ML13309B059

License Amendment Request Marked-up Page Corrections

ML13309B059
Person / Time
Site:	Browns Ferry
Issue date:	08/29/2013
From:	Shea J W Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13309B059 (9)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402August 29, 201310 CFR 50.410 CFR 50.90ATTN: Document Control DeskU.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRCDocket Nos. 50-259, 50-260, and 50-296

Subject:

License Amendment Request Marked-up Page Corrections

References:

1. Letter from TVA to NRC, "License Amendment Request to ChangeTechnical Specifications to Delete References to Section Xl of the ASMECode and Incorporate References to the ASME OM Code and AllowApplication of 25 Percent Extension of Surveillance Intervals toAccelerated Frequencies Utilized in the IST Program -TS-475,"

datedAugust 28, 2012 [ML12242A477]

2. Technical Specifications Task Force (TSTF)-479-A, Revision 0, "Changesto Reflect Revision to 10 CFR 50.55a,"

datedDecember 19, 20053. TSTF-497-A, Revision 0, "Limit Inservice Testing Program SR 3.0.2Application to Frequencies of 2 Years or Less," dated August 28, 2008In Reference 1, Tennessee Valley Authority (TVA) submitted a License Amendment Request (LAR) to modify Facility Operating Licenses DPR-33 for Browns Ferry NuclearPlant (BFN), Unit 1; DPR-52 for BFN, Unit 2; and DPR-68 for BFN, Unit 3.During review of the LAR, the NRC identified a minor typographical error on Technical Specification Page 5.0-12 for each of the three mark-ups provided for BFN, Units 1, 2, and3, i.e., in the last line of 5.5.6.a, the word "are" is to be deleted.

In a subsequent telephone conversation with the BFN NRC Project Manager, Ms. Farideh Saba, TVA agreed to submitthe corrected pages to replace the previous pages (Page 5.0-12 for BFN, Units 1, 2, and 3)in Reference

1. The enclosures to this letter provide the three corrected pages.DP yPrin~ted on recycled paper t U.S. Nuclear Regulatory Commission Page 2August 29, 2013TVA has determined that correcting the typographical error does not affect the previousconclusions regarding the no significant hazards considerations and the categorical exclusion from environmental review pursuant to the provision of 10 CFR 51.22(c)(9) for theLAR submitted in Reference 1.There are no new regulatory commitments in this letter. If you have any questions regarding these corrections, please contact Edward D. Schrull at (423) 751-3850.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on this29th day of August 2013.Ily,SheaPresident, Nuclear Licensing

Enclosures:

1. Corrected Marked-up Browns Ferry Nuclear Plant Technical Specification Pages 5.0-12 for Units 1, 2, and 32. Corrected Retyped Browns Ferry Nuclear Plant Technical Specification Pages 5.0-12 for Units 1, 2, and 3.cc (Enclosures):

NRC Regional Administrator

-Region IINRC Senior Resident Inspector

-Browns Ferry Nuclear Plant

Enclosure 2Corrected Retyped Browns Fe"y Nuclear Plant Technical Specification Pages .5-t2 for Units 1, 2, and 3 Programs and ManualsPrograms and Manuals5.55.5 Programs and Manuals5.5.4Radioacthm Effluent Controls Proarnm(continued)

h. Umitations on the annual and quarterly air doses resulting from noblegases released in gaseous effluents from each unit to areas beyond thesite boundary, conforming to 10 CFR 50, Appendix I;i. Limitations on the annual and quarterly doses to a member of the publicfrom iodine-131, Iodine-133,

tritium, and all radlonuclides In particulate form with half lives > 8 days in gaseous effluents released from eachunit to areas beyond the site boundary, conforming to 10 CFR 50,Appendix I; andj. Limitations on the annual dose or dose commitment to any member ofthe public beyond the site boundary due to releases of radioactivity andto radiation from uranium fuel cycle sources, conforming to 40 CFR 190.k. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to theRadioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic-or Trnan.Qnt1Umit This program provides controls to track the FSAR Section 4.2.5, cyclic andtransient occurrences to ensure that components are maintained within thedesign limits.5.5.6 Inservie Tastina PrommThis program provides controls for inservice testing of ASME CodeClass 1, 2 and 3 components.

The program shall Include the following:

a. Testing frequencies applicable to the ASME Code for Operations andMaintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:(contlnugal

.BFN-UNIT I5.0-t2Amendment No. 234,23W, Programs and Manuals5.55.5 Programs and Manuals5.5.4lef-71 7FF];JLs71Fum (continued)

h. Umitations on the annual and quarterly air doses resulting from noblegases released in gaseous effluents from each unit to areas beyond thesite boundary, conforming to 10 CFR 50, Appendix I;I. Limilations on the annual and quarterly doses to a member of the publicfrom iodine-131, iodine-133,

tritium, and all radionuclides in particulate form with haff lives 8 B days In gaseous effluents released from eachunit to areas beyond the site boundary, conforming to 10 CFR 50,Appendix I; andj. Umitations on the annual dose or dose commitment to any member ofthe public beyond the site boundary due to releases of radioactivity andto radiation from uranium fuel cycle sources, conforming to 40 CFR 190.k. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to theRadioactive Effluent Controls Program surveillance frequency.

5.5.5 Comoonent Cyclic or Transient LimitThis program provides controls to track the FSAR Section 4.2.5, cydic andtransient occurrences to ensure that components are maintained within thedesign limits.5.5.6 Inservios Testina ProaramThis program provides controls for Inservice testing of ASME CodeClass 1, 2, and 3 components.

The program shall Include the following:

a. Testing frequencies applicable to the ASME Code for Operations andMaintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:(continued)

BFN-UNIT 25&0-12Amendment No. 263,266, Programs and Manuals5.55.5 Programs and Manuals5.5.4 R81active Eficent Contols Progmm (continued)

h. Lirnitations on the annual and quarterly air doses resulting from noblegases released in gaseous effluents from each unit to areas beyond thesite boundary, conforming to 10 CFR 50, Appendix I;I. I-mitations on the annual and quarterly doses to a member of the publicfrom lodine-I 31, lodlne-133,

tritlum, and all radlonucldes In particulate form with half lives > 8 days In gaseous effluents released from eachunit to areas beyond the site boundary, conforming to 10 CFR 50,Appendix 1; andj. Limitations on the annual dose or does commitment to any member ofthe public beyond the site boundary due to releases of radloaclivity andto radiation from uranium fuel cycle sources, conforming to 40 CFR 190.k. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to theRadioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient LimitThis program provides controls to track the FSAR Section 4.2.5, cyclic andtransient occurrences to ensure that components are maintained within thedesign limits.5.5.6 Inseni"ce Testina ProaramThis program provides controls for Inservice testing of ASME CodeClass 1, 2, and 3 components.

The program shall Include the following:

a. Testing frequencies applicable to the ASME Code for Operations andMaintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:(continued)

BIFN-UNIT 35.0-12Amendment No. 242,226,