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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 April 5, 2016 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 -ALTERNATIVE TO THE PRESERVICE EXAMINATION REQUIREMENTS OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS OPERATION AND MAINTENANCE CODE FOR SNUBBERS (WBN-2/PSl-4) (CAC NO. MF7447)
Dear Mr. Shea:
By letter dated March 11, 2016, as supplemented by letter dated March 25, 2016 (Agencywide Documents Access and Management System Accession Nos. ML16054A586 and ML16089A163, respectively), Tennessee Valley Authority (TVA) submitted alternative request WBN-2/PSl-4 to the U.S. Nuclear Regulatory Commission (NRC). TVA is proposing an alternative to the requirements of the American Society of Mechanical Engineers (ASME)
Operation and Maintenance (OM) Code, 2001 Edition through 2003 Addenda, Subsection ISTD, Section ISTD-4110(d), "Preservice Examination Requirements," for the Class 2 steam generator snubbers at the Watts Bar Nuclear Plant, Unit 2 (WBN2). TVA is requesting that the inservice examination requirements of ASME OM Code, Subsection ISTD-4233 for fluid level be applied in lieu of the preservice examination requirements of OM Code, Section ISTD-4110(d) during the preservice period and up to the start of the first 10-year inservice inspection (ISi) interval for the snubbers at WBN2.
The NRC staff has determined that the proposed alternative request WBN-2/PSl-4 for WBN2, provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that TVA has adequately addressed all of the regulatory requirements set forth in Title 10, Code of Federal Regulations (10 CFR), Part 50, Section 55a(z)(1) for this alternative. Therefore, pursuant to 10 CFR 50.55a(z)(1 ), the NRC staff authorizes alternative request WBN-2/PSl-4 for WBN2 for the preservice period and up to the start of the first 10-year ISi interval for the snubbers at WBN2.
In its letter dated March 11, 2016, TVA included a regulatory commitment to periodically monitor the fluid level of the four SG snubber reservoirs during the first 10-year ISi interval until the first refueling outage. The frequency of the reservoir fluid level monitoring may be adjusted based on the trend of level change observed in the reservoirs. The NRC staff concludes that reasonable controls for the implementation and subsequent evaluation of proposed changes pertaining to the above regulatory commitment are best provided by the licensee's administrative processes, including its commitment management program. The above regulatory commitment does not warrant the creation of any regulatory requirements (i.e., items requiring prior NRC approval of subsequent changes).
J. Shea All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable.
If you have any questions, please contact the Project Manager, Robert Schaaf at 301-415-6020.
Sincerely, Benjamin G. Beasley, Branch Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION STEAM GENERATOR SNUBBER ALTERNATIVE REQUEST NO. WBN-2/PSl-4 RELATED TO THE STEAM GENERATOR SNUBBER PRESERVICE INSPECTION TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT. UNIT 2 DOCKET NUMBER 50-391
1.0 INTRODUCTION
By letter dated March 11, 2016 (Agencywide Document Access and Management System (ADAMS) Accession No. ML16074A274), as supplemented by letter dated March 25, 2016 (ADAMS Accession No. ML16089A163), Tennessee Valley Authority (TVA, the licensee),
submitted alternative relief request WBN-2/PSl-4 for the Watts Bar Nuclear Plant Unit 2 (WBN2), to the U. S. Nuclear Regulatory Commission (NRC). The licensee proposed an alternative to the preservice inspection (PSI) requirements of the 2001 Edition through 2003 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for the PSI of steam generator (SG) snubbers at WBN2.
Specifically, TVA is proposing an alternative to the requirements of ASME OM Code, 2001 Edition through 2003 Addenda, Subsection ISTD, Section ISTD-4110(d), "Preservice Examination Requirements," for the Class 2 SG snubbers at the WBN2. TVA is requesting that the inservice examination requirements of ASME OM Code, Subsection ISTD-4233 for fluid level be applied, in lieu of the preservice examination requirements of OM Code, Section ISTD-4110( d) during the preservice period and up to the start of the first 10-year inservice inspection (ISi) interval for the snubbers at WBN2. The licensee requested to use the proposed alternative in WBN-2/PSl-4, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 55a(z)(1 ), on the basis that the alternative provides acceptable level of quality and safety. *
2.0 REGULATORY EVALUATION
Section 55a(g)(4) of 10 CFR Part 50 requires that: "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) that are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of editions and addenda of the ASME B&PV [Boiler and Pressure Vessel] Code (or ASME
OM Code for snubber examination and testing) that become effective subsequent to editions specified in paragraphs (g)(2) and (g)(3) of this section and that are incorporated by reference in paragraphs (a)(1 )(ii) or (iv) for snubber examination and testing of this section [1 O CFR 50.55a],
to the extent practical within the limitations of design, geometry and materials of construction of the components," except where alternatives have been authorized pursuant to paragraphs 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2).
In proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety (10 CFR 50.55a(z)(1 )) or compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)). Section 50.55a allows the NRC to authorize alternatives and to grant relief from ASME Code requirements upon making the necessary findings.
Section 55a(b)(3)(v) of 10 CFR Part 50 allows the use of ASME OM Code, Subsection ISTD in lieu of ASME Section XI for preservice and inservice examination and testing of snubbers.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to authorize the alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
The applicable ASME B&PV Code Section XI for the WBN2 preservice snubber inspection is the 2001 Edition through 2003 Addenda. In lieu of the ASME Section XI for WBN2, TVA is using the ASME OM Code for the snubber preservice examination as allowed by 10 CFR 50.55a(b)(v). The applicable ASME OM Code for the WBN2 preservice snubber examination is the 2001 Edition through 2003 Addenda.
The licensee stated that this alternative request is applicable for the WBN2 preservice test period and up to start of the first 10-year ISi program for snubbers.
3.1 Steam Generator Snubber Relief Request WNB-2/PSl-4 Applicable Code Requirements ASME OM Code, paragraph ISTD-4110, "Preserrvice Examination Requirements," states, in part, that a preservice examination shall be performed on all snubbers during initial plant startup.
ASME OM Code, paragraph ISTD-4110(d), "Preservice Examination Requirements," states that if applicable, fluid is at recommended level, and fluid is not leaking from the snubber system.
ASME OM Code, paragraph, ISTD-4140, "Preservice Examination Corrective Action," states that snubbers that are installed incorrectly or otherwise fail to meet the requirements of ISTD-4110 shall be installed correctly, adjusted, repaired, or replaced.
Components for Which Relief is Requested
The licensee proposed an alternative from the ASME OM Code preservice examination requirements of paragraph ISTD-4110(d) for the following SG snubbers:
Table-1, Steam Generator Snubbers in Relief Request WBN-2/PSl-4 Snubber ID Snubber Description Type Manufacturer Model 2-SNUB-001-2SG1A Steam Generator# 1 Snubber A Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG1 B Steam Generator# 1 Snubber B Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG1C Steam Generator# 1 Snubber C Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG1 D Steam Generator# 1 Snubber D Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG1 E Steam Generator# 1 Snubber E Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG2A Steam Generator# 2 Snubber A Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG2B Steam Generator# 2 Snubber B Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG2C Steam Generator# 2 Snubber C Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG2D Steam Generator# 2 Snubber D Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG2E Steam Generator# 2 Snubber E Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG3A Steam Generator# 3 Snubber A Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG3B Steam Generator# 3 Snubber B Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG3C Steam Generator# 3 Snubber C Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG3D Steam Generator# 3 Snubber D Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG3E Steam Generator# 3 Snubber E Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG4A Steam Generator# 4 Snubber A Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG4B Steam Generator# 4 Snubber B Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG4C Steam Generator# 4 Snubber C Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG4D Steam Generator# 4 Snubber D Hydraulic Curtiss WriahUPHS PD14860 2-SNUB-001-2SG4E Steam Generator# 4 Snubber E Hydraulic Curtiss WriahUPHS PD14860 Licensee's Reason for Alternative Request Twenty, 12-inch bore, Curtiss Wright/Paul Munroe Hydraulics snubbers are utilized at WBN2 for dynamic restraint of the SGs. Five snubbers are installed on each SG and work together to support the SG during a seismic event. The snubbers are located inside the SG enclosures in an area where there are no permanent platforms and radiological conditions limit personnel access during normal power operation. There is one fluid reservoir for the 5 snubbers of each SG. The four fluid reservoirs are located in upper containment on the outside of the SG enclosures and are, thus, accessible during normal power operations.
The licensee states that during the preservice examination of the 20 SG snubbers, TVA identified evidence of leakage on 5 of the snubbers (i.e., 2-SNUB-001-2SG1B, -2SG1D, -
2SG1 E, -2SG4A, and -2SG4C). The licensee performed troubleshooting on these five snubbers with the help of an outside vendor and was successful at eliminating the leakage on two of the snubbers (i.e., 2-SNUB-001-2SG1 B, and -2SG4A). However, three snubbers (i.e.,
2-SNUB-001-2SG1 D, -2SG1 E, and -2SG4C) continue to exhibit minor leakage. Further troubleshooting of the three snubbers included wiping off the leakage, subsequent re-examination of the snubbers, and monitoring of the associated hydraulic reservoir levels.
