ML17333A327
| ML17333A327 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/28/1996 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| TAC-M92664, NUDOCS 9603040320 | |
| Download: ML17333A327 (6) | |
Text
February 28, 1996 Hr.
E.
E. Fitzpatrick, Vice President Indiana Michigan Power Company c/o American E ectric Power Service Corporation 1 Riverside Plaza
- Columbus, OH 43215
SUBJECT:
REACTOR PRESSURE VESSEL INTEGRITY ASSESSMENT FOR D.C.
COOK UNIT 1
(TAC NO. H92664)
Dear Hr. Fitzpatrick:
By letter dated November 20,
- 1995, you submitted a response to Generic Letter (GL) 92-01, Revision 1, Supplement 1 for the D.C.
Cook reactor vessels.
The response contained your evaluation of the best-estimate copper for the intermediate/lower shell circumferential weld that was fabricated using IP-3571 weld wire.
Enclosed is a request for additional information (RAI) in regard to that response.
Within 30 days of your receipt of this RAI, please respond with a plan for providing (1) the requested information, and (2) a revised pressurized thermal shock (PTS) assessment.
With this request, we consider our review of the information requested by GL 92-01, Revision 1, Supplement 1 to be complete for D.C.
Cook Unit 1.
Our review of the requested plant-specific PTS assessment will be performed separately.
Should you have any questions on this matter, please contact me at (301) 415-3017.
Sincerely, Docket No. 50-315 cc w/encl:
See next page Original signed by:
John Hickman, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation J.
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cj February 28, 1996 Hr. E.
E. Fitzpatrick, Vice President Indiana Michigan Power Company c/o American E ectric Power Service Corporation 1 Riverside Plaza
- Columbus, OH 43215
SUBJECT:
REACTOR PRESSURE VESSEL INTEGRITY ASSESSMENT FOR D.C.
COOK UNIT 1 (TAC NO. H92664)
Dear Hr. Fitzpatrick:
By letter dated November 20,
- 1995, you submitted a response to Generic Letter (GL) 92-01, Revision 1, Supplement 1 for the D.C.
Cook reactor vessels.
The response contained your evaluation of the best-estimate copper for the intermediate/lower shell circumferential weld that was fabricated using IP-3571 weld wire.
Enclosed is a request for additional information (RAI) in regard to that response.
Within 30 days of your receipt of this RAI, please respond with a plan for providing (1) the requested information, and (2) a revised pressurized thermal shock (PTS) assessment.
With this request, we consider our review of the information requested by GL 92-01, Revision 1,
Supplement 1 to be complete for D.C.
Cook Unit 1.
Our review of the requested plant-specific PTS assessment will be performed separately.
Should you have any questions on this matter, please contact me at (301) 415-3017.
Sincerely, Docket No. 50-315 cc w/encl:
See next page DISTRIBUTION Original signed by:
John Hickman, Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket File PDIII-1 R/F D. HcDonald PUBLIC ACRS E. Adensam(EGAl)
OGC B. Elliot K. Wichman J.
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No copy DOCUMENT NAME:
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Mr. E.
E. Fitzpatrick Indiana Michigan Power Company CC:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall P.O.
Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C.
Cook Nuclear Plant 1 Cook Place Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.
W.
Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 Stat'e Capitol
- Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. 0.
Box 30195
- Lansing, Michigan 48909 Donald C.
Cook Nuclear Plant Mr. S.
Brewer American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215 April 1995
RE VEST FOR ADDITIONA INFORMATION REACTOR PRESSURE VESSEL INTEGRITY ASSESSMENTS DONALD C.
COOK NUCLEAR PLANT UNIT 1
INDIANA MICHIGAN POW R COMPANY
- 1) Since the amount of copper reported for welds fabricated using heat number IP 3571 weld wire varies from 0.066X to 0.53X, the licensee should determine the best-estimate copper using a weighted average.
The weighted average for heat number IP 3571 weld material should be determined by: (a) determining the average amount of copper for each'weld in the database, (b) determining the number of coils used in the fabrication of the weld, and (c) dividing the sum of the products of the average amount of copper for a weld and the number of coils used to fabricate the weld by the number of coils to produce the welds.
Identify for each weld sample in the database the location within the sample where the measurements were taken.
The best-estimate nickel should be a
pimple average of the average nickel from each weld in the database.
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