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MONTHYEARML12222A1442012-08-0707 August 2012 Request to Use America Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Code Cases N-520-4 and N-520-5, Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not. Project stage: Request ML12279A1992012-09-26026 September 2012 OL - Acceptance of Requested Licensing Action Regarding Request to Use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Code Cases N-520-4 and N-520-5 Project stage: Acceptance Review ML12291A8862012-10-23023 October 2012 Request to Use ASME Code Cases N-520-4 and N-520-5 Regarding Alternative Rules for Renewal of Active or Expired N-Type Certificates Project stage: Other 2012-08-07
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Category:Letter
MONTHYEARML23319A2452024-01-29029 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 CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) 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 IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation 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 IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 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 ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 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 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 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 IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) 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 IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 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) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] Category:Safety Evaluation
MONTHYEARML23319A2452024-01-29029 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 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 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 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) ML20028F7332020-02-28028 February 2020 Issuance of Amendment Nos. 132 and 36 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 ML20024F8352020-02-24024 February 2020 Issuance of Amendment No. 35 Regarding One-Time Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML19336C5192019-12-10010 December 2019 Issuance of Amendment Nos. 131 and 34 Regarding Correction to Unbalanced Voltage Relay Instrumentation Values 2024-01-29
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 October 23, 2012 Mr. Michael D. Skaggs Senior Vice President Nuclear Construction Tennessee Valley Authority Lookout Place 6A 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 -APPROVAL OF REQUEST TO USE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE CASES N-520-4 AND N-520-5, "ALTERNATIVE RULES FOR RENEWAL OF ACTIVE OR EXPIRED N-TYPE CERTIFICATES FOR PLANTS NOT IN ACTIVE CONSTRUCTION, SECTION III, DIVISION 1" (TAC NO. ME9299)
Dear Mr. Skaggs:
By letter dated August 7, 2012, Tennessee Valley Authority (TVA) submitted a request for the use of alternatives to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code)Section III requirements at the Watts Bar Nuclear Plant (WBN),
Unit 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i), TVA requested to use the provisions of ASME Code Cases N-520-4 and N-520-5, "Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction,Section III, Division 1" on the basis that it provides an acceptable level of quality and safety.
Based on the enclosed safety evaluation, the NRC staff concludes that ASME Code Cases N-520-4 and N-520-5 provide an acceptable level of quality and safety to the requirements of Section NCA-8100, "Authorization to Perform Code Activities," of Section nI, Division 1 of the ASME Code. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(i), and is in compliance with the ASME Code's requirements. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative is authorized for WBN Unit 2, effective immediately and will continue until such time as the WBN Unit 2 N-3 Code Data Report is completed and signed by TVA, as the Owner; or until such time as the ASME Code Case is published in a future version of Regulatory Guide 1.84 and incorporated by reference in 10 CFR 50.55a(b), whichever is sooner. At that time, if TVA wishes to continue to use the Code Case, it may do so provided that all conditions, limitations and modifications regarding the use of the Code Case. if any, are met.
M. Skaggs
- 2 If you have any questions, please contact the Project Manager, Justin Poole at 301-415- 2048 or via e-mail at Justin.Poole@nrc.gov.
Sincerely, e ~f!!::i!ef lant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Safety Evaluation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO USE THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURES VESSEL CODE CASES N-250-4 AND N-520-5.
"ALTERNATIVE RULES FOR RENEWAL OF ACTIVE OR EXPIRED N-TYPE CERTIFICATES FOR PLANTS NOT IN ACTIVE CONSTRUCTION. SECTION III, DIVISION 1" WATTS BAR UNIT 2 DOCKET NO. 50-391
1.0 INTRODUCTION
By letter dated August 7,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12222A144) (Reference 1), Tennessee Valley Authority (TVA).
the applicant. requested approval for the use of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (the Code) Code Cases N-520-4 and N-520-5, "Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction,Section III, Division 1," at Watts Bar Nuclear Plant (WBN) Unit 2. These Code Cases correspond to Revision 4 and Revision 5 of Code Case N-520, respectively.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(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. The use of the Code Cases would allow TVA to transfer the responsibility for completion of partially installed piping systems and components to a new holder of an N-type Certificate (Certificate Holder). who is designated as such by the ASME.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a, systems and components of nuclear power reactors must meet the requirements of the Code. The Code requires that construction activities associated with ASME Code-class systems and components shall be conducted in accordance with the requirements of Section III, Division 1. Specifically, Subarticle NCA-81 00. "Authorization to Perform Code Activities," of Section III, Division 1, of the Code details the general provisions associated with Certificate Holders and the performance of ASME Code work by Certificate Holders.
