ML19254C978

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Forwards IE Info Notice 79-24, Overpressurization of Containment of PWR Plant After Main Steam Line Break. No Action Required
ML19254C978
Person / Time
Site: Comanche Peak  
Issue date: 10/01/1979
From: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Gary R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
References
NUDOCS 7910190209
Download: ML19254C978 (1)


Text

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  • / i REGloN IV 7 i i ; [I b 611 RYAN PL AZA DRIVE, SUITE 1000 eg %y;.g, j AR LINGTON, TEX AS 76012 7

,s.. ,.ng f g October 1, 1979 In Reply Refer To: RIV Docket Nos. 50-445/IE Information Notice No. 79-24 50-446/IE Information Notice No. 79-24 Texas Utilities Generating Company ATTN: Mr. R. J. Gary, Executive Vice President and General Manager 2001 Bryan Tower Dallas, Texas 75201 Gentlemen: Th; enclosed IE Information Notice provides information with regard to an analysis that identifies an event that could resul, in overpressu-rization of containment at a pressurized water reactor. Sincerely, 3 / l2 i _4' /., / v ,1 , 4 -{ ' y i v,' .s 1 s pf g Karl V. Seyfrit / Director

Enclosures:

1. Information Notice 79-24 2. List of IE Information Notices Issued in the Last Six Months 1181 017 ro201oo ZO 9 9

SSINS: 6870 Accession No: 7908220123 UNITED STATES 7flggf% NUCLEAR REGULA10RY COMMISSION 0FFI(" 0F INSPECTION AND ENF0PCEMENT - g 1ASHINGTON, D. C. 20555 v1 U IE Inform.. tion 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 analysis of containment pressurization as a result of a steam line break for North Anna Powet 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 licensae 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. 118?? 018

IE Information Notice No. 79-24 October 1, 1979 LISTING OF IE INFORMATION NOTICES-ISSUED IN 1979 Information Subject 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 teactors with an Operr ing Licensee (OL) c or r 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 ar ".lectrical 6/11/79 All Power Reactor Cable Support Systems f.scilities 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 Resear:h Reactors Mile Island and Test Reactors with Operating Licenses (OLs) 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 1189 019

IE I' formation Notice No. 79-24 October 1, 1979 79-18 Skylab Reentry 7/5/79 All holders of Reactor Operating Licenses (OLs) 79-19 Pipe Cracks in Stagnant 7/17/79 All Holders of Reactor Borated Water Systems at Operating Licenses (OLs) PWR Plants and Construction Permits (cps) 79-20 NRC Enforcement Policy 8/14/79 ^11 Holders of Reactor NRC Licensed Individuals Opeiaang Licenses (0Ls) 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) Enclosure Page 2 of 2 1181 020}}