ML20071H016
| ML20071H016 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick |
| Issue date: | 05/20/1983 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| GL-83-08, GL-83-8, JPN-83-46, NUDOCS 8305240463 | |
| Download: ML20071H016 (2) | |
Text
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h POWER AUTHORITY OF THE STATE OF NEW YORK t o CoLUMaus CIRCLE,..
NEW YORK, N.Y.1 o019 (212) 397-6200 LERoy w. sINCLAIR
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TRUSTEES WAL ER CINSKI JTMN S. DYSON nees anme, sr.avove
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G'!qsGE L. INGALLS May 20, 1981
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KSCHARD M. FLYNN JPN-83-46 JAMES t LAROCCA STEPHEN L BAUM
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muANo E. KiooER Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Domenic B. Vassallo, Chief Operating Reactor Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Generic Letter 83 Vacuum Breakers
Reference:
1.
NRC Generic letter 83-08, D.G. 5isenhut to L.W.
Sinclair, dated February 2, 1983.
Dear Sir:
Reference 1 requested a commitment to submit the results of the plant unique calculations which either formed the bases for vacuum breaker modifications or provided justification for their as-built acceptability.
Reference 1 also requested schedules for completion of any modifications. addresses these requests.
If you require any further information, please contact Mr.
J.A.
Gray, Jr. of my staff.
Very truly yours, B,ne J.P.
Bay Executive Vice President Nuclear Generation CO/
cc:
Mr. J.
Linville i
Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 136 Lycoming, New York 13093 G305240463 830520 PDR ADOCK 0S000333 P
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT ATTACHMENT -1 TO JPN 46 DATED May 20, 1983 As a result of the Mark I Owners Group effort, a plant unique analysis was performed to address potential failure of the torus to drywell vacuum breakers at FitzPatrick.
This report was prepared by Continuum Dynamics, Inc., and is entitled " Improved Dynamic Vacuum Breaker Valve Response for FitzPatrick", Revision 0, dated September, 1982.
The report addresses potential failure of the vacuum breakers in the chugging phase of blowdown to the torus during a loss-of-coolant accident.
It concludes that "the vacuum breakers in the FitzPatrick plant are predicted to not actuate during the chugging transient".
Based on this conclusion, the Authority maintains that no modifications to the subject valves are necessary, and that the Continuum Dynamics report forms the basis for justification of the valves' as-built acceptability.
Nevertheless, as a consequence of SIL #321 issued by the General Electric Company in December 1979, the Authority has implemented certain actions to address the General Electric suggestions.
In addition, the Authority is participating in a further study being performed through the Mark I Contain'nent Program concerning the report prepared by Continuum Dynamics, Inc..
This further work is being done as a result of recent NRC reviews of Mark I Plant Unique Analysis Report submittals.
Until this study is completed and the results evaluated, the Authority considers the 30 inch diameter Atwood Morrill vacuum breakers at the FitzPatrick Plant acceptable.
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