GO2-83-090, Forwards Applicability of Use of Square-Root-of-Sum-of- Square (Srss) Method for Combining Peak Dynamic Responses for Wa Nuclear Plant 2, Per .Rept Satisfies NUREG-0892 SER Confirmatory Item 6
| ML17277A463 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/03/1983 |
| From: | Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17277A464 | List: |
| References | |
| RTR-NUREG-0892, RTR-NUREG-892 GO2-83-090, GO2-83-90, NUDOCS 8303010357 | |
| Download: ML17277A463 (4) | |
Text
REGUI.ATORY ORNATION OISTRISUTION SYS'II<< (RIOSI AGCESSIO NBR: 8303010357 DOC ~ DATE: 83/02/03 NOTARIZED:
NO DOCKET FACIL:50 397 WPPSS Nuclear Projectg Unit 2~ Nashington Public Powe 05000397 AUTH'AME AUTHOR AFFILIATION BOUCHEY~G ~ DE washington Public Power Supply 'System
>RECIP,NAME RECIPIENT AFFILIATION SCHKENCERgA ~
Licensing Branch "2
~P C
SUBJECT:
Forwards."Appl icabil i ty of Use of Squar e Root of Sum of" Square
('SRSS)
Method for Combining Peak Dynamic Responses for NA Nuclear Plagt 2g," per 821103 l.tr,Rept satisfies NUREG-0892 SER Confirmatory Item 6, DISTRIBUTION CODE:
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 February 3, 1983 G02-83-090 Docket No. 50-397 Director of 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:
Reference:
NUCLEAR PROJECT NO.
2 SRSS COMBINATION OF DYNAMIC RESPONSES CONFIRMATORY ITEM NO.
6 OF NUREG-0892 Letter G02-82-886, G.D. Bouchey (SS) to A. Schwencer (NRC),
Same Subject, dated November 3, 1982 The referenced letter committed to submit a final technical report summari-zing results of the "Applicability of the Use of the Square-Root-of-the-Sum-of-Squares (SRSS)
Method for Combining Peak Dynamic Responses to Dynamic Loads for WNP,-2".
The scope of this study is in line with previous correspondence and discussions with the NRC.
Combinations of dynamic responses due to safety relief valve (SRV) discharge and seismic loads are considered at loca-tions typical of the containment vessel in the drywell region.
The study includes 96 combination samples of acceleration or displacement responses due to OBE or SSE seismic loading and single valve or all valve SRV loading.
Enclosed are sixty (60) copies of this report, which closes Confirmatory Item No. 6, Section,3.9.3.1 of NUREG-0892.
Very truly yours, G..D. Bouchey
- Manager, Nuclear Safety and Regulatory Programs jca Enclosure cc:,
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