ML19323B672
| ML19323B672 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/25/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 8005140054 | |
| Download: ML19323B672 (3) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION r
wAssiNcToN. o. c.20sss bE APRIL 2 5 1980 Docket Nos. 50-325 and 50-324 Mr. J. A. Jones Executive Vice President Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602
Dear Mr. Jones:
SUBJECT:
EFFECT OF A DC POWER SUPPLY FAILURE ON ECCS PERFORMANCE It has generally been recognized that the loss of a direct current (DC) power supply could disable several emergency core cooling system cogenants and thereby could result in a limiting single failure condition for some breaks. The enclosed letter report was submitted to the NRC staff by the General Electric Cogany to provide a definitive, generic, reference analysis of the effects of DC power supply failures on ECCS conformance calculations. The NRC staff is reviewing the analysis which compares the peak cladding tegeratures associated with various postulated DC power supply failure (ECCS egipment availability) cases to the peak cladding tegeratures for a HPCI (small break) failure and LPCI injection valve (large break) failure cases.
Since the study was based on plant design information which may have been incoglete or out-of-date, some uncer-tainty exists whether the worse ECCS system availability combinations have been identified for your operating Bh"As.
Accordingly, in order that we may have an adequate level of assurance that the systems com-binations assumed in the generic analysis are conservative for Brunswick Steam Electric Plant Units 1 'and 2, we request that you confirm the conclusion of the reference study regarding the mininum ECCS equipment availability with a DC power supply failure.
Include in your response a list of the ECCS equipment that would be available for large and small (1) recirculation loop discharge breaks, and (2) recirculation loop suction breaks. The listing of equipment available should take into account not only DC power supply failure, but also loss of equipment due to water spillage.
Please provide a schedule for your response within 30 days of the receipt of this letter.
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2-APRIL 2512D Mr. J. A. Jones This request for generic information was approved by GA0 under clearance number B-180225(579018); this clearance expires October 31, 1980.
Sincerely, W
Th s A. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Enclosure:
General Electric Conpany letter (R. E. Engel) to USNRC (P. S.
Check), "DC Power Source Failure for BWR/3 and 4," dated November 1, 1978.
cc w/ enclosure:
See next page 9
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APRIL 2 5 Emo Mr. J. A. Jones --
cc:
Richard E. Jones, Esquire Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 George F. Trowbridge, Esquire Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 John J. Burney, Jr., Esquire Burney, Burney, Sperry & Barefoot 110 North Fifth Avenue Wilmington, North Carolina 28401 Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 1057 Southport, North Carolina 28461 Southport - Brunswick County Library 109 W. Moore Street Southport, North Carolina 28461 Mr. Fred Tollison Plant Manager P. O. Box 458 Southport, North Carolina 28461
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