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Category:Report
MONTHYEARCNL-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 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 . WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) 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 WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)2020-12-16016 December 2020 Revised Pressure and Temperature Limits Report (PTLR) 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 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 CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2015-03-25025 March 2015 Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid 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 CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident 2024-01-03
[Table view] Category:Miscellaneous
MONTHYEARML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted 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 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 ML17313A1282017-11-0909 November 2017 Revised Pressure and Temperature Limits Report (PTLR) 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 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-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results 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 ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2015-03-25025 March 2015 Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML14163A6582014-09-18018 September 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML14212A6032014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule IR 05000391/19860602014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule ML14149A1502014-06-16016 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14133A5422014-05-23023 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13246A0222013-08-28028 August 2013 Submittal of Pre-op Test Instruction ML13178A2812013-06-26026 June 2013 10 CFR 50.59 Summary Report Supplement ML13144A5762013-05-22022 May 2013 Watt Bar, Units 1 & 2, Report of Drug Testing Error in Accordance with 10 CFR 26.719(c)(1) ML13126A2942013-04-29029 April 2013 10 CFR 50.59 Summary Report ML13121A0602013-04-29029 April 2013 Commitment Summary Report ML13080A3632013-03-18018 March 2013 Enclosure 3, Summer 2011 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A3662013-03-18018 March 2013 Enclosure 1, Summer 2010 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A0732013-03-12012 March 2013 Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation.. ML13175A1352013-03-0505 March 2013 2-PTI-092-03, Revision 0, Nuclear Instrumentation Source Range Noise Checks During Hot Functional Testing. ML12356A3172012-12-17017 December 2012 Submittal of Pre-op Test Instruction, 2-PTI-063-06, Revision 0, Safety Injection System Check Valve Test. ML12335A3402012-11-27027 November 2012 Tennessee Valley Authority - Fleet Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Flooding Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review of ML13108A2842012-11-12012 November 2012 Unit 1, Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report ML13175A1362012-11-0808 November 2012 2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification. ML13175A1342012-11-0101 November 2012 2-PTI-082-02, Revision 0, Rod Control - Non Hft. ML13175A1332012-10-22022 October 2012 2-PTI-085-01, Revision 0, Rod Control Functional Test. ML12236A1642012-07-19019 July 2012 Enclosure 1 Evaluation of Proposed Changes Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1 ML12223A1832012-03-29029 March 2012 Environmental Protection Agency 2012 - Facility Detail Report - Environmental Facts Warehouse Fii - Moccasin Bend Wwtp ML11362A0562011-12-20020 December 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 7 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 7 ML11341A1572011-11-30030 November 2011 Attachments 7 Through 9, WNA-CN-00157-WBT-NP, Revision 1, CAW-11-3316, and WBT-D-3566 Np, Incore Instrument System Signal Processing System Isolation Requirement ML11326A2842011-11-18018 November 2011 Commitment Summary Report ML11257A0502011-08-31031 August 2011 Attachment 7, WCAP-17427-NP, Rev. 1, Watts Bar Nuclear Plant Unit 2 Common Q Post Accident Monitoring System Computer Security Assessment, Attachment 8, Application for Withholding Proprietary Information from Public Disclosure and Attachme ML1104003852011-02-0707 February 2011 Enclosure 2, Appendix a, Hydrothermal Effects on the Ichthyhoplankton from the Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir ML1104003842011-02-0707 February 2011 Enclosure 1, Hydrothermal Effects on the Ichthyoplankton from Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir 2024-01-03
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NRC Region 2 - CIB1 / Watts Bar 2 - IP&S 194 Additional Questions Page 1 of 5 ITEM DESCRIPTION STATUS 1 Procedures for testing Unit 2 Emergency Diesel Generator Pending per email from J.
GC Surveillance Procedures that include SI equipment and support loads Fischer on 9/23/2014 from Unit 1 Basis: While reviewing some details of the question number 4 for That procedure for Unit 2 Load Testing of Diesel Generators for Loss of Offsite it is evident that has not been finalized yet.
Unit 1 procedures include interfacing with Unit 2 for a safety injection signal from Unit 1. However, I could not find the reverse when PTI 262 - 01(Train A) &
reviewing Unit 2 EDGs. The procedures do not appear to include a 02(Train B) safety injection signal from Unit 2 for the test of Unit 2 diesel generators or a Unit 2 safety injection signal when testing the Unit 1 EDGs. It appears that Unit 2 being in operation is not covered with the procedures that I was shown. Can you clarify this for me, please?
2 TVA issued calculations EDQ00099920070002 - Rev 43 and RII is Pending TVA meeting GC, reviewing it. TVA says it is necessary to close IP&S 210 on Grid with Transmission CJ reliability. We say it is necessary to close IP&S 194 on Adequacy of Operations RII waiting for Onsite Electric Distribution System to cover 2-unit operations. TVA TSO procedures disagrees with the last statement. Final Closure Package 10177824 requested.
had been issued in 06/26/2014.
3 IP&S - 231 Cable Separation inside panels. Previously inspected RII is waiting for July 20, GC and found not ready to close. TVA will do a final look inside panels 2015 to inspect this item.
and NRC should witness the final look or do a sampling one later.
4 IP&S - 315 Cable CAP sub-issue, electrical separation and isolation RII is waiting for July 20, CJ, in conduits throughout the plant. This is a large item, need to begin 2015 to inspect this item.
GC inspections. It will be hard to define completion 5 Provide summary of peak loads on shutdown boards 1A-A, 1B-B, 2A- Pending GC A, and 2B-B for different accident scenarios.
6 Calculation EDQ00099920070002 Rev 40 page 100 of 557 Section Pending and must be GC 3.6 Grid Voltage - 161 kV system short circuit contribution is requested provided with a 10% margin for possible variation in future grid. Is there an evaluation done using infinite grid source that would be even higher than the 10% margin or does this margin exceed the infinite bus scenario?
7 Calculation EDQ00099920070002 Rev 40 page 102 of 557 Section Pending and must be GC 3.17 - Cables being modeled at 90°C provides for an ampere rating requested for the particular AWG size but if termination are rated for 60°C or 75°C the ampere rating would be less which may be a problem with heating at the terminations.
8 Provide a copy of calculation WBN EEB-MS-TI05-0001 to review list Pending and must be GC of assumptions applicable to Calculation EDQ00099920070002 Rev requested 40 page 103 of 557 Section 4.
9 Calculation EDQ00099920070002 Rev 40 page 106 of 557 Section Pending and must be GC 6.0 - Does the calculation provide an analysis for minimum running requested voltages that point out lower than allowed voltage drop condition in the distribution system, including safety injection phase B? Indicate where is this information shown?
NRC Region 2 - CIB1 / Watts Bar 2 - IP&S 194 Additional Questions Page 2 of 5 10 Provide supporting documentation for the time delay setting of the Pending and must be GC DVR at 10 seconds and for the loss of voltage (LOV) at 0.75 requested seconds. Provide justification that these time delays do not need to be shorter or longer than the setting provided. Is the LOV coordinated with automatic reclosers provided in the offsite grid system in any significant manner?
11 Provide supporting documentation for any time delay provided for Pending and must be GC transferring SI loads from offsite power to diesel generators when the requested transfer has been initiated by the degraded voltage relay assuming the SI equipment has already started up and is running.
12 Calculation WBNEEBMSTI060029, Degraded Voltage Analysis Pending and must be GC Rev. 37. Page 55 of 374 Section 5.1.1.1., states that: The model is requested. May be
? configured such that the 6.9kV Shutdown Boards are fed solely from unnecessary based on a fixed voltage control utility set to 6555V. Does a fixed voltage NRRs acceptance of TVA control utility represent an infinite bus? DVR settings.
13 Calculation WBNEEBMSTI060029, Degraded Voltage Analysis Pending and must be GC Rev. 37. Page 55 of 374 Section 5.1.1.2., indicates that motor loads requested are evaluated to verify that the motor terminal voltage is (typically 460
+/- 10%) to prevent motor overheating damage. Is there a time constant associated with this motor overheating damage for a voltage below the -10% level?
14 Calculation WBNEEBMSTI060029, Degraded Voltage Analysis Pending and must be GC Rev. 37. Page 56 of 374 Section 5.2.1., indicates that the chosen requested upper limit for the degraded voltage reset ensures that motors and motor-operated valves (MOVs) have adequate starting voltage and that 6555V provides conservative results for block motor starting during an accident. How is this statement confirmed?
15 The circuits feeding the 480 volt safety related motors that are part of Pending and must be GC the ECCS are the all provided with Motor Circuit Protectors or requested Thermal-magnetic breakers. Do these calculations account for higher currents imposed on thermal magnetic breakers for longer time do to overload bypass?
16 Calculation WBNEEBMSTI060029, Degraded Voltage Analysis Pending and must be GC Rev. 37. Page 59 of 374 Section 5.4.4.1.6, please explain the entire requested discussion presented on this page. Provide the time-current curves for the Thermal Overloads (TOLs).
17 Calculation WBNEEBMSTI060029, Degraded Voltage Analysis Pending and must be GC Rev. 37. Page 71 of 374 Table 1-1 Steady-State Voltage Summary requested (Unit 1 Boards) are the voltage levels shown for Shutdown Board 1A1-A 1600 considering the current limiting reactors?
18 Calculation EDQ00099920070002 Rev 40 page 250 of 557 Pending and must be GC Attachment 11.3.i - Motor Starting Analysis ERCW pumps are still requested shown as 800HP and these are supposed to be 805HP. Does the voltage analysis change in any way? How is the Worst Case Terminal Voltage(%) developed? Why the 3.3% difference in voltage between ERCW PMP A-A and B-A? That equates to approximately 220+ volts.
19 Calculation EDQ00099920070002 Rev 40 page 332 of 557 Pending and must be GC Attachment 11.7 - Section 7.0 Summary of Results - Is the addition requested of Unit 2 inverter acceptable the same way Unit 1?
NRC Region 2 - CIB1 / Watts Bar 2 - IP&S 194 Additional Questions Page 3 of 5 20 Calculation EDQ00099920070002 Rev 40 page 396 of 557 Pending and must be GC Attachment 53479, a number of EDCRs replacing existing motors for requested larger motors on Unit 2. Changes motors from 75HP to 100HP.
Page 401 of 557 adds more load. Page 411 adds more.
21 Calculation EDQ00099920070002 Rev 40 page 518 of 557 Pending and must be GC Attachment for Chiller replacement is pointing to an overloaded requested transformer acceptability due to calculations considering 55° instead of 65 ° rise which allows heavier loading and in a third case, loads were not applied a diversity factor.
22 6.2 This analysis will meet the following criteria: Pending and must be CJ a. If the voltage on the 6.9 kV shutdown boards drops below the requested degraded voltage dropout voltage analytical limit of 6555V. It recovers above the upper boundary of the degraded voltage reset voltage (operational limit) of 6681V within the lower limit of the degraded voltage time delay of 8.5 seconds (Att. 11.6) so as not to isolate the 6.9kV shutdown boards from the preferred offsite power source.
- b. Voltage at 480V boards/MCCs recovers such that all components receive sufficient voltage to start within 5 seconds after a Safety Injection Signal (SIS) that block starts all ESF motors. Delaying the starting of safety injection motors and closure of the Main Feedwater isolation valves for five second with offsite3 power available is acceptable as per Westinghouses safety evaluation (Ref. 2.16).
Do these statements mean that this is an accident scenario that is assumed and modeled in this calculation or are these results from this calculation. This is important to understand the purpose of the calculation.
23 6.4 Motor Starting Analysis states: Pending and must be CJ This analysis is performed by setting utility bus at the 6.9kV requested shutdown board at the analytical dropout limit of the degraded voltage relay (6555V) and running the following analysis under normal, SIA and SIB loading:
- Individual motor starting analysis to determine starting voltage for continuous duty motors and MOVs If you set the shutdown board at 6555V and do a voltage drop analysis to find out the resulting voltage at each component, how will that determine the required voltage to start the load? The required voltage to start the load is a characteristic of the component and its application. This doesnt seem to prove of reveal anything. What is the purpose of this calculation and what are the results used for?
