ML18029A477
| ML18029A477 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 04/08/1985 |
| From: | Hufham J TENNESSEE VALLEY AUTHORITY |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM GL-84-23, TAC-45116, TAC-45117, TAC-45118, NUDOCS 8504160442 | |
| Download: ML18029A477 (6) | |
Text
REGULATORY It"'MATION DISTRIBUTION SYST (RIDS)
ACCESSION NBR:8504160002 DOC.DATE: 85/04/O8
. NOTARIZED: YES FACIL:50-259 Browns Ferry Nuclear Power Stationi Unit ii Tennessee 50-260 Browns Ferr y Nuclear Power Stationi Unit 2i Tennessee 50-296 Browns Ferry Nuclear Power Stationi Unit 3i Tennessee AUTH BYNAME AUTHOR AFFILIATION HUFHAMgJ ~ HE Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION VASSALLOiD ~ BE Operating Reactors Branch 2
SUBJECT:
Forwards response to Generic Ltr 84-23 re reactor vessel water level instrumentation in BHRs<per 850?1P requests DISTRIBUTION CODE:
A002D COPIES RECEIVED!LTR ENCL SIZE ~
TITLE:
OR Submittal: Inadequate Core Cooling (Item II,F,2)
GL 82'-28 NOTFS:NMSS/FCAF
- 1cy, 1cy NMSS/FCAF/PM,'L:06/26/73 NMSS/FCAF 1cy, icy NMSS/FCAF/PM'L:06'/28/74 NMSS/FCAF icy, icy NMSS/FCAF/PM'L:07/02/76 DOCKET 05000259 osooo26o 05000296 05000P59 05000260 05000296 RECIPIENT ID CODE/NAME NRR ORB2 BC CLARKgR INTERNAL: ACRS 17 NRA SHEAi J 01 NRR/DHFS/PSRB16 NRR/DL/ORB5 NRR/DSI/CPB 10 NRA/DSI/RSB 13-RGNP.'7 COPIES LTTR ENCL 1
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RECIPIENT ID CODE/NAME NRR ORB2 LA ADM/LFMB NRR/DHFS/HFEB15 NRR/DL/DRAB 08 NRR/DSI DIR 09, N
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EXTERNAL; LPDR NSIC NOTES; 03 06 NRC PDR 02 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 3P.
ENCL 31
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TENNESSEE VALLEYAUTHORlTY, CHATTANOOGA, TENNESSEE 37401 400 Chestnut Street Tower II April 8, 1985 Director of Nuclear Reactor Regulation Attention:
Mr. Domenic B. Vassallo, Chief Operating Reactor Branch No.
2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Vassallo:
In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 By your letter to H. G. Parris dated February 12,
- 1985, we received Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs, dated October 26, 1984 for act;ion.
Enclosed is our response to the generic letter for the Browns Ferry Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY
- Subscribed and sworn to before me this ~~
day of
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Notary Publi My Commission Expires
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anager gulations Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II ATTN:
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, Maryland 20814 8500lg0~~2 8>
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ADOCK 05000259 PAR An Equal Opportunity Employer
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ENCLOSURE
RESPONSE
TO GENERIC LETTER 84-23 DATED OCTOBER 26, 1984 REACTOR VESSEL WATER LEVEL INSTRUMENTATION IN BWR'S BROWNS FERRY NUCLEAR PLANT TVA has reviewed the improvements given in Generic Letter 84-23.
We are familiar with the basic concerns because of our close involvement with the BWR Owners'roup in issuing the S. Levy, Inc. repor t SLI-821 1 and are currently in the process of reviewing available options.
Two of the improvements are addressed below as requested by the Generic Letter.
Hi h Dr well Tem erature TVA is considering several feasible options to resolve this problem.
Each of the options that we consider feasible so far involve major modifications which have not yet been attempted as a backfit to an operating BWR.
For that reason, our evaluation process is ongoing.
We will submit an updated response by July 15, 1985.
Anglo Tri Instruments The modification process to convert Browns Ferry to analog trip instrumentation is currently in progress.
Level instruments which initiate Reactor Protection and Emergency Core Cooling systems and provide class 1E level indication in the control room will be converted to analog trip units.
The schedule for completion appears in the Browns Ferry Integrated Schedule currently as unit 1 cycle 6, unit 2 cycle 5, and unit 3 cycle 6 refueling outages.
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