ML17333A274
| ML17333A274 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/19/1996 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17333A275 | List: |
| References | |
| AEP:NRC:1166AC, NUDOCS 9601250139 | |
| Download: ML17333A274 (6) | |
Text
CATEGORY 1 REGULATOR INFORMATION DISTRIBUTIONOSTEM (RIDE)
ACCESSION NBR:9601250139 DOC.DATE: 96/01/19 NOTARIZED:
NO DOCKET ¹ FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 AUTH.NAME AUTHOR AFFILIATION'ITZPATRICK,E.
Indiana Michigan Power Co. (formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) ~
g
SUBJECT:
Forwards SG-95-12-010, "DC Cook Unit 1 1995 Interim Plugging Criteria 90 Day Rept," for Dec 1995.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT ID CODE/NAME PD3-1 LA HICKMANEJ INTERN l FILE CENTER 1
HICB NRR/DSSA/SRXB OGC/HDS2 EXTERNAL: NOAC COPIES LTTR,ENCL 1
1 1
1 1
1 1
1 1
1 1
0 1
1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL
<<1 1
1 1
1 1
1 1
1 1'OTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED(
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 12 ENCL 11
0 1
t
~r f
l k
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 8
January 19, 1996 Docket Nos.:
50-315 AEP:NRC:1166AC U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.
C.
20555 Gentlemen:
Donald C. Cook Nuclear Plant Unit 1 STEAN GENERATOR TUBE INSPECTIONS 90 DAY REPORT Amendment 200 to our unit 1 technical specifications, issued September 13, 1995, approved use of a 2.0 volt steam generator tube support plant interim plugging criterion for Cycle 15.
The safety evaluation report that accompanied the amendment required that we perform an assessment of the effectiveness of the methodology described in WCAP-14277.
The attachment to this letter contains this evaluation.
In summary, calculations performed for the assessment report for leak rates and probability of tube burst, based on actual end of cycle 14 bobbin coil voltage distributions were low, 0.23 gpm and 1.9 E-05, respectively.
Projected end of cycle 15 leakrate and probability of tube burst were also low, 0.70 gpm and 3.1 E-05.
Sincerely, E.
E; Fitzpatrick Vice President pit Attachment
t
U. S. Nuclear Regulatory Commission Page 2
AEP:NRC:1166AC CC:
A. A. Blind G. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector
- Bridgman J.
R. Padgett
ATTACHMENT TO AEP:NRC:1166AC D. C.
COOK UNIT 1 1995 INTERIM PLUGGING CRITERIA 90 DAY REPORT