ML17328A770
| ML17328A770 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/09/1990 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 AEP:NRC:0773AJ, AEP:NRC:773AJ, NUDOCS 9011190109 | |
| Download: ML17328A770 (4) | |
Text
,;, At"-.CELERATED D'RIBUTION DEMONS~TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DOCKET g
05000315 05000316 SUEUECT: Submits Reg Guide 1.97 status update,per 901005 ltr.
DISTRIBUTION CODE:
A003D COPIES RECEIVED:LTR t
ENCL L7 SIZE:
TITLE: OR/Licensing Submittal:
Suppl 1 to NUREG-0737(Generic Ltr 82-33)
NOTES:
ACCESSION NBR: 9011190109 DOC. DATE: 90/11/09 NOTARIZED:
NO FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.ED Document Control Branch (Document Control Desk)
RECIPIENT ID CODE/NAME PD3-1 LA COLBURN,T.
INTERNAL: NRR FILE ~~'1 EXTERNAL: NRC PDR COPIES LTTR E 1
2 CL RECIPIENT ID CODE/NAME PD3-1 PD OC/LFMB RES/DSIR/EIB NSIC COPIES LTTR ENCL NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 10 ENCL ~0
Indiana Michigan Power Company P.O. Box 16631 CoIumbus, OH 43216 R
AEP:NRC:0773AJ Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 REGULATORY GUIDE 1.97 STATUS UPDATE U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C, 20555 Attn; T, E. Murley November 9, 1990
Dear Dr. Murley:
The purpose of this letter is to update the status of each variable listed in our Regulatory Guide 1.97 submittal AEP;NRC:0773AB dated October 5, 1988.
Ve have completed all of the upgrade work shown in the table portion of our AEP:NRC:0773AB submittal with the following exceptions:
1)
Items B-04 and B-05:
The reactor coolant system hot and cold leg water temperature work on Unit 1 is expected to be completed during the present refueling outage.
This work was not completed on schedule due to the need for a subsequent request for an Appendix R exemption.
This Appendix R exemption was granted on February 9, 1990.
The work on Unit 2 has been completed.
2)
Item B-9:
The coolant inventory (reactor vessel water level) work described in AEP:NRC:0773AB involves upgrading the reactor coolant system hot leg temperature inputs.
This work was not completed as scheduled because of the above (item B-04) mentioned delays, The work on Unit 1 is expected to be completed during the present Unit 1 refueling outage.
The work on Unit 2 has been completed.
3)
Item E-5b:
The portable radiation monitoring instruments hav~
been cglibrated and are available for use in the range of 10 to 10 R/hr for gamma radiation.
Appropriate correction factors for beta/low energy gamma dose rates will be determined by December 1,
1990.
90ii i90109 90ii09 PDR ADOCK 050003i5 P
PDC PQP3 I/y
Dr. T. E. Murley AEP:NRC:0773AJ 4)
Item E-5c:
The plant and environs radioactivity variable (portable gamma spectroscopy system) is shown in AEP:NRC:0773AB as being completed.
However, the procedure for using this equipment and its final calibration is not expected to be completed until April 1, 1991.
5)
Item B-14:
As discussed with T. Colburn of your staff on September 20,
- 1990, 32 containment isolation valve position indication switches on each unit lacked the documentation required to verify their seismic adequacy.
These position indication switches will be seismically tested and the results of this testing are expected within one year.
At that time we should be able to verify their seismic adequacy.
If the seismic testing shows these switches to be inadequate, new seismically qualified position indicating switches will be purchased and installed.
These position indication switches are located on small sized sample lines and have no impact on the ability of the containment isolation valves to perform their intended safety function.
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its adequacy and completeness prior to signature by the undersigned.
Sincerely, M. P. Alexich Vice President ldp 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
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