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Category:Report
MONTHYEARWBL-24-047, Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program2024-09-25025 September 2024 Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program WBL-24-022, Cycle 5 Steam Generator Tube Inspection Report2024-05-16016 May 2024 Cycle 5 Steam Generator Tube Inspection Report WBL-24-007, Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program2024-03-0505 March 2024 Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program 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) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods 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 WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)2023-04-10010 April 2023 Revised Pressure and Temperature Limits Report (PTLR) CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche2023-03-20020 March 2023 Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-12-16016 December 2021 Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance .2021-12-0909 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-07-20020 July 2021 Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-21-040, Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-03-23023 March 2021 Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) ML21060A9132021-03-17017 March 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Watts Bar ISFSI CNL-21-011, Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-02-25025 February 2021 Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) WBL-21-006, Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-02-11011 February 2021 Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)2020-12-16016 December 2020 Revised Pressure and Temperature Limits Report (PTLR) CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program2020-04-16016 April 2020 Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2019-10-10010 October 2019 License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019 Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report L-19-026, Revised Pressure and Temperature Limits Report (PTLR)2019-04-0404 April 2019 Revised Pressure and Temperature Limits Report (PTLR) ML19039A0492019-02-0808 February 2019 Amd 1 to USAR Chapter 9 Auxiliary System NRC Additional Redactions ML19003A5692019-01-16016 January 2019 Review of the Fall 2017 Steam Generator Tube Inspection Report ML18242A0382018-08-30030 August 2018 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)2018-08-0101 August 2018 Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information2018-04-10010 April 2018 Seismic Probabilistic Risk Assessment Supplemental Information ML17356A2692017-12-20020 December 2017 Construction Lessons Learned Report ML17313A1282017-11-0909 November 2017 Revised Pressure and Temperature Limits Report (PTLR) CNL-17-134, Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations2017-10-13013 October 2017 Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations ML17272A0192017-09-29029 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17263A1162017-09-20020 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17209A5542017-07-28028 July 2017 Cycle 14 Steam Generator Tube Inspection Report CNL-17-050, Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index2017-05-30030 May 2017 Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index ML16215A1042016-08-0202 August 2016 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System Report ML16113A0202016-04-22022 April 2016 Submittal of Title 10, Code of Federal Regulations 50.59 Summary Report CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information2016-03-31031 March 2016 Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program2016-02-19019 February 2016 TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory CNL-15-204, Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit2015-09-21021 September 2015 Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report2015-07-31031 July 2015 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 32015-07-15015 July 2015 Individual Plant Examination of External Events (IPEEE) Report, Revision 3 CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information2015-07-0808 July 2015 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information CNL-15-097, Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-06-16016 June 2015 Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List CNL-15-039, Severe Accident Management Alternatives for Reactor Coolant Pump Seals2015-04-10010 April 2015 Severe Accident Management Alternatives for Reactor Coolant Pump Seals 2024-09-25
[Table view] Category:Technical
MONTHYEARWBL-24-047, Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program2024-09-25025 September 2024 Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program WBL-24-022, Cycle 5 Steam Generator Tube Inspection Report2024-05-16016 May 2024 Cycle 5 Steam Generator Tube Inspection Report 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) 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 WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)2023-04-10010 April 2023 Revised Pressure and Temperature Limits Report (PTLR) CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche2023-03-20020 March 2023 Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-12-16016 December 2021 Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance .2021-12-0909 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-07-20020 July 2021 Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-21-040, Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-03-23023 March 2021 Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) CNL-21-011, Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-02-25025 February 2021 Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) WBL-21-006, Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-02-11011 February 2021 Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)2020-12-16016 December 2020 Revised Pressure and Temperature Limits Report (PTLR) CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program2020-04-16016 April 2020 Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2019-10-10010 October 2019 License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019 Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report L-19-026, Revised Pressure and Temperature Limits Report (PTLR)2019-04-0404 April 2019 Revised Pressure and Temperature Limits Report (PTLR) ML19039A0492019-02-0808 February 2019 Amd 1 to USAR Chapter 9 Auxiliary System NRC Additional Redactions ML17356A2692017-12-20020 December 2017 Construction Lessons Learned Report CNL-17-134, Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations2017-10-13013 October 2017 Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations CNL-17-050, Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index2017-05-30030 May 2017 Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index CNL-15-204, Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit2015-09-21021 September 2015 Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report2015-07-31031 July 2015 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report CNL-15-097, Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-06-16016 June 2015 Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNL-15-039, Severe Accident Management Alternatives for Reactor Coolant Pump Seals2015-04-10010 April 2015 Severe Accident Management Alternatives for Reactor Coolant Pump Seals ML15030A5082015-01-30030 January 2015 Tritium Production Program, Updated Plans for Cycle 13 Operation and Updated Evaluation of the Radiological Impacts of Tritium Permeation Into the Reactor Coolant System ML14100A0392014-04-0202 April 2014 Submittal of Pre-Operational Test Instruction CNL-14-038, Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2014-03-31031 March 2014 Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML13338A6832013-11-26026 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Watts Bar Nuclear Plant, Units 1 and 2, TAC MF0950 and MF1177 ML13196A3762013-07-0909 July 2013 Submittal of Pre-op Test Instructions ML13206A0042013-06-24024 June 2013 Methodology for Evaluating the Potential for Multiple Dam Failures Due to Seismic Events ML13115A0362013-04-11011 April 2013 Engineering Information Record 51-9198783-000, Watts Bar WBN1C11 SG Inspection 180-Day Report ML13148A0142013-04-0404 April 2013 Preoperational Test, 2-PTI-068-13, Rev. 1, Shutdown from Outside the Main Control Room. ML13162A3102013-04-0303 April 2013 2-PTI-002-01, Rev 000, Condensate System. ML13081A0032013-03-13013 March 2013 Revised Watts Bar Nuclear Plant Unit 1/Unit 2 As-Designed Fire Protection Report. Part 2 of 2 ML13081A0022013-03-13013 March 2013 Revised Watts Bar Nuclear Plant Unit 1/Unit 2 As-Designed Fire Protection Report. Part 1 of 2 ML13162A3112013-02-25025 February 2013 2-PTI-026-01, Rev 000, High Pressure Fire Protection. ML13050A3982013-01-31031 January 2013 2-PTI-072-01, Rev 000, Containment Spray Pump Value Logic Test. ML13044A1142013-01-31031 January 2013 Multiple Spurious Operation Evaluation Report R1976-20-01, Dated January 2013, Revision 2 ML13162A3122012-11-16016 November 2012 2-PTI-003A-03, Rev 000, Main Feedwater System Functional Test. ML12298A0592012-10-18018 October 2012 Submittal of 2-PTI-099-05, Rev 0, Overpower Delta-T & Overtemperature Delta-T Turbine Runback. ML13050A3972012-08-20020 August 2012 2-PTI-068-04, Rev 000, Pressurizer Relief Tank. ML12236A1652012-07-19019 July 2012 Application to Revise Watts Bar Nuclear Plant (WBN) Unit 1 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-UFSAR-12-01) ML12215A3382012-02-29029 February 2012 Enclosure 2, WCAP-17309-NP, Rev. 1, Watts Bar, Unit 2 Evaluation for Tube Vibration Induced Fatigue ML12073A3922012-02-29029 February 2012 WNA-VR-00283-WBT-NP, Rev. 7, Nuclear Automation Watts Bar Unit 2 NSSS Completion Program I&C Projects Iv&V Summary Report for the Post Accident Monitoring System. Attachment 2 ML12073A2252012-02-28028 February 2012 Attachment 6, TVA Calculation WBPEVAR8807025, Revision 8, Bypassed and Inoperable Status Indication Logic Input Indications (Letter Item 4) ML12073A3592012-02-28028 February 2012 WBT-D-3769 Np, Common Q Pams Secure Development and Operational Environment Sser 23 Appendix Hh Action Item 98 Requests for Additional Information 2024-09-25
[Table view] |
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Enclosure 2 TVA Letter Dated December 3, 2010 Attachments Attachment 4 "Seismic Evaluation of Nuclear Instrumentation System Console 2-M-13 with Gammametrics Equipment for Watts Bar Unit 2,"
EQ-EV-39-WBT-NP, Revision 1, dated March 2009 1
Westinghouse Non-Proprietary Class 3
( Westinghouse S EIS MIC EVALUATION OF NUCLEAR INS TRUMENTATION S YS TEM CONS OLE 2-M-13 WITH GAMMAMETRICS EQUIPMENT FOR WATTS BAR UNIT 2 EQ-EV-39-WBT-NP Revision 1 March, 2009 File Code: WBT-149-NIS-13B Author: ElectronicallyApproved* Date: March 2009 J. J. Zhang, Senior Engineer RRAS/Equipment Qualification Reviewer ElectronicallyApproved* Date: March 2009 M. S. Norrell, Project Manager RRAS Watts Bar 2 Completion Project Reviewer: ElectronicallyApDroved* Date: March 2009 A. P. Drake, Program Manager RRAS Watts Bar 2 Completion Project Verifier: ElectronicallyApproved* Date: March 2009 J. E. Drexler, Principal Engineer RRAS/Equipment Qualification Approved: ElectronicallyApproved* Date: March 2009 G. G. Ament, Manager RRAS/ Equipment Qualification All Rights Reserved
© 2009 Westinghouse Electric Company, LLC Nuclear Services 1000 Westinghouse Drive New Stanton, PA 15672-9606
- ElectronicallyApproved Records Are Authenticatedin the Electronic Document Management System.
