RHR-410 248 Fx 6078 7441 248 Fy 19757 6663 248 Fz 6044 7564 248 Mx 37744 46110 248 My 10836 8834 248 Mz 34946 43374 In summary, the above tabulations demonstrate that all support direc-tions a} e acceptable when normal thermal loads are included in the faulted load combination. Only one support (RHR-597) and two anchors (RHR-238 and RHR-970N) experienced a Phase II load greater than the existing design load but less than the actual support capacity. Base-plates on all supports have been evaluated to confirm that IE Bulletin 79-02 criteria were met.

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Attachment 1 Page 3 of 3 In addition, the two nozzles in anchor group 37 (N-3 and N-4 on RHR heat exchanger lA) have been evaluated using the Phase II loads. As presented in our response to FSAR guestion 110.41, equipment nozzles react much the same as anchors with respect to the Phase II load com-bination. In turn, equipment supports are acceptable if nozzle allow-able loads are acceptable. In both nozzle cases the loads were acceptable;,

nozzlerN-3 is currently included in the scope of an unrelated evaluation using as-built conditions;. that evaluation utilizes thermal loads in the faulted combination.

As-built conditions, including actual weld sizes, were used throughout the anchor group 37 evaluation whenever available.

As requested in the FSAR question, detailed calculations are provided as attachments for the support and two anchors discussed above. Computer analysis referenced in the calculations has not been attached but is available if required.

FOOTNOTES:

(1) See attachment for actual support evaluation confirming adequacy.

(2) Phase II loads are the sums of thermal plus deadweight plus faulted dynamic plus faulted end movemment. Phase II faulted anchor load combinations are the sum of refined faulted loads including thermal from one side and the existing faulted load including thermal from the second side. Fx, Fy, and Fz are loads in pounds; Mx, My, and Mz are moments in footpounds.

(3) Consistent with the existing calculations, and note (2) above, all anchors were evaluated against absolute summations of Phase II 1oads except RHR-970N which users vector summations.

'I ATTACHMENT 2 Calcu1ation 8.16.5037, pages 1-26, 70-80