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MONTHYEARML14260A3652014-09-12012 September 2014 3 - ASME, Code Section XI-Inservice Inspection Program for the Unit 1 Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval and Unit 3 Third Ten-Year Inspection Interval, Request for an Alternative. Project stage: Request ML14349A7932014-12-15015 December 2014 NRR E-mail Capture - FW: Request for Additional Information (RAI) Regarding Browns Ferry Units 1, 2, and 3 Alignment of Inservice Inspection (ASME Section XI) Intervals (MF4854, MF4855, and MF4856) Project stage: RAI ML15028A4042015-01-27027 January 2015 Response to NRC Request for Additional Information Regarding Request for an Alternative ISI-45 Project stage: Response to RAI ML15191A3722015-08-0606 August 2015 Relief from the Requirements of American Association of Mechanical Engineers Code Section XI Inservice Inspection (ISI) Program, Request for an Alternative ISI-45 Project stage: Approval 2014-09-12
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Category:Letter
MONTHYEARIR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-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 ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual 2024-09-03
[Table view] Category:Safety Evaluation
MONTHYEARML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23116A2472023-05-23023 May 2023 Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control ML23101A1102023-05-16016 May 2023 Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications ML23073A2902023-05-0202 May 2023 Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times ML23054A2902023-03-13013 March 2023 Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22273A1032022-11-22022 November 2022 Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification ML22220A2602022-11-21021 November 2022 Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A ML22298A2852022-11-14014 November 2022 Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526 ML22138A3252022-06-24024 June 2022 Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis ML22084A0012022-04-0505 April 2022 Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes ML22020A2282022-03-16016 March 2022 Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2 ML22010A1952022-01-12012 January 2022 Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters ML21173A1772021-07-27027 July 2021 Issuance of Amendment Nos. 317, 340, and 300 Regarding Adoption of Title 10 of the Code of Federal Register Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21075A0762021-04-30030 April 2021 Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis ML21041A4892021-04-0808 April 2021 Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3 ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20253A1812020-09-23023 September 2020 Proposed Alternative to the Requirements of the American Society of Mechanical Engineers Code ML20085G8962020-06-26026 June 2020 Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times ML19329E3192020-01-0202 January 2020 SE Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC Nos. MF4540, MF4541 and MF4542; EPID No. L-2014-JLD-0044) ML19294A0112019-12-26026 December 2019 Issuance of Amendment Nos. 311, 334, and 294 Adopt Technical Specifications Task Force Traveler, TSTF-542, Revision 2 ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML19198A0012019-08-13013 August 2019 Issuance of Amendment Nos. 308, 331, and 291 to Extend Implementation Due Date for Modifications 102 and 106 Related to NFPA 805 (Eid L-2019-LLA-0140) ML19037A1372019-04-0202 April 2019 Revisions to Modifications 85, 102 and 106 Related to National Fire Protection Association 805 Performance-based Standard for Fire Protection of Light Water Reactor Electric Generating Plants ML19010A2742019-03-18018 March 2019 Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority ML19016A2152019-02-28028 February 2019 Relief from the Requirements of American Association of Mechanical Engineers Code Section XI Inservice Inspection Program, Request for an Alternative ISI-46 ML18323A1722018-12-31031 December 2018 Relief Request No. 1 ISI 29 Regarding Second 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Welds ML18323A0262018-12-0404 December 2018 Relief Request No. 1-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Reactor Vessel Welds ML18241A3192018-10-0909 October 2018 Issuance of Amendment Nos. 306, 329, and 289 to Revise Approved NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants-Revision ML18251A0032018-09-27027 September 2018 Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292) ML18236A3312018-09-24024 September 2018 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML18197A3072018-08-30030 August 2018 Issuance of Amendments Regarding Request to Change Technical Specification 3.3.1 and Surveillance Requirement 3.2.4 ML18171A3372018-07-10010 July 2018 Issuance of Amendment to Revise License Condition 2.C(18)(a)3 ML18138A4522018-05-29029 May 2018 Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20 ML17289A0322017-12-22022 December 2017 Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160) ML17261A0362017-10-0606 October 2017 Request for Request 3-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Examination Coverage of Inside Radius and Nozzle-to-Vessel Welds ML17215A2432017-10-0202 October 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566) ML17032A1202017-08-14014 August 2017 Non-Proprietary Issuance of Amendments Regarding Extended Power Uprate ML17145A5522017-08-11011 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Alternative Request IST-RR-1 for the Fourth 10-Year Inservice Testing Interval (CAC Nos. MF9087, MF9088, and MF9089) ML17034A3602017-03-27027 March 2017 Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ... 2024-01-03
