ML20141K710

Discusses Response to GL 95-03 by Ltrs Dated 960201,950816 & 0627 for Virgil C Summer Nuclear Station.Submittals Provided Info Requested by Generic Ltr.Tac M92280 Closed

ML20141K710
Person / Time
Site:	Summer
Issue date:	05/27/1997
From:	Andrea Johnson NRC (Affiliation Not Assigned)
To:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
References
GL-95-03, GL-95-3, TAC-M92280, NUDOCS 9705290329
Download: ML20141K710 (3)

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UNITED STATES NUCLEAR REGU!.ATORY COMMISSION WASHlhGToN, D.C. FA-0001

%, . . . . . p! May 27, 1997 Mr. Gary J. Taylor Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 29065

$UBJECT: COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES," DATED APRIL 28, 1995, FOR VIRGIL C. SUMMER NUCLEAR STATION (TAC N0. M92280)

Dear Mr. Taylor:

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 to (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 l the requested actions.

l 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 i Appendix B to Title 10, Part 50, of the Code of Federal Regulations (10 CFR '

Part50).

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

(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 this evaluation, as well as past inspection scope and i 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.

(3) Develop plans for the next steam generator tu.e inspections as they pertain to the detection of circumferential cracking. The inspection plans should address, but not be limited to, scope (including sample

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4 4-expansion criteria, if applicable), methods, equipment, and criteria (including personnel training and qualification),

i i To document the outcome of these actions, the NRC staff requested that addressees prepare and submit (1) a safety assessment justifying continued i

operation predicated on the evaluation performed in 1 and 2 above, and (2) a summary of the inspection plans developed in action 3 above and a schedule for the next planned inspection.

) In response to GL 95-03, you provided letters dated February 1, 1996,

! August 16, 1995, and June 27, 1995 for Vigil C. Summer Nuclear Station. The l replacement of steam generators at Virgil C. Summer Nuclear Station in l December 1994, provided a new baseline for cracking and indications of the a

plants steam generator tubes. These submittals provided the information requested by GL 95-03; therefore TAC No. M92280 is closed.

1 The staff's findings are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."

l If you have any questions regarding this rnatter, please contact me at (301) 415 1497.

Sincerely, ,

(Original Signed By) i Allen R. Johnson, Project Manager i' Project fdrectorate 11-1 Divisior of Reactor Projects - I/II

{ Office of Nuclear Reactor Regulation

. Docket No. 50-395 l

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i Mr. Gary J. Taylor VIRGIL C. SUMMER NUCLEAR STATION

South Carolina Electric & Gas Company cc

l Mr. R. J. White Nuclear Coordinator S.C. Public Service Authority c/o Virgil C. Summer Nuclear Station

Post Office Box 88, Mail Code 802 g Jenkinsville, South Carolina 29065 J. B. Knotts, Jr., Esquire

. Winston & Strawn Law Firm i 1400 L Street, N.W.

l Washington, D.C. 20005-3502 4

Resident Inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 1 a er a 3 b3 Chairman, Fairfield County Council Drawer 60 Winnsboro, South Carolina 29180 4

Mr. Virgil R. Autry Director of Radioactive Waste Management Bureau of Solid & Hazardous Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Mr. Robert M. Fowlkes, Manager Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 303 Post Office Box 88 Jenkinsville, South Carolina 29065 Ms. April R. Rice, Manager Nuclear Licensing & Operating Experience South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 830 Post Office Box 88 Jenkinsville, South Carolina 29065

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