ML17324A992
| ML17324A992 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/23/1986 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17324A994 | List: |
| References | |
| AEP:NRC:0692AR, AEP:NRC:692AR, NUDOCS 8607150140 | |
| Download: ML17324A992 (4) | |
Text
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I~')I ACCESSION NBR:
FAC IL: 50-315 50-316 AUTH. NAI'fE ALEXXCH>N. P.
RECIP. NANE DENTQNp H. R.
It
( jy PEQUL'ATM INFORMATION-'5XSTRXBUTIO~STEN' R IS/)
8607150140 DOC. DATE: 86/06/23 NOTARIZED:
NO Donald C.
Cook Nuclear Power Planti Unit ir Indiana Donald C.
Cook Nuclear Power Planti Unit 2.
Ind iana AUTHOR AFFILIATION Indiana 5 michigan Electric Co.
RECIPIENT AFFILIATION Office of Nuclear Reactor Regu'lation.
Direc tor
',t I i \\
DOCNET Rc 0500031 5 05000316 (post 851125
SUBJECT:
Supplemental application for amends to Licenses DPR-58 8c DPR-74> revising Tech spec
- 3. O. 4 to ref 1 ect that spec inapplicable to alternate safe shutdown capability in fire scenario per App R to 1QCFR50.
...,.........,..........,... I...,
I.,.~tea TITLE:
QR Submittal: Fire Protection NOTES:
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 June 23, 1986 AEP:NRC:0692AR Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 ADDENDUM TO TECHNICAL SPECIFICATIONS FOR APPENDIX R TO 10 CFR 50, ALTERNATE SAFE SHUTDOWN Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
The purpose of this letter is to modify our letter AEP:NRC:0692AJ, dated May 30, 1986, which provided our proposed Technical Specifications (T/Ss) for alternate safe shutdown.
In the process of implementing the administrative controls associated with these T/Ss, we discovered that Specification 3.0.4 applies to these T/Ss for opposite unit shutdown support if they are interpr'eted literally.
Such an interpretation could cause us unnecessary operational difficulties.
For example, one unit cannot enter Mode 4 (from Mode 5) if the opposite unit does not have a
centrifugal charging pump and the associated unit cross-tie flow path available.
It was not our intention that the provisions of Specification 3.0.4 apply to our alternate safe shutdown capability.
We proposed the compensatory action of posting fire watches in the unit lacking opposite unit support in those fire areas required in order to preclude loss of safe shutdown systems.
We feel that this is adequate to maintain our safe shutdown capability in a fire scenario.
Therefore, we have modified certain T/S pages of Attachment 3 to our letter of May 30, 1986 to state that Specification 3.0.4 does not apply.
The attachment to this letter contains all proposed changes to the Donald C.
Cook Nuclear Plant Technical Specifications for alternate safe shutdown.
It is intended that this attachment supersede Attachment 3 to AEP:NRC:0692AJ.
Attachments 1 and 2 to that letter are unchanged by this submittal.
We have indicated the changes proposed in the attachment to this letter that are different from those in Attachment 3 to AEP:NRC:0692AJ by using double margin bars.
8607150140 860623 PDR ADOCK 05000315 P
/god I/
~ Mr. Harold R. Denton AEP:NRC:0692AR This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, A
Al ich b,4 Vice President Pp cm Attachments cc:
John E. Dolan W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman