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MONTHYEARML1108300372011-03-21021 March 2011 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval, Request for Relief 3-ISI-26 Project stage: Request ML11159A0532011-06-10010 June 2011 Request for Additional Information Regarding Relief from Weld Examination Coverage Requirements, Request for Relief 3-ISI-26 Project stage: RAI ML12018A0862012-03-14014 March 2012 Safety Evaluation for Relief Request 3-ISI-26, for Third 10-Year Inservice Inspection Interval Project stage: Approval 2011-06-10
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump 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 ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump 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 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 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 ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision 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 ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions 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 ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 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 ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation 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 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 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification 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 ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information 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 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 ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
[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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Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 March 14,2012 Mr. Joseph W. Shea Corporate Manager -Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB..BROWNS FERRY NUCLEAR PLANT, UNIT 3 -SAFETY EVALUATION FOR RELIEF REQUEST 3-ISI-26, FOR THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. ME5914)
Dear Mr. Shea:
Bya letter dated March 21, 2011, as supplemented by a letter dated July 14, 2011 (Agencywide Documents Access and Management System Accession Nos. ML 110830037 and ML 11159A053 respectively), the Tennessee Valley Authority (TVA, the licensee) submitted Relief Request 3-ISI-26.
This submittal requested relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 based on it being impractical to perform the required examinations.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g)(5)(iii), the request proposes the use of an alternative.
More specifically, TVA has proposed an alternative to achieve less than the ASME Code required examination coverage for the N6A-NV nozzle-to-vessel weld. Based on our review of your submittals, the U.S. Nuclear Regulatory Commission (NRC) has concluded that the method of record is impractical; however, the NRC staff finds that the alternative proposed provides reasonable assurance of structural integrity.
Therefore, the NRC finds that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
This relief is granted and the alternate proposed by TVA is authorized for the remainder of the third 10-year inservice inspection interval at Browns Ferry Nuclear Plant, Unit 3, which began November 19, 2005, and ends November 18, 2015.
J. Shea If you have any questions regarding this matter, please contact Ms. Eva Brown at (301) 415-2315.
Sincerely, Douglas A. Broaddus, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-296
Enclosure:
Safety Evaluation cc w/enclosure:
Distribution via Listserv
ReG!!,_ 0.,.:r J.. ... ('I << 0 .... !il: <J> l' UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ",') 'f/!.O ****i< SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST TO EXAMINE WELD TO THE MAXIMUM EXTENT PRACTICAL TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 3 DOCKET NO. 50-296
1.0 INTRODUCTION
By a letter dated March 21, 2011, as supplemented by a letter dated July 14, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 110830037 and ML 11159A053 respectively), the Tennessee Valley Authority (TVA, the licensee) submitted Relief Request (RR) 3-ISI-26 pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g)(5)(iii), for the Browns Ferry Nuclear Plant, Unit 3 (BFN-3). This submittal requested relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90. More specifically, the licensee has requested to achieve less than the ASME Code required examination coverage for the N6A-NV nozzle-to-vessel weld on Unit 3. The Code of Record for the third inservice inspection (lSI) interval at Unit 3 is the 2001 Edition through 2003 Addenda of the ASME Code.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access provisions and the preservice 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.
The regulations require that lSI of components and system pressure tests conducted during the 10-year intervals be in compliance with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b), 12 months prior to the start of the 120-month interval.
The ASME Code of record for Unit 3 is the 2001 Edition through 2003 Addenda of the ASME Code,Section XI. Enclosure
-Pertinently, the ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1, which has been approved unconditionally in Regulatory Guide (RG) 1.147, Revision 15, "Inservice Inspection Code Case Acceptability, ASME Code Section XI, Division 1," allows that "a reduction in examination coverage for any Class 1 or Class 2 weld may be acceptable provided that the reduction in coverage for that weld is less than 10 [percent]
.. " Additionally ASME Code Case N-648-1, "Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles,Section XI Division 1," conditionally accepted by the U.S. Nuclear Regulatory Commission (NRC), permits the ASME Code users to perform a VT-1 [visual] examination in lieu of a volumetric examination for specific locations on welds such as the subject weld. Section 50.55a(g)(6)(i) to 10 CFR states that: ... The Commission will evaluate determinations
[submitted by the licensee]
under paragraphs (g)(5) of this section [10 CFR 50.55a] that code requirements are impractical.
The Commission may grant relief and may impose such alternative requirements as it determines are authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
The NRC staff notes that September 24, 2008, BFN-3 precedent (ADAMS Accession No. ML082480573) cited by the licensee was applicable and applied in completing this review. 3.0 LICENSEE EVALUATION ASME Code Requirement The ASME Code,Section XI, Table IWB-2500-1, Item No. C3.90 component examinations require a volumetric examination of the nozzle-to-vessel welds. The extent of the examination is "all nozzles," specifically the volume illustrated in Figure IWB-2500-7(a), and essentially 100 percent of the weld and adjacent base material.
