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Category:Letter
MONTHYEARIR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),”2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),” ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS 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) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 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 IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information 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 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) 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 ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) 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-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 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 IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods 2024-08-07
[Table view] Category:Safety Evaluation
MONTHYEARML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 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 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 ML22293A4082022-11-14014 November 2022 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML22257A0512022-11-0404 November 2022 Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A ML22276A1612022-10-24024 October 2022 Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22272A5682022-10-12012 October 2022 Authorization of Alternatives to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Operating and Maintenance Code ML22187A1812022-09-20020 September 2022 Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML22187A0192022-09-20020 September 2022 Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps ML22014A2062022-05-0404 May 2022 Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors 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 ML22070A0022022-03-28028 March 2022 Review of the Fall 2021 Mid Cycle Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Report ML21306A2872022-01-25025 January 2022 Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement ML21334A2952022-01-18018 January 2022 Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement ML21334A3892022-01-12012 January 2022 Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis ML21271A1372021-12-16016 December 2021 Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level ML21189A3072021-11-0303 November 2021 Issuance of Amendment Nos. 149 and 56 Regarding Modification of Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21158A2842021-09-17017 September 2021 Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation ML21153A0492021-07-26026 July 2021 Issuance of Amendment No. 147 Regarding Change to Steam Generator Tube Inspection Frequency and Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-510 ML21161A2392021-06-24024 June 2021 Issuance of Amendment No. 54 Regarding Use of Temperature Adjustment to Voltage Growth Rate for the Generic Letter 95-05 Steam Generator Tube Repair Criteria ML21148A1002021-06-17017 June 2021 Issuance of Amendment No. 53 Regarding Neutron Fluence Calculation Methodology ML21099A2462021-05-14014 May 2021 Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21130A6012021-05-13013 May 2021 Correction of Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B ML21078A4842021-05-0505 May 2021 Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications ML21110A0372021-04-29029 April 2021 Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B ML21064A4082021-03-10010 March 2021 Correction of Safety Evaluation for License Amendment Nos. 143 and 50 (EPID L-2020-LLA-0005) (Non-Proprietary) ML21015A0342021-03-0909 March 2021 Issuance of Amendment No. 144 Regarding Post Accident Monitoring Instrumentation ML21034A1692021-02-26026 February 2021 Issuance of Amendment Nos. 143 and 50 Regarding Implementation of Full Spectrumtm Loss-of-Coolant Accident Analysis (LOCA) and New LOCA-Specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology ML20232C6222021-02-11011 February 2021 Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037 ML21027A1672021-02-0909 February 2021 Issuance of Amendment No. 48 Regarding Use of Alternate Probability of Detection Values for Beginning of Cycle in Support of Operational Assessment ML20350B4932021-01-25025 January 2021 Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition 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 ML20245E4132020-12-0808 December 2020 Issuance of Amendment Nos. 139 and 45 Regarding Revisions to Technical Specification 3.6.15, Shield Building 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 ML20239A7912020-10-28028 October 2020 Issuance of Amendment Nos. 137 and 43 Regarding Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 541, Revision 2 ML20226A4442020-10-21021 October 2020 Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate ML20167A1482020-08-19019 August 2020 Issuance of Amendment Nos. 136 and 41 Regarding the Automatic Transfer from a Unit Service Station Transformer to a Common Station Service Transformer ML20156A0182020-08-10010 August 2020 Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve ML20076A1942020-04-30030 April 2020 Issuance of Amendment Nos. 134 and 38 Regarding Adopting the Title 10 CFR Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants ML20057E2422020-03-30030 March 2020 Issuance of Amendment Nos. 133 and 37 Regarding Changes to Technical Specifications Pertaining to Diesel Generator Start Instrumentation (EPID-L-2020-LLA-0003) 2024-07-15
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 October 1, 2015 SUBJECT: WATTS BAR NUCLEAR PLANT, UNIT 2 -RELIEF FROM THE REQUIREMENTS OF THE ASME CODE FOR THE FIRST 10-YEAR INTERVAL OF THE STEAM GENERATOR INSERVICE INSPECTION (TAC NO. MF6474) Dear Mr. Shea: By letter dated July 10, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15196A455), as supplemented by letters dated September 4, 2015, and September 23, 2015 (ADAMS Accession Nos. ML 15271A140 and ML 15266A457, respectively), Tennessee Valley Authority (the licensee) requested relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, regarding the preservice inspection program for Watts Bar Nuclear Plant (WBN), Unit 2. Specifically, the licensee submitted Request for Relief WBN-2/PSl-3 requesting relief from performing a volumetric examination of the Class 2 lower shell-to-cone weld SG-4B-5-2 of steam generator number 2, due to inaccessibility caused by the upper steam generator support bracket. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed Request for Relief WBN-2/PSl-3 and concludes, as set forth in the enclosed safety evaluation, that granting relief 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. The NRC staff has determined that the volumetric inspection of Class 2 lower shell-to-cone weld SG-4B-5-2 of steam generator number 2 is impractical because it cannot be performed with the current design of WBN, Unit 2.
