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| | issue date = 06/29/2017 | | | issue date = 06/29/2017 |
| | title = 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 Alternative.. | | | title = 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 Alternative.. |
| | author name = Shea J W | | | author name = Shea J |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
| | addressee name = | | | addressee name = |
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Category:Letter type:CNL
MONTHYEARCNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-013, Cycle 22 Reload Analysis Report2024-03-14014 March 2024 Cycle 22 Reload Analysis Report CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-105, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 222022-11-0808 November 2022 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 22 CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) 2024-05-08
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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.