TVA has stated that any leakage observed at present has been minor. For example, the worst-case snubber exhibits approximately 10 drops per day or less. The vendor has determined the type of leakage exhibited by the remaining three WBN2 SG snubbers is not abnormal under
current plant conditions (cold) and the snubber seal design is such that the seating characteristics should improve as the plant transitions into normal operating conditions.
The licensee proposes an alternative to the requirements of ISTD-4110(d) so that during the PSI period, TVA will not need to replace the SG snubbers that have been identified with minor leaks.
Licensee's Proposed Alternative The licensee proposes to perform periodic monitoring of fluid levels in the four SG snubber reservoirs and to use inservice examination requirements of the ASME OM Code, ISTD-4233 for fluid level in lieu of the preservice examination requirements of ISTD-4110(d) during the WBN2 preservice test period and up to start of the first 10-year ISi interval program for snubbers at WBN2. In the letter dated March 25, 2016, the licensee states that level monitoring will be performed weekly until WBN2 reaches normal operating pressure and temperature and sufficient level data points have been collected to establish a trend. The level monitoring frequency will be adjusted commensurate with the reservoir level trend.
The licensee also states that if reservoir fluid level cannot be maintained above the required minimum level, then the associated snubbers will be identified as unacceptable and the requirements of ISTD-4270, "lnservice Examination Failure Evaluation," and ISTD-4280, "lnservice Examination Corrective Action," will be applied. In addition, any time the reservoir level is observed to be less than the required minimum level, the condition will be entered into the TVA corrective action program (CAP) for operability determination and corrective action.
3.2 NRC Staff Evaluation The ASME OM Code, ISTD-4110(d) requires that during the preservice examination of snubbers, if applicable, fluid is at recommended level, and fluid is not leaking from the snubber system. ASME OM Code, ISTD-4140, requires that during preservice examination if snubbers that are installed incorrectly or otherwise fail to meet the requirements of ISTD-411 O shall be installed correctly, adjusted, repaired, or replaced. Therefore, the ASME OM Code requires that leaking snubbers be corrected, repaired or replaced.
As described above, during preservice examination, the licensee discovered that 5 of the 20 SG snubbers have minor fluid leakage, which was documented in the TVA CAP. The licensee was successful at eliminating leakage of 2 of the 5 snubbers, but 3 snubbers continue to exhibit minor leakage. The snubber vendor has determined that the type of leakage exhibited by the WBN2 SG snubbers is not abnormal under cold shutdown conditions and the snubber seal design is such that the sealing characteristics should improve as the plant transition into normal conditions. As such, leaking snubbers will perform their required safety function under design basis conditions as long as they are filled with fluid.
In order to maintain the SG snubbers filled with fluid, the licensee proposes:
- 1. Periodically monitoring of fluid level of all the four reservoirs during the WBN2 preservice test period up to start of the first 10-year inservice inspection interval at WBN2. The initial level monitoring will be performed weekly until WBN2 reaches normal operating
pressure and temperature and sufficient level data points have been collected to establish a trend. The fluid level monitoring frequency will be adjusted commensurate with the reservoir level trend.
- 2. Performing the evaluation and corrective action requirements of the ASME OM Code, ISTD-4270 and ISTD-4280, if the reservoir level cannot be maintained at the minimum required fluid level. If at any time the reservoir level is observed to be less than the required minimum level, the condition will be entered into TVA CAP for operability determination and corrective action.
The NRC staff has reviewed the licensee's proposed alternative described above and has determined that periodic monitoring of the fluid level of all the four SG snubber reservoirs (i.e.,
weekly during the PSI period up to start of the first 10-year ISi interval, and adjusted based on the trend of fluid level observed in the reservoirs) will provide adequate assurance that the SG snubber fluid level will be maintained within the manufacturer's recommendation. By maintaining the snubbers' fluid level, the operability of the snubbers will be maintained. Based on the above, the NRC staff has determined that the snubbers' operability will be maintained during the preservice period and up to the start of the first 10-year ISi program. Therefore, the NRC staff finds that the proposed alternative is acceptable.
4.0 CONCLUSION
Based on the above evaluation, the NRC staff concludes that the licensee's proposed alternative is authorized pursuant to 10 CFR 50.55a(z)(1) based on the alternative providing an acceptable level of quality and safety. The licensee's proposed alternative is consistent with the objective of inservice testing which is to determine degradation in safety-related components and provides reasonable assurance of operational readiness. Accordingly, the proposed alternative is authorized for the preservice period and up to start of the first 10-year ISi interval for snubbers at WBN2.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable.
Principle Contributor: Gurjendra S. Bedi, NRR
J.Shea All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable.
If you have any questions, please contact the Project Manager, Robert Schaaf at 301-415-6020.
Sincerely,
/RAJ Benjamin G. Beasley, Branch Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ DISTRIBUTION:
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