ML17326A753
| ML17326A753 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/01/1980 |
| From: | Dowd A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.30, TASK-2.K.3.31, TASK-TM AEP:NRC:00398A, AEP:NRC:398A, NUDOCS 8010080432 | |
| Download: ML17326A753 (5) | |
Text
REGULAT
'NFORMATION DISTRIBUTIO YSTEM (RIDS) 1 ACCESSION NBR:8010080032 DOC ~ DATE: 80/10/01 NOTARIZED:
NO DOCKET FAcIL:50 315 Donald c.. cook Nuclear Po~er Planti Unit 1F Indiana 8
05000315 50 316 Dona Id C.',
Cook Nuclear Power Plant~
Uni t 2F Indiana 8
05000316 AUTH BYNAME,"
AUTHOR AFFLL',IATION DOWDFA ~ J ~
Indiana L Michigan Electric. Co.
RECIP ~ NAME RECIPIENT'FFILlATION DENTONFH ~ RE Ofifice o.f Nuclear= Reactor Regulat{oni Director
SUBJECT:
Forwards responses toi Items II~ K ~ 3 ~ 30 L II,K~ 3 ~ 31 of 800905>>
ltr re preliminary. clarification of. TMI action plan requirements,.
DISTRIBUTION CODE!
A001S COPIES RECEIVED;L)TR ~'NCL<
SIZE!
/
p TITLE: General Di st ribut i on for; sf tet Issuance of Operat ing License NOTES:I8E:3 copies al l material
~
05000315'5000316 RECIPIENT ID CODE/NAME, ACTION:
VARGAF 8 ~
00 COPIES LA'TR ENCL'3 13 RKC IP IENT ID CODE/NAME>>
COPIES LTTR ENCLl INTERNAL~a D/DIRRHUM FAC08 NRC PDR 02 OR ASSESS BR'0 1*
1 1
1 0
IE K!
0 RKG. f 06 11 01 2
2 1,
0 1
1XTERNAL'CRS
- NSIC, 09 05i 16 16 1
1 LPDR 03 oop 8 ]ggo V/
TOTAL NUMBER OF~ COPIES REQUIRED:
LTTR 3/
ENCL P6
8 li 1 l e
~
l
~
4
~
il v;
c 'tn
(
I E
F 1
E N
II II I
, INDIANA L MICHIGAN ELECTRIC COMPANY P. O. 8OX 18 80 WLING GR E EN STATION NEW YORK, N. Y. 10004 October 1, 1980 AEP:NRC:00398A Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 TMI Action Plan Items II.K.3.30 and II.K.3.31 Revised Small Break LOCA Models and Analysis Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Denton:
The Attachment to this letter contains our responses to Items II.K.3. 30 and II.K.3.31 of Enclosure 4 to Mr. D.
G. Eisenhut's letter of September 5,
1980 entitled, "Preliminary Clarification of TMI Action Plan Requirements".
Very truly yours, A. J.
Dowd Vice President cc:
R.
C. Callen
'G. Charnoff D. V. Shaller - Bridgman John E. Dolan R.
S. Hunter R.
W. Jurgensen NRC Resident Inspector at Cook Plant - Bridgman 8Moooo
0
}
ATTACHMENT TO AEP:NRC:00398A AEP Res onses to TMI Action Plan Items II.K.3.30'and II.K.3.31 II.K.3.30:
Revised Small-Break LOCA Methods To Show Conformance With 10 CFR 50, Appendix K
The present small break models used to analyze and license the Donald C.
Cook Nuclear Plant are in conformance with 10 CFR 50, Appendix K.
- However, Westinghouse has indicated that they will address the scheduled completion date of January 1,
1982.
Westinghouse will provide a'etailed outline of the scope and schedule of this effort by means of a direct letter to the NRC on or before October 1, 1980.
The comple-tion arid approval of the Westinghouse effort will demonstrate the satisfactory performance of the Westinghouse-designed NSS Systems in small-break LOCA scenarios regardless of core fuel design.
This is based on the results of all the small LOCA analyses performed to date by Westinghouse which have shown that small-break LOCA behavior is minimally affected by the exact details of fuel design.
II;K.3.31:
Plant Specific Calculations To Show Compliance With 10 CFR 50.46 If the results of the new Westinghouse model (and subsequent NRC review and approval) indicate that the present small-break LOCA analyses for the Cook Plant are not in conformance with 10 CFR Part 50.46, a new analysis will be submitted to the NRC in accordance with the NRC schedule.