ML17334A478
| ML17334A478 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/22/1983 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17334A479 | List: |
| References | |
| AEP:NRC:0692H, AEP:NRC:692H, NUDOCS 8308240454 | |
| Download: ML17334A478 (3) | |
Text
REGULATORY..4l-'ORMATION DISTRIBUTION SYS i EH (RIDS)
ACCESSION NOR:8308240454 DOC ~ DATE: 83/08/22 NOTARIZED:
FACIL:50 315 Donald'C.
Cook Nuclear Power Planti Unit 1E 50 316 Donala C,
Cook huclear Power Plant~
Unit 2p AUTH'AME AUTf(OR AFFILIATION ALEXICH~H,P~
Indiana 8 Hichigan Electric Co ~
RECIP ~ NAME RECIPIENT AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulationi Di NO DOCKET Indiana 8
05000315 Indiana L
+0-rector
SUBJECT:
.Forwards "Supplemental Info<Safe Shutdown Capability Assessment 8, Pro'posed Modsi 10CFR50iApp RqSection IIIAGE" per 830623 meeting<Request for exemption for containm nt zones withdrawn ~
DISTRISUTION CODE:
AOOSS COPIES RECEIVED:LTR ( ENCL ~SIZEt TITLE'.
OR Submittal: Fire Protection NOTES:
RECIPIENT ID CODE/NAME NRR ORB 1 BC 01 INTERNAL: ELt)/HDS3 IE/WHITNEYE L NRR -WAHBACH NRH/DL DIR RGN3 COPIES LTTR ENCL 3
3 1
0 1
1 0
1 1
1 1
RECIPIENT ID CODE/NAHE IE FILE 06 NRR FIORAVANT07 NH
.E/CEB 09 G
F IL 00 COPIES LTTR ENCL 1
1 2
?
2 2
1 1
"EXTERNAL: ACRS NRC PDR NTIS 11 02 3
3 1
1 1
1'PDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22" ENCL
INDIANA R MICHIGAN ELECTRIC COMPANY P. O. 8OX 18 8OWLING GREEN STAT(ON NEW YORQ, N. Y. 10004 August 22, 1983 AEP:NRC:0692H Donald C. Cook Nuclear Plant Unit No.
1 and 2
Docket No. 50-315 and 50-316 License No. DPR-58 and DPR-74 Fire Protection 10 CFR 50 Appendix R Section IXX G Exemptions and Review of Safe Shutdown Analysis Report Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
. Washington, D. C.
20555
Dear Mr. Denton:
Please 'refer to our letter to"you dated March 31, 1983 (AEP:NRC:0692E) and Mr.. Wigginton's letter to us dated July 28, 1983 summarizing the meeting held on June 23, 1983 in Washington, D. C. to discuss this subject.
We are enclosing two copies of our report titled, "Supplemental Information, Safe Shutdown Capability Assessment and Proposed Modifications".
This report has been prepared in close cooperation and consultation with Engineering Planning and Management Xnc. It provides information and claxification related to our previous submittal.
Based on further discussion with NRC staff and their clarifications of 10 CFR 50, Appendix R, Sections IXI G.2 and III G.3, we formally withdraw our request for exemption for the following containment zones:
- Unit 1 and 2 Piping Annulus (Zones 66, 74)
- Unit 1 and 2 Lower Volume (Zones 67, 75)
- Unit 1 and 2 Accumulator Enclosure (Zones
- 120, 121)
- Unit 1 and 2 Instrument Room (Zones 122, 123)
References to these exemptions should be deleted from our report titled, "Safe Shutdown Capability Assessment and Proposed Modifications 10 CFR 50, Appendix R, Section III G" (Submitted to you March 31, 1983).
In particular, sections 7.1 and 7.13 to 7.20 should have the "Exemption Request" lead paragraph deleted.
The modification to install automatic detection systems proposed earlier is therefore withdrawn since such detection is not necessary to achieve adequate fire protection compliance under Section III G.2 (d) or (f).
8308240454 830822 PDR ADOCK 05000315 F
Mr. Harold R. Dent AEPsNRC:0692H We request that you delete the last paragraph of page 5-4 of the report submitted to you on March 31, 1983.
The paragraph
- states, "Although acceptable as... loss of systems control from the Control Room".
This paragraph is commentary and is not relevant to our discussion on alternative shutdown.
We accept your position that a review and walkdown of the shutdown procedures is appropriate.
We believe that such a review should be performed on procedures that reflect the changes resulting from the implementation of these modifications.
We estimate that these changes will be in place by the end of the refueling outage of Unit 2 in 1985.
We believe that the Supplemental Information provides all the information requested in the June 23rd meeting.
Should you desire any additional information, or have any questions regarding the submittalg we will be glad to meet with members of your staff at their convenience.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Very truly yours,
, ~
h
. P.
exich"'ice President MPA:cam cc:
John E. Dolan W. G. Smith, Jr.
Bridgman R. C. Callen G. Charnoff E.
R. Swanson, NRC Resident Inspector - Bridgman