ML17332A888
| ML17332A888 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/16/1995 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1173E, GL-92-01, GL-92-1, NUDOCS 9508210259 | |
| Download: ML17332A888 (6) | |
Text
PRIORITY (ACCELERATED RZDS PROCESSZNG)
REgULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9508210259 DOC.DATE: 95/08/16 NOTARIZED: YES DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 P
50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
(formerly Indiana 6 Michigan Ele RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)
I
SUBJECT:
Responds to GL 92-01,Rev 1,Suppl 1, "Reactor Vessel Structural Integrity."
0 DISTRIBUTION CODE:
A028D COPIES RECEIVED'LTR L ENCL 0 SIZE:
TITLE: Generic Letter 92-01, Rev 1, Suppl 1 Responses
+Reactor Vessel Struct NOTES RECIPIENT ID CODE/NAME PD3-1 PD INTERNA~'ILE CE 1
PE/PDI-1 OGC/HDS2 EXTERNAL: NOAC COPIES LTTR ENCL RECIPXENT ID CODE/NAME HICKMAN,J NRR/DE/EMCB NUDOCS-ABSTRACT RES/DE/MEB NRC PDR COPIES LTTR ENCL 1
2 1
1 N
NOTE TO ALL "RZDS" RECZPlENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL
-DESK, ROOM OWFN 5DS (415-2083)
TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 11 ENCL 10
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s'ndiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 August 16, 1995 AEP'NRC'1173E Docket Nos.:
50-315 50-316 U.
S. Nuclear Regulatory Commission ATTN:
Document'ontrol Desk Washington, D.
C.
20555 Gentlemen:
Donald C.
Cook Nuclear Plant Units 1 and 2
RESPONSE
TO NRC GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1 REACTOR VESSEL STRUCTURAL INTEGRITY NRC review of reactor pressure vessel (RPV) data submitted pursuant to the requirements of generic letter (GL) 92-01, revision 1
determined that licensees may not have considered all pertinent data in their responses.
Supplement 1 to GL 92-01, revision 1 was issued and requires licensees to identify, collect, and report any new data pertinent to the structural integrity of their RPVs and to assess the impact of the data on their RPV integrity analyses.
This document addresses the GL 92-01, revision 1, supplement 1 "Required Response" part (1) requirement to provide within 90 days a
description of those actions taken or planned to locate all data relevant to the determination of the RPV integrity, or an explanation of why the existing data base is considered complete as previously submitted.
In light of the information contained in supplement 1 to NRC GL 92-01, revision 1 and presentations made at the "NRC Workshop on RPV Integrity Issues" on July 11-13, 1995, it is recognized that additional RPV data may exist.
Actions to locate all pertinent RPV data will, therefore, be accomplished for Donald C.
Cook Nuclear Plant as described in the following paragraphs.
The unit 1
RPV was fabricated by Combustion Engineering.
Information used
,for the RPV integrity
- analyses, previously submitted to NRC in our letter AEP:NRC:08940, dated October 29,
- 1990, was developed using information obtained from unit 1's material surveillance program and from sister plants.
To locate and review all other relevant RPV data for unit 1, we will check the available RPV industry data bases (listed below) and, as 9508210259 950816 PDR 'DOCK 05000315 I
P PDR
U. S. Nuclear Regulatory Commission Page 2
AEP:NRC:1173E appropriate, initia'te confirmatory follow-up communications with sister plants.
Industry data bases to be consulted will include:
a)
EPRI's surveillance capsule database
- PREP3, b)
Westinghouse Owners Group's database RPVDATA, c) Combustion Engineering's Report "Reactor Vessel Group Records Evaluation Program, Phase 2 for the Donald C. Cook Reactor Pressure Vessel Plates,
- Forgings, Welds and Cladding," d) NRC's "Reactor Vessel Integrity Database" (RVID), and e)
Oakridge National Laboratory's "Power Reactor Embrittlement Database" (PR-EDB).
Unit 2 RPV was fabricated by Chicago Bridge
& Iron.
Information used for the RPV integrity analyses previously submitted to NRC in our letter AEP:NRC:0894T, dated March 12, 1993, was developed using information obtained from unit 2's material surveillance program.
To locate and review all other relevant RPV data for unit 2, we will check the available industry data bases (listed below) and, as appropriate, initiate confirmatory follow-up communications with sister plants.
Industry data bases to be consulted include:
a)
EPRI's surveillance capsule database PREP3, b) Westinghouse Owners Group's database
- RPVDATA, c)
NRC's "Reactor Vessel Integrity Database" (RVID),
and d)
Oakridge National Laboratory's "Power Reactor Embrittlement Data Base" (PR-EDB).
Following our review of the available industry RPV data bases, we will summarize our findings and address GL 92-01, revision 1,
supplement 1 "Required Response" part (2).
Sincerely, EZ+pm'.
E. Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS Q+>< DAY OF r~~
~ 1995 otary Pu lic eh
'b J
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~rj
-J
U.
S. Nuclear Regulatory Commission Page '3 AEP:NRC:1173E cc:
A. A. Blind G. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector
- Bridgman J.
R. Padgett