Letter Sequence Supplement |
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TAC:MF7224, Add Action for Two Inoperable Control Room AC Subsystems, Add Action for Two Inoperable Creatcs Trains (Open) |
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Category:Letter type:MNS
MONTHYEARMNS-18-044, Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments2018-07-26026 July 2018 Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles2018-07-0303 July 2018 Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles MNS-18-042, Independent Spent Fuel Storage Installation (ISFSI)2018-06-28028 June 2018 Independent Spent Fuel Storage Installation (ISFSI) MNS-18-040, Submittal of Information Related to Pressurizer Surge and Spray Nozzle Thermal Sleeves Attachment Welds for License Renewal2018-06-26026 June 2018 Submittal of Information Related to Pressurizer Surge and Spray Nozzle Thermal Sleeves Attachment Welds for License Renewal MNS-18-039, Independent Spent Fuel Storage Installation (ISFSI)2018-06-19019 June 2018 Independent Spent Fuel Storage Installation (ISFSI) MNS-18-001, Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable2018-05-31031 May 2018 Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable MNS-18-030, 2017 Annual Radiological Environmental Operating Report2018-05-15015 May 2018 2017 Annual Radiological Environmental Operating Report MNS-18-029, Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A2018-05-0909 May 2018 Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A MNS-18-029, McGuire Nuclear Station, Units 1 and 2 - Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-2018-05-0909 May 2018 McGuire Nuclear Station, Units 1 and 2 - Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A MNS-18-028, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report MNS-18-017, Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-02-26026 February 2018 Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs MNS-18-018, McGuire, Units 1 & 2, Submittal of Emergency Plan Implementing Procedure Changes2018-02-22022 February 2018 McGuire, Units 1 & 2, Submittal of Emergency Plan Implementing Procedure Changes MNS-18-009, McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 18-12018-01-31031 January 2018 McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 MNS-18-003, End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports2018-01-11011 January 2018 End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017 Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-12-12012 December 2017 Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-17-026, Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles2017-12-0808 December 2017 Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles MNS-17-042, McGuire Nuclear Station, Unit 1, Submittal of Cycle 26, Revision 0, Core Operating Limits Report2017-10-0909 October 2017 McGuire Nuclear Station, Unit 1, Submittal of Cycle 26, Revision 0, Core Operating Limits Report MNS-17-040, (Mns), Units 1 and 2 - Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force ..2017-09-27027 September 2017 (Mns), Units 1 and 2 - Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force .. MNS-17-038, Startup Ascension Summary Report Measurement Uncertainty Recapture Power Uprate2017-09-25025 September 2017 Startup Ascension Summary Report Measurement Uncertainty Recapture Power Uprate MNS-17-039, McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 17-12017-09-19019 September 2017 McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 17-1 MNS-17-031, License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition2017-09-14014 September 2017 License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition MNS-17-037, Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 20172017-08-10010 August 2017 Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 2017 MNS-17-033, Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval2017-08-0202 August 2017 Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval MNS-17-034, 16C4435-RPT-002, Rev. 1, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for McGuire Nuclear Station.2017-07-24024 July 2017 16C4435-RPT-002, Rev. 1, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for McGuire Nuclear Station. MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-06-28028 June 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-25025 May 2017 Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-17-016, Nuclear Regulatory Commission (NRC) Annual Commitment Change Report2017-05-18018 May 2017 Nuclear Regulatory Commission (NRC) Annual Commitment Change Report MNS-17-020, Transmittal of McGuire, Units 1 and 2, 2016 Annual Radiological Environmental Operating Report2017-05-0505 May 2017 Transmittal of McGuire, Units 1 and 2, 2016 Annual Radiological Environmental Operating Report MNS-17-019, McGuire Nuclear Station, Units 1 and 2 - Submittal of Annual Radioactive Effluent Release Report2017-04-28028 April 2017 McGuire Nuclear Station, Units 1 and 2 - Submittal of Annual Radioactive Effluent Release Report MNS-17-008, Letter of Intent to Submit Plant-Specific Reactor Vessel Internals Inspection Plans2017-02-23023 February 2017 Letter of Intent to Submit Plant-Specific Reactor Vessel Internals Inspection Plans MNS-16-092, License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-12-19019 December 2016 License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-16-091, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity.2016-12-0808 December 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity. MNS-16-086, Emergency Plan, Revision 16-42016-12-0707 December 2016 Emergency Plan, Revision 16-4 MNS-16-078, Written Notification Joslyn Clark Overload Heater Element Part No. 24552016-10-19019 October 2016 Written Notification Joslyn Clark Overload Heater Element Part No. 2455 MNS-16-077, Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program2016-09-29029 September 2016 Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program MNS-16-070, Response to Request for Additional Information to Relief Request 16-MN-0032016-08-18018 August 2016 Response to Request for Additional Information to Relief Request 16-MN-003 MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-18018 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident MNS-16-062, Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping2016-08-10010 August 2016 Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping MNS-16-046, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity2016-06-30030 June 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information2016-06-30030 June 2016 License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information MNS-16-053, Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping2016-06-23023 June 2016 Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping MNS-16-052, Supplement to License Amendment Request for the Removal of Superseded Technical Specification Requirements, Dated May 5, 2016, TAC Nos. MF7682 and MF76832016-06-16016 June 2016 Supplement to License Amendment Request for the Removal of Superseded Technical Specification Requirements, Dated May 5, 2016, TAC Nos. MF7682 and MF7683 MNS-16-042, Withdrawal of Relief Request Serial No. 15-MN-0022016-05-17017 May 2016 Withdrawal of Relief Request Serial No. 15-MN-002 MNS-16-020, License Amendment Request Removal of Superseded Technical Specification Requirements2016-05-0505 May 2016 License Amendment Request Removal of Superseded Technical Specification Requirements MNS-16-041, Supplement to Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051..2016-05-0505 May 2016 Supplement to Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051.. MNS-16-036, Relief Request 16-MN-001, Limited Weld Examinations2016-04-28028 April 2016 Relief Request 16-MN-001, Limited Weld Examinations MNS-16-039, Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program2016-04-26026 April 2016 Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program