ML18032A228

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Responds to Suggesting That Util Develop Integrated Surveillance Program for All Three Units More Related to Fluence than to Predetermined Exposure.Util Will Reconsider Need for Program Based on Surveillance Results
ML18032A228
Person / Time
Site: Browns Ferry  
Issue date: 05/15/1987
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8705270297
Download: ML18032A228 (6)


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Tennessee Valley Authority RECIP. NANE RECIPIENT AFFILIATION Document Control Branch (Document Control Desk

SUBJECT:

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~u TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 157 Lookout Place U.S. Nuclear Regulatory Commission ATTN:

Document, Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of Tennessee Valley Authority Docket Nos.

50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM UNITS 1, 2, AND 3 The Browns Ferry Nuclear Plant Technical Specifications for all three units presently specify that the reactor vessel beltline material surveillance capsules be withdrawn from each reactor at one-fourth service life and three-fourths service life.

In a letter from J. A. Domer to D. B. Vassallo dated July 23,

1985, TVA provided an interpretation of one-fourth service life as being equivalent to 8.0 effective full-power years (EFPY) and, similarly, three-fourths service life as being equivalent to 24.0 EFPY.

In a letter from R. J. Clark (NRC) to S. A. White (TVA) dated October 27,

1986, NRC suggested that TVA develop an integrated surveillance program for all three BFN units that is more related to estimated fluence than to a predetermined exposure interval (e.g.,

24 EFPY).

At this time, TVA believes that development of an integrated surveillance program related to fluence rather than to a set time would be premature.

If developed now, such a program would be based on extrapolations of the limited dosimetry measurements which were taken for unit 1 during the first fuel cycle.

Since dosimetry measurements for 8 EFPY would be more credible than cycle 1 dosimetry data, TVA prefers to consider the development of a revised program based on the testing and analysis results from an 8 EFPY capsule.

Therefore, we propose to withdraw the first set of surveillance specimens from each reactor vessel at the end of each unit's cycle which most closely approximates 8.0 EFPY of operation.

This is a valid method for meeting the current BFN technical specification requirement of one-fourth service life.

Based on the results of the first set of surveillance specimens, TVA will reconsider the need to develop an integrated surveillance program and the proposal to base the surveillance program on estimated neutron fluence.

10 CFR 50, Appendix H, Section III requires a report of the test results from 7052 02 o oo025 0297 870515 PDR ADQC PDR p

An Equal Opportunity Employer

U.S. Nuclear Regulatory Commission MN 15 1937 the first set of BFN surveillance specimens.

TVA will address in that report any proposed changes to the surveillance program as a result of evaluating those test results.

Very truly yours, TENNESSEE VALLEY AUTHORITY R. Gridley, irector Nuclear Safety and Licensing, cc:

Mr. G.

G. Zech, Assistant Director Regional Inspections Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. J. A. Zwolinski, Assistant Director for Projects Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission 4350 East. West Highway EWW 322

Bethesda, Maryland 20814 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 2, P.O.

Box 311

Athens, Alabama 35611