J. Shea -2 -If you have any questions, please contact Mr. Justin Poole at (301) 415-2048 or Justin.Poole@nrc.gov. Docket No. 50-391 Enclosure: Safety Evaluation cc w/enclosure: Distribution via Listserv Sincerely, /l -----::;; \ .. z/c:l" ( $(i8 aUichocho, Chief / Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST REGARDING THE PRESERVICE INSPECTION PROGRAM 1.0 INTRODUCTION FOR A STEAM GENERA TOR WELD TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-391 By letter dated July 10, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15196A455), as supplemented by letters dated September 4, 2015, and September 23, 2015 (ADAMS Accession Nos. ML 15271A140 and ML 15266A457, respectively), Tennessee Valley Authority (TVA, the licensee) requested relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, regarding the preservice inspection program for Watts Bar Nuclear Plant (WBN), Unit 2. Specifically, the licensee submitted Request for Relief WBN-2/PSl-3 requesting relief from performing a volumetric examination of the Class 2 lower shell-to-cone weld SG-4B-5-2 of steam generator (SG) number 2 due to inaccessibility caused by the SG upper lateral restraint support. 2.0 REGULATORY EVALUATION WBN, Unit 2, received its construction permit in 1973. For plants having a construction permit between January 1, 1971, and July 1, 1974, Title 10 of the Code of Federal Regulations (1 O CFR) Section 50.55a(g)(2) requires that their ASME Code Class 1 and 2 components, including supports: ... must be designed and be provided with access to enable the performance of inservice examination of such components (including supports) and must meet the preservice examination requirements set forth in editions and addenda of Section Ill or Section XI of the ASME Code incorporated by reference ... in effect 6 months before the date of issuance of the construction permit. lnservice and preservice examinations performed in accordance with Section XI of the ASME Code and applicable addenda are a way to detect anomaly and degradation indications so that structural integrity of these components can be maintained.
-2 -The ASME Code,Section XI, IWC-2200, specifies requirements for ASME Code, Class 2, components for the preservice examination, and the detailed inspection requirements in Table IWC-2500-1 apply to both preservice and inservice examinations. If an inservice examination requirement for a component cannot be met, licensees may seek relief from the ASME Code requirements pursuant to 10 CFR 50.55a(g)(5)(iii) for impracticality, or if appropriate, propose an alternative pursuant to 10 CFR 50.55a(z) for acceptable level of quality and safety or for hardship. The detailed preservice inspection requirements are contained in Table IWC-2500-1 of the ASME Code,Section XI, which also governs inservice inspection. As a result, the regulations in 10 CFR 50.55a(g)(5) and (6) that cover licensee impracticality determinations apply to both preservice and inservice inspections. In accordance with 10 CFR 50.55a(g)(5)(iii), determination of impracticality must be based on the demonstrated limitations experienced when attempting to comply with the ASME Code requirements for the inspection. Pursuant to 10 CFR 50.55a(g)(6), the Commission may grant relief and may impose such alternative requirements as it determines are authorized by law, will not endanger life or property or the common defense and security, and are 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 ASME Code of record for WBN, Unit 2, for the preservice inspection is the 2001 Edition of the ASME Code,Section XI, with 2003 Addenda. 3.0 TECHNICAL EVALUATION 3.1 The Licensee's Request for Relief The licensee requests relief from the ASME Code,Section XI, Item No. C1.10, of Table IWC-2500-1. Note 1 of Table IWC-2500-1 requires the volumetric inspection to be 100 percent of the weld length. Note 3 of Table IWC-2500-1 allows one weld to be inspected for multiple vessels of similar design, size and service, such as SGs. For the ASME Code,Section XI, volumetric examination for WBN, Unit 2, TVA examined weld SG-48-5-2 on SG number 2 only. Due to the SG upper lateral restraint support interference, 76 percent of the weld volume was not examined. The licensee achieved approximately 24 percent weld volume examination coverage. The same welds on the other three SGs were not examined, since they are of similar design and configuration. The licensee states that both the original WBN, Unit 1, SGs and the existing WBN, Unit 2, SGs were fabricated at approximately the same time in 1975 and contain the same weld configurations. These welds were examined volumetrically by radiography during fabrication in accordance with ASME Code, Section Ill, requirements. The licensee requests a one-time relief to address the requirements of the WBN, Unit 2, preservice inspection program.