The WBN Unit 2 ASME Code class piping systems and components were designed and constructed to meet the 1971 edition with addenda through the Summer 1973 Addenda of Section III of the Code; this is the construction Code of Record for WBN Unit 2. The applicant's
-2 ASME Section III Quality Assurance Manual, in effect at the time WBN Unit 2 construction activities were suspended, was written to meet the requirements of the 1980 edition through the Winter 1981 addenda of the Code. In accordance with 10 CFR SO.SSa(a)(3), alternatives to the requirements of select portions of 10 CFR SO.SSa may be used, when authorized by the U.S.
Nuclear Regulatory Commission (NRC), if the applicant demonstrates that the proposed alternatiVes would provide an acceptable level of quality and safety (10 CFR SO.SSa(a)(3)(i>>.
The TVA submitted the subject request for the NRC staff's review and approval to use alternative Code Cases under the provisions of 10 CFR SO.SSa(a)(3)(i). Specifically, TVA has requested NRC authorization of an alternative to the requirements of Section III of the Code by requesting the use of Code Case N-S20-4 and Code Case N-S20-S, which would permit TVA to transfer responsibility for partially installed material and associated documentation to an active Certificate Holder. This would allow the active Certificate Holder to complete work associated with partially installed piping and components at WBN Unit 2.
3.0 TECHNICAL EVALUATION
3.1 The Applicant's Requesting for Alternative 3.1.1 Background Construction activities were halted on a number of nuclear power plants in the late 1970s and 1980s and this interrupted Code activities. As a result, Code Case N-S20 was developed and revised (Code Case N-S20-1) to provide guidance on what a Certificate Holder had to do to document and certify the work performed. These cases considered the situation where the Certificate Holder had maintained its Certificate. Under these two Code Cases, the N-type Certificate could be renewed at the site without a survey.
In its letter dated February 1, 2008 (Reference 2), TVA requested NRC approval to use ASME Code Case N-S20-2. The NRC subsequently granted approval for the use of Code Case N-S20-2 by letter dated October 2,2008 (Reference 3). The applicant's N-type Certificate for WBN Unit 2 expired in October 1996. The Code Case was used as part of the completion of construction activities associated with ASME Section III systems and components of WBN Unit 2. The Code Case allowed the applicant to obtain a temporary Certificate of Authorization from ASME to begin transferring documentation of the partially completed ASME Section III systems and components to the jurisdiction of a subcontractor that is an ASME Section III N-type Certificate Holder. The subcontractor will complete the construction of the WBN Unit 2 systems and complete the associated N-S Code Data Reports to certify that the required portions of the plant were constructed in accordance with Section '" of the Code and allow the applicant to document completion of the plant as part of the Owner'sSection III requirements.
An N-S Code Data Report is a Certificate Holder's documentation for installation or shop assembly of a nuclear power plant's components, supports, or appurtenances. The N-S Code Data Reports were not completed on most of the WBN Unit 2 systems because construction activities were halted before the facility's completion. Code Case N-S20-2 allowed the start of partially completed work to be properly documented through the issuance of "Partial N-S Code Data Reports," which are then transferred to the TVA subcontractor N-type Certificate Holder's jurisdiction for final completion of the documentation. TVA was not authorized to perform any physical work or repairs under the temporary Certificate of Authorization.
