ML19259D310
| ML19259D310 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/01/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Tallman W PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| References | |
| NUDOCS 7910170646 | |
| Download: ML19259D310 (1) | |
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UNITED STATES E } e ( [,,g NUCLEAR REGULATORY COMMISSION 3.y}[)'y.:_j REGION I
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Docket Nos. 50-443 OCT f gg79 50-444 Public Service Company of New Hampshire ATTN:
Mr. W. C. Tallman President 1000 Elm Street Manchester, New Hampshire 03105 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,
/
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oyce H. Grier
" Director
Enclosures:
1.
IE Information Notice 79-24 2.
List of IE Information Notices Issued in the Last Six Months cc w/encls:
John D. Haseltine, Project Manager 1160 177 791017069g C
ENCLOSURE 1 SSINS:
6870 Accession No:
7908220123 UNITED STATES
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NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT J d&M'
_L, 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. subraitted 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 experienced 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 early notification of a possitlv significant matter that is still under review by the NRC staff.
It is spected that recipients will review the information for possible applicability to their facilities.
No specific actioa 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 178
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 MONT4S 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 ;9 OL or CP 79-13 Indicaticn 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 9L or CP 79-16 Nuclear Incident at 6,'22/79 All research and Three Mile Island test rea. tors 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 Voper Grid Plate 79-18 Skylab Reentry 7/5/79 All holders of reactor OLs
IE Information Notice No. 79-24 Date:
October 1, 1979 Page 2 of 2 LISTING OF IE INFORMATION NOTICES 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 Cem-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 Diesel Generator 9/26/79 All power reactor faci-Lube Oil Coolers lities with an OL or CP 1160 180