MNS-16-026, Transmittal of Updated Final Safety Analysis Report, Revision 192016-04-0505 April 2016 Transmittal of Updated Final Safety Analysis Report, Revision 19 MNS-15-068, License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors.2016-03-24024 March 2016 License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors. 2018-07-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report2023-03-16016 March 2023 Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report RA-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds2023-02-28028 February 2023 Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)2023-02-15015 February 2023 End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI) RA-22-0195, Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle2022-06-29029 June 2022 Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2022-04-0707 April 2022 Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative2022-01-31031 January 2022 Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative RA-21-0321, Response to Request for Additional Information (RAI) Regarding Refuel 24 (C2R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2021-12-14014 December 2021 Response to Request for Additional Information (RAI) Regarding Refuel 24 (C2R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-21-0259, Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-10-0404 October 2021 Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(4 RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan2021-03-11011 March 2021 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-21-0017, Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage2021-01-29029 January 2021 Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage RA-20-0104, Response to NRC Request for Additional Information - Catawba Nuclear Station-SG Report (RA-19-0391)-C2R232020-04-0606 April 2020 Response to NRC Request for Additional Information - Catawba Nuclear Station-SG Report (RA-19-0391)-C2R23 RA-20-0087, Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period2020-04-0202 April 2020 Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period RA-20-0002, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2020-02-13013 February 2020 Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-19-0280, Response to NRC RAI Clarifications Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.12019-07-10010 July 2019 Response to NRC RAI Clarifications Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 RA-19-0189, Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.12019-04-0808 April 2019 Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 RA-19-0004, Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 22019-03-0707 March 2019 Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 2 RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-19-0005, Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2019-01-30030 January 2019 Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A RA-18-0162, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2018-12-0606 December 2018 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal RA-18-0229, Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.12018-12-0303 December 2018 Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.1 RA-18-0213, Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles2018-11-0101 November 2018 Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles RA-18-0097, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-08-17017 August 2018 (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System ML18191A5642018-07-10010 July 2018 Attachment 3 - Response to NRC Request for Additional Information MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles2018-07-0303 July 2018 Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles ML20052D9362018-07-0303 July 2018 Response to Nrg Request for Additional Information (RAI) Regarding NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018 (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System NRC-18-0016, Response to Request for Additional Information (Set 2) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1..2018-02-21021 February 2018 Response to Request for Additional Information (Set 2) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1.. CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus2017-12-28028 December 2017 Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information ML17349A1572017-12-12012 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Temporary Changes to Technical Specifications to Address the 'A' Train Nuclear Service Water System Non-Conforming Condition MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-12-12012 December 2017 Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017 Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)2017-08-0909 August 2017 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001) RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.2017-07-20020 July 2017 Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. RA-17-0036, Supplement to the Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-07-17017 July 2017 Supplement to the Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-06-28028 June 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal RA-17-0029, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-06-0808 June 2017 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers RA-17-0030, Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-06-0808 June 2017 Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-25025 May 2017 Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017 Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017 Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016 Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. ML16294A2542016-10-13013 October 2016 Response to Request for Additional Information Regarding Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation2016-10-0303 October 2016 Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation 2023-07-07
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DUKE Steven D. Capps~ Vice President ENERGY° McGuire Nuclear Station Duke Energy MG01VP I112700 Hagers Ferry Road Huntersville, NC 27078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com Serial No. MNS-16-023 March 16, 2016 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Duke Energy Carolinas, LLC (Duke Energy)McGuire Nuclear Station (MNS), Units 1 and 2 Docket Numbers 50-369 and 50-370, Renewed Facility Operating License NPF-9 and NPF-17 Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Renewed Facility Operating License NPF-35 and NPF-52 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications
REFERENCES:
- 1. Letter from Steven D. Capps (Duke Energy) to NRC (Serial: MNS-16-002), dated January 7, 2016 (ADAMS Accession Number ML16029A077), Proposed Technical Specifications (TS) Amendment TS 3. 7.10, "Con trol Room Area Chilled Water System" (MNS), and TS 3. 7.11, "Control Room Area Chilled Water System" (CNS)2. NRC letter from G. Edward Miller to Steven D. Capps (Duke Energy), dated March 1, 2016 (ADAMS Accession Number ML1 6055A333), McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2 -Supplemental Information Needed For Acceptance of Requested Licensing Action RE: License Amendment Request for Control Room Chilled Water System Technical Specifications (TAC Nos.MF7224, MF7225, MF7226, and MF7227)
U.S. Nuclear Regulatory Commission MNS-1 6-023 Page 2 By letter dated January 7, 2016 (Reference 1), Duke Energy submitted a License Amendment Request (LAR) for Technical Specifications (TS) TS 3. 7.10, "Con trol Room Area Chilled Water System" (MNS), and TS 3.7.11, "Control Room Area Chilled Water System" (CNS).The NRC staff reviewed the LAR and determined that supplemental information is needed regarding the acceptability of the proposed LAR in terms of regulatory requirements and the protection of public health and safety and the environment.
