ML20205P537

Informs of Closeout of NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes

ML20205P537
Person / Time
Site:	Summer
Issue date:	11/04/1988
From:	Hayes J Office of Nuclear Reactor Regulation
To:	Bradham O SOUTH CAROLINA ELECTRIC & GAS CO.
References
IEB-88-002, IEB-88-2, TAC-67327, NUDOCS 8811080200
Download: ML20205P537 (3)

Text

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.s November 4, 1988 DISTRIBUTION

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NRC PDR Local PDR PD21 r/f S. Varga (14E4)  ;

G. Lainas Docket No. 50-395 E. Adensam P. Anderson J. Hayes .

Mr. O. S. Bradham OGC i Vice President, Nuclear Operations E. Jordan (MMBB3302)

South Carolina Electric & Gas Company B. Grimes (9A2)

Virgil C. Sunner Nuclear Station ACRS (10)

P. O. Box 88 Jenkinsville, South Carolina 29065

Dear fir. Bradham:

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SUBJECT:

CLOSE0VT OF NRC BULLETIN 88-02, "RAPIDLY PROPAGATING FATIGUE CRACKS IN STEAM GENERATOR TUBES" - V. C. SUMMER NUCLEAR STATION (TAC NO. 67327)

A March 24, 1988 letter from Mr. D. A. Nauman of your company to the Region II Administrator, Dr. J. Nelson Grace, presented your response to item A of NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks in Steam Generator Tubes."

This response indicated that the March and April inspections of the steam generators at the V. C. Sunr.er Station had revealed no denting at the uppermost support plates. The March 24, 1988 letter also indicated that you intended to revise Surveillance Test Procedure (STP) 404.901, "Steam Generator Tube Inspec-tion," prior to the performance of the next eddy current inspection which is occurring during the present outage. The letter further statt:d that the i revision to STP 404.901 would incorporate the following actions if denting is

, found:

(a) an enhanced primary-to-secondary 'eak rate monitoring program will be

initiated, and 1

(b) a program will be established to minimize the probability of a rapidly propagating fatigue failure.

I During a site visit the week of October 18, 1988, STP 404.901 was reviewed to verify whether or not you have in place administrative controls to ensure that

item B of Bulletin 88-02 is implemented and that item C of the Bulletin is  :

implemented in the event that denting of the uppermost support plates is found  :

during subsequent inspections of the steam generators. The findings are as -

follows:

1. Section 2.2.1, Definitions, does not define denting., Denting should L be defined in the procedure in a manner consistent with item A of Bulletin j 88-02. ,

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2. Acceptance Criterion 9.3 requires a report be filed with the NRC of the eddy current test results when denting is found. In addition, this j dCCeptance requirement indicates that fluClear Licensing should be informed 30 that Enhanced Monitoring Programs, Engineering Evaluations, and/or .

Special Reports to the NRC may be inplemented, it would appear that the [g E

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Mr. O. S. Bradham )

i l requirements for meeting Bulletin 88 02 should be delimated in STP 404.901. Some statement to the effect that if denting is foind then the provisions of item C of t;RC Bulletin 88 02 will be implemeitoi would seem appropriate. The March 24, 1988 letter seems to be unclear in that the ,

revision to STP 404.901 does not specifically call for the initlat ion ci l the enhanced primary-to-secondary leak rate monitoring program nor the i establishment of the program to minimize the probability of a rapidly ,

propagating fatigue failure. It only states that an Enhanced Monitoring '

Program jma be initiated. The procedure should be clear that the require ments of Bulletin 88-02 will be implemented.

]

These findings were discussed with Mr. C. McKinney of your staff and, following his discussion with the members of your staff responsible for STP 404.901, he indicated that the definition of denting would be added to the STP. Since Connitment 2 of STP 404.901 references the NRC Bulletin 88 02, the STP does not need to refer to item C of the Bulletin. Mr. McKinney indicated that the STP would be clarified to assure that the enhanced monitoring program and the

. program to minimize the probability of a rapidly propagating fatigue failure 4

of a tube would be initiated upon the determination of denting in one of the steam generators. Mr. McKinney indicated that these changes would be made to i the STP prior to the next refueling outage. With this action, Bulletin 88-02

will be closed out upon the implementation of the changes noted here.

i Sincerely,

/s/

John J. Hayes, Jr. Project !!anager 1

Project Directorate 11-1 Division of Reactor Projects I/II l cc: See next page 1

, (SUliLTR10/27)

• SEE PREVIOUS CONCURREllCES i .

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NAME : PAnderson* :JJHayes:ch* : CYCheng*  : EA ensam  :  :  :

DATE : 11/02/88  : 11/02/88  : 11/03/88  : th/3/88

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OFFICIAL RECORD COPY

Mr. O. S. Bradhan.

South Carolina Electric & Gas Company Virgil C. Sumer Nuclear Station cc:

Mr. William A. Williams, Jr.

Technical Assistant - Nuclear Operations Santee Cooper P.O. Box 764 (Mail Code 153)

Columbia, South Carolina 29218 J. B. Knotts, Jr. , Esq.

Bishop Cook, Purcell and Reynolds 1400 L Street, N.W.

Washington, D. C. 20005-3502 Resident inspector /Sumer NPS c/o U.S. Nuclear Regulatu,"y Comission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region !!

U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council P.O. Box 293 Winnsboro, South Carolina 29180 Attorney General Box 11549 Columbia, South Carolina 29211 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 South Carolina Electric & Gas Company Mr. A. R. Koon, Jr. , Manager Nuclear Licensing Virgil C. Sumer Nuclear Station P. O. Box 88 Jenkinsville, South Carolina 29065 l

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