ML20141C915

Informs of Completion of Licensing Action for GL 95-03, Circumferential Cracking of SG Tubes, for Plant,Units 1 & 2.Tacs M92264 & M92265,closed

ML20141C915
Person / Time
Site:	Point Beach
Issue date:	05/13/1997
From:	Gundrum L NRC (Affiliation Not Assigned)
To:	Grigg R WISCONSIN ELECTRIC POWER CO.
References
GL-95-03, GL-95-3, TAC-M92264, TAC-M92265, NUDOCS 9705190269
Download: ML20141C915 (3)

Text

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.p ,2 UNITED STATES gtg, a

{o Jf NUCLEAR REGULATORY COMMISSION

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1. m ,*f' l May 13, 1997 Mr. Richard R. Grigg Chief Nuclear Officer l Wisconsin Electric Power Company o

231 West Michigan Street, Room P379 Milwaukee, WI 53201 i

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC' LETTER 95-03, i "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES," DATED APRIL 28,

, 1995, FOR POINT BEACH NUCLEAR PLANT, UNIT NOS. 1 AND 2 (TAC NOS. M92264 AND M92265) l_

Dear Mr. Grigg:

). On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic i Letter (GL) 95-03, "Circumferential Cracking of Steam Generator Tubes," to all i

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.

l (2) Request that all-addressees implement the actions described within the generic letter.

j (3) Require that all addressees submit te f.he 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 l steam generator tubes may be susceptible. The staff also noted that the '

performance of steam generator tube examinations is controlled, in part, by Appendix B to Title 10, Part 50, of the Code of Federal Regulatfons (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 other relevant factors, develop a safety assessment justifying continued operation until the next scheduled steam generator tube inspections.

NRC FILE CENTER COPY w 9705190269 970513 '"

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R. R. Grigg ,

(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 i (including personnel training and qualification).

l To document the outcome of these actions, the NRC staff requested that addressees prepare and submit the following: l (1) A safety assessment justifying continued operation, predicated on the evaluation performed in accordance with requested actions 1 and 2 ,

(above).

(2) A summary of the inspection plans developed in accordance with requested 4 action 3 (above) and a schedule for the next planned inspection. '

4 In response to GL 95-03, you provided letters dated June 26, 1995, and

October 6,1995, for Point Beach Nuclear Plant. These submittals provided the information requested by GL 95-03; therefore TAC Nos. M92264 AND M92265 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 Linda L.

Gundrum at (301) 415-1380.

Sincerely, LinhaT.bunhruk,krojectManager Project Directorate III-l Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc: See next page DISTRIBUTION: '

Docket File PUBLIC PDIII-1. Reading J. Roe C. Jamerson L. Gundrum K. Karwoski, EMCB S. Dembek, SP0-L OGC ACR5 J. McCormick-Barger, RIII DOCUMENT NAME: G:\WPDOCS\PTBEACH\PTB92264.LTR Ta ,eceive e copy of this docwnent,indcate in the ben: "C' = Copy without ettechment! enclosure "E" = Copy with a,ttachment/ enclosure *N* = No copy 0FFICE PM:PD31 E LA:PD31 E D:PD31 4 nsg NAME LGundrum:>M W CJamerson (M , JHannopf' O "

DATE 5/ts /97 5/13 /97 31 5/ L3/97 0FF1CIAL RECORD COPY

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4. .

Mr. Richard R. Grigg Point Beach Nuclear Plant Wisconsin Elec.tric Power Company Unit Nos. 1 and 2 cc:

Ernest L. Blake, Jr.

Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.

4 Washi:<, ton, DC 20037 Mr. Scott A. Patulski Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck

Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, Wisconsin 54228 Chairman-Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers,. Wisconsin 54241 Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin P.O.' Box 7854 Madison, Wisconsin 53707-7854 Mus lW7

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