ML20151U964
| ML20151U964 | |
| Person / Time | |
|---|---|
| Issue date: | 08/08/1988 |
| From: | Rossi C Office of Nuclear Reactor Regulation |
| To: | Grace D BWR OWNERS GROUP, GENERAL PUBLIC UTILITIES CORP. |
| References | |
| IEB-85-003, IEB-85-3, NUDOCS 8808220002 | |
| Download: ML20151U964 (2) | |
Text
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- AUG 0 81988 Donald N. Grace, Chairman f-[
Boiling Water Reactor Owners' Group c/o GPU Nuclear i Upper Pond Road, Building E Parsippany, New Jersey 07054
Dear Mr. Grace:
Terrance A. Picken's letter of September 2, 1986 forwarded a copy of NEDC-31322, "BWR Owners' Group Report on the Operational Design Basis of Selected Safety-Related Motor-0perated Valves." It is our understanding that this report is to be used by the member utilities as a basis for the selection of valves and their maximum expected differential pressures in preparation of their responses to Bulletin 85-03, "Motor-0perated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings."
Our review of the BWR Owners' Group report prompted a request for additional in-formation which was forwarded to Mr. Pickens in Mr. Edward L. Jcrdan's letter of January 30, 1987. The NRC staff's review of Robert F. Janecek's August 5,1987 response to this request fer additional information indicated that there was a basic misunderstanding as to which valves should be addressed in the licensees' responses to the bulletin. This, plus numerous telephone conversations between our staffs, led to the issuance of Supplement 1 to Bulletin 85-03 on April 27, 1988.
Your letter of July 20, 1988 forwarded a copy of Supplement 1 to NEDC-31322.
Our review of this supplement indicates that it resolves the issue concerning which valves are to be addressed in the licensees' responses to the bulletin and supplement.
Therefore, we have concluded that NEDC-31322, as amended by Supplement 1, presents an acceptable methodology for selection of valves and their maximum expected differential pressure in response to Bulletin 85-03 and Supplement 1 to Bulletin 85-03.
Sincerely, (5 I 9808220002B$hE PDR TOPRP E PDR C Charles E. Rossi, Director Divisicn of Operational Events Assessment Office of Nuclear Reactor Regulation DISTRIBUTION w/NEDC-31322 and its supplement SARichards, RV MPHuber, Rlll TKoshy, RI DENorman, RIV SGTingen, RII DISTRIBUTION w/o NEDC-31322 and its supplements TTMartin, NRR LJCallan, RIV AFGibson, RII EGGreenman, RIII WVJohnston, RI WFKane, RI DFKirsch, RV JLMilhoan, RIV dIQ HJMiller, RIII LAReyes, RII EJBrown, AE0D 8 '
TMRoss, NRR RJKiessel, NRR 00Rothberg, RES CERossi, NRR CHBerlinger, NRR
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lh1 Kiessel R/F WDLanning, NRR DOEA R/F PDR DCS OGCB R/F Central. Files /$ ,
- SEE PREVIOUS CONCURRENCES
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Donald N. Grace, Chairman Boiling Water Reactor Owners' Group c/o GPU Nuclear 1 Upper Pond Road, Building E '
Parsippany, New Jersey 07054 1
Dear Mr. Grace:
Terrance A. Picken's letter of September 2, 1986 forwarded a copy of NEDC-31322, "BWR Owners' Group Report on the Operational Design Basis of Selected Safety-Related Motor-0perated Valves." It is our understanding that this report is to be used by the member utilities as a basis for the selection of valves and their maximum expected differential pressures in preparation of their responses ;
to Bulletin 85-03, "Motor-0perated Valve Common Mode Failures During Plant l Transients Due to Improper Switch Settings." )
Our review of the BWR Owners' Group report prompted a request for additional in-formation which was forwarded to Mr. Pickens in Mr. Edward L. Jordan's letter of 1 January 30, 1987. The NRC staff's review of Robert F. Janecek's August 5, 1987 ;
response to this request for additional information indicated that there was a l basic misunderstanding as to which valves should be addressed in th' 'icensees' !
responses to the bulletin. This, plus numerous telephone conversations between our staffs, led to the issuance of Supplement 1 to Bulletin 85-03.
Your letter of July 20, 1988 forwarded a copy of Supplement 1 to NEDC-31322. )
Our review of this supplement indicates that it resolves the issue concerning l which valves are to be addressed in the licensees' respor.ses to the bulletin l and supplement. 1 Therefore, we have concluded that NEDC-31322, as amended by Supplem.!nt 1, I presents an acceptable methodology for selection of valves and their maximum i expected differential pressure in response to Bulletin 85-03 and Supplement 1 l to Bulletin 85-03. j Sincerely, l l
Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation ,
__0istribution - See next page i
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8/f/88 8/ ' /88 8/ /88 l 1
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