ML073030318

Browns Ferry Units 2 & 3 - Technical Specifications (TS) Change TS-418 - Extended Power Uprate (EPU) - Response to Round 14 Request for Additional Information (RAI) - SBWB-85 (TAC Nos. MC5263 and MC5264)

ML073030318
Person / Time
Site:	Browns Ferry
Issue date:	10/24/2007
From:	O'Grady B Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC5263, TAC MC5264
Download: ML073030318 (9)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 Brian O'Grady Vice President, Browns Ferry Nuclear Plant October 24, 2007 TVA-BFN-TS-418 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop OWFN, Pl-35 Washington, D. C. 20555-00.01 Gentlemen:

In the Matter of ) Docket Nos. 50-260 Tennessee Valley Authority ) 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) -UNITS 2 AND 3 -TECHNICAL SPECIFICATIONS (TS) CHANGE TS-418 -EXTENDED POWER UPRATE (EPU) -RESPONSE TO ROUND 14 REQUEST FOR ADDITIONAL INFORMATION (RAI) -SBWB-85 (TAC NOS. MC5263 AND MC52 64)By letter dated June 25, 2004 (ADAMS Accession No.ML041840301),, TVA submitted a license amendment application for EPU operation of BFN Units 2 and 3. BFN Units 2 and 3 are currently licensed for operation at 3458 Megawatts thermal (MWt) and the pending EPU amendments would change the BFN operating licenses for Units 2 and 3 to increase the maximum authorized power level by approximately 14 percent to 3952 MWt.On October 9, 2007 (ML072760660) the NRC staff issued a Round 14 RAI on TS-41.8, which included a single question, SBWB-85. Enclosure 1 to this letter provides TVA's response to SBWB-85. Enclosure 2 contains a compact disk with data from the Enclosure 1 figures, which was requested by NRC.Printed on recycled paper U. S. Nuclear Regulatory Commission Page 2 October 24, 2007 TVA has determined that the additional information provided by this letter does not affect the no significant hazards considerations associated with the proposed TS changes. The proposed TS changes still qualify for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c) (9).If you have any questions regarding this letter, please contact James Emens at (256)729-7658.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 24th day of October, 2007.Sincerely, Brian 0' Grady

Enclosures:

1. Response to Round 14 Request for Additional Information

-SBWB-85 2. Data CD Contents U. S. Nuclear Regulatory Commission Page 3 October 24, 2007 Enclosures cc (Enclosures):

State'Health Officer Alabama State Department of Public Health RSA Tower -Administration Suite 1552 P.O. Box 303017 Montgomery, Alabama 36130-3017 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 Eva Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)UNITS 2 and 3 TECHNICAL SPECIFICATIONS (TS) CHANGE TS-418 EXTENDED POWER UPRATE (EPU)RESPONSE TO ROUND 14 REQUEST FOR ADDITIONAL INFORMATION SBWB-85 NRC RAI SBWB-85 (Units 2 and 3)With regards to the AREVA fuel, provide the hot bundle and core average two-phase (or mixture) levels versus time for the 0.05 ft 2 break. Also for this break, please provide the liquid mass or liquid levels versus time in the average core and hot bundle.TVA Response to RAI SBWB-85 (Units 2 and 3)The requested level data is not available since the core volumes are modeled as homogeneous nodes. However, in response to the NRC request, the liquid mass in each of the core average and hot bundle nodes for both mid- and top-peaked 0.05 ft 2/PD breaks is provided in Figures A.1 through A.4.These figures illustrate the liquid water distribution in the average core and hot channel calculations, similar to the information that a mixture level would provide if it were calculated.

The requested total liquid mass versus time data is also provided in the files on the compact disk provided in Enclosure 2.El-I O 0O 0 ci c>do c>J 0~0>05 o o 0 0 d 6 d 6 o o 0 0 0 0 0 0 (wql) sselA p!nbil Figure A.1 Liquid Mass in the Core Average Nodes 0.05 FT2/PD SF-BATT MID 102P/105F EPU N\ CQ *I I E E I I 0 0 0 0 6 0 E ,0 Co o0 N 0" (wql) sseij p!nbf!1 Figure A.2 Liquid Mass in the Hot Bundle Nodes 0.05 FT2/PD SF-BATT KID 102P/105F EPU 0 6" 0 Co 0 00 c;C)0 clJ 0 0 6 o*4_C0 od 0 0 0 0 0 0 0 0 0 0 0 0 (wql) sseVlj p!nbi-!Figure A.3 Liquid Mass in the Core Average Nodes 0.05 FT2/PD SF-BATT TOP 102P/105F EPU 0 0 0 CD 0 00 I I6 I Iý I I I I I I I I I Ip0 Fige o 0.05E- TOP 08. 0-(w~ql) ssevN p!nbFI Figure A.4 Liquid Mass in the Hot Bundle Nodes 0.05 FT2/PD SF-BATT TOP 102P/1057 EPU ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)UNITS 2 and 3 TECHNICAL SPECIFICATIONS (TS) CHANGE TS-418 EXTENDED POWER UPRATE (EPU)DATA CD CONTENTS The data in each file is tabulated in an x-y data format. A brief description of the contents of each file is provided below.Contents of data CD mid average core Total average core mass versus time for mid-peaked 0.05 ft 2 break case mid hot bundle Total hot bundle mass versus time for mid-peaked 0.05 ft 2 break case topaveragecore Total average core mass versus time for top-peaked 0.05 ft 2 break case tophot bundle Total hot bundle mass versus time for top-peaked 0.05 ft 2 break case E1-i A