ML17325B574: Difference between revisions

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     ~    A supplement to this LER will be provided if the results of the evaluation provide substantial changes to the significance, implications. consequences or corrective actions.
     ~    A supplement to this LER will be provided if the results of the evaluation provide substantial changes to the significance, implications. consequences or corrective actions.
     ~    Action to restore operability to the sump level and flow leak detection subsystem will be taken prior to entry into operational Mode 4.
     ~    Action to restore operability to the sump level and flow leak detection subsystem will be taken prior to entry into operational Mode 4.
Sincerely, M. W. Rencheck
Sincerely, M. W. Rencheck Vice President Nuclear Engineering Ilrb Attachment c:          J. E.          Oyer Region Ill R. P.          ~ower P.. A.      3arrett D. F.          Kunsemiller R.            Whale sg D.            Hahn Records Center, INPO NRC Resident Inspector eg1905050i03 990503 PDR    ADOCK          050003i5 S                                PDR
                            -
Vice President Nuclear Engineering Ilrb Attachment c:          J. E.          Oyer Region Ill R. P.          ~ower P.. A.      3arrett D. F.          Kunsemiller R.            Whale sg D.            Hahn Records Center, INPO NRC Resident Inspector eg1905050i03 990503 PDR    ADOCK          050003i5 S                                PDR
           .4FI'r~l rnerica's Enery    Inrlner-}}
           .4FI'r~l rnerica's Enery    Inrlner-}}

Latest revision as of 01:13, 4 February 2020

Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B574
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 05/03/1999
From: Rencheck M
INDIANA MICHIGAN POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17325B575 List:
References
RTR-REGGD-01.045, RTR-REGGD-1.045 NUDOCS 9905050103
Download: ML17325B574 (2)


Text

~ CATEGORY +

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RZDS)

ACCESSION NBR:9905050103 DOC.DATE: 99/05/03 NOTARIZED: NO FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M DOCKET 05000315 I

AUXHTNAME AUTHOR AFFILIATION RENCHECK,M.W. Indiana Michigan Power Co. (formerly Indiana &, Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Forwards LER 99-010-00 re RCS leak detection sys sensitivity not in accoradnce with design requirements. Listed C commitments identified in submittal. A DZSTRZBUTZON CODE: ZE22T COPTER RECEZVED:LTR 1 ENCL J SZEE: I TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES: E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD3-1 PD 1 1 STANG,J 1 1 INTERNAL: AEOD/SPD/RRAB 1 1 FIL CENTER 1 1 R NRR/DIPM/IOLB 1 1 QMB 1 1 NRR/DRIP/REXB 1 1 NRR/DSSA/SPLB 1 1 RES/DET/EZB 1 1 RGN3 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 , 1 LMZTCO MARSHALL 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 D

N NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZAT1ONi CONTACT THE DOCUMENT CONTROE DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16

indiana Michigan Power Company Cook Nudger Plere One Cook Bere Bi'dgrnen, ka 491 06 61 6 st66 5901 INDIANA IIICHIOiAN IaoM%R May 3, 1999 United States Nuclear Regulatory Commission Document Control Desk

'Washington, DC 20555 Operating r.icense DPR-58 Docket No, 50-315 Document Control Manager:

In accordance with the criteria established by10 CFR 50.73 entitled Licensee Event Re ort

~Sstem, the following report is being sobmttled:

A LER 315/99-010-00, "Reactor Coolant System Leak Detection System Sensitivity Not in Accordance with Design Requirements."

The following commitments were identified in this submittal:

~ An evaluation will be performed to clearly define the design and I'censing bases for the containment sump level and flow leak detection subsystem.

~ A supplement to this LER will be provided if the results of the evaluation provide substantial changes to the significance, implications. consequences or corrective actions.

~ Action to restore operability to the sump level and flow leak detection subsystem will be taken prior to entry into operational Mode 4.

Sincerely, M. W. Rencheck Vice President Nuclear Engineering Ilrb Attachment c: J. E. Oyer Region Ill R. P. ~ower P.. A. 3arrett D. F. Kunsemiller R. Whale sg D. Hahn Records Center, INPO NRC Resident Inspector eg1905050i03 990503 PDR ADOCK 050003i5 S PDR

.4FI'r~l rnerica's Enery Inrlner-