ML13309B059

License Amendment Request Marked-up Page Corrections

ML13309B059
Person / Time
Site:	Browns Ferry
Issue date:	08/29/2013
From:	James Shea 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 37402 August 29, 2013 10 CFR 50.4 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket 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 Change Technical Specifications to Delete References to Section Xl of the ASME Code and Incorporate References to the ASME OM Code and Allow Application of 25 Percent Extension of Surveillance Intervals to Accelerated Frequencies Utilized in the IST Program - TS-475," dated August 28, 2012 [ML12242A477]

2.

Technical Specifications Task Force (TSTF)-479-A, Revision 0, "Changes to Reflect Revision to 10 CFR 50.55a," dated December 19, 2005

3.

TSTF-497-A, Revision 0, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less," dated August 28, 2008 In Reference 1, Tennessee Valley Authority (TVA) submitted a License Amendment Request (LAR) to modify Facility Operating Licenses DPR-33 for Browns Ferry Nuclear Plant (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, and 3, 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 submit the 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 y

Prin~ted on recycled paper t

U.S. Nuclear Regulatory Commission Page 2 August 29, 2013 TVA has determined that correcting the typographical error does not affect the previous conclusions 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 the LAR 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 this 29th day of August 2013.

Ily, Shea President, Nuclear Licensing

Enclosures:

1. Corrected Marked-up Browns Ferry Nuclear Plant Technical Specification Pages 5.0-12 for Units 1, 2, and 3

2. Corrected Retyped Browns Ferry Nuclear Plant Technical Specification Pages 5.0-12 for Units 1, 2, and 3.

cc (Enclosures):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

Corrected Retyped Browns Fe"y Nuclear Plant Technical Specification Pages.5-t2 for Units 1, 2, and 3

Programs and Manuals Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioacthm Effluent Controls Proarnm (continued)

h. Umitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, Iodine-133, tritium, and all radlonuclides In particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public beyond the site boundary due to releases of radioactivity and to 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 the Radioactive 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 and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Inservie Tastina Promm This program provides controls for inservice testing of ASME Code Class 1, 2 and 3 components. The program shall Include the following:

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

(contlnugal BFN-UNIT I 5.0-t2 Amendment No. 234,23W,

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 lef-71 7FF];JLs71Fum (continued)

h. Umitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; I. Limilations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with haff lives 8 B days In gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Umitations on the annual dose or dose commitment to any member of the public beyond the site boundary due to releases of radioactivity and to 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 the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Comoonent Cyclic or Transient Limit This program provides controls to track the FSAR Section 4.2.5, cydic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Inservios Testina Proaram This program provides controls for Inservice testing of ASME Code Class 1, 2, and 3 components. The program shall Include the following:

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

(continued)

BFN-UNIT 2 5&0-12 Amendment No. 263,266,

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 R81active Eficent Contols Progmm (continued)

h. Lirnitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; I.

I-mitations on the annual and quarterly doses to a member of the public from lodine-I 31, lodlne-133, tritlum, and all radlonucldes In particulate form with half lives > 8 days In gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix 1; and

j.

Limitations on the annual dose or does commitment to any member of the public beyond the site boundary due to releases of radloaclivity and to 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 the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR Section 4.2.5, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Inseni"ce Testina Proaram This program provides controls for Inservice testing of ASME Code Class 1, 2, and 3 components. The program shall Include the following:

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

(continued)

BIFN-UNIT 3 5.0-12 Amendment No. 242,226,