ML19254B399
| ML19254B399 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/14/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Bryan J UNION ELECTRIC CO. |
| References | |
| NUDOCS 7909270472 | |
| Download: ML19254B399 (1) | |
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UMTED STATES 3,
o NUCLEAR REGULATORY COMMISSION A'
.E REGION lli t
799 ROOSEVELT ROAD OLEN ELLYN. ILLINOIS 60137 e
SEP 1418/9 Docket No. 50-483 Docket No. 50-486 Union Electric Company ATIN:
Mr. John K. Bryan Vice President - Nuclear P. O. Box 149 St. Louis, MO 63166 Gentlemen:
The enclosed IE Information Notice No. 79-22 provides information with regard to a potential unreviewed safety question involving high energy lines and control systems.
Sincerely, CwAN
[/ James G. Kep er Director
Enclosures:
1.
IE Information Notice No. 79-22 2.
List of IE Information Notices Issued in the Last Six Months cc w/ enc 1:
Mr. W. H. Weber, Manager, Nuclear Construction Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Region I & IV Ms. K. Drey Hon. C. J. Frass, Chairman Missouri Public Service Commission j
,048 127 I90927047]
14
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Accession No: 790822018e SSINS: 6870 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 September 14, 1979 IE Information Notice No. 79-22 QUALIFICATION OF CONTROL SYSTFMS Public Service Electric and Gas Company notified the NRC of a potential unreviewed safety question at their Salem Unit I 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, Westinghouse has informed their customers that the performance of non-safety grade equipment 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 a high 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 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 requested at this time.
If NRC evaluations so indicate, further licensee actions may be requested or required.
If you have questions regarding this mattei please contact the Director of the appropriate NRC Regional Office.
No written respcase to this Information Notice is required.
1048 128
IE Information Notice No. 79-22 Enclosure September 14, 1979 Page 1 of 2 LISTING OF IE INFORMATION NOTICES ISSUED IN LAST SIX MONTHS Information Subject Date Issued To Notice No.
Issued 79-05 Use of Improper Materials 3/21/79 All power reactor in Safety-Related Components facilities with an OL or CP 79-06 Stress Imalysis of 3/23/79 All Holders of Safety-Related Piping Reactor OL or CP 79-07 Rupture of Radwaste Tanks 3/26/79 All power reactor facilities with an OL or CP 79-08 Interconnection of 3/28/79 All power reactor Cont;minated Systems with facilities with an Service Air Systems Used OL and Pu Processing As the Source of Breathing fuel facilities Air 79-03 Spill of Radioactively 3/30/79 All power reactor Contaminated Resin facilities with an OL 79-10 Nonconforming Pipe 4/16/79 All power reactor Support Struts facilities with a CP 79-11 Lower Reactor Vessel Head 5/7/79 All holders of Reactor Insulation Support Problem OLs and cps 79-12 Attempted Damage to New 5/11/79 All Fuel Facilities Fuel Assemblies Research Reactors, and Power Reactors with an OL or CP 79-13 Indication of Low Water 5/29/79 All Holders of Reactor Level in the Oyster Creek OLs and cps Reactor 79-14 NRC Position of Electrical 6/11/79 All Power Reactor Cable Support Systems Iacilities with a CP I
Deficien4 Procedures 6/7/79 All Holders of Reactor 79-15 i
OLs and cps 1048 129
a IE Information Notice No. 79-22 Enclosure September 14, 1979 Page 2 of 2 LISTING 01 IE INFORMATION NOTICES ISSUED IN 1979 Information Subject Date Issued To Notice No.
Issued 9
79-16 Nuclear Incident at Three 6/22/79 All Research Reactors Mile Island and Test Reactors with OLs 79-17 Source Holder Assembly Damage 6/20/79 All Holders of Reactor Damage From Misfit Between OLs and cps Assembly and Reactor Upper Grid Plate 79-18 Skylab Reentry 7/5/79 All Holders of Reactor OLs 79-19 Pipe Cracks In Stagnant 7/17/79 All Holders of Reactor Borated Water Systems At OLs and cps PWR Plants 79-20 NRC Enforcement Policy 8/10/79 All Holders of Reactor NRC Licensed Individuals OLs and cps and Productic Licensees with Licensed i
Operators 79-21 Transportation and Commercial 9/7/79 All power and research Burial of Radioactive Material reactors with OL's
.