ML17326A063: Difference between revisions

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| issue date = 07/22/1999
| issue date = 07/22/1999
| title = Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
| title = Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
| author name = RENCHECK M W
| author name = Rencheck M
| author affiliation = INDIANA MICHIGAN POWER CO.
| author affiliation = INDIANA MICHIGAN POWER CO.
| addressee name =  
| addressee name =  

Revision as of 16:48, 18 June 2019

Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A063
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 07/22/1999
From: Rencheck M
INDIANA MICHIGAN POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17326A064 List:
References
NUDOCS 9907280074
Download: ML17326A063 (3)


Text

4 A,I'K(iuRY g*REGULATORY INFORMATZON DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9907280074 DOC.DATE: 99/07/22 NOTARIZED:

NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power'lant, Unit 1, Indiana M 05000315 AUTH.NAME AUTHOR AFFILIATION RENCHECK,M.W.

Indiana Michigan Power Co.RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Forwards LER 98-014-03,"'Response to High-High Containment Pressure'rocedure Not Consistent With Analysis of Record." Revised info marked by sidebars in right hand margin.l7 Commitments made by util, listed.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR t ENCL 1 SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME LPD3-1 PD INTERNAL ILE CE E NRR/DRIP/REXB RES/DET/ERAB RGN3 FILE 01 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME STANG, J NRR/DIPM/IOLB NRR/DSSA/SPLB RES/DRAA/OERAB COPIES LTTR ENCL 1 1 1 1 1.1 1 1 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR 1 1 1 1 1 1 LMITCO MARSHALL NOAC QUEENER,DS NUDOCS FULL TXT 1 1 1 1 1 1 NOTE TO ALL ERIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LIS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATIONS CONTACT THE DOCUMENT CONTR DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15 Indiana'hlichiga~

Power Company~Cook Hudew Raor Onecook Rart Mgnarl ha 49106 6i 6 465 5901 Z INDIANA NICHIGAN PWER July 22, 1999 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating License DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee EventP LER 315/98-014-03,"Response to High-High Containment Pressure" Procedure Not Consistent with Analysis of Record.This revision to the LER provides the safety significance of the identified condition, corrects a flow value in the Analysis section, and clarifies commitments as identified below.This information is marked by sidebars in the right hand margin.The commitments identified in this LER are as follows:~The containment integrity analysis will be used to determine a conservative time for actuation of RHR spray.This task will be completed by August 31, 1999.~Functional Restoration Procedure FRZ-1,"Response to High-High Containment Pressure", will be revised to be consistent with the new analysis.As Unit 2 will be returned to service first, the Unit 2 procedure will be revised and approved by December 1, 1999, with the procedure for Unit 1 scheduled for revision and approval by January 30, 2000.~A program will be developed to identify, document and control the key accident analyses assumptions used in accident analysis.Implementation of the program will be complete by August 31, 1999.Sincerely, M.W.encheck Vice President-Nuclear Engineering 9'ai07280074 990722 PDR ADQCK 050003i5 S PDR

/mbd Attachment J.E.Dyer, Region III R.P.Powers J.Streeter G.P.Arent R., Whale D.Hahn Records Center, INPO NRC Resident Inspector