GO2-83-982, 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: |
| 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 I ENCL QCSIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts K Related Correspondence NOTFS:
RECIPIENT ID CODF/NAME NRR/DL/ADL NRR L82 LA INTERNAL; ELD/HOS2 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQB NRR/DE/MEB 18 NRR/DE/SAB, 24 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRA/DSI/AEB 26 NRR/DS I/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DS I/RSB 23 RGNS EXTERNAL: ACRS 41 DMB/DSS (AMDTS)
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1 RECIPIENT ID CODE/NAME NRR LB2 BC AULUCKER~
01 IE FILE IE/OEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/DSI/h1ETB 12 NRR RAB 22 FI 04 RM/DDAMI/MI8 BNL(AMDTS ONLY)
FEMA REP OIV 39 NRC PDR 02'TIS COPIES LTTR ENCL 1
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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
Dear Mr. Schwencer:
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 3i1080isb 831028 PDR ADOCK 05000397 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:
Hanger Number Data Point Number Previous Calculated Phase II Support Capacity Faulted Load (Less Than Combination
(
)
Code:Allowables RHR-600
-602
-601
-601
-605
-358
-366
-368
-267
-268
-278
-365
-408
-409
-409
-353
-352
-249
-249
-593
"-594
-597
-582
-583
-266
-606 RCIC-116
-116
-117 1329 Fx 1252 Fy 1252 Fy 1250 Fz 1314 Fx 1020 Fx 4140 Fy 2250 Fz 213 Fx 2102 Fx 6202 Fx 1220 Fx 1245 Fx 246 Fx 246 Fz 1034 Fx 1034 Fz 1345 Fx 1345 Fy 1992 Fx 990 Fz 988 Fx 1850 Fx 1855 Fz 1215 Fx 1325 Fz 121 Fx 121 Fy 127 Fy 4097 (Support loads RHR-601 since 6421 6872 4133 5884 6220 8250 4117 2221 3992 6928 3073 1692 3330 4447 12182 6247 3057 4294 3809 7630 2224 2140 4723 3986 2362 740 2295 6577 were incorporated into Phase I) 12670 18647 9224 12646 11808 11701 5737 7308 10532 14436 5929 3685 4906 7647 13882 9583 6982 5139 4465 (1) 6635 4674 4537 11166 5745 8693 2647 8100
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Attachment 1
Page 2 of 3 Anchor Number RHR-975N RC IC-912N RHR-958N RHR-238 RHR-970N('
gl)
RHR-410 Data Point Number 188 Fx 188 Fy 188 Fz 188 Mx 188 My 188 Mz 118 Fx 118 Fy 118 Fz 118 Mx 118 My 118 Mz 3520 Fx 3520 Fy 3520 Fz 3520 Mx 3520 My 3520 Mz 201 Fx 201 Fy 201 Fz 201 Mx 201 My 201 Mz
- 431 Fx 431 Fy 431 Fz 431 Mx 431 My 431 Mz 248 Fx 248 Fy 248 Fz 248 Mx 248 My 248 Mz Phase II Faulted Load Combination 3644 11604 3515 22925 6340 23920 3070 1917 3970 10671 21576 7461 17109 10660 4536 28165 20732 75892 4981 13288 8849 55599 7631 37257
(':) (3) 6078 19757 6044 37744 10836 34946 Previous Calculated Anchor Capacity (Less than Code Allowables 5196 11156 4797 30262 4417 39549 4378 2319 4565 16087 31909 5596 25053 9555 5523 37564 23812 96828 5702 8935 6869 51494 11636 39761 7619
~"26653 3506 34530 10717 69833 7441 6663 7564 46110 8834 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.
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ATTACHMENT 2 Calcu1ation 8.16.5037, pages 1-26, 70-80