ML20141K650

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

ML20141K650
Person / Time
Site:	Callaway
Issue date:	05/27/1997
From:	Thomas K NRC (Affiliation Not Assigned)
To:	Randolph G UNION ELECTRIC CO.
References
GL-95-03, GL-95-3, TAC-M92228, NUDOCS 9705290272
Download: ML20141K650 (4)

Text

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Mr. Garry L. Randolph Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, Missouri 65251

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES," DATED APRIL 28, 1995, FOR UNION ELECTRIC COMPANY, CALLAWAY PLANT, UNIT 1 (TAC NO. M92228)

Dear Mr. Randolph:

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 i generator tube 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 Federal 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 other relevant factors, develop a safety assessment l justifying continued operation until the next scheduled steam generator i i tube inspections, NRC HLE CENTER CDPy DXg f 9705290272 970527 PDR ADOCK 05000483 P PDR _

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l Mr. Garry L.'Randolph May 27, 1997 l

(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 1 (including personnel training and qualification).

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 action 3 (above) and a schedule for the next planned inspection.

In response to GL 95-03, you provided letters dated June 27, 1995, and January 12, 1996 for the Callaway Plant. These submittals provided the information requested by GL 95-03; therefore' TAC No. M92228 is closed. For l your information, the staff's findings regarding this issue are contained in i NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."

If you have any questions regarding this matter, please contact me at (301) 1 415-1362. ~l Sincerely, j l

ORIGINAL SIGNED BY ]

Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects - III/IV ,

Office of Nuclear Reactor Regulation I l Docket No. 50-483 DISTRIBUTION:

Docket File ACRS, TWFN PUBLIC PDIV-2 Reading J. Roe OGC, 015B18 l cc: See next page E. Adensam W. Johnson, RIV l W. Bateman P. Gwynn, RIV 1 K. Thomas E. Peyton K. Karwoski, EMCB S. Dembek, SP0-L 1

DOCUMENT NAME

CAL 92228.LTR OFC PDIV-2/PM PDIV-2/LA l NAME KTkm[s:ye EPfy O F

! DATE 5/Ti97 5671/97 I 0FFICIAL RECORD COPY

Mr. Garry L. Randolph May 27, 1997 (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).

(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, and January 12, 1996 for the Callaway Plant. These submittals provided the information requested by GL 95-03; therefore TAC No. M92228 is 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) 415-1362.

Sincerely, W fn. \ vwns-Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket No. 50-483 cc: See next page f

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Mr, Garry L. Randolph

. May 27, 1997 l cc:

Professional Nuclear Mr. Otto L. Maynard Consulting, Inc. President and Chief Executive Officer 19041 Raines Drive Wolf Creek Nuclear Operating Corporation Derwood, Maryland 20855 P.O. Box 411 {

Burlington, Kansas 66839 i l Gerald Charnoff, Esq. '

l Thomas A. Baxter, Esq. Mr. Dan I. Bolef, President Shaw, Pittman, Potts & Trowbridge Kay Drey, Representative 2300 N. Street, N.W. Board of Directors Coalition Washington, D.C. 20037 for the Environment 6267 Delmar Boulevard Mr. H. D. Bono University City, Missouri 63130 l Supervising Engineer, Site Licensing Mr. Lee Fritz Union Electric Company Presiding Comissioner Post Office Box 620 Callaway County Court House Fulton, Missouri 65251 10 East Fifth Street Fulton, Missouri 65151 U.S. Nuclear Regulatory Comission Resident Inspector Office Mr. Alan C. Passwater, Manager 8201 NRC Road Licensing and Fuels l Steedman, Missouri 65077-1302 Union Electric Company Post Office Box 66149 i

Mr. J. V. Laux, Manager St. Louis, Missouri 63166-6149 Quality Assurance Union Electric Company

! Post Office Box 620 Fulton, Missouri 65251 Manager - Electric Department Missouri Public Service Comission l 301 W. High Post Office Box 360 .

Jefferson City, Missouri 65102 Regional Administrator, Region IV U.S. Nuclear Regulatory Comission Harris Tower & Pavilion l 611 Ryan Plaza Drive, Suite 400 l Arlington, Texas 76011-8064 Mr. Ronald A. Kucera, Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, Missouri 65102 l

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