ML20246J992
| ML20246J992 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/11/1989 |
| From: | Michael Ray TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8905170222 | |
| Download: ML20246J992 (3) | |
Text
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place MAY 111989
)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-259 Tennessee Valley Authortty
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - CIVIL / SEISMIC MEETING TRANSCRIPT DISCREPANCIES During the transcribed civil / seismic meeting of February 17, 1989,- discussions occurred in the following areas which require additional support or clarification:
a) Amplified response spectra (ARS) to be used for new work (transcript minutes page 13, lines 1-17)
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 seismit qualification of all BFN plant features, 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 l
developing a presentation when in September 1986, it was requetted by NRC l
that a submittal ba 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.
l l
On page 76, line 9. TVA stated that Impell Corporation was hired to prepare criteria and resolve this issue.
This chould be clarified to state that TVA developed the CRDH criteria and Impell was centracted to implement a program utilizing this criteria.
p 890517o222 890511 F;DR F
ADOCr< 05000259 ig FDC An Equal opportunity Emp! oyer
r l
. MAY 111989
'U.S. Nuclear Regulatory Commission l
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 i
deleted and "BFN-50-C-7107" should be inserted.
On page 82, line 15, " Appendix A to Criteria 7103," should be deleted and "BFN-50-C-7107" should be inserted.
l On page 88, line 6, the word " Frequencies" should be replaced by the word j.
" Hertz."
L On page 90, lines 1 and 2, the words "U-Bolts" should be replaced by l
"unistrut clamps / guides."
c) Entry of limiting condition for operation (LCO) action statement following support operability determination (pages 105-111)
The record of this discussion should be clarified to 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 cporability can be determined in accordance with the guidelines of Site Director Standard Practice 9.19, and plant operation maintained.
This determination is independer.t of the decision to replace or restore an affected support. When a required system is determined to be inoperable, the LCO 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 LCO timeframe may show that the system is operable with the existing condition, and the LCO does not apply.
If any questions exist relative to the above, please get in touch with Patrick P. Carter, at (205) 729-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY M
NuclearLice[nsing sq Manager and Regulatory Affairs cc: See page 3 l
r "1
'U.S. Nuclear Regulatory Commtssion MAY 111989:
cc: Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Assistant Director for Inspection Pr s
TVA Projects Divisit.s U.S. Nuclear Regulate Commission Region II 101 Marietta Street, NW, 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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