ML16102A339

Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate

ML16102A339
Person / Time
Site:	Browns Ferry
Issue date:	04/14/2016
From:	Farideh Saba Plant Licensing Branch II
To:	James Shea Tennessee Valley Authority
Saba F
References
CAC MF6741, CAC MF6742, CAC MF6743
Download: ML16102A339 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Apr:"il 1 4' 201 6 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37 402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE (CAC NOS. MF6741, MF6742, AND MF6743)

Dear Mr. Shea:

By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant, Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that additional information is needed. On March 28, 2016, the NRC staff forwarded, by electronic mail, a draft Request for Additional Information (RAI) to TVA On April 8, 2016, the NRC staff held a conference call to provide the licensee with an opportunity to clarify any portion of the draft RAI and discuss the timeframe for which TVA may provide the requested information. As agreed by the NRC and TVA staff, TVA will respond to the enclosed RAI by May 23, 2016.

J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.

Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT. UNITS 1. 2. AND 3 DOCKET NOS. 50-259. 50-260. AND 50-296 By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant, Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.

The NRC staff from the Balance of Plant Branch (SBPB), previously in Containment and Ventilation Branch, Division of Safety Systems reviewed the information the licensee provided and determined that the following additional information is required in order to complete the evaluation.

SBPB-RAI 1 The licensee in Section 2.7.3 of Power Uprate Safety Analysis Report (PUSAR) (Attachment 6 1 of letter dated September 21, 2015) states: "The conductance of heat through the building structure to the control room is expected to increase only slightly." What is the source of heat that causes an increase of conductance of heat through the control room building structure under extended power uprate (EPU) conditions?

SBPB-RAI 2 The licensee in Table 2.7-1 of PUSAR states the temperature of the General Floor Area at Elevation (El) 639 will increase to a peak of 128. 7 degrees Fahrenheit for the most limiting reactor building room.

(a) Is the General Floor Area at El 639 the most limiting reactor building room in the current analysis and by how much is the peak EPU temperature in this room greater than the peak temperature in the current analysis?

(b) The temperature increase reflects an increase in the heat load from EPU operation.

Explain why the HVAC system is adequate to handle this increased heat load in the reactor building.

1 Attachment 7 contains a non-proprietary version of Attachment 6 Enclosure

SBPB-RAI 3 Section 2.7.5 of the PUSAR does not describe any evaluation of the impact of the EPU on the turbine building ventilation system.

(a) Describe all turbine building equipment changes that impact its heat load and provide a comparison of the power rating between the present and proposed equipment for EPU.

(b) What is the present and the proposed EPU turbine building ventilation system heat load?

(c) Describe the impact and changes in the turbine building ventilation system for EPU.

ML16102A339 *by memorandum OFFICE DORL/LPLll-2/PM DORL/LPLll-2/LA DSS/SCVB 1/BC* DORL/LPLI 1-2/BC DORL/LPLI 1-2/PM NAME FSaba BClavton RDenniq BBeasley FSaba DATE 4/12/2016 4/11/2016 3/24/2016 4/14/2016 4/14/2016