ML17053B037
| ML17053B037 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/14/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider R NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 7909270425 | |
| Download: ML17053B037 (8) | |
Text
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Docket No. 50-220 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA19406 SEP i4 III79 eleven E.
'iagara Mohawk Power Corporation ATTN:
Mr.
R.
R. Schneider Vice President Electric Operations 300 Erie Boulevard Mest
- Syracuse, New York 13202 Gentlemen:
The enclosed Information Notice provides information with regard to a potential unreviewed safety question involving high energy lines and control systems.
Sincerely,
~
~
~
Boyce H. Grier Director
Enclosures:
l.
IE Information Notice No. 79-22 2.
List of IE Information Notices Issued in the Last Six Months cc w/encls:
T.
E.
- Lempges, General Superintendent, Nuclear Generation T. J. Perkins, Station Superintendent C.
L. Stuart, Operations Supervisor E.
B.
Thomas, Jr.,
Esquire A. Z.
- Roisman, Natural Resources Defense Council
ENCLOSURE 1 Accession No:
79082201%2 SSINS:
6870 V
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASMINGTON, D. C.
20555 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 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 saf'ety 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
'ignificant 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.
0 ENCLOSURE 2 Information Subject Notice No.
IE Information Notice No. 79-22 Date:
September 14, 1979 Page 1 of 2 LISTING OF -IE INFORMATION NOTICES ISSUED IN THE LAST SIX MONTHS I
Date Issued to 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'Analysis of Safety-Related Piping 3/23/79 All power reactor facilities with an 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 Contaminated Systems with Service Air Systems Used As the Source of Breathing Air 3/28/79 All power reactor facilities with an OL and Pu Processing fuel facilities 79"09 79" 10 79-11 79-1.2 Spill of Radioactivity Contaminated Resin Nonconforming Pipe Support Struts Lower Reactor Vessel Head Insulation Support Problem Attempted Damage to New Fuel Assemblies 3/30/79, 4/16/79 5/7/79 5/11/79 All power reactor facilities with an OL All power reacto~
facilities with a CP All power reactor facilities with an OL or CP All Fuel Facilities, Research
- Reactors, and Power Reactors with an OL'or CP 79" 13 Indication of Low Water Level in the Oyster Creek Reactor 5/29/79 All power reactor facilities with an OL or CP 79-14 Safety Classification of Electrical Cable Support Systems 6/11/79 All applicants for, and holders of a power reactor CP
Enclosure 2
IE Information Notice No, 79-22 Date:
September 14, 1979 Page 2 of 2 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Information Subject Notice No.
Date Issued Issued to 79-15 79-16 79-17 79-18 79" 19 Deficient Procedures Nuclear Incident at Three Mile Island Source Holder Assembly Damage from Misfit Between Assembly and Reactor Upper Grid Plate Skylab Reentry Pipe Cracks in Stagnant Borated Water Systems at PWR Plants 6/7/79 All power reactor facilities with an OL or CP 6/22/79 All research and test reactors with an OL 6/20/79 All holders of reactor OLs and CPs 7/5/79 All holders of reactor OLs 7/17/79 All power reactor facilities with an OL or CP 79-20 NRC Enforcement Policy
-'RC Licensed Individuals 8/14/79 I
All Holders of Reactor OLs and CPs and Production Licensees with Licensed Operators 79-20 (Revision No. 1) 79-21 Same Title as 79-20 Transportation and Com-mercial Burial of Radio-active Material 9/7/79 Same as 79-20 9/7/79 All power and research reactors with OLs