ML19343A080
| ML19343A080 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/19/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8009160035 | |
| Download: ML19343A080 (1) | |
Text
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CENTRAL FILES
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NUCLEAR REGULATORY COMMISSION PDR:HQ
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August 19, 1960 Docket No, 50-298 Nebraska Public Power District ATTN:
J. M. Pilant, Director Licensing & Quality Assurance Post Office Box 499 Columbus, Nebraska 68601 Gentlemen:
This IE Information Notice is provided as an early notification of a possibly significant matter.
I:: is expected that recipients will review the. informa-tion for possible applicability to their facilities.
No specific action or response is requested at this time.
If further NRC evaluations so indicate, an II Circular or 3ulletin will be issued to recommend or request specific licensee actions.
If you have questions.regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely,
,O N
M c b N A(
- W N o Seyfrit I
k @ Karl V.
Director
Enclosures:
1.
II Infor=ation Notice No. 80-30 2.
Recently Issued II' Information Notices cc:
L. C. Lessor, Superintendent Cooper Nuclear Station Post Office Box 98 3rownville, Nebraska 68321 l
800g1gg OQG
SSINS No.:6870 Accession No.:
80061900S7 IN 80-30 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 19, 1980 IE Information Notice No. 80-30:
POTENTIAL FOR UNACCEPTABLE INTERACTION BETWEEN THE CONTROL ROD DRIVE SCRAM FUNCTION AND NON-ESSENTIAL CONTROL AIR AT CERTAIN GE BWR FACILITIES Continued NRC evaluation of possible failure modes of the centrol rod drive system related to the Browns Ferry event (IE Bulletin 80-17), has identified a
- potentially significant single failure mechanism which could degrade the scram function. The slow loss of non-essential control air pressure could degrade the scram function e.t certain facilities which have relatively poor communica-tion between the scram discharge volume (SDV) and the scram discharge instru-mented volume (SDIV) such that the SDIV drains more rapidly than the SDV drain rate into the SDIV.
The significance of such a single failure warrants transmission of an interim assessment by the NRC Office for Analysis and Evaluation of Operational Data as an early notification of a possibly significant matter that is still under review by the NRC staff.
It is expected that recipients will review the information for possible applicability to their facility.
No specific action or response is requested at this time.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Enclosure:
Memo from C. Michelson to H. Denton, dated August 18, 1980 DUPLICATE DOCUMENT Entire document previously entered into system under:
ANO 90%l8I e eG "I No. of pages: J
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