IR 05000483/1996010

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Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-483/96-10
ML20137S072
Person / Time
Site: Callaway 
Issue date: 04/07/1997
From: Howell A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Schnell D
UNION ELECTRIC CO.
References
NUDOCS 9704150022
Download: ML20137S072 (5)


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SUBJECT:

NRC INSPECTION REPORT 50-483/96-10 AND NOTICE OF VIOLATION

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Dear Mr. Schnell:

Thank you for your letter of March 13,1997, in response to our letter and Notice of

i Violation dated February 14,1997. We have reviewed your reply and find it responsive to

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the concerns raised in our Notice of Violation. We will review the implementation of your

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corrective actions during a future inspection to determine that full compliance has been f

achieved and will be maintained.

Sincerely,

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grthur T. HoA/x

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11111, Director Division of tor Safety i

Docket No.: 50-483 i

License No.: NPF-30 cc:

Professional Nuclear Consulting, Inc.

19041 Raines Drive Derwood, Maryland 20855

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9704150022 970407

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Gerald Charnoff, Esq.

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Thomas A. Baxter, Esq.

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2300 N. Street, N.W.

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Washington, D.C. 20037

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H. D. Bono, Supervising Engineer

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Site Licensing

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Union Electric Company

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G. L. Randolph, Vice President

Nuclear Operations

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Union Electric Company

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P.O. Box 620 Fulton, Missouri 65251 Manager Electric Department Missouri Public Service Commission

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301 W. High.

P.O. Box 360 Jefferson City, Missouri 65102 Ronald A. Kucera, Deputy Director Department of Natural Resources P.O. Box 176

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Jefferson City, Missouri 65102

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Otto L. Maynard, President and Chief Executive Officer

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Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839 Dan 1. Bolef, President Kay Drey, Representative Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, Missouri 63130

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Lee Fritz, Presiding C'ommissioner

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'10 East Fifth Street

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. Fulton, Missouri 65151 i

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Alan C. Passwater, Manager Licensing and Fuels.

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Union Electric' Company-

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P.O. Box 66149

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St. Louis, Missouri 63166-6149 j

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J. V. Laux, Manager

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Regional Administrator Resident inspector DRP Director DRS-PSB Branch Chief (DRP/B)

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i REGIONIV UmoN March 13,1997 88"8/df Schnell Etscrmc l' !"'"*"'

U. S. Nuclear Regulatory Commission Attn: Document ControlDesk Mail Stop PI-137 i

Washington, DC 20555-0001 ULNRC-3536 Gentlemen:

REPLY TO NOTICE OF VIOLATION INSPECTION REPORT NO. 50-483/96010 CALLAWAY PLANT This responds to Mr. Thomas P. Gwynn's letter dated February 14,1997, which transmitted a Notice of Violation for events discussed in Inspection Report 50-483/96010. Our response to the violation is presented in the attachment.

None of the material in the response is considered proprietary by Union Electric.

If you have any questions regarding this response, or if additional information is required, please let me know.

Very truly yours,

/J7h Donald F. Scimell DFS/bjp Attaciunent: 1) Response to Violation 9 T-0 3 02-4 ? 0320e n r

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>m cc: - Mr. James E. Dyer Regional Administrator-Acting U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman,MO 65077 Ms. Kristine M. Thomas (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission

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Mail Stop 13E16

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Washington, DC 20555-2738 Manager, Electric Department Missouri Public Service Commission PO Box 360 Jefferson City, MO 65102 Mr. Thomas A. Baxter Shaw, Pittman, Potts, & Trowbridge 2300 N. Street N.W.

Washington, DC 20037 Manager, Plant Support Wolf Creek Nuclear Operating Corporation PO Box 411 Burlington,KS 66839

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Attachment to ULNRC-3536 March 13,1997 i

Page1 Statement of Violation

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During an NRC inspection conducted on October 21 through December 9,1996, one violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:

Criterion IX of Appendix B to 10 CFR Part 50 states, in part, " Measures shall be established to assure that special processes, including... nondestructive testing, are controlled and accomplished.. using qualified procedures in accordance with applicable codes, standards, specifications, criteria, and other special requirements."

