ML17256A664

Forwards Containment Vessel Evaluation of Dome Liner & Studs, Re SEP Topic III-7.B, Load Combinations (Containment Liner Analysis).

ML17256A664
Person / Time
Site:	Ginna
Issue date:	04/28/1983
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
Shared Package
ML17256A666	List: ML17256A664 ML17256A668
References
TASK-03-07.B, TASK-3-7.B, TASK-RR NUDOCS 8305060271
Download: ML17256A664 (4)

Text

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'ACCESSION NBR:8305060271 DOC DATE: 83/04/28 NOTARIZED: NO DOCKET FACIL:50 BYNAME244 Robert Emme,t

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Ginna Nuclear Plant~ Unfit ii Rochester G 05000244

'AUTH AUTHOR AFFILIATION MAIERg J,E ~ Rochester Gas 8 Electric

~ NAME RECIPIENT AFFILIATION Corp'ECIP CRUTCHFIELDgD ~ Operating Reactors Branch 5

SUBJECT:

Forwards,"Containment Vessel Evaluation of Dome Liner L Studsi" re SEP,Topic III-"7'~ "load Combinations (Containment Liner Analysis) ~ ,"

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DISTRIBUTION CODEt A035S,COPIES RECEIVED:LTR ( "ENCL ( SIZE+..'baE

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TITlE: OR Submittal: SEP Topic NOTES;NRR/DI./SEP 1cy, 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCI- ID CODE/NAME LTTR ENCL NRR ORB5 BC 01 3 3 INTERNAL: NRR/DL/ORAB 11 1 1 NRR/DL/SEPB 12 3 -3 1 1 NRR/DS I/CSB 07 1 1 EG FJ 04 1 1 RGN1 1 EXTERNAL: ACRS 14 e LPDR 03 1 1 NRC PDR 02 1 1 NTIS 5 1 1 NOTES: 1 1 (TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCl 21

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VOHt4 8< MAILER TEI.EPHOHE Vice Preeident AREA coDE Tle 546.2700 April 28, 1983 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

SEP Topic III-7.B, Load Combinations (Containment Liner Analysis)

R. E. Ginna Nuclear Power Plant Docket 50-244

Dear Mr. Crutchfield:

Enclosed is a report "Containment Vessel Evaluation of Dome Liner and Studs" prepared by Gilbert/Commonwealth for Rochester Gas and Electric. The purpose of the report is to describe the analysis performed to evaluate the post-accident behavior of the containment liner and studs. The conclusion reached in the report is that failure of some studs in certain areas of the liner, although not expected, is possible. However, it is determined that this condition would not cause tearing of the liner, and thus would not prevent the liner from maintaining its post-accident leak-tight integrity.

As a point of clarification, it should be noted that the accident pressure and temperature profiles used in NUREG/CR-2580 (the SMA/LLL liner analysis) are for the steam line break condition, rather than a LOCA, as implied. This is obvious from the LLL analysis presented in Appendix A to the Safety Evaluation Report for SEP Topics VI-2.D and VI-3, Mass and Energy Release for Pipe Breaks Inside Containment", November 3, 1981. Nonetheless, as shown by the attached analysis, the liner integrity will be maintained for all accident situations.

Very truly yours, J n E. Maier C

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