EQ-EV-39-W13T-NP, Revision I 1 of 22
RECORD OF REVISIONS Revision Description of Revision Author(s) Page(s)
Number 0 Original Issue J. J. Zhang 1 through 22 1 1. The number of the NIS Console J. J. Zhang 1 through 22 for Watts Bar Unit 2 is changed from 1-M-13 to 2-M-13 based on the email of the Project Manager Mr. Mike Norrell sending to Westinghouse Jie Zhang on March 13, 2009 (Reference 14).
Please note that the configuration of the NIS Console 2-M-13 is the same as the NIS Console 1-M-13 (Reference 14).
Therefore, the change of the NIS Console number does not impact the effectiveness of the calculation performed in this report.
- 2. Reference 14 is added and attached in Appendix A.
EQ-EV-39-WBT-NP, Revision I 2 of 22
TABLE OF CONTENTS Section Description Page RECORD OF REVISIONS 2 TABLE OF CONTENTS 3 LIST OF FIGURES 4 LIST OF TABLES 4
1.0 INTRODUCTION
5 2.0 EVALUATIONS 7 2.1 Seismic Qualification of NIS Console 7 2.2 Structural Integrity of Gammametrics Equipment Mounting 10 3.0
SUMMARY
OF RESULTS AND CONCLUSIONS 15
4.0 REFERENCES
16 APPENDIX A 17 APPENDIX B 22 EQ-EV-39-WBT-NP, Revision 1 3 of 22
LIST OF FIGURES Figure Description Page 1 Schematic of the NIS Console Modified at WAT (Reference 5) 5 2 Weight Zones of NIS Console Tested (Data from Reference 7) 7 3 WAT Modified NIS Console Weight Distribution (Data from 8 Reference 7) 4 WBT Modified NIS Console Weight Distribution 8 5 Top and Side Views of Gammametrics Intermediate Range 11 (Reference 9)
LIST OF TABLES Table Description Page 1 Comparison of Gammametrics Equipment for Watts Bar Unit 1 and 6 Unit 2 2 Peak Accelerations of WAT/WBT Specific IERS at NIS Console 10 (Reference 7) (5% Critical Damping)
I 4 of 22 EQ-EV-39-WBT-NP, Revision EQ-EV-39-WBT-NP, Revision 1 4 of 22
1.0 INTRODUCTION
At Watts Bar Unit 2 (WBT), the Gammametrics equipment is to be used to replace the Westinghouse Source Range and Intermediate Range drawers in the Westinghouse Nuclear Instrumentation System (NIS) console2-M-13. Also, two Shutdown Monitors are to be installed in the NIS console above the Source Range drawers. A similar modification had been conducted on the NIS console at Watts Bar Unit 1 (WAT). Westinghouse Letter WAT-D-9249 (Reference 1) dated April 3, 1993 indicated that this modification at WAT would not adversely impact the seismic qualification of the NIS console documented in WCAP-8021 (Reference 2) and WCAP-8830 (Reference 3). The report WCG-ACQ-0516 (Reference 4) demonstrated that the Gammametrics equipment installed using the existing Westinghouse Slide and Slide Brackets would maintain structural integrity when subjected to the plant specific Safe Shutdown Earthquake (SSE) event. Reference 4 documented that the four-bay NIS console 1-M-13 defined in Drawing ]a,b,c (Reference 5) were used and modified at WAT as shown in Figure 1.