- 3 By letter dated June 25,2010 (Reference 4), TVA submitted a request for NRC approval to use Code Case N-520-3. Code Case N-520-3 included only a minor revision from the previous version of the Code Case (N-520-2). This revision permitted the extension of a temporary Certificate of Authorization for an additional year to complete and transfer documentation of the partially completed ASME Section III systems and components to the jurisdiction of a subcontractor who is an ASME Section III N-Certificate holder. By letter dated September 29, 2010 (Reference 5), the NRC approved TVA's request to use Code Case N-520-3 as an alternative to the requirements of the Code, pursuant to 10 CFR 50.55a(a)(3)(i).
3.1.2 Applicant's Proposed Alternative Pursuant to 10 CFR 50.55a(a)(3)(i), TVA requested that the NRC staff approve the use of Code Cases N-520-4 and N-520-5. The NRC has not yet reviewed these two Code Cases nor approved their generic use by the industry through the usual process of incorporation into Regulatory Guide (RG) 1.84, "Design, Fabrication, and Materials Code Case Acceptability, ASME Section III," and incorporation into 10 CFR 50.55a. As such, the use of these Code Cases is reviewed on a case-by-case basis.
3.1.3 Applicant's Basis for Request for Alternative In its August 7,2012, submittal, TVA stated that the use of ASME Code Cases N-520-4 and N-S20-S provide an acceptable level of quality and safety for the required quality process of the construction of WBN Unit 2 to the rules and requirements of ASME Section III, pursuant to 10 CFR SO.SSa(a)(3)(i).
3.1.4 Description of the Proposed Alternative The NRC staff has previously reviewed and approved the use of the second and third revisions to Code Case N-520 at WBN Unit 2, as discussed previously. Revision 4 to Code Case N-S20 resulted in only administrative changes to the Code Case. Specifically, Revision 4 separated the requirements for active and expired N-type Certificate Holders into two separate sections, designated as "1 - Current N-type Certificates" and "2 - Expired N-Type Certificates."
Revision S to Code Case N-S20 was developed to address the issue of materials (pipe, elbows, tees, etc.), which had been partially installed by a Certificate Holder whose certificate expired prior to completion of work on the materials. The applicant notes that this revision was generated due to the lack of clarity in previous revisions of the Code Case regarding the transfer of partially installed material and supporting documentation to an active Certificate Holder. The resulting revision to the Code Case added the following provisions regarding the documentation of procurement and partial installation and subsequent transfer of partially installed material:
The responsibility for material and supporting documentation procured to the original Construction Code, during initial construction, may be transferred to the new Certificate Holder, provided the following requirements are met:
(1) The material is only for use to complete the construction of items originally included as part of expired Certificate Holder's scope.
-4 (2) The material is identified and traceable to a Certified Material Test Report and applicable procurement documentation (3) The transfer process shall be defined and controlled by the Certificate Holders, documented in their Quality Assurance manuals, and reviewed and verified by the Authorized Nuclear Inspection Supervisor.
The applicant points out in its August 7,2012, submittal that these provisions will be used for instrument and sample line materials which were procured and partially installed by the applicant. The Code Case provisions can only be applied to material which has fully traceable and appropriate ASME Section III, Division 1, documentation (i.e., Certified Material Test Reports (CMTRs>>. The applicant also notes that the new Certificate Holder completing installation of the partially installed material will ensure that the materials are still acceptable for use. If the partially installed materials are not acceptable, the material will be replaced.
3.2 NRC Staff Evaluation The NRC staff reviewed Revision 4 and Revision S of Code Case N-S20, the use of which the applicant has requested, to determine whether the changes made to the Code Case are acceptable with respect to whether the requested alternative provides an acceptable level of quality and safety. The NRC staff notes that the only distinction between Code Case N-S20-3, which has previously been approved by the NRC staff for use by the applicant, and Code Case N-S20-4 is an administrative change which separates the Code Case requirements for active and expired Certificate Holders. Given that this administrative change does not affect quality or safety in the use of the Code Case, the NRC staff finds the use of Code Case N-S20-4 acceptable.