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- . A\Jgust 6, 2015 Mr. Joseph W . Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - RELIEF FROM THE REQUIREMENTS OF AMERICAN ASSOCIATION OF MECHANICAL ENGINEERS CODE SECTION XI INSERVICE INSPECTION PROGRAM, REQUEST FOR AN ALTERNATIVE ISl-45 (TAC NOS. MF4854, MF4855, AND MF4856)
Dear Mr. Shea:
By letter dated September 12, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14260A365), as supplemented on January 27, 2015 (ADAMS Accession No. ML15028A404), the Tennessee Valley Authority (the licensee) submitted Relief Request (RR) ISl-45 to the Nuclear Regulatory Commission (NRC) for an alternative to the inservice inspection (ISi) interval requirements described in Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The requested alternative would align the separate ISi interval dates for the three BFN units to a single interval date starting February 1, 2016.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50 ,
Section 55a , Paragraph (a)(3)(i) , the licensee requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety. By Federal Register Notice 79 FR 65776, dated November 5, 2014, which became effective on December 5, 2014, the paragraph headings in 10 CFR 50.55a were revised. Accordingly, relief requests that had been previously covered under 10 CFR 50.55a(a)(3)(i) are now covered under the equivalent 10 CFR 50.55a(z)(1 ).
The NRC staff has reviewed the subject request and concludes , as set forth in the enclosed safety evaluation, that the proposed alternative for RR ISl-45 provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore , the NRC staff authorizes RR ISl-45 to allow the BFN Units 1, 2, and 3 to use the proposed alternative date of February 1, 2016, for the beginning of BFN Units 1, 2, and 3 next 10-year inspection interval.
All other ASME Code ,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
J. W . Shea If you have any questions, please contact Farideh Saba at (301) 415-1447 or farideh .saba@nrc.gov.
Sincerely,
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Shana R. Helton, Branch Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NO. ISl-45 REGARDING ALIGNMENT OF INSERVICE INSPECTION INTERVALS TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296
1.0 INTRODUCTION
By letter dated September 12, 2014, as supplemented by letter dated January 27 , 2015 (Agencywide Documents Access and Management System Accession Numbers ML14260A365 and ML15028A404, respectively) , the Tennessee Valley Authority (the licensee) submitted Relief Request (RR) ISl-45 for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The licensee is requesting an alternative from inservice inspection (ISi) interval scheduling requirements described in Section XI of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (Code) , to align the three separate ISi 10-year interval dates of the three BFN Units, 1, 2, and 3.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50 , Section 55a, Paragraph (a)(3)(i) , the licensee requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(a)(3)(i) , the licensee proposed an alternative to the 2001 and 2004 ASME Code,Section XI , "Rules for lnservice Inspection of Nuclear Power Plant Components ,"
paragraph IWA-2432 that states that successive 10-year inspection intervals should start 1O years after the previous inspection interval.
By Federal Register Notice 79 FR 65776, dated November 5, 2014, paragraph headings in 10 CFR 50.55a were revised and made effective December 5, 2014, such that material previously contained in 10 CFR 50.55a(a)(3) is now contained in 10 CFR 50.55a(z)(1 ).
Therefore , relief requests that had been previously covered under 10 CFR 50.55a(a)(3)(i) are now covered under the equivalent 10 CFR 50.55a(z)(1 ).
Enclosure
Pursuant to 10 CFR 50.55a(g)(4) , ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, to the extent practical within the limitations of design, geometry, and materials of construction of the components. Paragraph 50.55a(g)(4)(ii) states that inservice examination of components and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements in the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, and is subject to the limitations and modifications listed therein .
It states, in part, in 10 CFR 50.55a(z)(1 ), that alternatives to the requirements of 10 CFR 50.55a(g) may be used , when authorized by the U.S. Nuclear Regulatory Commission (NRC) , if the licensee demonstrates that the proposed alternatives would provide an acceptable level of quality and safety.
