ML19208C774
| ML19208C774 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/14/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Boyer V PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 7909270433 | |
| Download: ML19208C774 (1) | |
Text
-llD y?g&* **%e4'o, s-UNITED STATES y ) >,,7 ',g NUCLEAR REGULATORY COMMISSION 3.--
5 REGION I 0,
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631 PARK AVENUE
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,e KING OF PRUSSIA, PENNSYLVANIA 19406 Docket Nos. 50-352 50-353 SEP 14 W3 Philadelphia Electric Company Attention:
Mr. V. S. Boyer Vice President Engineering and Research 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:
The enclosed Information Notice provides information with regard to a potential unreviewed safety question involving high energy lines and control systems.
Sincerely,
.m}
? W.WN Boyce H. Grier
" Director
Enclosures:
1.
IE Information Notice No. 79-22 2.
List of IE Information Notices Issued in the Last Six Months 1049 323 67 9092 70%
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ENCLOSURE 1 W
Accession No: 790822018R SSINS:
6870 UNITED STATES NUCLEAR REGULATORY COMMI5aION 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 nouified the NRC of a potential unreviewed
'afety question at their Salem Unit 1 facility.
This notification was based on a continuing ri few 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 prote6tive functions performed by safety grade equipc.ent.
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 tne 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.
1049 324
ENCLOSURE 2 IE Information Notice No. 79-22 Date:
September 14, 1979 Page 1 of 2 LISTING 0F 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 1/?3/79 All power reactor Safety-Related 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 Pipe 4/16/79 All power reactor Support Struts facilities with a CP 79-11 Lower Raactor Vessel Head 5/7/79 All power reactor Insulation Support Problem facilities with an OL or CP 79-12 Attenpted 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 5/29/79 111 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 1049 725
IE Information Notice No. 79-22 Date:
September 14, 1979 Page 2 of 2 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Information Subject Date Issued to i
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 Fipe 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-reactors with OLs active Material 1049 326