-3 -3.2 NRC Staff Evaluation The ASME Code,Section XI, Table IWC-2500-1, requires 100 percent volumetric examination of SG circumferential shell welds (listed as Item No. C1.10 in the table). The licensee was unable to obtain the volumetric code coverage of 100 percent of the subject welds due to the upper lateral restraint support interference. The licensee provided further information in its September 4, 2015, supplement that the SG upper lateral support ring configuration presents an annular gap of approximately 1.5 inches between the cone outer surface and the interior of the lateral support ring, restricting access to the weld. As a result, access to the examination volume is limited from only the conical side of the weld joint, and axial ultrasonic testing (UT) scans can only be conducted from the conical side of the joint. Additionally, circumferential scans from the conical shell did not provide for coverage of the required volume. In the July 10, 2015, submittal, the licensee stated that a total of 24 percent volumetric examination coverage was achieved. In the September 4, 2015, supplement, the licensee stated that the 24 percent coverage was achieved from one axial scan direction only, but the ASME Code required four scan directions (two opposing axial and two circumferential directions). When the four scan directions are considered, the total examination volume achieved is 6.57 percent. The licensee further stated that, "increased coverage can only be realized by the removal or repositioning of the upper lateral supporting ring, which is not practical." The large size, weight, and design of the upper lateral supporting ring assembly demonstrates to the NRC staff that removal or repositioning of the ring is impractical and would be a burden on the licensee. However, granting relief pursuant to 10 CFR 50.55a(6)(i) relies on the determination that reasonable assurance of structural integrity of the subject weld is maintained. To demonstrate the quality of weld SG-48-5-2 outside of the inspection coverage area by using the limited UT inspection results, the licensee stated in the September 23, 2015, supplement that no recordable indications were observed during UT inspection of W8N, Unit 2, weld SG-48-5-2, and all three inspection reports of W8N, Unit 1, found no apparent discrepancies during their examinations of similar welds. The results demonstrate that the burden associated with performing UT examination of additional weld volume would likely result in no recordable indications and, therefore, would not significantly contribute to the determination that reasonable assurance of the structural integrity of weld SG-48-5-2 is maintained. Additionally, the licensee provided further information that the structural integrity of the subject weld is supported by the industry operating experience (OE) with circumferential shell welds of SGs of the same vintage as the W8N, Unit 2, that indicated no known inservice failures exist of the same SG weld. Additionally, the SG circumferential shell welds were volumetrically examined by radiograph during fabrication in accordance with ASME Code, Section 111, requirements, and both the original W8N, Unit 1, SGs and the existing W8N, Unit 2, SGs were fabricated at approximately the same time in 1975. The successful operation of the W8N, Unit 1, SGs for multiple refueling cycles supports (1) the quality of the SG circumferential shell welds and (2) the effectiveness of the fabrication facility's radiograph examination for detecting defects in these welds. Therefore, reliance on the field UT examination results to determine SG circumferential shell weld quality is significantly reduced.
-4 -Finally, the SGs are subject to the hydrostatic pressure test of the ASME Code,Section XI, which provides additional opportunities to detect weld flaws that could result in leakage from the SG shell. Based on (1) the limited UT inspection results for WBN, Units 1 and 2, showing no weld flaw indications; (2) OE from industry and WBN, Unit 1, showing no inservice safety issues caused by detected flaws in the subject welds; (3) examinations by radiograph during fabrication in accordance with ASME Code, Section Ill, requirements; and (4) the required hydrostatic pressure test of the ASME Code,Section XI, the NRC staff finds that reasonable assurance of structural integrity of the SG circumferential shell welds has been maintained. 4.0 CONCLUSION The NRC staff reviewed the licensee's submittals and concludes that complying with the specified ASME Code requirements for the SG circumferential shell welds described in Section 3.1 above is impractical. Furthermore, the NRC staff concludes, based on the four reasons summarized above, that there is reasonable assurance of structural integrity of the subject SG circumferential shell welds. As set forth above, the NRC staff 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 on the facility. Therefore, the NRC staff grants relief for the subject examination of the components contained in Request for Relief WBN-2/PSl-3 for the preservice inspection. 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 lnservice Inspector. Principal Contributor: S. Sheng Date:October 1 , 2015 J. Shea -2 -If you have any questions, please contact Mr. Justin Poole at (301) 415-2048 or J us tin. Poole@nrc.gov. Sincerely, IRA/ Jessie F. Quichocho, Chief Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 Enclosure: Safety Evaluation cc w/enclosure: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNrrDeEvib Resource LPWB R/F RidsACRS_MailCTR Resource SSheng, NRR RidsRgn2MailCenter Resource RidsNrrlLABClayton Resource RidsNrrPMWattsBar2 Resource RidsNrrDorllp_WB Resource ADAMS A ccess1on N o.: ML 15273A126 *b 1y e-ma1 OFFICE DORL/LPLIV-2/PM DORL/LPWB/PM DORL/LPWB/LA DE/EVIB/BC* (LRonewicz for) NAME MOrenak JPoole BClayton JMcHale DATE 10/01/2015 10/01/2015 10/01/2015 9/24/2015 OFFICIAL RECORD COPY DORL/LPWB/BC JQuichocho 10/01/2015