NL-17-067, Browns Ferry, Units 1, 2, and 3 - Administrative Changes to Proposed Revised Technical Specification Pages Related to Application to Revise Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request an A

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Browns Ferry, Units 1, 2, and 3 - Administrative Changes to Proposed Revised Technical Specification Pages Related to Application to Revise Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request an Al
ML17180A158
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/29/2017
From: Shea J W
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-17-067
Download: ML17180A158 (23)


Text

U.S. Nuclear Regulatory Commission CNL-17-067 Page 2 June 29 , 2017 The following pages are affected: BFN , Unit 1, TS pages 5.0-12 and 5.0-13 BFN , Unit 2, TS pages 5.0-12 and 5.0-13 BFN , Unit 3, TS pages 5.0-1 2 and 5.0-13 The proposed change for each Unit on page 5.0-12 is to include the word " (Deleted)" in the title of TS Section 5.5.6. The proposed change for each Unit on page 5.0-13 is to remove the unused Section number and include the phrase " This page intentionally left blank." Enc l osure 1 to this letter contains the revised proposed TS pages (mark-up version) for BFN , Un i ts 1, 2, and 3. Enclosure 2 to this letter contains revised proposed TS pages listed above (c l ean version) for BFN, Units 1, 2, and 3. The differences between the proposed revised TS pages included in this letter and the proposed TS pages from the referenced applicat i on are minor and administrative in nature. The diffe r ences do not affect the description and assessment of the proposed TS changes included as Enclosure 1 to the referenced application.

All other proposed TS changes i ncluded in the referenced appl i cation are unaffected by these differences. Consistent with the standards set forth in 10 CFR 50.92(c), TVA has determ i ned that the revised proposed TS pages do not affect the no significant hazards cons i deration determination associated with the referenced application. There are no new regulatory commitments associated with this submittal.

If you should have any questions regarding this submittal , please contact Ed Schrull at (423) 751-3850. I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of June 2017. Sincerely , Joseph W. Shea Vi ce President

-Nuclear Regulatory Affairs & Support Services Enclosures cc: See Page 3

Programs and Manuals 5.5 (continued)

BFN-UNIT 1 5.0-12 Amendment No. 234 , 239 , 283 August 30, 2013 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued) h.Limitations on the annual and quarterly air doses resulting fromnoble gases released in gaseous effluents from each unit to areasbeyond 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 radionuclides 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; andj.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 theRadioactive 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 Inservice Testing Program 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:

Programs and Manuals 5.5 (continued)

BFN-UNIT 1 5.0-13 Amendment No. 234 , 283 August 30, 2013 5.5 Programs and Manuals 5.5.6 Inservice Testing Program (continued)

ASME OM Code and applicable Addenda terminology for inservice testing activities Required Frequencies for

performing inservice testing

activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every

6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days b.The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Test Program for performing Inservice testing activities;c.The provisions of SR 3.0.3 are applicable to inservice testing activities; andd.Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

Programs and Manuals 5.5 (continued)

BFN-UNIT 2 5.0-12 Amendment No. 253 , 266 , 310 August 30, 2013 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued) h.Limitations on the annual and quarterly air doses resulting fromnoble gases released in gaseous effluents from each unit to areasbeyond 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 radionuclides 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; andj.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 theRadioactive 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 Inservice Testing Program 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:

Programs and Manuals 5.5 (continued)

BFN-UNIT 2 5.0-13 Amendment No. 253 , 310 August 30, 2013 5.5 Programs and Manuals 5.5.6 Inservice Testing Program (continued)

ASME OM Code and applicable Addenda terminology for inservice testing activities Required Frequencies for

performing inservice testing

activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every

6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days b.The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Test program for performing inservice testing activities;c.The provisions of SR 3.0.3 are applicable to inservice testing activities; andd.Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

Programs and Manuals 5.5 (continued)

BFN-UNIT 3 5.0-12 Amendment No. 212 , 226 , 269 August 30, 2013 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued) h.Limitations on the annual and quarterly air doses resulting from noblegases 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 radionuclides 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; andj.Limitations on the annual dose or dose commitment to any member ofthe 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 theRadioactive 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 Inservice Testing Program 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:

Programs and Manuals 5.5 (continued)

BFN-UNIT 3 5.0-13 Amendment No. 212 , 269 August 30, 2013 5.5 Programs and Manuals 5.5.6 Inservice Testing Program (continued)

ASME OM Code and applicable Addenda terminology for inservice testing activities Required Frequencies for

performing inservice testing

activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every

6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days b.The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Test Program for performing inservice testing activities;c.The provisions of SR 3.0.3 are applicable to inservice testing activities; andd.Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.