a,c Figure 1 Schematic of the NIS Console Modified at WAT (Reference 5)
EQ-EV-39-WBT-NP, Revision 1 5 of 22
Tennessee Valley Authority (TVA) provided the following information in the response (WBT-TVA-0078 25401-011-TiA-GGG-00050-001/002) to Westinghouse letter WBT-TVA-0078 (Reference 6) about the modifications to the NIS console at WBT:
- 1. The NIS console for WAT is the same as the one for WBT.
Therefore, the NIS console defined in Drawing [ Ia.b,c (Reference 5) is to be installed at WBT with the modifications shown in Figure 1.
- 2. Gammametrics equipment used for WBT is different than the one used for WAT in terms of the weight and the height.
Table 1 Comparison of Gammametrics Equipment for Watts Bar Unit 1 and Unit 2 K 3. The drawer Slide for securing the Gammametrics equipment to the NIS console and the Slide Brackets at WBT are the same as those at WAT.
- 4. The same mounting screws and bolts are used to secure the Gammametrics equipment to the NIS console at WAT and WBT.
- 5. The shutdown monitors at WBT are identical to the ones at WAT.
- 6. The Amplified Response Spectra (ARS) applicable to the NIS console at WBT are the same as the applicable ARS at WAT.
The WAT/WBT ARS Required Response Spectra (RRS) at Elevation 755.5 feet in the Auxiliary-Control Building is applicable to the mounting location of the NIS console (Reference 4).
The seismic evaluation performed herein is to demonstrate that the use of the Gammametrics equipment at WBT will not invalidate the existing seismic qualification of the Westinghouse NIS console. Also, the Gammametrics equipment using the Westinghouse Slide and Slide Brackets will maintain structural integrity when subjected to WBT specific seismic events.
EQ-EV-39-WBT-NP, Revision 1 6 of 22
2.0 EVALUATIONS 2.1 Seismic Qualification of NIS Console The addition of Gammametrics equipment to the Westinghouse NIS console 1-M-13 at WAT was evaluated and documented in Westinghouse Letter WAT-D-9249 (Reference 1) and Westinghouse Calculation Note [ ]a,b,c (Reference 7). The total weight and three weight zones of the NIS console tested are shown in Figure 2, while Figure 3 shows the modified NIS console weight zone data for the WAT application from Reference 7. Table 1 identifies that the WBT Gammametrics Source and Intermediate Range drawers have different weights than the WAT modification. These weight differences result in the WBT modified NIS console weight distribution shown in Figure 4.
ax Figure 2 Weight Zones of NIS Console Tested (Data from Reference 7)
EQ-EV-39-WBT-NP, Revision 1 7 of 22
a,c Figure 3 WAT Modified NIS Console Weight Distribution (Data from Reference 7) axc Figure 4 WBT Modified NIS Console Weight Distribution-EQ-EV-39-WBT-NP, Revision 1 8 of 22
With respect to the original NIS console, the weight differences of the WBT NIS console modified are as follows, aub,c The weight zones and total weight of the WBT NIS console with Gammametrics equipment shift less than 10% with respect to the original NIS console. Therefore, the modification to the WBT NIS console is acceptable and will not discontinue the applicability of the seismic qualification of the NIS console documented in WCAP-8021 (Reference 2) and WCAP-8830 (Reference 3).
At WBT, the reduction of 72 lb in the weight of the modified NIS console would reduce the seismic loadings applied on the cabinet mounting. When subjected to the WAT/WBT specific seismic events, the mounting of the modified NIS console hence would have an increased safety margin.
EQ-EV-39-WBT-NP, Revision 1 9 of 22
2.2 Structural Integrity of Gammametrics Equipment Mounting The Gammametrics Source Range defined in Drawing [ ]abc (Reference 8) and the Gammametrics Intermediate Range defined in Drawing [ ]abc (Reference 9) have identical dimensions. Six (D)0.19" holes are specified in References 8 and 9 for the securing of drawers to the NIS console as shown in Figure 5 and Gammametrics Source Range and Intermediate Range are considered to be secured onto the NIS console with six 8-32 ASTM A307 (SAE Grade 2) screws. As documented on Page 11 of WCG-ACQ-0516 (Reference 4), Gammametrics equipment is mounted in the NIS console at WAT with six 8-32 screws (A307).
