ML17326A383
| ML17326A383 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/07/1979 |
| From: | Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:00137A, AEP:NRC:137A, NUDOCS 7912110312 | |
| Download: ML17326A383 (6) | |
Text
REGULATORY ~ORMATION DISTRIBUTION SYS 1 (RIDS)
ACCESSION NBR:7912110312 DOC ~ DATE; 79/12/07 NOTARIZED:
NO DOCKET FACIL:50"315 Donald C,, Cook Nuclear PoWer Planti Unit 1E Indiana L
0 50 316 Donald C,
Cook Nuclear Power Planti Unit 2E Indiana 8
0500 AUTH BYNAME AUTHOR AFFILIATION OOLANzJ ~ Es Indiana L Michigan Electric Co.
RECIP ~ NAME RECIPIENT AFFILIAT I ON DENTONeH ~ RE Office of Nuclear Reactor Regulation
SUBJECT:
"Submits revised schedule for final repts on results of facility analytical evaluation.
COPIES LTTR EN L
7 RECIPIENT IO CODE/NAME ACTION:
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W DISTRIBUTION CDDE:
ABOIS COPIES RECEIVED:LTR g ENCL Q
SIZE:
TITLE: General Distribution for after Issuance of Operating Lic NOTES: ~ e E,- H Q.S
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RECIPIENT COPIES ID CODE/NAME LTTR ENCL INTERNALs Og 12 LE 15 CORE PERF BR 18 REAC SFTY BR 20 EEB 2?
BR INKMAN OELD EXTERNALS 03 LPOR 23 ACRS 12" 1
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NRC POR 14 TA/EDO 17 ENGR BR 19 PLANT SYS BR 21 EFLT TRT SYS EPB-DOR 00 NSIC
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INDIANA L MICHIGAN ELECTRIC COMPANY P. O.
BOX 18 Bo WLIN G G R E EN ST ATION NEW YORK, N. Y. 10004 December 7,
1979 AEP:NRC:00137A Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License No.
DPR-58 and DPR-74 Mr. Harold R. Denton, Director Office of the Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C;,
20555
Reference:
Letter No. AEP:NRC:00137 Dated September 26, 1979
Dear Mr. Denton:
This letter is in reference to Condition C.3(a) to the operating license for Unit 2 of the Donald C.
Cook Nuclear Plant No. DPR-74.
In our above referenced.letter we requested an extension to complete the analytical evaluation until September 01,,1980.
- However, as agreed upon during the meeting between the utility group, Westinghouse and the NRC Staff held on November 28, 1979 we will be sending the final reports on the results of the analytical evaluation on the following revised schedule:
(,1)
By January 25, 1980 a complete evaluation will be submitted per-taining to the following items:
a.
Reactor Vessel Support evaluation for breaks inside the reactor cavity.
b.
Integrity of the attached ECCS piping systems.
c.
NSS component support evaluation for primary pipe breaks outside the reactor cavity.
1
Mr. Harold R. Denton, Director AEP: NRC: 00137 (2)
By July 1, 1980, a complete evaluation will be submitted for the remaining issues including reactor internals,
- CRDM, fuel assemblies as stated in the NRC's letter dated January 25, 1978.
AEP interprets 10 CFR 170 Subsection 22 as requiring that no submittal fee accompany this request.
Very truly yours, JED:em ohn E. Dolan Vice President cc:
R.
C. Callen G. Charnoff D. V. Shaller-Bridgman R.
S. Hunter R.
W; Jurgensen
Mr. Harold R. Denton, Director AEP:NRC:00137A bc:
S. J. Milioti/J. I. Castresana/T.
Satyan H.
N. Scherer, Jr'.
G.
P. Field/H. L. Alexander F. Hering/S.
H. Steinhart R.
F.
Kroeger J.
F. Stietzel
-Bridgman David L. Wigginton -NRC NRC Resident Inspector at Cook Plant -Bridgman DC-N-6773.1 AEP:NRC:00137A P.Wilkens Rochester,Gas 8 Electric Company T. Campbell
-Westinghouse Electric Corporation Steve B. Hosford -
NRC