ML20247H912
| ML20247H912 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/25/1989 |
| From: | Michael Ray TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8905310365 | |
| Download: ML20247H912 (4) | |
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 SN 1578 Lookout Place L
MAY 251989 l~
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,-D.C. 20555 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) - CIVIL / SEISMIC MEETING TRANSCRIPT DISCREPANCIES This letter supercedes the previous letter sent to you on liay 11, 1989.
During the transcribed civil / seismic meeting of February 17, 1989, discussions occurred in'the following areas which require a'dditional support or clarification:
a) Amplified response spectra (ARS) to be used for new work (transcript minutes page 13, lines 1-17)
In the transcript meeting, TVA informed NRC of its intention to use ARS developed from the 1940 El Centro, North-South component, earthquake input ground motion for design of the seismic class I civil structures, HVAC items, cable tray, conduit, platforms, etc.
Subsequently', during an NRC audit (February 20-24, 1989) of the seismic design basis, the ARS and analysis methods to be used at Browns Ferry were discussed in more detail.
The matrix shown in the attached table reflects a composite of the agreements reached during this civil / seismic meeting and the audit.
The matrix has been reviewed and accepted by the NRC staff.as the basis for seismic qualification of all BFN plant features. TVA agrees that new BFN work will be performed in accordance with this attached table.
b) Control rod drive hydraulic (CRDH) piping The record should be clarified to note that five percent damping was initially discussed with the staff in May 1986.
Subsequently, NRC requested justification for the five percent damping, modifications required, and a schedule for modifications.
TVA was in the process of developing a presentation when in Sep+ ember 1986, it was requested by NRC that a submittal be documented in lieu of a presentation.
TVA documented a submittal to the NRC staff in April 1987.
In the interim however, NRC verbally informed TVA that the use of five percent damping was unacceptable.
On page 76, line 9, TVA stated that Impell Corporation was hired to prepare criteria and resolve this issue.
This should be clarified to state that TVA developed the CRDH criterla and Impell was contracted to O
implement a program utilizing this triteria.
8905310365 890525 PDR ADOCK 05000259, l
P PNU
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An Equal opportunity Employer
MAY 251989
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l U.S. Nuclear. Regulatory Commission I
i On page 80, line 14. "BFN-50-C-7103 and 7107," should be deleted and "BFN-50-C-7107" should be inserted.
On page 80, lines 24 and 25, " Appendix A to Criteria 7103," should be deleted and "BFN-50-C-7107" should be. inserted.
On page 82, line 15, " Appendix A to Criteria 7103," should be daleted and "BFN-50-C-7107" should be inserted.
On page 88, line 6, the word " Frequencies" should be replaced by the word
" Hertz."
On page 90, lines 1 and 2, the words "U-Bolts" should be replaced by "unistrut clamps / guides."
c) Entry of limiting condition for operation (LCO) action statement following support operabi'ity determination (pages 105-111)
The record of this discussion should be clarified tc state that operation of Browns Ferry unit 2 will be in compliance with applicable technical specifications (TS) and instructions.
Accordingly, for nonsnubber type supports, system operability can be determined in accordance with the guidelines of Site Director Standard Practice 9.19, and plant operation maintained.
This determination is independent of the decision to replace
.or restore an affected support. When a required system is determined to be inoperable, the LC0 is entered, retroactive to the time the problem was identified.
If rework cannot be completed in the required LC0 timeframe, the prescribed TS action statements shall be applicable.
Further engineering evaluations performed during the LC0 timefre.me may show that the system is operable with the existing condition, and the LCO does not h ply.
If any questions exist relative to the above, please get in touch with Patrick P. Carier, at (205) 729-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY s
Managdr, Nu e Licensing and Regulatory Affairs Enclosure cc: See page 3
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U.S. Nuclear Regulatory Commission MAY:251989
'a cc;(Enclosure):
Ms. S. C. Black, Assistant Director for. Projects'_
TVA Projects Division U.S. Nuclear. Regulatory Commission One. White Flint,-North-11555 Rockville Pike j;,
Rockville, Maryland 20852 Mr. B.-A. Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NN, Suite 2900 Atlanta,. Georgia' 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama-35609-2000
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