ML18036A301

Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising Tech Specs Section 3.6/4.6, Pressure/Temp Limits, to Mod Wording Consistent W/Guidance in Generic Ltr 88-11

ML18036A301
Person / Time
Site:	Browns Ferry
Issue date:	07/19/1991
From:	Burzynski M TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18036A302	List: ML18036A301 ML18036A303
References
GL-88-11, TVA-BFN-TS-293, NUDOCS 9107230218
Download: ML18036A301 (9)

Text

ACCgLRiRATED DISTRIBUTION DEMOIRATION SYSTEM

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9107230218 DOC.DATE: 91/07/19 NOTARIZED: YES DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION BURZYNSKI,M.J. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amends to Licenses DPR-33,DPR-52 6 DPR-68, revising Tech Specs Section 3.6/4.6, "Pressure/Temp Limits," D to mod wording consistent w/guidance in Generic Ltr 88-11.

DISTRIBUTION CODE: AOOSD COPIES RECEIVED:LTR Q ENCL + SIZE:

TITLE: OR/Licensing Submittal: Reactor Vessel MaterialMurveillance Report NOTES RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL KREBS,M. 1 0 HEBDON,F 1 1 ROSS,T. 2 2 WILLIAMS,J. 2 2 D INTERNAL ACRS 6 6 NRR/DEST/MTB 9H 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/ESGB 8D 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SRXB 8E 1 1 NRR/PMAS/ILRB12 1 1 OC/WEBB 1 0 OGC/HDS3 1 0 OI 1 1 RES/DSIR/EIB 1 1 RESJMEB 1 1 EXTERNAL: EGGG NAGATA,P. 1 1 NRC PDR 1 1 NSIC 1 1 ORNL KAM,F 1 1 D

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25

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Tennessee Valley Authority, 1101 Market Street, Chattanooga. Tennessee 37402 JUL i9 1991 TVA-BFN-TS-293 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 59-296 BROMMS FERRY NUCLEAR PLANT (BFN) TVA BFN TECHNICAL SPECIFICATION (TS)

NO. 293

References:

1. Generic Letter 88-11, dated July 12, 1988, "NRC Position on Radiation Embrittlement of Reactor Vessel Material and Its Impact on Plant Operations"

2. TVA Response to Generic Letter 88-11, dated November 30, 1988 In accordance with the provisions of 10 CFR 50.4 and 50.90, we are submitting a request for an amendment to licenses DPR-33, DPR-52, and DPR-68 to change the BFN Technical Specifications for Units 1, 2, and 3 (Enclosure 1). This proposed amendment, will revise TS Section 3.6/4.6, Pressure/Temperature Limits, to modify the current TS wording and pressure/temperature limit curves to make them consistent with the guidance contained in Generic Letter (GL) 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations," dated July 12, 1988. This GL requires that the nil-ductility reference temperature of the reactor material be calculated based on Regulatory Guide 1.99, Revision 2.

9iQ?2302i8 9i0719 )0 IPDR'<@DOCK 05000259 P PDR

2 U.S. Nuclear Regulatory Commission JUL l9 Set Description, reason for change, and justificati.on in support of the proposed changes are enclosed (Enclosure 2). A proposed determination of no signi.ficant hazards consideration is provided in Enclosure 3.

For BFN Unit 1, the current TS is not bounding with respect, to pressure/temperature limits determined using the RG 1.99, Revision 2 methodology. Unit 1 is in an extended outage wi.th a restart date to be determined. BFN Units 2 and 3 current TSs are bounding with respect to pressure/temperature limi.ts determined using the Revisi.on 2 methodology.

Units 2 and 3 will be bounded by the present TS until approximately 10 effective full power years, whi.ch is expected to carry the units through two additional cycles. Units 2 and 3 have more operating margin than Unit 1 because the most limiting weld in those reactor vessels has less copper and nickel content and a lower initial nil-ductility transition temperature.

This submittal fulfills TVA's commitment to Generic Letter 88-11.

If you have any questions, please telephone Patrick P. Carier at (205) 729-3566.

Very truly yours, TENNESSEE VALLEY AUTHORITY M. J. urzyns i, Project Manager, Nuclear Licensing and Regulatory Affairs Subscribed and sworn to before me

.on this~ttt'Sey of~%1991.

Notary Public L

'E,My cothsniss3.on Expires II Enclosures cc: See page 3

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U.S. Nuclear Regulatory Commission JUL i9 531 cc (Enclosures):

American Nuclear Insurers Attention: Librarian The Exchange, Suite 245 270 Farmington Avenue Farmington, Connecticut 06032 Ms. S. C. Black, Deputy Director; Project Directorate II-4 U.S. Nuclear Regulatory Commission One ophite Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Gary Daly, Chairman Limestone County Commission 310 Mashington Street Athens, Alabama 35611 Dr. C. E. Fox State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36194 Mr. J. E. Jones General Electric Company 735 Broad Street Suite 1108 James Building Chattanooga, Tennessee 37402 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One Mhite Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Milson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

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ENCLOSURE 1 Py