24 6.6.1 SI Actuated 89-10 MOVs Pending and must be CJ This portion of the calculation appears to say there are cases requested analyzed where certain safety related MOVs will not receive adequate voltage to start, but this will be OK because the voltage recovers in 5 seconds, and no damage will be done to the MOV while being stalled for 5 seconds. What documentation supports the conclusion that no damage will be done to the MOVs experiencing locked rotor current for 5 seconds?
NRC Region 2 - CIB1 / Watts Bar 2 - IP&S 194 Additional Questions Page 4 of 5 25 6.9 Short Circuit states: The results of the calculated short circuit Pending and must be CJ study cases are contained in Attachment 11.3.e. The analyzed requested configurations are listed in Attachment 11.1 The overloaded buses are identified in Attachment 11.3.g How is that consistent with the following?
8.1.1.4 Bus/Board Loading Based on a review of ETAP output reports for various APS alignments listed in Attachment 11.1, loading of all buses /boards were determined to be within their rating specified in Section 3.27 Also 9.2 Bus/Board Loading All Class 1E and non-Class 1E buses have adequate ratings.
26 9.4 89-10 MOV Analysis Pending and must be CJ 9.4.1 All Unit 1 and 2 89-10 MOVs results require review by requested Mechanical Design Group to determine the acceptability of the available terminal voltage.
NRC needs to review the documented results of this review by the Mechanical Design Group and those documents need to be referenced in this calculation.
27 8.1.7 Fault Capability Pending and must be CJ The maximum short circuit on the safety related motor control centers requested is 17218A and thus exceeds the interrupting rating of 14000A for the 100A frame EF3 magnetic circuit breakers. These circuit breakers are used with starter circuits and as per Ref. 2.12 the combination starter circuit interrupting rating is 22000A. Therefore, the interrupting rating exceeds the available short circuit.
Have these underrated EF3 breakers now been replaced on the both units?
28 8.2.4 Fault Capability Pending and must be CJ Available fault current for 6.9kV RCP boards breakers exceeds the requested breaker interrupting rating when all eight U1 and U2 RCP motors along with other BOP loads are transferred to the 161kV system with one CSST A or B out of service. To alleviate this condition, whenever CSST A or B is out of service, load shed logic has been activated to trip 2 RCP boards of each unit prior to transfer of Units 1 and 2 BOP loads to the remaining CSST A or B (Section 5.1).
If there is a trip of two RCPs while the plant is running, it will trip the plant. Why is that an OK fix?
29 Appendix 10.3, 6.0 Summary of Results and Conclusions Pending and must be CJ Based on the analysis, as stated in Section 5.0, all motors have requested adequate starting voltage to perform their intended safety function during an accident condition with the APS (6.9kV shutdown boards) at the degraded voltage relay dropout limit of 6555V. Available voltage for the MOVs requires review by Mechanical. See Section 9.4.
Is this still the conclusion of this calculation?
NRC Region 2 - CIB1 / Watts Bar 2 - IP&S 194 Additional Questions Page 5 of 5 30 Please provide an explanation of the meaning of the following Pending and must be CJ statements. requested Statement in Table of Contents:
Note: Analysis in Appendices 10.4 through 10.10 has been rolled over in to the ETAP analysis in the main body of the calculation.
3.17 The cables are modeled at 90°C. ETAP uses this cable information to perform voltage drop analysis. Cable temperature of 25°C is used to perform short circuit analysis and ETAP automatically converts the cable data from 90°C to 25°C.
3.24 Analysis for the available voltage at the 89-10 MOVs, which operate under Steady State conditions and are not required to operate on accident signal, is performed under degraded voltage conditions. Voltage under degraded voltage conditions is enveloping of the voltage under steady state conditions, therefore, separate analysis with available voltage under steady state conditions is not performed.
4.15 Continued operation of Unit 1 MOVs is currently justified based on the analysis in Ref. 2.36. The current evaluation for Unit 1 89-10 MOVs is this calculation is not valid until this calculation becomes calculation of record for Unit 1 except for the single motor start analysis at degraded voltage for which this is the calculation of record for Unit 1.
4.17 FSAR Section 8.2 shall be revised to address the following::
- Replace the statement design basis accident in one unit and a concurrent full load rejection is the other unit with design basis accident in one unit and simultaneous orderly shutdown of the other unit