ML19224D298
| ML19224D298 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/07/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Clayton F ALABAMA POWER CO. |
| References | |
| NUDOCS 7907110312 | |
| Download: ML19224D298 (2) | |
Text
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O 101 M ARIETT A STREET.N.W. ATLANT A, GEORGt A 30303 d Imy 7 1979 In Reply Refer To: ,RII:JPO { 50-348 3
- m50-36 p Alabama Power Company Attn
Mr. F. L. Clayton, Jr. Senior Vice President Post Office Box 26?l Birmingham, Alabama 35291 Gentlemen: This Information Notice is provided as an early notification of a possibly significant matter. It is expected that recipients vill review the information for possi* ole applicability to their facilities. If further No specific action or response is requested at this time. NRC evaluctions so indicate, an IE Circular or Bulletin vill be issued to recocnend or request specific licensee actions. If you have ques-tions regarding this matter, please contact the Director of the appro-riate NRC Regional Office. Sincerely, O b Director
Enclosure:
1. IE Information Notice No. 79-11 2. Draft Transmittal Letter L\\) 7907110 3 f2 .) ) .1
MAY 7 1979 Alabama Power Company cc w/ encl: A. R. Barton Executive Vice President Post Office Box 2641 Birmingham, Alabama 35291 C. Biddinger, Jr. Manager-Corporate Quality Assurance Post Office Box 2641 Birmingham, Alabama 35291 H. O. Thrash Manager-Nuclear Generation Post Office Box 2641 Birmingham, Alabama 35291 H. G. Hairston, III Plant Manager Drawer 470 Ashford, Alabama 36312 R. E. Hollands, Jr. QA Supervisor Post Office Box U Ashford, Alabama 36312 r ,/ i E i fl i ,,f .] s e
UNITED STATES NUCLEAR REGULATORY CO?NISSION OFFICE OF INSPECTION AND ENFORCDENT WASHINGTON, D.C. 20555 thy 7, 1979 IE Inforcation Notice No. 79-11 1G'ER REACTOR VESSEL HEAD INSUIATION SUPPORT PROBLE?i 1 Virginia Electric and Power Co=pany, North Anna Power Station No. 1978, a field modification pertaining to the reported on Nove=ber 8, system which was not seistically lower vessel head insulation support A subsequent stress analysis the time of codification. the ASME Code allowable stress and the yield stress for analyzed at indicated that guide the operating base earthquake (OBE) on some of the instrument tubes were exceeded. 1 field r.odification, the lower vessel head For the North Anna No. insulation was supported by angle brackets that are cla= ped onto the ~ guide tubes. This additional gridwork to about 20 of the 53 instrument load on the guide tubes was not considered in the original stress analysis. The maximum stress occurs in the socket velds between the Thinble guide The tubes and the Instrumentation nozzles that penetrate the vessel. maximu= stress was about 70 percent of the ulticate and, therefore, violation of the pressure boundary would not be expected. VEPC0 plans to modify the supporting arrange = nt by building a framework underneath the insulation, which will take the loading off the guide tubes. All holders of operating licenses and/or construction permits should be aware of the potential problem of exceeding the allowable stress and the yield stress for OBE. This Information Notice is provided as an em ly notification of a It is expected that recipients vill review possibly significant matter.the inforeation for possible applicability to their fac No specific action or response is requested at this time. evaluatio reco==end or request specific licensee actions. If you have questions regarding the catter, please contact the Director of the appropriate NRC Regional Office. No written response to this inforcation notice is required.. 7906060158 j35 i~c
Enclosure IE Information Notice No. 79-11 Page 1 of 1 May 7, 1979 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Date Issued To Information Subject Issued Notice No. 79-01 Bergen-Paterson Hydraulic 2/2/79 All power reactor facilities with an Shock and Sway Arrestor OL or a CP 79-02 Atte=pted Extortion - 2/2/79 All Fuel Facilities Low Enriched Uraniu= 79-03 Limitorque Valve Geared 2/9/79 All power reactor facilities with an Limit Switch Lubricant OL or a CP 79-04 Degradstion of 2/16/79 All power reactor facilities with an Engineered OL or a CP Safety Features 79-05 Use of Improper Materials 3/21/79 All power reactor facilities with an in Safecy-Related Cocponents OL or CP 79-06 Stress Analysis of 3/23/79 All Holders of Reactor OL or CP Safety-Related Piping 79-07 Rupture of Radwaste Tanks 3/26/79 All power reactor facilities with an OL or CP 79-08 Interconnection of 3/28/79 All power reactor facilities with an Contaminated Syste=s with OL and Pu Processing Service Air Syste=s Used fuel facilities As the Source of Breathing Air 79-09 Spill of Radioactively 3/30/79 ~ All power reactor facilities with an Contaminated Resin OL 79-10 Nonconforcing Pipe 4/16/79 All pover reactor facilities with a Support Struts CP 1 i.F 1-as.3 .}}