ML19209D003
| ML19209D003 | |
| Person / Time | |
|---|---|
| Site: | Atlantic Nuclear Power Plant |
| Issue date: | 10/01/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Collier A OFFSHORE POWER SYSTEMS (SUBS. OF WESTINGHOUSE ELECTRI |
| References | |
| NUDOCS 7910180588 | |
| Download: ML19209D003 (1) | |
Text
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- o UNITED STATES 8'3 NUCLEAR REGULATORY COMMISSION i
E REGION 11
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101 MARIETTA ST N.W., SUITE 3100
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ATLANTA, GEoRCIA 30303 00T 1 1979 In Reply Refer To:
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7 Offshore Power Systems Attn:
A. R. Collier, President P. O. Box 8000 Jacksonville, Florida 32211 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, James P. O'Reilly Director
Enclosures:
1.
Information Notice No. 79-24 2.
List of IE Information Notices Issued in the Last Six Months ll77 J96 4
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7910180
SSINS: 6870 Accession No: 7908220123 UNITED STATES NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
'J WASHINGTON, D. C.
20555 October 1, 1979 IE Information Notice No. 79-24 OVERPRESSURIZATION OF CONTAINMENT OF A PWR PLANT AFTER A MAIN STEAM LINE BREAK VirginiaElectricandPowerCo.submitthdareportdatedSeptember7,1979that identified a deficiency in the original analysis of containment pressurization as a result of a steam line break for North Anna Power f tation, 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 analysis. 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 possibly significant matter that is still under review by the NRC staff.
It is expected that recipients will review the information f z possible applicability to their facilities. No specific action or response is requested at this time.
If NRC evaluations so indicate, further licensee act.ons may be requested or required.
No written response to this Information Notice is required.
If you have any questicas regarding this matter please contact the Director of the appropriate NRC Regional Office.
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IE Information Notice No. 79-24 Enclosure October 1, 1979 Page 1 of 2 LISTING OF IE INFORMATION NOTICES ISSUED IN LAST SIX MONTHS Information Subject Date Issued To Notice No.
Issued 79-24 Overpressurization of 10/1/79 All power reactor Containment of a PWR facilities holding Plant After a Main Steam OLs and cps Line Break 79-23 Emergency Diesel Generator 9/26/79 All Holders of cps Lube Oil Coolers and OLs 79-22 Qualification of Control 9/17/79 All Holders of cps Systems 9/14/79 All Holders of OLs 79-21 Transportation and Commer-9/11/79 All Licensees as Supple-cial burial of Radioactive mental Information to Maierials IE Bulletin Nos. 79-19
& 79-20 79-20 NRC Enforcement Policy 9/7/79 All Holders of Reactor (Rev. 1)
NRC Licensed Individuals OLs and cps and Production Licensees with Licensed Operators 79-20 NRC Enforcement Policy 8/14/79 All Holders of Reactor NRC Licensed Individuals OLs and cps and Production Licensees with Licensed Operators 79-19 Pipe Cracks in Stagnant 7/18/79 All Holders of Reactor (Correction - Borated Water Systems at OLs and cps Enclosure)
PWR Plants 79-19 Pipe Cracks In Stagnant 7/17/79 All Holders of Reactor Borated Water Systems At OLs and cps PWR Plants 79-18 Skylab Reentry 7/6/79 All Holders of Reactor OLs
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IE Information Notice No. 79-24 Enclosure October 1, 1979 Page 2 of 2 LISTING OF INFORMATION NOTICES ISSUED IN LAST SIX MONTHS Information Subject Date Issued To Notice No.
Issued 79-17 Source Holder Assembly Damage 6/20/79 All Holders of Reactor Damage From Misfit Between OLs and cps Assembly and Reactor Upper Grid Plate 79-16 Nuclear Incident at Three 6/22/79 All Research Reactors Mile Island and Test Reactors with OLs 79-15 Deficient Procedures 6/7/79 All Holders of Reactor OLs and cps 79-14 NRC Position of Electrical 6/11/79 All Power Reactor Cable Support Systems Facilities with a CP 79-13 Indication of Low Water 5/29/79 All Holders of Reactor level in the Oyster Creek OLs and cps Reactor 79-12 Attempted Damage to New 5/10/79 All Fuel racilities Fuel Assemblies Research Reactors, and Power Reactors with an OL or CP 79-11 Lower Reactor Vessel Head 5/7/79 All holders of Reactor Insulation Support Problem OLs and cps 1177 J99 O
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