ML17333A895

Discusses Completion of Licensing Action for GL 95-03, Circumferential Cracking of SG Tubes,

ML17333A895
Person / Time
Site:	Cook
Issue date:	05/15/1997
From:	John Hickman NRC (Affiliation Not Assigned)
To:	Fitzpatrick E INDIANA MICHIGAN POWER CO.
References
GL-95-03, GL-95-3, TAC-M92235, TAC-M92236, NUDOCS 9705210122
Download: ML17333A895 (8)

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1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 May 15.

1997

+O-BIG)~I4 Hr.

E.

E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive

Buchanan, HI 49107

SUBJECT:

DONALD C.

COOK NUCLEAR PLANT, UNIT NOS.

1 AND 2 COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAN GENERATOR TUBES,"

DATED APRIL 28, 1995 (TAC NOS.

M92235 AND H92236)

Dear Hr. Fitzpatrick:

On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-03, "Circumferential Cracking of Steam Generator Tubes," to all holders of operating licenses or construction permits for pressurized-water reactors.

The NRC issued GL 95-03 for three principal reasons:

(1)

Notify addressees about the safety significance of the recent steam generator tube inspection findings at Maine Yankee Atomic Power Station; (2)

Request that all addressees implement the actions described within the generic letter; and (3)

Require that all addressees submit to the NRC a written response regarding implementation of the requested actions.

In addition, GL 95-03 alerted addressees to the importance of performing comprehensive examinations of steam generator tubes using techniques and equipment capable of reliably detecting the types of degradation to which the steam generator tubes may be susceptible.

The staff also noted that the performance of steam generator tube examinations is controlled, in par t, by Appendix B to Title 10, Part 50, of the Code of'ederal Regulations (10 CFR Part 50).

In GL 95-03, the NRC staff also requested that licensees take the following actions:

(1)

Evaluate recent operating experience with respect to the detection and sizing of circumferential indications to determine the applicability to their plants; (2)

On the basis of the evaluation in Item (1) above, as well as past inspection scope and results, susceptibility to circumferential cracking, threshold of detection, expected or inferred crack growth rates, and I i other relevant factors, develop a safety assessment justifying continued operation until the next scheduled steam generator tube inspections; and 97052iOi22 9705i5 PDR ADCICK 050003i5 P

PDR

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J

E. Fitzpatrick (3)

Develop plans for the next steam generator tube inspections as they pertain to the detection of circumferential cracking.

The inspection plans should address, but not be limited to, scope (including sample expansion criteria, if applicable),

methods, equipment, and criteria (including personnel training and qualification).

To document the outcome of these

actions, the NRC staff requested that addressees prepare and submit the following:

(1)

A safety assessment justifying continued operation, predicated on the evaluation performed in accordance with requested Actions 1 and 2 above; and (2)

A summary of the inspection plans developed in accordance with requested Action 3 above, and a schedule for the next planned inspection.

In response to GL 95-03, you provided letters dated June 27,

1995, October 13,

1995, and December 19, 1995.

These submittals provided the information requested by GL 95-03; therefore, TAC Nos.

M92235 and M92236 are Closed.

For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."

If you have any questions regarding this matter, please contact me at (301) 415-3017.

Sincerely, Original signed by:

Docket Nos.

50-315/316 cc:

See next page John B. Hickman, Project

Manager, Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation DISTRIBUTION:

'Docket File EAdensam (EGAl)

JRoe OGC GGrant, RIII

SDembek, SPO-L PUBLIC PD3-3 Reading GMarcus ACRS KKarwoski, EMCB DOCUMENT NAME:

G:iDCCOOK C092235.LTR OFFICE PM:PD33 C

LA:PD33 NAME DATE JHickman W/r~/97 CBo le

/

/97 OFFICIAL RECORD COPY

I r

E. Fitzpatrick (3)

Develop plans for the next steam generator tube inspections as they pertain to the detection of circumferential cracking.

The inspection plans should address, but not be limited to, scope (including sample expansion criteria, if applicable),

methods, equipment, and criteria (including personnel training and qualification).

To document the outcome of these actions, the NRC staff requested that addressees prepare and submit the following:

(1)

A safety assessment justifying continued operation, predicated on the evaluation performed in accordance with requested Actions 1 and 2 above; and (2)

A summary of the inspection plans developed in accordance with requested Action 3 abov'e, and a schedule for the next planned inspection.

In response to GL 95-03, you provided letters dated June 27,

1995, October 13,

1995, and December 19, 1995.

These submittals provided the information requested by GL 95-03; therefore, TAC Nos.

M92235 and H92236 are Closed.

For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."

If you have any questions regarding this matter,'lease contact me at (301) 415-3017.

Sincerely, Original signed by:

Docket Nos.

50-315/316 cc:

See next page John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation DISTRIBUTION:

Docket Fi1 e EAdensam (EGAl)

JRoe OGC GGrant, RIII

SDembek, SPO-L PUBLIC PD3-3 Reading GMarcus ACRS KKarwoski, EHCB DOCUMENT NAME:

G:

DCCOOK C092235.LTR OFFICE NAME DATE PH:PD33 C

JHickman s /s~j'97 LA:PD33 CBo le

/

/97 OFFICIAL RECORD COPY

r e

Hr. 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, 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 Michigan 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 August 1 996

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