ML17329A030
| ML17329A030 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/21/1991 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1033F, GL-88-17, NUDOCS 9105300271 | |
| Download: ML17329A030 (4) | |
Text
FQRD 1
REGULA.
,Z INFORMATION DISTRIBUTIO SYSTEM (RIDS) 4 ACCESSION NBR:9105300271 DOC.DATE: 91/05/21 NOTARIZED:
NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana 05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana 05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
Indiana Michigan Power Co. (formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEYFT.E, Document Control Branch (Document Control Desk)
SUBJECT:
.Responds to 900521 request re licensee response to generic ltr 88-17, "Loss of DHR." Corporate procedures implemented that incorporate reasonable set of contr'ols to ensure accuracy
& completeness prior to signature by undersigned.
DISTRIBUTION CODE:
A061D COPIES RECEIVED:LTR 3 ENCL 8 SIZE:
2 TITLE: OR/Licensing Submittal:
Loss of Residual Heat Removal (RHR) GL-87-12 X
NOTES:
RECIPIENT ID CODE/NAME PD3-1 LA COLBURNFT ~
INTERNAL NRR BALUKJ IAN F H NRR/DOEA/OTSB11 0
REG FIL 01 EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD3-1 PD NRR TRAMMELL,C NRR/DST 8E2 OGC/HDS2 RES/DSIR/EIB NSIC COPIES LTTR ENCL 0
TOTAL NUMBER OF COPTER REQUTRED:
LTTR 14 ENCL
k 1
0 14
~1 I
t r L
I 1
l
Indiana Michigan Power Company P.O. Box 16631, Columbus, OH 43216 AEP:NRC:1033F Donald C, Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 GENERIC LETTER 88-17 FOLLOW-UP U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn:
T ~ E. Murley May 21, 1991
Dear Dr. Murley:
In a May 21, 1990 letter concerning the programmatic enhancements that we committed to in response to Generic Letter 88-17, "Loss of Decay Heat Removal," you requested that we inform you in writing when the actions we committed to would be implemented and the modifications are determined to be operational.
This letter is in response to that request.
We committed to have the programmatic enhancements that did not depend on hardware changes implemented by May 1990.
This was done with one exception.
A permanent procedure for loss of RHR was to be developed following the receipt of the Emergency
Response
Guidelines (ERG) and Background Document from the Westinghouse Owners Group (WOG).
We advised you in our February 6,
1989 letter (AEP:NRC:1033C) that the WOG guidance was scheduled for issuance in the fall of 1989.
In reality the WOG did not provide this guidance to us until February 1991.
After receiving the guidance, a
procedure was prepared that will be issued this summer as soon as the operators are trained, Interim emergency response procedures were developed and will remain in place until the ERG-based procedure is implemented.
In addition, we committed to have all hardware-related modifications, with the exception of installing RHR motor current monitoring capabilities, completed by the end of the 1990 refueling outages for both Units 1 and 2.
These modifications were completed and determined to be operational during the outages that ended on January 26, 1991 for Unit 1 and November 10, 1990 for Unit 2.
The RHR motor current monitoring capabilities will be installed by the end of the next refueling outages for each unit, as we originally committed.
9105300271 910521
,", PDR
- DOCH, 05000315 p
god'/
lay
~ ~ ~
L Dr. T. E. Murley AEP: NRC: 1033F This document has been prepared following Corporate procedures that incorporate a reasonable set of controls that ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, ee~~~4 E.
E. Fitzpatrick Vice President EEF/dag cc:
D, H. Williams, Jr A. A. Blind - Bridgman J.
R. Padgett G. Charnoff A. B. Davis - Region III NRC Resident Inspector
- Bridgman NFEM Section Chief