ML18039A269

Suppl 1 to TS Change 384 to Licenses DPR-52 & DPR-68, Allowing Units 2 & 3 to Operate at Uprated Power of 3458 Mwt Representing Power Level Increase of Five Percent

ML18039A269
Person / Time
Site:	Browns Ferry
Issue date:	03/16/1998
From:	Abney T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18039A270	List: ML18039A269 ML18039A271
References
TVA-BFN-TS-384, NUDOCS 9803250169
Download: ML18039A269 (12)

Text

CATEGORY j.

REGULA Y INFORMATION DISTRIBUTI .SYSTEM (RIDS)

ACCESSION NBR:9803250169 DOC.DATE: 98/03/16 NOTARIZED: YES DOCKET ¹ FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME 'UTHOR AFFILIATION ABNEY,T.E. 'ennessee Valley Authority RECIP . NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Suppl 1 to TS Change 384 to Licenses DPR-52 &. DPR-68, allowing Units 2 & 3 to operate at uprated power of 3458 MWt representing power level increase of five percent.

DISTRIBUTION CODE: D030D COPIES RECEIVED:LTR I ENCL ) SIZE:

TITLE: TVA Facilities - Routine Correspondence E

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 PD2-3 1 1 PD2-3-PD 1 1 DEAGAZIO,A 1 1 INTERNAL: ACRS 1 1 LE CENTER 0 1 1 OGC/HDS3 1 0 RES DE/SSEB/SES 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

U NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 8

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Tennessee Valley Authority, Post Office Box 2000, Decatur, Aiabarna 35609-2000 March 16, 1998 TVA-BFN-TS-384 Supplement 1 10 CFR 50.90 U. S,. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20S55 Gentlemen:

In the Matter of )Docket Nos. 50-260 Tennessee Valley Authority ) 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 2 AND 3 TECHNICAL SPECIFICATION (TS) NO. 384 SUPPLEMENT 1 REQUEST FOR LICENSE AMENDMENT FOR POWER UPRATE OPERATION In accordance with the provisions of 10 CFR 50.4 and 50.90, TVA is submitting a request for an amendment TS-384 to licenses DPR-52 and DPR-68 to change the Technical Specifications for Units 2 and 3. The proposed change modifies the Unit 2 Primary Containment Isolation Instrumentation function for the Reactor Water Cleanup System and raises the primary containment peak temperature value following high energy line breaks (HELB) inside primary containment in support of the BFN request for power uprate.

In a letter issued October 1, 1997, TVA provided a proposed TS change that will allow Units 2 and 3 to operate at an uprated power of 3458 MWt representing a power level increase of five percent. In that letter, TVA noted that the Environmental Qualification (EQ) of electrical equipment portion of a S percent power uprate analysis had not been completed. This letter provides supplemental. information in support of the TS-384 amendment request and 'completes the information necessary to support the overall uprate request.

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U. S. Regulatory Commission

~ Page 2 March 16, 1998 The EQ software program establishing environmental conditions currently in the BFN Licensing Basis approved by the staff is based on the MONSTER computer model to establish overall post accident reactor building thermal profiles. The MONSTER software program, based on the CONTEMPT4 MOD2 code with enhancements added by TVA, was utilized by TVA during the recovery of the nuclear power units. The MONSTER software is no longer available due to a change in computer systems.

Therefore, an updated code, Generation of Thermal-Hydraulic Information for Containments (GOTHIC) was used as the basis to evaluate changes in EQ thermal profiles in the reactor building due to uprate power conditions. The utilization of the GOTHIC code will result in a modified reactor building temperature response due to HELB. TVA has previously used the MONSTER computer code to perform containment analyses and high energy line break analyses. TVA has been a long time participant in the industry development of GOTHIC. Due to the additional capabilities of GOTHIC, TVA will to replace MONSTER with GOTHIC as the software basis for EQ thermal profile generation.

The BFN Reactor Building MONSTER model has been converted to a GOTHIC model. GOTHIC was not used to generate mass and energy releases. It was only used to model the building pressure and temperature response. Mass and energy releases for power uprate were calculated using the RELAP5 computer program models. The mass and energy released increased due to the higher reactor pressure required for uprated power conditions.

In determining the HELB pipe break size and locations for the EQ analysis, TVA has invoked the provisions of NRC Branch Technical Position, MEB 3-1, Revision 2, Postulated Rupture Locations in Fluid System Piping Outside Containment, part of Standard Review Plan 3.6.2, Determination of Rupture and Dynamic Effects Associated With the Postulated Rupture of Piping.

In accordance with 10 CFR 50.49, Environmental Qualification evaluations based on the power uprate HELB analyses results for BFNP Units 2 and 3 will be performed for safety related electrical equipment located in harsh environment areas prior to BFN going to uprate conditions' 1

This commitment was identified as part of the October 1, 1997 letter. As such, no new commitment has been established.

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U. S. Regulatory Commission

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Page 3 March 16, 1998 The primary containment peak temperature response to high energy steam line breaks was also analyzed at uprated conditions using the General Electric computer code SHEX.

The increased reactor pressure required for operation at uprated conditions results in higher mass and energy releases following postulated line breaks inside primary containment.

The maximum post-accident drywell temperature has increased from 322' to 336' based on the results of the containment response analyses. This increase will also be evaluated prior to implementing uprated conditions.

TVA has determined that there are no significant hazards considerations associated with the proposed change and that the change is exempt from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9). The BFN Plant Operations Review Committee and the BFN Nuclear Safety Review Board have reviewed this proposed change and determined of BFN Units 2 and 3 in accordance with the that'peration proposed change will not endanger the health and safety of the public. Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and enclosures to the Alabama State Department of Public Health.

Enclosure 1 to this letter provides the description and evaluation of the proposed change. This includes TVA's determination that the proposed change does not involve a significant hazards consideration, and is exempt from environmental review. Enclosure 2 contains copies of the appropriate TS pages from Unit 2 and 3 marked-up to show the proposed change. Enclosure 3 forwards the revised TS pages for Units 2 and 3 which incorporate the proposed change. The TS markup and revised pages are based on the proposed BFN improved Standard Technical Specifications submitted to NRC September 6, 1996.

TVA requests that the proposed amendment become effective before the startup for Cycle 9 operation in November 1998 for Unit 3 and before the startup for Cycle 11 in April of 1999 for Unit 2. Enclosure 4 provides the commitment made in this submi t tal .

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U. S. Regulatory Commission

~ Page' March 16, 1998 If you have any questions about this change, please telephone me at (205) 729-2636.

S cere To ~ e Manager of 'cens'ng and Indu try Aff irs Subscribed d sw rn to before me o this 16th da o f March 1998.

Notary Public My Commission Expires 10/08/98 Enclosures cc: See page 5

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U. S. Regulatory Commission

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Page' March 16, 1998 cc (Enclosures):

Chairman Limestone County Commission 310 West Washington Street Athens, Alabama 35611 Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S. W.

Suite 23T85 Atlanta, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. Albert W. De Agazio, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701

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