ML19209C198
| ML19209C198 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/14/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Millen C PUBLIC SERVICE CO. OF COLORADO |
| References | |
| NUDOCS 7910120188 | |
| Download: ML19209C198 (1) | |
Text
CENTRAL FILES
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UNITE D STATES PDR:HQ NUCLEAR REGULATORY COMMISSION
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September 14, 1979 Docket No. 50-267 Public Serv..e Company of Colorado ATTN: Mr. C. K. Millen Senior Vice President Post Office Box 840 Denver, Colorado 80201 Ga.ti.' men:
The enclosed IE Information Notice provides information with regard to a potential unreviewed safety question involving high energy lines and control systems.
Sincerely, 7$ 55W%
Karl V. Seyfrit Director
Enclosures:
- 2. List of IE Information Notices Issued in the Last Six Months cc:
D. W. Warembourg, Nuclear Production Manager Fort St. Vrain Nuclear Station P. O. Box 368 Platteville, Colorado 80651 L. Brey, bbnager, Quality Assurance (Same Address) s i<
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
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po 936I9M IE Information Notice No. 79-22 Date:
September 14, 1979 Page 1 of 1 QUALIFICATION OF CONTROL SYSTEMS Public Service Electric and Gas Company notified the NRC of a potential unrev'.wed 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, 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, :uipment. These non-safety grade systems include:
Steam generator power operate'd relief valve control system Pressurizer power operated relief valve control systea 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 characteristics of the safety systems. Further, Westinghouse has recommended to their custemers that they review their systems to determine whether any unreviewed safety questions exist.
This IE Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the information for posstble applicability to their facilities. No specific action or response is reque sted 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.
No written response to this Information Notice is required.
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IE Information Notice No. 79-22 September 14, 1979 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Information Subj ect Date Issued To Notice No.
Issued 79-10 Nonconforming Pipe 4/16/79 All power reactor Support Struts facilities with a Construction Permit (CP) 79-11 Lower Reactor Vessel Head 5/7/79 All Holders of Reactor Insulation Support Problea Operating Licenses (OLs)
Construction Permits (cps) 79-12 Attempted Damage to New 5/11/79 All fuel facilities, Fuel Assemblics research reactors, and power reactors with an Operating Licensee (OL) or a Construction Permit (CP) 79-13 Indication of Low Water 5/29/79 All Holders of Operating Level in the Oyster Creek License (OL) or Reactor Construction Permit (CP) 79-14 NRC Position of Electrical 6/11/79 All Power Reactor Cable Support Systems facilities with a Construction Permit (CP) and applicants 79-15 Deficient Procedures 6/7/79 All Holders of Reactor Operating Licenses (OLs) and Construction Permits (cps) 79-16 Nuclear Incident at Three 6/22/79 All Research Reactors Mile Island and Test Reactors with Operating Licenses (OLs) 79-17 Source Holder Assembly 6/20/79 All Holders of Reactor Damage From Misfit Between Operating Licenses (OLs)
Assembly and Reactor Upper and Construction Grid Plate Permits (cps)
Enclosure Page 1 of 2 i'
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IE Information Notice No. 79-22 September 14, 1979 79-18 Skylab Reentry 7/5/79 All holders of Reactor Operating Licenses (OLs) 79-19 Pipe Cracks in Stagnant 7/17/79 All Holders of Reactor Borated Water Systems at Operating Licenses (OLs)
PWR Plants and Construction Permits (cps) 79-20 NRC Enforcement Policy 8/14/79 All Holders of Reactor NRC Licensed Individuals Operating Licenses (OLs) and Construction Permits (cps), Research Reactors, Test Reactors Licensees with Licensed Operators 79-21 Transportation and 9/7/79 All power and research Commerical Burial reactors with Operating of Radioactive Material License (OL)
Enclosure Page 2 of 2 i
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