ML19254C977
| ML19254C977 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/01/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Aswell D LOUISIANA POWER & LIGHT CO. |
| References | |
| NUDOCS 7910190207 | |
| Download: ML19254C977 (1) | |
Text
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UNITED STATES
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REGION IV U
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611 RY AN PL AZA ORIVE, SUITE 1000 7 c, Ng;![a t,j ARLINGTON, TEX AS 76012 e na a
'4,,,,\\,g' October 1, 1979 In Reply Refer To:
RIV Docket No.
50-382/IE Information Notice No. 79-24 Louisiana Powe' and Light Co.
ATTN:
Mr. D.
L. Aswell Vice Pre:ident of Power Production 142 Delarende Street New Orleans, Louisiana 70176 Gentlemen:
The enclcsed IE Information Notice provi. 3 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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,2-Karl V. Seyfrit Director
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Enclosures:
1.
List of IE Information Notices Issued in the Last Six Months 118? 013 R-20 7910100 t
SSINS:
6870 Accession No:
7908220123 UNITED STATES
~'3 h gj%h" NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT g3_
WASHINGTON. D. C.
20555 IE Information Notice No. 7.9-24 D e:
October 1, 1979 Page 1 of 1 OVERPRESSUPIZATION 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 containr2nt pressurization as a result of a steam line break for North Anna Power Stat.on, 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 approxiraately 10 minutes. The long-term blowdown of the water supplied under runcut conditions by the auxill.ry feedwater system had not been considered in the earlier analysis. The cor rective action is now under review by the owner, architect engineer, and NSSS supplier.
Tnis 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.
118(7 0!4
IE Informat*on 7.otice No. 79-24 October 1, 1979 LISTING OF IE INFORMATION 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) 79-71 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 reactors with aa 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 79-13 Deficient Procedures 6/7/79 All Holders of Reactor Operating Licenses (0Ls) and Construction Permits (cps) 79-16 Nuclear Incident at Three 6/22/79 All Research 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 (0Ls)
Assembly and Reactor Upper and Construction Grid Plate Permits (cps)
Enclosure Page 1 of 2 11851 015
IE Information Notice No. 79-24 October 1, 1979 79-18 Skylab Reentry 7/5/79 All holders of Reactor Operating Licenses (0Ls) 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 All Holders of Reactor NRC Licensed I.idividuals Operating Licenses (OLs) ar3 Construction Permits (cps), Research Reactors, Test Reactors Licensees with Licensed Operators 79-21 Transportation ant 9/7/79 All power and research Commerical curial reactors with Operating of Radioactive Material License (0L) 79-2' 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 1189i 0i6