At WBT, the Gammametrics equipment is to be installed with the existing Westinghouse Slides and Slide Brackets. The structural adequacy of the screws securing the Gammametrics equipment to the Westinghouse Slides and Slide Brackets when subjected to the applicable WATIWBT ARS Set (B+C) SSE RRS was demonstrated in WCG-ACQ-0516 (Reference 4).
However, the evaluation documented in Reference 4 used the seismic accelerations associated with the floor response spectra rather than the amplified seismic accelerations within the NIS cabinet.
2.2.1 Seismic Loadings Westinghouse Calculation Note [ ]a,b,c (Reference 7) documented the In-Equipment Response Spectra (IERS) at the mounting locations of Shutdown Monitors, Source Range and Intermediate Range drawers in the NIS console with respect to the applicable WAT/WBT ARS Set (B+C) SSE RRS. Table 2 summarizes the peak accelerations of the IERS at 5% critical damping.
Table 2 Peak Accelerations of WATIWBT Specific IERS at NIS Console (Reference 7)_
(5% Critical Damping) ac As indicated on Page 15 of WCG-ACQ-0516 (Reference 4), it is not required to evaluate the structural adequacy of the Shutdown Monitors since the Shutdown Monitors maintained structural integrity during the seismic qualification testing documented in Reference 9.13 of Reference 4. The mounting adequacy of the Gammametrics Source Range and Intermediate Range is to be analyzed with the WAT/WBT specific IERS at their mounting locations.
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a~c Figure 5 Top and Side Views of Gammametrics Intermediate Range (Reference 9)
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2.2.2 Stresses The Gammametrics Intermediate Range weighs more than the Gammametrics Source Range and will be used for the calculation.
The equivalent static coefficient method with a static coefficient of 1.5 is used to calculate the K I seismic loading in accordance to IEEE Std 344-1987 (Reference 10). The maximum seismic loadings acting on-the Center of Gravity (CG) of the Gammametrics Intermediate Range are calculated as follows, ab,c Since the CG of the Intermediate Range is not at the center of the six screw pattern as shown in Figure 5, the seismic forces FF-B and Fv will produce the torsion on the screws as follows, The allowable stress of ASTM A307 (SAE Grade 2) is -,fl1owabe = 20ksi and roTlowblo = 1Ok-si per Table 1.5.2.1 on Page 5-24 of AISC Steel Manual (Reference 11). These allowable stress values are based on the nominal area of the unthreaded portion of the screw. Since the Size 8 screws in question are smaller than the sizes covered by ASTM A307, the tensile stress area of Size 8 screws is used in lieu of the nominal area. Per Table 4a on Page 1750 of Machinery's Handbook (Reference 12), the tensile stress area of a Size 8-32 screw is A, = 0.014ill .
A 1/3 increase in the allowable stress for the seismic loading permitted by Section 1.5.6 of AISC Steel Manual (Reference 11) is applied. Thus, combined shear and tension is addressed in the following in accordance with Section 1.6.3 and Table 1.6.3 on Pages 5-23 and 5-25 of AISC Steel Manual (Reference 11),
a,bc Revision I1 12 of 22 EQ-EV-39-WBT-NP, Revision 12 of 22
For conservatism, it is considered that only four screws at the corners of the screw pattern take the shear induced by the torsion. The polar moment of inertia of screw pattern is equal to The ja,b,c The maximum shear stress induced by the torsion is calculated as follows, a,b.,c The maximum total shear stress on a screw is a,b,c K
The maximum tensile stress on a screw is
]abc Based on the shear stress, the allowable tensile stress is determined as a,b,c Therefore, the Factors of Safety are a,b,c EQ-EV-39-WBT-NP, Revision 1 13 of 22
In addition, the front panels of the Gammametrics Intermediate Range and Source Range drawers are to be secured to the Westinghouse securing hardware defined in the Westinghouse Field Change Notice WBTM-10714 (Reference 13). The securing of the drawers front panels to the NIS cabinet will further extend the safety margin of the Gammametrics equipment mounting with six screws.
