ML19249F311
| ML19249F311 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay, Diablo Canyon |
| Issue date: | 09/17/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Crane P PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7910110300 | |
| Download: ML19249F311 (1) | |
Text
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UNITED STATES E
NUCLEAR REGULATORY COMMISSION o
5-E nEGION V h
1990 N. CALIFORNIA BOULEVARD k ','-M '[ #
o SulTE 202, WALNUT CREEK PLAZA e
,,y WALNUT CREEK, CALIFORNIA 94596 September 17, 1979 Docket flos. 50-133 50-275 50-323 Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94105 Attention: Mr. Philip A. Crane, Jr.
Assistant General Counsel Gentlemen:
The enclosed Information flotice No. 79-22 provides information with regard to a potential unreviewed safety question involving high energy lines and control systems.
Sincerely, kYmdC~--
R. H. Engelken Director [-
Enclosures:
1.
List of IE Information Notices Issued in Last Six Months cc w/ enclosures:
H. Barr, PG&E W. Raymond, PG&E R. Ramsay, PG&E, Diablo Canyon J. Worthington, PG&E E. Weeks, PG&E, Humboldt Bay
}0/6 072 7910110300
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vf Accession flo: 79082201I2 SSINS:
6870 UtlITED STATES flVCLEAR REGULATORY COMMlSSION OFFICE OF INSPECTION AND ENFORCEMEilT WASHIflGTON, D.C.
20555 September 14, 1979 IE Information flotice fio. 79-22 OVALIFICATI0f: OF CONTROL SYSTEtiS Public Service Electric and Gas Company notified the NRC of a potential unreviewed safety question at their Salem Unit 1 facility.
This notification was based on a continuing review by Westinghouse of the environmental qualifications of equipment that they supply for nuclear steam supply systems. Based on the present statto of this effort, Westinghouse has informed their customers that the performance of non-safety grade equipment subjected to an adverse environnent could impact the protective functions performed by safety grade equipment. These non-safety grade systems include:
Steam generator power operated relief valve control system Pressurizer power operated relief valve control system Main feedwater control system Automatic rod control system These systems could potentially malfunction due to ahigh energy line break inside or outside of containment. NRC is also concerned that the adverse environment could also give erroneous information to the plant operators.
Westinghouse states that the consequences of such an event could possibly be more limiting than results presented in Safety Analysis Reports, however, Westinghouse also states that the severity of the results can be limited by operator actions together with operating characterisitics of the safety systems.
Further, Westinghouse has recommended to their customers that they review their systems to determine whether any unreviewed safety questions exist.
This Information flotice is provided as an early notification of a possibly significant natter.
It is expected that recipients will review the information for possible applicability to their facilities.
fio specific action or response is requested at this time.
If NRC evaluations so indicate, further licensee actions may be requested or required.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office, flo written response to this Information Motice is required.
107; 073
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