ML18136A041
| ML18136A041 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 09/14/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 7910110279 | |
| Download: ML18136A041 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 SEP 14 1979 Virginia Electric and Power Co~pany Attn:
W.L. Proffitt Senior Vice President Post Office Box 26666 Richmond, Virginia 23261 Gentlemen:
The enclosed Information Notice provides information with regard to a potential unreviewed safety question involving high energy lines and control systems.
Enclosures:
- 2. List of IE Information Notices Issued in the Last Six Months Sincerely, J!Lfi~
Ja~*P. O'Reil.<<y Director
- i.
19101102 7 9
Virginia Electric and Power Company cc w/encl:
W.R. Cartwright, Station Manager Box 402 Mineral, Virginia 23117 P.G. Perry Senior Resident Engineer Post Office Box 38 Mineral, Virginia 23117 W.L. Stewart, Manager Post Office Box 315 Surry, Virginia 23883 e September 14, 1979
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Accession No: 7908220Il&
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 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, 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 po,ssibly 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 matter, please contact the Director of the appropriate NRC Regional Office.
No written response to this Information Notice is required.
IE Information Notice No. 79-22 September 17, 1979 LISTING OF IE INFORMATION NOTICES ISSUED IN LAST SIX MONTHS Information Notice No. 79-22 79-21 79-20 (Rev. 1) 79-20 79-19 (Correction -
Enclosure) 79-19 79-18 79-17 79-16 79-15 79 Subject Qualification of Control Systems Transportation and Commer-cial Burial of Radioactive Materials NRC Enforcement Policy NRC Licensed Individuals NRC Enforcement Policy NRC Licensed Individuals Pipe Cracks in Stagnant Borated Water Systems at PWR Plants Pipe Cracks In Stagnant Borated Water Systems At PWR Plants Skylab Reentry Source Holder Assembly Damage Damage From Misfit Between Assembly and Reactor Upper Grid Plate Nuclear Incident at Three Mile Island Deficient Procedures NRC Position of Electrical Cable Support Systems Date Issued 9/17/79 9/14/79 9/11/79 9/7 /79 8/14/79 7 /18/79 7/17/79 7/6/79 6/20/79 6/22/79 6/7 /79 6/11/79 Enclosure Page 1 of 2 Issued To All Holders of CPs All Holders of OLs All Licensees as Supple-mental Information to IE Bulletin Nos. 79-19
& 79-20 All Holders of Reactor OLs and CPs and Production Licensees with Licensed Operators All Holders of Reactor OLs and CPs and Production Licensees with Licensed Operators All Holders of Reactor OLs and CPs All Holders of Reactor OLs and CPs All Holders of Reactor OLs All Holders of Reactor OLs and CPs All Research Reactors and Test Reactors with OLs All Holders of Reactor OLs and CPs All Power Reactor Facilities with a CP
IE Information Notice No. 79-22 September 17, 1979 LISTING OF INFORMATION NOTICES ISSUED IN LAST SIX MONTHS Information Notice No. 79-13 79-12 79-11 79-10 Subject Indication of Low Water Level in the Oyster Creek Reactor Attempted Damage to New Fuel Assemblies Lower Reactor Vessel Head Insulation Support Problem Nonconforming Pipe Support Struts Date Issued 5/29/79 5/10/79 5/7 /79 4/16/79 e
Enclosure Page 2 of 2 Issued To All Holders of Reactor OLs and CPs All Fuel Facilities Research Reactors, and Power Reactors with an 01 or CP All holders of Reactor OLs and CPs All power reactor facilities with a CP