ML20116J557

Submits Info Re SG F* TS Amend

ML20116J557
Person / Time
Site:	Farley
Issue date:	08/07/1996
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9608130274
Download: ML20116J557 (2)

Text

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. Southern Nucitar Op2 rating Company

. Post Office Box 1295

, Birmingham. Alabama 35201 Telephone (205) 868-5131 L k o.ve uerey Vice President Southern Nudear Operating Company Faney Project the Southem elecinc system August 7, 1996 Docket Nos.: 50-364 10 CFR 50.4 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Joseph M. Farley Nuclear Plant - Unit 2 Steam Generator F* Technical Specification Amendment Ladies and Gentlemen:

By letter dated July 15,1996, Southern Nuclear forwarded a proposed methodology for the determination of NDE measurement uncertainties to be used with the proposed F* technical specification amendment. In subsequent discussions with the NRC Staff, a concern has been expressed that only five essential variables were addressed in the methodology. Appendix H of the EPRI PWR Steam Generator Tube Examination Guidelines provides a list of a number of essential variables that were not included in the proposed methodology.

The essential variables cited in the methodology for the determination of the NDE uncertainty for the measurement of the position, length and inclination of the indication (July 15,1996 Southern Nuclear to NRC letter) assume that the coil to be used is qualified for the detection of degraded regions of the tube. The specific measurement uncertainties addressed by this test program are affected by the five major groupings ofvariables listed. For this reason, some of the typical essential variables were omitted in this description. All qualification testing performed to validate the use of any specific technique is documented via a technique sheet.

This includes, for example, frequencies, sampling rate, and other essential variables.

The techniques and coils used will have been qualified for the detection of degradation. The technique documentation will include information beyond what is typically included in the Appendix H documentation because the uncertainties to be measured are largely due to the control of the motion of the probe (rotation and axial translation). Thus,the delivery system, direction of the test and the probe speed are the primary contributors to this type of uncertainty. The coil type has some effect in terms of field spread. The various measurements and their uncertainties will be fully documented with respect to all cssential variables of the test.

9608130274 960807 DR ADOCK 0500 4 g )/ 'h E __ ___ _ . . - - - - - - - - _

. U. S.-Nuclear Regulatory Commission Page 2 If there are any questions, please advise.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY

()0 ))lru-Dave Morey Sworn to andsubscribed before me this dayaf YY 1996

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cL d2/h hbalsr' Notary Pulflic My Commission Expires: //f97 REM / cit:F_NDEl. doc cc: Mr. S. D. Ebneter, Region II Administrator Mr. B. L Siegel, NRR Senior Project Manager Mr. T. M. Ross, Plant Sr. Resident Inspector Mr. T. A. . Reed, NRR - Materials and Chemical Engineering Branch Dr. D. E. Williamson, State Department of Public Health

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