ML17333A511

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Forwards SE & Technical Ltr Rept Re Second 10-yr Interval ISI Augmented Vessel Exam Alternative
ML17333A511
Person / Time
Site: Cook  
Issue date: 07/26/1996
From: Reinhart M
NRC (Affiliation Not Assigned)
To: Fitzpatrick E
AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
Shared Package
ML17333A512 List:
References
TAC-M93613, NUDOCS 9607290155
Download: ML17333A511 (4)


Text

Hr.

E.

E. Fitzpatrick, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43215 July 26, 1996

SUBJECT:

D.C.

COOK, UNIT 1, SECOND 10-YEAR INTERVAL INSERVICE INSPECTION AUGMENTED VESSEL EXAMINATIONALTERNATIVE (TAC NO. M93613)

Dear Mr. Fitzpatri ck:

By letter dated July 28,

1995, Indiana Michigan Power Company (IHPCo) submitted a request to the NRC staff to use an alternative augmented examination regarding the reactor pressure vessel (RPV) shell welds at D.C.

Cook Nuclear Plant, Units 1 and 2.

In letters dated January 25,

1996, April 30,
1996, and May 6,
1996, you deferred the alternative to the required augmented reactor vessel exam for D.C.

Cook Nuclear Plant, Unit 2, and provided additional and clarifying information to support the request for Unit 1.

The staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory, has reviewed and evaluated the information provided by your submittals.

Based on the information submitted, the staff concludes that IHPCo has maximized examination coverage to the extent practical, and that imposing additional examinations would result in a considerable hardship without a

compensating increase in the level of quality and safety.

Therefore, your proposed alternative using the augmented RPV examination of the accessible weld volumes from the inside surface provides an acceptable level of quality and safety to satisfy the requirements of 10 CFR 50.55a(g)(6)(ii)(A),

and is authorized pursuant to 10 CFR 50.55a(g)(6)(ii)(A)(5).

The staff's evaluation and conclusions are contained in the enclosed safety evaluation.

9607290155 960726 PDR ADQCK 050003l5 P

PDR Docket Nos.

50-315 and 50-316 Sincerely, Original signed by Kevin Connaughton for Hark Reinhart, Acting Director Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Enclosure:

Safety Evaluation w/attached Technical Letter Report cc w/encl:=-

See next page DISTRIBUTION: See next page DOCUMENT NAME:

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Hr.

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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 Hanager 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'ost Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan, 48909 Drinking Water and Radiological Protection Division Michigan Department of Environmental equality 3423 N. Hartin Luther King Jr Blvd P. 0.

Box 30630 CPH Mailroom

Lansing, Michigan 48909-8130 Donald C.

Cook Nuclear Plant Hr. S.

Brewer American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43215 June l996

STR UT ON FO D.C.

COOK RELIEF RE VEST DATED: July 26, 1996 (Docket. Fi 1 e'UBLIC PD3-I R/F JRoe EAdensam (EGA1)

JHickman CJamerson GBagchi OGC GHi11 (4)

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