ML18079A986
| ML18079A986 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/14/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 7909270440 | |
| Download: ML18079A986 (4) | |
Text
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. 50-272 S.E:P 1 4 1979 Public Service Electric and Gas Company ATTN: Mr. F. W. Schneider ... Vice President~ Production 80 Park.Place Newark, New Jersey 07101 Gentl emen :. The enclosed Information Notice provides information with regard to a potential unreviewed safety question involving high energy lines and control systems. Sincerely,
Enclosures:
- 1.
IE Information Notice No. 79-22
- 2.
List of IE Information Notices Issued in the Last Six Months cc w/encls: F. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station \\
1-- ENCLOSURE 1 UNITED STATES
- 1,L-{
Accession No: 79082201Jf SSINS: 6870 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 QUALIFICATION OF CONTROL SYSTEMS IE Information Notice No. 79-22 Date: September 14, 1979 Page l of 1 ~ Public Service Electric and Gas Company notified the NRC of a potential unreviewed safety question at their Salem Unit l 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 graue 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 ahigh 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 informatipn* 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 Di~ector of the appropriate NRC Regional Office. No written response to this Information Notice is required.
Information
- Notice No.
79-05 79-06 79-07 79-08 79-n9 79-10 79-11 79-l.2 79-13 79-14 ENCLOSURE 2 IE Information Notice No. 79-22 Date: September 14, 1979 Page l of 2 LISTING OF IE INFORMATION NOTICES ISSUED IN THE LAST SIX MONTHS Subject
- Date.
Issued to Issued Use of Improper Materials 3/21/79 A 11 power reactor f acil i ti es with an OL or CP in Safety:--Related Components Stres.s Analysis of 3/23/79 All power reactor facilities with an OL or CP Safety-Related Piping Rupture of Radwaste Tanks Interconnection of Contaminated Systems with Service Air Systems Used As the Source of Breathing Air Spill of Radioactivity Contaminated Resin Nonco~forming Pipe Support Struts Lower Reactor Vessel Head Insulation Support Problem Attempted Damage to New Fuel Assemblies Indication of Low Water Level in the Oyster Creek Reactor Safety Classification of Electrical Cable Support Systems 3/26/79 All power reactor facilities with an OL or CP 3/28/79 A 11 power reactor facilities* with an OL and Pu Processing fuel facilities 3/30/79 All power reactor factlities with an OL 4/16/79 All power reactor facilities with a CP 5/J/79 All power reactor facilities with an OL or CP 5/ll/79 All Fuel Facilities, Research Reactors, and Power.Reactors with an OL or CP 5/29/79 All power reactor facilities with an OL or CP 6/11/79 All applicants for, and holders of a power reactor CP Information Notice No. 79-15 79-16 79-17 79-18 79-19 79-:-20 79-20 (Revision No. 1) 79-21 IE Information Notice No. 79-22 Date: September 14, 1979 Page 2 of 2* LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Subject Defi dent 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 NRC Enforcement Policy ~ NRC Licensed Individuals Same Title as 79-20 Transportation and Com-mercial Burial of Radio-active Material Date Issued to Issued 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 I 8/14/79 All Holders of Reactor Ols and CPs and Production Licensees with Licensed Operators 9/7/79 Same as 79-20 9/7/79 All power and research reactors with Ols \\ '}}