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3.0
SUMMARY
OF RESULTS AND CONCLUSIONS Gammametrics equipment is to be used to replace the Westinghouse Source Range and Intermediate Range drawers of NIS console 2-M-13 installed at Watts Bar Unit 2. In addition, two Shutdown Monitors are to be added to NIS console 2-M-13. Seismic evaluation was performed to demonstrate that this modification to NIS console 2-M-13 will not invalidate the seismic qualification of NIS console 2-M-13 for the Seismic Category I application at Watts Bar Unit 2. The qualification documented herein for the modified NIS console 2-M-13 is based on combined seismic qualification tests reported in WCAP-8021 (Reference 2) and WCAP-8830 (Reference 3), and the seismic analysis performed in Section 2.0.
The seismic evaluation was performed considering the use of the 8-32 ASTM A307 (SAE Grade 2) coarse thread screws for the mounting of Gammametrics equipment. The results of this evaluation are only applicable provided fastening configurations that are equal or greater in strength are used in the application of these results.
The seismic evaluation completed and documented in this report demonstrates that the NIS console 2-M-13 with the use of Gammametrics Source Range and Intermediate Range and Shutdown Monitors is qualified for the Seismic Category I application at Watts Bar Unit 2 in accordance to IEEE Std. 344-1987 (Reference 10). Gammametrics Source Range and Intermediate Range mountings will maintain structural integrity when subjected to the plant specific seismic events.
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4.0 REFERENCES
- 1. Westinghouse Letter WAT-D-9249, "Tennessee Valley Authority Watts Bar Nuclear Plant Unit 1 Weight Zone Evaluation for NIS Console Modification," April, 1993. (Attached in Appendix B)
- 2. Westinghouse Electric Corporation Report WCAP-8021, "Seismic Testing of Electrical and Control Equipment (PG&E Plants)," May, 1973. (Westinghouse Proprietary)
- 3. Westinghouse Electric Corporation Report WCAP-8830, "Seismic Operability Demonstration Testing of the Nuclear Instrumentation System Bistable Amplifier,"
October, 1976. (Westinghouse Proprietary)
- 4. Tennessee Valley Authority Report WCG-ACQ-0516, "Seismic Qualification of Monitoring Details for Source Range and Intermediate Range on 1-M-13," April, 1993. (Attached in EDMS)
- 5. ]ab,c
- 6. Tennessee Valley Authority Response to Westinghouse Letter WBT-TVA-0078 25401 -01 1-T1 A-GGG-00050-001/002, "Response to Request for Confirmation of Information Related to NIS Excore Gammametrics Equipment," October, 2008. (Attached in EDMS) 7.
abc
- 8. 1a,b~c 9.
- 10. IEEE Std 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers, Inc., 1987.
- 11. AISC Steel Manual, Eighth Edition, American Institute of Steel Construction, Inc.,1978.
- 12. Machinery's Handbook, 28th Edition, Industrial Press Inc., 2008.
- 13. Westinghouse Field Change Notice WBTM-10714, Rev. 0, "NIS Seismic Hardware,"
March, 1985.
- 14. a,b,c EQ-EV-39-WBT-NP, Revision 1 16 of 22
APPENDIX A References 1, 8, 9 and 14 are attached here.
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a*c
- Reference 1 K
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Reference 8 ac EQ-EV-39-WBT-NP, Revision 1 19 of 22
Reference 9 ac EQ-EV-39-WBT-NP, Revision 1 20 of 22
Reference 14 a,c EQ-EV-39-WBT-NP, Revision 1 21 of 22
AP P ENDIX B The following References are attached with this report in EDMS.
Reference 4 Tennessee Valley Authority Report WCG-ACQ-0516, "Seismic Qualification of Monitoring Details for Source Range and Intermediate Range on 1-M-13," April, 1993.
Reference 6 Tennessee Valley Authority Response to Westinghouse Letter WBT-TVA-0078 25401-011-T1A-GGG-00050-001/002, "Response to Request for Confirmation of Information Related to NIS Excore Gammametrics Equipment," October, 2008.
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