ML20154L646
| ML20154L646 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/26/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8806010016 | |
| Download: ML20154L646 (4) | |
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 1578 Lookout Place y g 2 6 19 %
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 s
Gentlemen:
In the Matter of
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Docket Nos. 50-259 Tennessee Valley Authority
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50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - EVALUATION OF STRUCTURES FOR REINFORCING BAR CUTS Our letter to J. M. Taylcr dated November 10, 1986, provided TVA's assessment of how certain design deficiencies identified at Sequoyah Nuclear Plant (Inspection Reports _50-327/86-27, 50-328/86-27) applied to BFN.
Item D.4.3-1, Evaluation of Structures for Reinfo_rcing Bar Cuts, was determined to be applicable to BFN.
TVA committed to performing an evaluation to identify areas where unevaluated rebar cuts exist and determine if a loss of function or reduction in capability of the concrete results from the cut rebar.
This evaluation was to be a part of a review of all engineering change notices (ECNs) implemented since issuance of the BFN operating license.
TVA has determined that a different approach will better adh ess potential situations involving unevaluated cuts in reinforcing bars.
The ECN review will not be performed as rebar cuts are not tracked by the ECN process.
The worst case situations involving possible unevaluated rebar cuts will be determined by examining those areas in the Reactor Building with the highest design floor slab live loading and attached loads in conjunction with the greatest potential for unevaluated cuts in reinforcing bars. A walkdown of i
these worst case areas will be performed to predict any unevaluated rebar cuts.
The walkdown will utilize nondestructive examination techniques such
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as, but not limited to, rebar meters and visual observations to determine if 1
unevaluated rebar cuts exist.
If any such rebar cuts are predicted to exist, calculations will be performed to demonstrate continued structural adequacy.
These calculations will also include an evaluation of any significant attached loads not in the original BFN design.
This evaluation will be completed prior to unit 2 restart.
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8806010016 880526 PDR ADOCK 05000259 P
PDR I
An Equal opportunity Employer
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,..,. e U.S. Nuclear Regulatory Commission lAjp(261988 If you have any questions concerning.this matter, please telephone Patrick Carter, BFN Site Licensing, at (205) 729-2689.
Very truly yours, TENNES E LEY AUTHORITY R.
- idley, Irector Nuclear Licensing and Regulatory Affairs Enclosure cc (Enclosure):
Mr. K. P. Barr, Acting Assistant Director
.for Inspection Programs TVA Projects Olvision U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. G. G. Zech, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12, P.O. Box 637 Athens, Alabama 35611 l
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Commitments Made In This Letter 1.
The worst case situations involving possible unevaluated rebar cuts will be determined by examining.those areas in the Reactor Building with the highest design floor slab live loading and attached loads in conjunction with the greatest potential for unevaluated cuts in reinfor_cing bars.
A walkdown of these worst case areas will be performed to predict any unevaluated rebar cuts.
The walkdown will utilize nondestructive-examination techniques such as, but not limited to, rebar meters and visual observations to determine if unevaluated rebar cuts exist.
If any such rebar cuts are predicted to exist,. calculations will be performed to demonstrate continued structural adequacy.
These calculations will also include an evaluation of anu significant attached loads not in the original BFN design.
This evaluacion will be completed prior to unit 2 restart, l
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. ;.- 0 Commitments Made In This Letter 1.
The worst case situations involving possible unevaluated rebar cuts will be determined by examining those areas'in the Reactor Building with the highest design floor slab live loading and attached loads in conjunction with the greatest potential for unevaluated cuts in. reinforcing bars.
A walkdown of these worst case areas will be performed to predict any unevaluated rebar cuts.
The walkdown will utilize nondestructive examination techniques such as, but not limited to, rebar meters and visual observations to determine if unevaluated rebar cuts exist.
If any such rebar cuts are predicted to exist, calculations will be performed to demonstrate continued structural adequacy.
These calculations will also include an evaluation of any'significant attached loads not in the original BFN design.
This evaluation will be completed prior to unit 2 restart,
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