Based on the above and subject to the following technical evaluation the NRC staff* finds that the regulatory authority exists for the licensee to propose and the NRC to authorize the proposed alternative.
3.0 TECHNICAL EVALUATION
3.1 The Licensee's Requested Relief ASME Codes of Record BFN Unit 1 is currently in its second 10-year ISi interval. The code of record for this interval is ASME Section XI, 2001 Edition with 2003 Addenda . The Unit 1 second 10-year ISi interval is currently scheduled to end on June 1, 2017.
BFN Unit 2 is currently in its fourth 10-year ISi interval. The code of record for this interval is ASME Section XI, 2004 Edition. The Unit 2*fourth 10-year ISi interval is currently scheduled to end on May 25, 2021 .
BFN Unit 3 is currently in its third 10-year ISi interval. The code of record for this interval is ASME Section XI , 2001 Edition with 2003 Addenda . The Unit 3 third 10-year ISi interval is currently scheduled to end on November 18, 2015.
The proposed start of the forthcoming aligned 10-year ISi interval for all BFN units is February 1, 2016, with an ending date of February 1, 2026. Therefore, BFN Units 1 and 2 will begin their next interval (third and fifth , respectively) prior to that originally scheduled and BFN Unit 3 will begin its next interval (fourth) 2 months and 14 days after that currently scheduled .
The code of record for the proposed forthcoming aligned third (BFN Unit 1), fifth (BFN Unit 2) ,
and fourth (BFN Unit 3) 10-year ISi intervals, will be ASME Section XI , 2007 Edition with 2008 Addenda.
ASME Code Requirements The scheduling of successive inspection intervals is described in ASME Code Section XI . The 2001 and 2004 editions of ASME Code Section XI , paragraph IWA-2432 state that successive 10-year inspection intervals should start 10 years after the previous inspection interval.
The Licensee's Proposed Alternative The licensee is requesting authorization to allow use of an alternative to the interval timetable currently required by ASME Section XI and the 10 CFR 50.55a for updating the ISi programs.
The licensee is proposing to start the next inspection interval for all three units on February 1, 2016. The licensee also requests the start date for the remaining subsequent 120 month interval ISi programs be the same for all three units.
The licensee states that this alternative will apply to the ISi , Pressure Test, and Repair Replacement Activity Programs and that examinations performed under Subsection IWE (Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Plants), will not be affected by this request for an alternative. BFN Units 1, 2, and 3 employ a General Electric Company Mark 1 steel containment design consisting of a drywell and pressure suppression chamber. The requirements of Subsection IWL (Requirements for Class CC Concrete Components of Light-Water Cooled Plants) are not applicable to the steel containment (Class MC) vessels.
The Licensee's Basis for Proposed Alternative BFN Units 1, 2, and 3 entered commercial service on August 1, 1974, March 1, 1975, and March 1, 1977, respectively. These commercial service start dates established the initial inspection intervals for ISi of the units. Due to extended shutdowns of all three BFN units in the years since entering commercial service, these ISi interval dates were altered in accordance with ASME Code, Subsection IWA-2430(e) of the 2001 Edition with 2003 Addenda of Section XI. Every ten (10) years, an update to the ISi Program is required , in accordance with 10 CFR 50.55a(g)(4)(ii) .
Currently, BFN's three units have different inspection interval schedules. There are three different ISi Programs using two different Code Editions and Addenda . When the next interval update occurs, which will be for BFN Unit 3 in November 2015, the three units will be using three different Editions and Addenda of ASME Section XI. The licensee is proposing to start the next inservice inspection interval for all three units on February 1, 2016. The Edition and Addenda of ASME Code Section XI chosen for the interval updates will be in accordance with 10 CFR 50.55(g)(4)(ii).
The licensee stated that there are distinct advantages for the BFN units to be on the same ISi schedule and Edition of the ASME Section XI. There are fewer procedures to maintain and procedures will be meeting the requirements of one Edition/Addenda of the Code instead of several versions. The ISi program documents can be combined into one document covering all three units, which reduces the chance of applying incorrect ISi requirements. Use of one set of procedures and documents will not result in a reduction in the quality of the ISi program or the safety of the plant.
