ML19284B792
| ML19284B792 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/19/1980 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19284B793 | List: |
| References | |
| NUDOCS 8101060353 | |
| Download: ML19284B792 (3) | |
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.DCCKET FILE ASR READING 3EC 19 1980 0Farr Docket Nos: 50-369/370 7
MEMORANDUM FOR:
B. J. Youngblood, Chief Licensing Branch 1 DOL FROM:
Olan D. Parr, Chief Auxiliary Systems Branch, DSI y
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SUBJECT:
SUtttARY OF MEETING ON DECEMBER 17, 1980
'On December 17, 1980, we met with Duke Power Company (DPC) at NRC office in Bethesda to discuss how the McGuire's AFWS reliability can be enhanced.
(Also see reference 1, 2, and 3.) A list of meeting attendees is attached.
DPC indicated that the reliability of McGuire's AFWS could be improved to at least the same degree for those operating Westinghouse plants as published in NUREG-0611, if operator action were taken into consideration. The operator action involves the opening of either the orificed control valves or the nomally closed isolation valves between the two motor driven pump trains. Since the time response requirements for AFW flow delivery for feed line rupture transient is approximately 10 minutes and the loss of feedwater transient is more than 20 minutes, thus allowing sufficient time for operator to take proper action. Other alternate operator action discussed was lowering the steam geeerator (SG) pressure which would allow higher AFW flow rate. Nevertheless, NRC staff suggested that DPC should, for the short term, re-examine the AFW flow requirement using realistic infomation such as SG water inventory and readtor power level. For the long tem. DFC should consider automating those neemally closed isolation valves between the motor drieen pump trains. DPC representatives indicated that they will consider the staff's suggestions.
origp1 sir *4 D Otan D. Patf Olan D. Parr, Chief
_ Auxiliary Systems Branch Division of Systems Integration
Enclosure:
As stated cc:
D. Eisenhut D. Ross P. Check 4.
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References:
1.
Surrnary of meeting held 6n October 28-29, 1980. McGuire Nuclear Station, Units 1 and 2.
2.
Duke Power Company's response, dated November 10, 1980, to NRC/Sandia Laboratories questions posted during the October 28-29, 1980 meeting at McGuire.
3.
Memo for B. J. Yount; blood from Olan D. Parr, cated December 4,1980.
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MEETING ATTENDEES Name Affiliation William E. Shopsky Westinghouse - Nuclear Safety - NTD David L. Canup Duke Power Co. - Design Engineering Glenn E. Lang Westingiiouse - Nuclear Safety Sam D. Alexander Duke Power - Design Eng.
G. A. Copp Duke Power - Licensing
- 0. D. Parr NRR/DSI/ASB G. L. Fidler Westinghouse - NC0D/ Projects Armand Lakner NRC/ DST /RRAB V. Leung NRR/DSI/ASB R. Ramirez NRR/DHFS/HFEB R. A. Birkel NRR A. Thadani NRR