The NRC staff also notes that the revisions to the Code Case that resulted in Code Case N-S20-S are consistent with the overall intent and purpose of the provisions for expired N-type Certificate Holders in previous revisions of the Code Case, which is the transfer of Code activities from expired Certificate Holders to active Certificate Holders. The NRC staff also notes that the provisions in Code Case N-S20-S can only be applied for material that has fully traceable and appropriate documentation (i.e., CMTRs). Additionally, the entire process is documented in the Quality Assurance manuals of the expired Certificate Holder and the new Certificate Holder and overseen by an Authorized Nuclear Inspection Supervisor. Combined, these provisions ensure that an adequate level of quality and safety will be maintained in the transfer of ownership of the partially installed material. Therefore, the NRC staff concludes that the use of Code Case N-S20-S by the applicant provides an acceptable level of quality and safety.
The NRC staff recognizes that the NRC actively participates in the ASME review and approval of Code Cases through its membership on Code committees. During its review, the NRC staff considered that through these Code committee activities, the NRC was provided a number of opportunities to review the requirements in Code Case N-S20 and apply any additional measures necessary to ensure that Code Case N-S20-S contained sufficient provisions for the transfer of partially installed materials and associated documentation to a new Certificate Holder, such that an adequate level of quality and safety are maintained through its use. These Code Cases were reviewed and approved by ASME. However, these Code Cases are not yet
- S referenced in RG 1.B4 for generic use. As such, the NRC must consider the use of these Code Cases on a case-by-case basis.
4.0 CONCLUSION
As set forth above, the NRC staff concludes that ASME Code Cases N-S20-4 and N-S20-S provide an acceptable level of quality and safety to the requirements of Section NCA-B100, "Authorization to Perform Code Activities," of Section III, Division 1 of the ASME Code.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR SO.SSa(a)(3)(i), and is in compliance with the ASME Code's requirements. Therefore, pursuant to 10 CFR SO.SSa(a)(3)(i), the proposed alternative is authorized for WBN Unit 2, effective immediately and will continue until such time as the WBN Unit 2 N-3 Code Data Report is completed and signed by TVA, as the Owner; or until such time as the ASME Code Case is published in a future version of RG 1.B4 and incorporated by reference in 10 CFR SO.SSa(b), whichever is sooner. At that time, if TVA wishes to continue to use the Code Case, it may do so provided that all conditions, limitations and modifications regarding the use of the Code Case, if any, are met.
S.O REFERENCES (1) Letter from R. A. Hruby, Jr., TVA, to NRC Document Control Desk, "Watts Bar Nuclear Plant (WBN) Unit 2 - Request to Use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Code Cases N-S20-4 and N-S20-S,
'Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction,Section III, Division 1,'" August 7, 2012. (ADAMS Accession No. ML12222A144)
(2) Letter from M. Bajestani, TVA, to NRC Document Control Desk, "Watts Bar Nuclear Plant (WBN) Unit 2 - Request to Use American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code, Code Case N-S20-2, 'Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants not in Active Construction,Section III, Division 1, '" dated February 1, 200B. (ADAMS Accession No. MLOB03701BS)
(3) Letter from L. Raghavan, NRC, to A. S. Bhatnagar, TVA, "Watts Bar Nuclear Plant, Unit 2 - Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certificates (TAC No. MDB314)," October 2, 200B. (ADAMS Accession No. MLOB2S60373)
(4) Letter from M. Bajestani, TVA, to NRC Document Control Desk, "Watts Bar Nuclear Plant (WBN) Unit 2 - Request to Use American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code, Code Case N-S20-3, 'Alternative Rules for Renewal of active or expired N-Type Certificates for Plants not in Active Construction,Section III, Division 1,'" dated June 2S, 2010. (ADAMS Accession No. ML101760222)
-6 (5) Letter from S. J. Campbell, NRC, to A. S. Bhatnagar, TVA, "Watts Bar Nuclear Plant, Unit 2 - Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certificates (TAC No. MD8314)," September 29,2010. (ADAMS Accession No. ML102700527)
Principal Contributor: William Jessup Date: October 23,2012
M. Skaggs -2 If you have any questions, please contact the Project Manager, Justin Poole at 301-415- 2048 or via e-mail at Justin.Poole@nrc.gov.
Sincerely, IRA!
Jessie F. Quichocho, Acting Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50~391
Enclosure:
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