ML18039A370

Requests Addl Info Re TS Change TS-384 to Permit Operation of Units at Uprated Power Level of 3458 Mwt

ML18039A370
Person / Time
Site:	Browns Ferry
Issue date:	06/03/1998
From:	Raghavan L NRC (Affiliation Not Assigned)
To:	Zeringue O TENNESSEE VALLEY AUTHORITY
References
TAC-M99711, TAC-M99712, NUDOCS 9806080127
Download: ML18039A370 (8)

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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 3une 3, 1998 Mr. O. J. Zeringue Chief Nuclear Officer And Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 2 AND 3: REQUEST FOR ADDITIONALINFORMATIONRELATINGTO TECHNICALSPECIFICATION CHANGE NO. TS-384 - POWER UPRATE OPERATION (TAC NOS. M99711 AND M99712)

Dear Mr. Zeringue:

By letter dated October 1, 1997, the Tennessee Valley Authority (TVA)proposed revisions to the Browns Ferry Nuclear Plant (BFN) Units 2 and 3 Technical Specifications to permit operation "ofthe units at the uprated power level of 3458 Mwt. The staff has determined that the following additional information is required to complete the review of the proposed action.

These questions are related to the General Electric document Power Uprate Safety Analysis for the Browns Ferry Nuclear Plant Units 2 and 3, No. NEDC-32751 P dated September 1997.

In Section 4.1.1.1, Containment long term pool temperature response, it is indicated that a pre-uprate SHEX code benchmark evaluation was performed using a heat exchanger K-factor of 223 BTU/sec-.'F, 92'F Residual heat removal (RHR) service water (SW) temperature, 6500 gpm RHR fiow rate, and 4000 gpm RHR SW flow rate. The analysis resulted in a peak suppression pool temperature of 1750'F.

These values are not

'onsistent with the existing BFN analysis which used a heat exchanger K-factor of 228 BTU/sec-'F, 95'F RHR service water temperature, 6500 gpm RHR flow rate, and 4500 gpm RHR SW flow rate and reported a peak pool temperature of 1770'F. The existing analysis was performed using the May-Wittdecay heat curve while the uprate was performed using the ANS/ANSI 5.1 (2a uncertainty).

The comparative analysis should use the same input assumptions.

Please justify this inconsistency'discrepancy.

Also, please provide the containment temperature and pressure profiles.

2.

Section 4.1.1.2, Containment Gas Temperature Response indicates that at uprated power, the calculated peak drywell airspace temperature exceeds the drywell shell design temperature, but only at the beginning of the accident and for a short period of time. This is not considered a threat to the drywell shell structure due to relative long drywell shell heat-up time. Please provide the containment temperature profiles after a loss-of-ccolant-accident.

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0. J. Zeringue June 3, 1998 3.

Section 4.1.2.3, Subcompartment Pressurization, indicates that the sacrificial shield wall design remains adequate because the peak pressure in the annulus region increases slightly due to the power uprate.

Please provide details of the results to justify your conclusion.

4 Section 4.1.4, Combustible Gas Control In Containment, predicts an earlier startup of the containment atmospheric dilution system at uprated power due to the increase in hydrogen and oxygen generation rates and that the predicted startup time willnot result in system operation outside established design or operational restraints.

Please provide the time responses.

Please provide the required information no later than June 25, 1998.

Sincerely, L. Raghavan, Senior Project Manager Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-260 and 50-296 cc: See next page

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2 O. J. Ze'ringue 3une 3, 1998 3.

Section 4.1.2.3, Subcompartment Pressurization, indicates that the sacrificial shield wall design remains adequate because the peak pressure in the annulus region increases

" slightly due to the power uprate.

Please provide details of the results to justify your conclusion.

Section 4.1.4, Combustible Gas Control In Containment, predicts an earlier startup of the containment atmospheric dilution system at uprated power due to the increase in hydrogen and oxygen generation rates and that the predicted startup time willnot result in system operation outside established design or operational restraints.

Please provide the time responses.

Please provide the required information no later than June 25, 1998.

Sincerely,

/s/

L. Raghavan, Senior Project Manager Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-260 and 50-296" cc: See next page

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Mr. O. J. Zeringue Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT CC:

Mr. J. A. Scalice, Senior Vice President Nuclear Operations Tennessee Valley Autho'rity 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Jack A. Bailey, Vice President Engineering 8 Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. C. M. Crane, Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 General Counsel Tennessee Valley Authority ET 10H 400 West Summit Hill Drive Knoxville, TN 37902 Mr. Raul R. Baron, General Manager Nuclear Assurance Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Karl W. Singer, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Mark J. Burzynski, Managar Nuclear Licensing Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Timothy E. Abney, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority

~ P.O. Box 2000 Decatur, AL 37402-2801 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Mr. Leonard D. Wert Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant I0833 Shaw Road Athens, AL35611 State Health Officer Alabama Dept. of Public Health 434 Monroe Street Montgomery, AL35130-170I Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611

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