ASME Code Case N-460 effectively states that 90 percent coverage is adequate to meet the ASME Code requirement.
ASME Code Case N-460 has been approved for use by the NRC in RG 1.147, Revision 15. System/Component for Which Relief is Requested Relief is requested for the examination of the N6A-NV nozzle-to-vessel weld, a C3.90 component.
ASME Code Requirement for Which Relief is Requested Relief is requested from meeting the required 100-percent inspection coverage of the ASME Section XI Code, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 requirements for this weld.
-Licensee's Proposed Alternative Examination The licensee stated, In lieu of the Code require[d]
essentially 100 percent volume UT [ultrasonic testing1 examination, on the nozzle-to-vessel weld, TVA proposes a UT examination of accessible areas to the maximum extent practical given the component design configuration of the RPV nozzle-to-vessel weld. The licensee further stated that the examination as performed achieved a 5S.9-percent coverage.
Licensee's Basis for Requesting Relief The submittal identified that the design configuration of the subject weld precludes 100-percent examination due to inherent limitations of the barrel-type nozzle-to-vessel weld design. Achieving 100-percent coverage would require a substantial redesign of the nozzle itself. The licensee indicated that scanning from the nozzle surface is ineffective due to the weld location and asymmetrical inside surface of the nozzle-to-vessel convergence.
It was noted that the licensee considered automated UT, but cited past experience to conclude that such an examination would not Significantly improve the coverage.
The licensee continued with a discussion on the fact that the coverage achieved included the most challenged areas of the weld, the quality of their inspection program, and the impracticality of radiographic examination.
4.0 TECHNICAL
EVALUATION The ASME Code requirement for the subject weld requires an examination of "100 [percent]
welds in all components," while the licensee achieved an approximate UT coverage of 5S.9 percent of the examination area. This is not unusual for subject welds of the nozzle-to-shell variety in older plant designs such as Unit 3. The licensee documented the examination in several detailed diagrams, provided in the submittal, making clear the impediment to reaching the required surface examination coverage.
Geometrically the curvature of the head and the size of the fillet on the weld make achieving the required coverage impractical.
The NRC staff accepts that redesigning the nozzle is impractical.
Alternatives such as automated UT or radiography are equally impractical, as they would not provide significantly enhanced surety of the integrity of the subject weld. While it may be possible to marginally increase coverage with further careful examination, the fact that the inner portion of the weld was successfully examined provides a sufficient measure of surety regarding the structural integrity of the weld, as the inner portions are the most challenged portions of the weld. The NRC staff notes that RRs were approved for similar weld examinations at Unit 3 in 200S. Further assurance of weld integrity is provided in the form of a VT-1 visual examination performed on the inner radius of the nozzle in 200S, as noted in the July 14, 2011, letter. The visual examination was performed consistent with ASME Code Case N-64S-1, which was conditionally approved for use in RG 1.147.
Based on the above, the NRC staff concludes that, if significant service-induced degradation had occurred, there is reasonable assurance that evidence of degradation would have been detected by the ultrasonic and visual examinations performed by the licensee within the examined area. In light of the above, the NRC staff concludes that relief should be granted from further action in examining this weld for the Unit 3 third 10-year lSI interval.
5.0 CONCLUSION
Due to issues at Unit 3, the ASME Code requirements with respect to the subject weld are impractical.
Redesign of the nozzle performing radiographic examination of the weld to achieve of the ASME Code requirements would be a burden to the licensee.
The weld coverage achieved provides reasonable assurance of the structural integrity of the subject weld. Therefore, the licensee's request for relief is granted pursuant to 10 CFR 50.55a(g)(6)(i) for the Unit 3 third 10-year lSI interval.
The NRC has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed. All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
This relief is granted and the alternate proposed by TVA is authorized for the remainder of the third 10-year inservice inspection interval at Browns Ferry Nuclear Plant, Unit 3, which began November 19, 2005, and ends November 18, 2015. Principal Contributor:
D. Widrevitz Date: March 14,2012 J. Shea -2 If you have any questions regarding this matter, please contact Ms. Eva Brown at (301) 415-2315.
Sincerely, IRA! Douglas A. Broaddus, Chief Plant licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-296
Enclosure:
Safety Evaluation cc w/enclosure:
Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMBrownsFerry RidsNrrLABClayton RidsRg n2MailCenter LPL2-2 R/F RidsOgcRp RidsNrrDeEvib MKotzalas, EDO RidsNrrDorlLpl2-2
DWidrevitz, NRR RidsAcrsAcnw_MailCTR ADAMS Accession No ML 12018A086
- Via e-mail OFFICE LPL2-2/PM LPL2-21LA EVIB/BC LPL2-2/BC NAME EBrown BClayton HGonzalez(A)*
DBroaddus DATE 01/19/12 01/18/12 10/27/11 03/14/12 OFFICIAL RECORD COpy