ML19249F318
| ML19249F318 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/14/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 7910110307 | |
| Download: ML19249F318 (1) | |
Text
'o UNITE D STATES 8 'v,
8g NUCLEAR REGULATORY COMMISSION T/'
n 5-hI. E itEGION V
'A/.3 1990 N. CALIFORNI A P.OULE VARD g ' # I - *I g' SulTE 202, t/ALNUT CREEK PLAZA WALNUT CI1EE K, CALIFORNI A 0*,595 4 4,,a September 14, 1979 Docket t'o. 50-312 Sacrar. ento Municical Utility District P. O. Box 15330 Sacramento, California 95813 Attention:
Mr. John J. Mattimoe Assistant General Manager Gentlemen:
The enclosed Information liotice No. 79-22 provides information with regard to a potential unreviewed safety question involving high energy lines and control systems.
Sincerely,
/btF~,a L~-
R. H. Engelken Director
Enclosures:
1.
Information !!otice 79-22 x
2.
List of IE Information tiotices Issued in Last Six Months cc w/ enclosures:
R. J. Rodriguez. SMUD L. G. Schwieger, SMUD 1076 082 7910110307
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Accession No: 79082201E SSINS:
6870 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSI'ECTION AND ENFORCEMENT -
WASHINGTON, D.C.
20555 September 14, 1979 IE Infermation l'otice No. 79-22 QUALIFICATION OF CONTROL SYSTEMS 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 status of this effort, Westinahouse has informed their customers that the performance of non-safety grade quipment subjected to an adverse environment 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 aiich 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 consegmces 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 Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or response is rcquested at this time.
If NRC evaluations so indicate, further licensee actions may be requested or required.
If you have questions regarding this natter, please contact the Director of the appropriate NRC Regional Office.
No written response to this Information Notice is required.
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