ML19259D304
| ML19259D304 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/01/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Boyer V PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 7910170630 | |
| Download: ML19259D304 (1) | |
Text
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jo, UNITED STATES g * -r,( (,g NUCLEAR REGULATORY COMMISSION REGION I h, +' %/ [/ [E 3'
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,e KING OF PRUSSIA, PENNSYLVANIA 19406 Docket Nos. 50-352 50-353 OCT 1 B71 Philadelphia Electric Company Attention:
Mr. V. S. Boyer Vice President Engineering and Research 2301 Market Street Pniladelphia, Pennsylvania 19101 Gentlemen:
The enclosed Information Notice provides information with regard to an analysis that identifies an event that could result in overpressurization of containment at a pressurized water reactor.
Sincerely,
/hYf he oyce H. Grier Director
Enclosures:
1.
IE Information Notice 79-24 2.
List of IE Information Notices Issued in the Last Six Months
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ENCLOSURE 1 SSINS:
6870 Accession No:
7908220123 h h f /P ~
UNITED STATES NUCLEAR REGULATORY COMMISSION lluw/U y
0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.
20555 IE Information Notice No. 79-24 Date:
October 1, 1979 Page 1 of 1 OVERPRESSURIZATION OF CONTAINMENT OF A PWR PLANT AFTER A MAIN STEAM LINE BREAK Virginia Electric and Power Co. submitted a report dated September 7, 1979 that identified a deficiency in the original analyses of containment pressuri-zation as a result of a steam line break for North Anna Power Station, Units 3 and 4.
Stone and Webster Engineering Corporation performed a reanalyses of containment pressure following a main steam line break and determined that, if the auxiliary feedwater system continued to supply feedwater at runout conditions to the steam generator that had experienccd the steam line break, containment design pressure would be exceeded in approximately 10 minutes.
The long term blowdown of the water supplied under runout conditions by the auxiliary feedwater system had not been considered in the earlier analyses.
The corrective action is now under review by the owner, architect engineer, and NSSS supplier.
This Information Notice is provided as an e cly notification of a possibly significant matter that is still under review by the NRC staff.
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.
No written response to this Information Notice is required.
If you have any questions regarding this matter please contact the Director of the appropriate NRC Regional Office.
1160 141
.s ENCLOSURE 2 IE Information Notice No. 79-24 Date:
October 1, 1979 Page 1 of 2 LISTING OF IE INFORMATION NOTICES ISSUED IN THE LAST SIX MONTHS Information Subject Date Issued to Notice No.
Issued 79-10 Nonconforming Pipe 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 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 1160 142
e s
IE Information Notice No. 79-24 Date:
October 1, 1979 Page 2 of 2 LISTING OF IE INFORMATION NOTICd5 ISSUED IN 1979 Information Subject Date Issued To Notice No.
Issued 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-reactors with OLs active Material 79-22 Qualification of Control 9/14/79 All power reactor faci-Systems lities with an OL or CP 79-23 Emergency Ciesel Generator 9/26/79 All power reactor faci-Lube Oil Coolers lities with an OL or CP 1160 143