ML19254E578
| ML19254E578 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/01/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Millen C PUBLIC SERVICE CO. OF COLORADO |
| References | |
| NUDOCS 7911010495 | |
| Download: ML19254E578 (1) | |
Text
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[** a'c,o NUCLEAR REGULATORY COMMISSION o
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ARLINGTON, TEXAS 76012 October 1, 1979 Docket No. 50-267 Public Service Company of Colorado ATTN:
Mr. C. K. Millen Senior Vice President P. O. Box 840 Denver, Colorado 80201 Gentlemen:
The enclosed IE Information Notice provides information with regard to an analysis that identifies an event that could result in overpressu-rization of containment at a pressurized water reactor.
Sincerely,
/
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l V W Karl V. Deyfrit,
j Director
Enclosures:
1.
List of IE Information Notices Issued in the Last Six Months cc:
D. W. Warembourg, Nuclear Production Manager Fort St. Vrain Nuclear Station P. O. Box 368 Platteville, Colorado 80651 L. Brey, Manager, Quality Assurance 1283 108 s
LC 7911010 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 ori,Inal analysis of containment pressurization as a result of a steam line break for North Anna Power Station, Units 3 and 4.
Stone and Webster Engineering Corporation performed a reanalysis 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 IE 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.
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IE Information Notice No. 79-24 October 1, 1979 LISTING OF IE IKFORMATION NOTICES ISSUED IN 1979 Information Subj ect Date Issued To Notice No.
Issued 79-10 Nonconforming Pipe 4/16/79 All power reactor Support Struts facilities with a Construction Permit (CP) 79-11 Lower Reactor Vessel Head 5/7/79 All Holders of Reactor Insulation Support Problem Operating Licenses (OLs)
Construction Permits (cps) 79-12 Attempted Damage to New 5/11/79 All fuel facilities, Fuel Assemblies research reactors, and power raa.cors with an Operating Licensee (OL) or a Construction Permit (CP) 79-13 Indication of Low Water 5/29/79 All Holders of Operating Level in the Oyster Creek License (OL) or Reactor Construction Permit (CP) 79-14 NRC Position of Electrical 6/11/79 All Power Reactor Cable Support Systems facilities with a Construction Permit (CP) and applicants 79-15 Deficient Procedures 6/7/79 All Holders of Reactor Operating Licenses (OLs) and Construction Permits (cps) 79-16 Nuclear Incident at Three 6/22/79 All Research Reactors Mile Island and Test Reactors with Operating Licenses (0Ls) 79-17 Source Holder Assembly 6/20/79 All Holders of Reactor Damage From Misfit Between Operating Licenses (OLs)
Assembly and Reactor Upper and Construction Grid Plate Permits (cps)
Enclosure Page 1 of 2 1283 !i0
e IE Information Notice No. 79-24 October 1, 1979 79-18 Skylab Reentry 7/5/79 All holders of Reactor Operating Licenses (CLs) 79-19 Pipe Cracks in Stagnant 7/17/79 All IIolders of Reactor Borated Water Systems at Operating Licenses (OLs)
PWR Plants and Construction Permits (cps) 79-20 NRC Enforcement Policy 8/14/79 All Holders of Reactor NRC Licensed Individuals Operating Licenses (OLs) and Construction Permits (cps), Research Reactors, Test Reactors Licensees with Licensed Operators 79-21 Transportation and 9/7/79 All power and research Commerical Burial reactors with Operating of Radioactive Material License (OL) 79-22 Qualification of Control 9/14/79 All power reactor Systems facilities with an Operating Licenses (OL) and Construction Permits (CP) 79-23 Emergency Diesel Generator 9/26/79 All power reactor Lube Oil Coolers facilities with an Operating License (OL) or Construction Permit (CP)
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