ML19343A082
| ML19343A082 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/19/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | John Miller GEORGIA POWER CO. |
| References | |
| NUDOCS 8009160039 | |
| Download: ML19343A082 (1) | |
Text
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UNITED STATES d
NUCLEAR REGULATORY COMMISSION o
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101 MARIETTA ST., N.W..SUITF 3100 b
ATLANTA, GEORGIA 3o303 o
In Reply Refer To:
1 S 1980 R 4JPON
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Georgia Power Company
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ATTN:
J. H. Miller, Jr.
Executive Vice President 270 Peachtree Street Atlanta, GA 30303 Gentlemen:
This Information Notice is provided as an early notification of a possibly signi-ficant matter.
It is expected that recipients will review the information for possible applicability to their facilities. No specific action or response is
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requested at this time. If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions. If f
you have questions regarding this matter, please contact the Director of the appro-priate NRC Regional Office.
Sincerely, James P. O'Reill Director
Enclosures:
1.
IE Information Notice No. 80-30 2.
List of Recently Issued IE Information Notices cc w/ encl:
M. Manry, Plant Manager C. E. Belflower, Site QA Supervisor W. A. Vidner, Vice President and Genreral Manager-Nuclear Generation
SSINS No.:6870 Accession No.:
8005190057 IN 80-30 UNITED STATES NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 19, 1980 IE Information Notice No. 80-30:
POTENTIAL FOR UNACCEPTABLE INTERACTION l
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 control 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 at 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 c~ 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 9 0 % 1 9 e c 6 "1 No. of pages:
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