ML19208C772
| ML19208C772 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/14/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Leonard J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| NUDOCS 7909270429 | |
| Download: ML19208C772 (1) | |
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- o UNITED STATES y' f ).,, c ' j NUCLEAR REGULATORY COMMISSION
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KING OF PRUSSIA, PENNSYLVANIA 13406 4.....,o Docket No. 50-333 Power Autho:ity of the State of New York James A. FitzPatrick Nuclear Power Plant ATTN:
Mr. J. D. Leonard Resident Manager P. O. Box 41 Lycoming, New York 13093 Gentlemen:
The enclosed Irformation Notice provides information with regard to a potential unreviewed safety question involving high energy lines and control systems.
Sincerely, en Boyce H. Grier Director
Enclosures:
1.
IE Information Notice No. 79-22 2.
List of IE Information Notices Issued in the Last Six Months cc w/encls:
George T. Berry, Executive Director P. W. Lyon, Manager - Nuclear Operations A. Klausmann, Director, Quality Assurance M. C. Cosgrove, Quality Assurance Supervisor J. F. Davis, Chairman, Safety Review Committee V. J. Cassan, Assistant General Counsel G. M. Wilverding, Licensing Supervisor 7 9 09 270 4Z7 1049 311
ENCLOSURE 1 1tf Accession No: 790822018E SSINS:
6870 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, 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 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 matter, please contact the Director cf the appropriate NRC Regional Office.
No written response to this Information Notice is required.
1049 512.
ENCLOSURE 2 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 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 Analysis of 3/23/79 All power reactor Safety-Reiated Piping 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 3/28/79 All power reactor Contaminated Systems with facilities with an Service Air Systems used OL and Pu Processing As the Source of Breathing fuel facilities Air 79-09 Spill of Radioactivity 3/30/79 All power reactor Contaminated Resin facilities with an OL 79-10 Nonconforming Pfpe 4/16/79 All power reactor Support Struts facilities with a CP 79-11 Lower Reactor Vessel Head 5/7/79 All power reactor Insulation Support Problem facilities with an OL or CP 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 power reactor Level in the Oyster facilities with an Creek Reactor OL or CP 79-14 Safety Classification of 6/11/79 All applicants for, Electrical Cable Support and holders of a Systems power reactor CP
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IE Information Notice No. 79-22 Date:
September 14, 1979 Page 2 of 2 LISTING OF IE INFORMAT:0N NOTICES ISSUED IN 1979 Information Subject i
Date Issued to Notice No.
Issued 79-15 Deficient Procedures 6/7/79 All power reactor facilities with an OL or CP 79-16 Nuclear Incident at 6/22/79 All research and Three Mile Island test reactors with an OL 79-17 Source Holder Assembly 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 power reactor Borated Water Systems at facilities with an PWR Plants OL or CP 79-20 NRC Enforcement Policy -
8/14/79 All Holders of Reactor NRC Licensed Individuals OLs and cps and Production Licensees with Licensed Operators 79-20 Same Title as 79-20 9/7/79 Same as 79-20 (Revision No. 1) 79-21 Transportation and Com-9/7/79 All power and research mercial Burial of Radio-reacto:'s with OLs active Material
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