ML17053B104
| ML17053B104 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/01/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider R NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 7910170620 | |
| Download: ML17053B104 (8) | |
Text
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Docket No. 50-220 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA19406 OCT '1 IgyII
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'i Mohawk Power Corporation ATTN:
Mr.
R.
R. Schneider Vice President Electric Operations 300 Erie Boulevard West
- Syracuse, New York 13202 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, oyce
. Grier Director
Enclosures:
1.
IE Intormation Notice 79-24 2.
List of IE I'nformation Notices Issued in the Last Six Months cc w/encls:
T.
E.
- Lempges, General Superintendent, Nuclear Generation T. J.
- Perkins, Station Superintendent.
C.
L. Stuart, Operations Supervisor E.
B. Thomas, Jr.,
Esquire A. Z.
- Roisman, Natural Resources Defense Council
I ENCLOSURE 1 SSINS:
6870 Accession No:
7908220123 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE 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 experienced the steam line break, containment design pressure would be exceeded in approximately 10 minutes.
The long term blowdown of'he 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 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.
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 Notice No.
Date Issued Issued to 79-10 79-11 79-12 79" 13 79-14 79-15 79-16 79-17 79-18 Nonconforming Pipe Support Struts Lower Reactor Vessel Head Insulation Support Problem Attempted Damage to New Fuel Assemblies Indication of Low Water'evel in the Oyster Creek Reactor Safety Classification of Electrical Cable Support Systems Deficient Procedures Nuclear Incident at Three Mile Island Source Holder Assembly Damage from Misfit Between Assembly and Reactor Upper Grid Plate Skylab"'Reentry 4/16/79 5/7/79, 5/11/79 5/29/79 6/11/79 6/7/79 6/22/79 6/20/79 7/5/79 All power reactor facilities with a CP All power reactor facilities with an OL or CP All Fuel Facilities, Research
- Reactors, and Power Reactors with an OL or CP All power reactor facilities with an OL or CP All applicants for, and holders of a power reactor CP All power reactor facilities with an OL or CP All research and test reactors with an OL All holders of reactor OLs and CPs All holders of reactor OLs
Enclosure 2
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IE Information Notice No. 79-24 Date:
October 1, 1979 Page 2 of 2 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Information Subject Notice No.
Date Issued Issued To 79-19 79-20 79-20 (Revision No. 1) 79-21 79-22 79-23 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 qualification of Control Systems Emergency Diesel Generator Lube Oil Coolers 7/17/79 All power reactor facilities with an OL or CP 8/14/79 All Holders of Reactor OLs and CPs and Producti on Licensees with Licensed Operators 9/7/79 Same as 79-20 9/7/79 All power and research reactors with OLs 9/14/79 All power reactor faci-lities with an OL or CP 9/26/79 All power reactor faci-lities with an OL or CP
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