The licensee, in its letter dated January 27, 2015, clarified that non-destructive type examinations on piping and components that have not been completed for the existing interval will be performed as required prior to the planned synchronization of the inspection interval dates.
The licensee states that all examinations required by both the current ASME Code and the later ASME Code edition/addenda will be performed during the overlap period of the intervals.
Subsequent 10-year intervals will be in accordance with the applicable rules in force at that time .
Duration of Proposed Alternative The proposed alternative is a one-time modification of the ends of the current 10-year ISi intervals at each unit. The proposed date for the new 10-year ISi Inspection intervals is February 1, 2016. Therefore, BFN Unit 1 and 2 will begin their next interval (third and fifth ,
respectively) prior to that originally scheduled and BFN Unit 3 will begin its next interval (fourth) 2 months and 14 days after that originally scheduled.
3.2 NRC Staff Evaluation The licensee is proposing to synchronize the beginning of the next 10-year ISi inspection intervals for BFN Unit 1, 2, and 3, to February 1, 2016. The licensee is requesting this relief pursuant to the provisions of 10 CFR 50.55a(z)(1) on the basis that the alternative provides an acceptable level of quality and safety.
As described in letter dated September 12, 2014, and clarified in letter dated January 27, 2015, (ADAMS Accession Numbers ML14260A365 and ML15028A404, respectively) , the schedule for ISis will not be affected by use of the alternate start date for the of the 10-year inspection intervals. Adoption of the proposed alternate ISi interval start date would leave one outage for BFN Unit 1 and three outages for BFN Unit 2 left in the currently scheduled intervals. All examinations that would have been scheduled for the remaining outages will still be performed under the revised schedule. For BFN Units 1 and 2, when these examinations are completed ,
the scheduling of examinations will revert to the requirements of the applicable Edition and Addenda of ASME Section XI. For BFN Unit 3, the licensee's proposed change in the beginning of interval date from November 14, 2015, to February 1, 2015, will not affect the schedule of examinations.
As an example, weld inspections for intergranular stress corrosion cracking Category D welds at BFN Unit 2 that are currently scheduled to be conducted during the 20th refueling outage, currently the third period of the fourth 10-year inspection interval, will still be conducted in the 20th refueling outage, which would be the second period of the fifth inspection interval using the proposed alternate start date for the fifth inspection interval.
One effect of ending the BFN Unit 1 and 2 10-year ISi intervals early would be the earlier adoption of a later edition of an NRG-approved version of ASME Code Section XI for ISis occurring before the end of the currently scheduled intervals. Later NRG-approved code editions include the most-recent NRG-approved changes and have fewer conditions in 10 CFR 50.55a. Adoption of a later NRG-approved code does not result in a reduction in inspection quality.
With the currently scheduled intervals when BFN Unit 3 begins a new interval on November 14, 2015, three different editions of ASME Code (2001 for Unit 1, 2004 for Unit 2, and 2007 for Unit
- 3) will be used at the BFN site. With the ISi program documents combined into one document covering all three units, there will be a reduced chance of the licensee applying the incorrect ISi requirements. The use of one set of procedures and documents will not reduce the quality of the ISi program or the safety of the plant.
As the alternative alignment for the next inspection intervals for BFN Units 1, 2, and 3, result in no changes in ISi schedule and the licensee will use an edition of ASME Code Section XI incorporated by reference in 10 CFR 50.55a for the inspections, the NRC staff has determined that the proposed synchronization of the 10-year inspection intervals for the three units provides an acceptable level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the proposed alternative described in RR ISl-45 provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore , the NRC staff authorizes RR ISl-45 to allow the licensee to use the date of February 1, 2016, for the beg inning of the BFN Units 1, 2, and 3 next 10-year inspection interval.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributors: Stephen Cumblidge Candace Pfefferkorn Date: August 6, 2015
ML15191A372 OFFICE NRR/DORULPL2-2/PM NRR/DORULPL2-2/PM NRR/DORULPL2-2/LA NRR/DE/EPNB/BC NAME CPfefferkorn FSaba BClayton DAiiey DATE 08/05/15 08/06/15 08/05/15 08/06/15 OFFICE NRR/DORULPL2-2/BC NAME SHelton DATE 08/06/15