ML20148D145

Discusses Completion of Licensing Action for GL 95-03, Circumferential Cracking of SG Tubes, Dtd 950428,for Plants,Unit 1 & 2

ML20148D145
Person / Time
Site:	Prairie Island
Issue date:	05/22/1997
From:	Wetzel B NRC (Affiliation Not Assigned)
To:	Richard Anderson NORTHERN STATES POWER CO.
References
GL-95-03, GL-95-3, TAC-M92266, TAC-M92267, NUDOCS 9705300095
Download: ML20148D145 (3)

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1. 1. pera% N BUL l p= L UNITED STATES

! < B NUCLEAR REGULATORY COMMISSION -

• WASHINGTON, D.C. 3088M001 May 22, 1997 Mr. Roger O. Anderson, Director

!. Licensing and Management issues l Northern States Power Company i 414 Nicollet Mall Minneapolis, Minnesota 55401

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03,

! "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES," DATED APRIL 28,1995, FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NOS.1 AND 2 (TAC NOS. M92266 AND M92267)

Dear Mr. Anderson:

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:

i. (1) Notify addressees about the safety significance of the recent steam generator tube l  ; inspection findings at Maine Yankee Atomic Power Station.

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

(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 part, by Appendix B to Title 10, Part 50, of the Code of FederalRegulations (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 ev@sation 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.

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9705300095 970522 PDR- ADOCK050002y2

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s ' Mr. RogIr And:rson .  ;

1 (3) Develop plans for the next steam g9nerator 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 r;ersonnel training and qualification). j To document the outcome of these actions, the NRC staff requested that addressees l prepare and submit the following:

(H -A safety assessment justifying continued operation, predicated on the evaluation ]

rsrformed in accordance with requested actions 1 and 2 (above). .

I (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 27,1993, and April 8,1996, for Prairie Island Nuclear Generating Plant Units 1 and 2. These submittals provided the information requested by GL 95-0.9 therefore TAC Nos, M92266 and M92267 are closed.

For your information, the staff's findings regarding this issue are contaY,ed in i NUREG-1604, "Circumferential Cracking of Steam Generator Tubes." l If you have any questions regarding this matter, please contact me at (301) 415-1355.

I Sincerely, i Original signed by t Beth A.' Wetzel, Project Manager

! Project Directorate 111-1 Division of Reactor Projects -lil/IV l Office of Nuclear Reactor Regulation Docket Nos: 50-282 and 50-306 ,

t cc: See next page t

DISTRIBUTION 5 Docket File.; .

PUBLIC PD# 3-1 Reading

, J. Roe

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K. Karwoski S. Dembek J. McCormick-Barger, Rlli DOCUMENT NAME: G:\WPDOCS\ PRAIRIE \Pl92266.LTR l To receive a copy of this document, indicate in the box C = Copy w/o attachment / enclosure E-Copy with attachmeat/enclosu o N

= No copy OFFICE PM:PD31 E\ LA:PD31 E D:PDL1A BWetzel:d[ CJamersonChJHa' k NAME DATE 5 6/97 d 5/[97 O 5fM/97  ;

OFFICIAL RECORD COPY

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! ' .Mr. Roger O. Anderson, Director Prairie Island Nuclear Generating Northern States Power Company Plant cc:

J. E. Silberg, Esquire Site Licensing Shaw, Pittman, Potts and Trowbridge Prairie Island Nuclear Generating 2300 N Street, N. W. Plant Washington DC 20037 Northern States Power Company 1717 Wakonade Drive East Plant Manager Welch, Minnesota 55089 Prairie Island Nuclear Generating i Plant Tribal Council l Northern States Power Company Prairie Island indian Community 1717 Wakonade Drive East ATTN: Environmental Department Welch, Minnesota 55089 5636 Sturgeon Lake Road Welch, Minnesota 55089 Adonis A. Nebiett Assistant Attorney General Office of the Attorney General 455 Minnesota Street Suite 900 St. Paul, Minnesota 55101-2127 U.S. Nuclear Regulatory Commission Resident inspector's Office i 1719 Wakonade Drive East Welch, Minnesota 55089-9642 l 4

Regional Administrator, Region til U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Mr. Jeff Cole, Auditor / Treasurer Goodhue County Courthouse Box 408 Red Wing, Minnesota 55066-0408 Kris Sanda, Commissioner Department of Public Service 121 Seventh Place East Suite 200 St. Paul, Minnesota 55101-2145 November 1996

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