Section 2.3 of Procedure ETP-BB-01309, " Steam Generator Eddy Current Testing Acquisition and Analysis Guidelines," Revision 7, states, "All techniques used shall be qualified in accordance with Appendix H of the EPRI PWR Steam Generator Examination Guidelines, Revision 4."

Westinghouse Report DDM-96-009," Documentation of Appendix H Compliance and Equivalency," identifies the qualified Appendix H analysis span and phase rotation settings for plus point coil examination of tube expansion transition regions to be, respectively, one-half screen height response to a 40 percent notch and rotation set to 20 degrees for a 100 percent through-wall notch.

Contrary to the above, analysis of plus point probe eddy current data during Refueling Outage RF8 was not controlled.to assure use of Appendix H qualified settings for span and phase rotation, as evidenced by:

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Specific direction was not provided by the primary eddy current analysis contractor, Westinghouse, to the analysts on span and phase rotation settings to be used for analysis of plus point coil examination data.

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Procedure ETP-BB-01309, Revision 7, provided span and phase rotation settings for only the rotating pancake coil. These settings differed from those used in the qualification of the plus point coil and were inappropriate for use with that coil.

This is a Severity Level IV violation (Supplement 1) (50-483/9610-01).

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Attachment to ULNRC-3536 March 13,1997 Page 2

.Hackground/ Reason for the Violation i

Prior to Refuel 8 (October 1996), steam generator Rotating Pancake Coil (RPC) eddy current examinations at Callaway were conducted using a standard 3-coil probe. Industry experience indicated the + Point probe was capable of detecting smaller flaws and had the ability to identify previously undetected defects at locations such as the top of tubesheet area. Although we had not experienced problems with the previous technology, Union Electric made the decision to use the more sensitive + Point probe to enhance our steam generator condition monitoring program. Our eddy current contractor was advised of the change, and made preparations to provide the proper probes and personnel.

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Union Electric provides eddy current test and analysis guidelines to its inservice inspection (ISI) contractors in procedure ETP-BB-01309 entitled: " Steam Generator Eddy Current Acquisition and Analysis Guidelines". Because eddy current test (ECT) hardware and analysis techniques are rapidly evolving and technically challenging, we supplement our staff knowledge with that of recognized external authorities in defining ISI requirements associated with our steam generators. Accordingly, prior to Refuel 8, we involved representetives from the Electric Power Research Institute (EPRI) as well as from j

Westinghouse and Framatome (our primary contractor and contractor for secondary independent data review respectively) in the updating of our guidelines to assure incorporation of the latest technology and techniques, including the requirement that analysts and test techniques must be qualified in accordance with Appendix H of EPRI's i

ISI guidelines. Our procedure was also reviewed as part of Union Electric's QA surveillance -(SP96-015) of the steam generator program. Despite this extensive review effort, we failed to incorporate specific details for setup of the newly developed + Point probe in our document. These details, however, were provided indirectly to our conta utors and weie known and implemented by the anelpts through our imposition of Appendix H qualifications on the work.

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Corrective Steps Taken and Results Achieved:

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Failure to incorporate span and phase rotation criteria into our guidance procedure for setup of the + Point ECT probe was not identified until after the outage. At that point, discussions were held with the lead analysts for Westinghouse and Framatome who confirmed that + Point setups had been performed in accordance with Appendix H techniques and industry practice. Therefore, our omission of specific + Point setup instructions in the guidelines did not compromise the reliability and accuracy of the + Point eddy current analysis.

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.ULNRC-3536

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March 13,' 1997 t

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Corrective Stens to Avoid Further Violations:

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. Procedure ETP BB-01309 will be revised to incorporate proper guidance for setup of the

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+ Point coil (and any others prior to use at Callaway). Union Electric will continue to utilize outside expertise for assistance in establishing steam generator ISI program

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requirements. To do otherwise would risk obsolescence of knowledge and loss of

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initiative in this rapidly changing field of technology. Direction will be provided to '

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specifically maintain our procedures and requirements in conformance to Appendix H qualifications and current industry practice, thus ensuring the reliability of the ISI j

program..

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- Date when Full Comoliance will be Achieved:

Full compliance will be achieved prior to the next steam generator inspection during.

Refuel 9, currently scheduled to commence in April,1998.

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