ML17333A741

Authorizes Licensee to Use Code Case N-533 Until Such Time as Code Case Included in Future Rev of RG 1.147,per 10CFR50.55a(a)(3)(i)

ML17333A741
Person / Time
Site:	Cook
Issue date:	01/16/1997
From:	Marcus G NRC (Affiliation Not Assigned)
To:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
Shared Package
ML17333A742	List: ML17333A741 ML17333A743
References
RTR-REGGD-01.147, RTR-REGGD-1.147 TAC-M97179, TAC-M97180, NUDOCS 9701210441
Download: ML17333A741 (6)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 january 16, 1997

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Mr. E.

E. Fitzpat}ick, Vice President Indiana Michigan Power Nuclear Generation Group 500 Circle Drive

Buchanan, MI 49107

SUBJECT:

D.C.

COOK, UNIT NOS.

1 AND 2, RELIEF REQUEST IN REGARD TO VT-2 EXAMINATIONS AND CORRECTIVE ACTIONS (TAC NOS.

M97179 AND M97180)

Dear Mr. Fitzpatrick:

By letters dated October 25, 1996 (AEP:NRC:0969AY) and November 27,

1996, (AEP:NRC:0969AZ, Attachments 2 and 3) Indiana Michigan Power Company (IMPCo),

the licensee for the D.C.

Cook Nuclear Plant Units 1 and 2, requested relief from the requirements of the 1989 Edition of the ASME Boiler and Pressure Vessel

Code,Section XI, in regard to VT-2 visual examination of insulated components stated in paragraph IWA-5242(a) and corrective measures if leakage occurs at bolted connections during system pressure

tests, stated in Subsection IWA-5250(a)(2).

Based on the information submitted, the staff concludes that IMPCo's proposed alternative to use Code Case N-533 in lieu of the requirements of Subsection IWA-5242(a) of the 1989 Edition of the ASME Code,Section XI, provides an acceptable level of quality and safety.

Therefore, pursuant to 10 CFR 50.55a(a)(3)(i) you are authorized to use Code Case N-533 until such time as the code case is included in a future revision of Regulatory Guide 1. 147.

At that time you are to follow all provisions in Code Case N-533, with limitations issued in Regulatory Guide 1. 147, if any, if you continue to implement this relief request.

The staff also reviewed IMPCO's proposed alternative to the requirement of Subsection IWA-5250(a)(2) of the ASME Code,Section XI, 1989 Edition.

IMPCo has proposed to perform an evaluation of the bolted connection to determine the susceptibility of the bolting to corrosion and the potential for failure.

If the evaluation concludes that bolting is degraded or is non-conclusive in determining degradation of bolting, the bolt closest to the source shall be

removed, VT-3 examined and evaluated in accordance with IWA-3100(a).

When the removed bolt shows evidence of rejectable degradation, all remaining bolting shall be removed and VT-3 examined and evaluated in accordance with IWA-3100(a).

This alternative will provide an acceptable level of quality and

safety, as the integrity of the joint will be maintained.

Therefore, the licensee's proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i).

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E. Fitzpatrick Indiana Hichigan 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, Site Vice President 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 State Capitol Lansing, Michigan 48909 Drinking Water and Radiological Protection Division Hichigan Department of Environmental guality 3423 N. Hartin Luther King Jr Blvd P. 0.

Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 Donald C.

Cook Nuclear Plant Hr. Steve J.

Brewer Indiana Michigan Power Nuclear Generation Group 500 Circle Drive

Buchanan, Michigan 49107 hu6ust 1996

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

r Sincerely, enclosel safety I

II Original signed by G. Kelly for:

Gail H. Marcus, Director Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear'Reactor Regulation Docket Nos.

50-315 and 50-316

Enclosure:

Safety Evaluation cc w/encl:

See next page DISTRIBUTION Docket File PUBLIC EAdensam (EGAl)

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

Sincerely, Original signed by G. Kelly for:

Gail H. Marcus, Director Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316

Enclosure:

Safety Evaluation cc w/encl:

See next page DISTRIBUTION Docket File PUBLIC EAdensam (EGA1)

JHickman OGC JCaldwell, RIII PD3-3 R/F EBarnhill

BMcCabe, EDO JRoe PPatnaik ACRS GHill (4)

DOCUMENT NAME:

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