By letter dated March 1, 2016 (Reference 2), the supplemental information was requested.
The supplemental information requires submission by March 17, 2016. The Duke Energy responses to the supplemental information are provided in the Enclosure to this letter.The conclusions of the original Significant Hazards Consideration and Environmental Considerations contained in the January 7, 2016, LAR (Reference
- 1) are unaffected as a result of this supplemental response.Pursuant to 10 CER 50.91, a copy of this LAR supplement is being provided to the appropriate States of North and South Carolina officials.
There are no regulatory commitments contained in this letter or its enclosure.
If you have any questions or need additional information on this matter, please contact Lee A. Hentz at (980) 875-4187.I declare under penalty of perjury that the foregoing is true and correct. Executed on March 16, 2016.Sincerely, Steven D.
Enclosure:
Response to Supplemental Information U.S. Nuclear Regulatory Commission MNS-1 6-023 Page 3 cc: (with enclosure)
Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission
-Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1 257 G.A. Hutto Ill (Catawba)Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station J. Zeiler Senior Resident Inspector (McGuire)U.S. Nuclear Regulatory Commission McGuire Nuclear Station G.E. Miller NRC Project Manager (McGuire)U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A 111555 Rockville Pike Rockville, MD 20852-2738 J.A. Whited Project Manager (Catawba)U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 B1A 11555 Rockville Pike Rockville, MD 20852-2738 S.E. Jenkins Manager Radioactive
& infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.Columbia, SC 29201 W.L. Cox, IlI Section Chief, Division of Environmental Health Radiation Protection Section North Carolina Department of Environment and Natural Resources 1645 Mail Service Center Raleigh, NC 27699 U.S. Nuclear Regulatory Commission M NS-1 6-023 Enclosure 1 Page 1 of 3 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications By letter dated January 7, 2016 (Agencywide Documents Access and Management System Accession No. ML 16029A077), Duke Energy Carolinas, LLC (Duke Energy or the licensee), submitted a license amendment request for McGuire Nuclear Station, Units 1 and 2 (MNS 1 and 2) and Catawba Nuclear Station, Units 1 and 2 (CNS 1 and 2). The proposed amendment would modify the Control Room Area Chilled Water System Technical Specifications to allow a finite time to address a loss of both trains provided Control Room temperature remains below 90°F.The NRC staff has reviewed your application and concluded that the information delineated below is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment.
For MNS and CNS NRC Question 1 With both trains of the Control Room Area Chilled Water System inoperable, the effects of heat stress due to the rising temperature, under some circumstances, may impede the operators' ability to take actions required to safely operate the nuclear power unit. From a human factors perspective, please describe any effects that the proposed change may have on the control room operators.
In this description, include a justification that any impacted persons will still be able to successfully perform their job role.Duke Energy Response to Question 1 This question was further clarified during the March 1, 2016, conference call between the NRC Staff and Duke Energy: "What would be the impact on the Control Room Operators if the Control Room remained at or near 90°F for the duration of the proposed Condition B Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />." Duke Energy has in place an Administrative Procedure, "Heat and Cold Stress," based on an industry standard, that evaluates activities which expose workers to adverse environmental conditions and provides means and methods to avoid heat stress related health incidents.
Control Room activities can be considered "Light work: sitting or standing with moderate arm or trunk movement, monitoring equipment, minimal walking." Per the Procedure's "Stay Time Chart," there are no stay time limits for light work up to a wet bulb globe temperature (WBGT) of 90°F. Stay time is defined as the recommended amount of time that a worker is expected to safely work in a moderate to high heat environment.
Control Room temperature is measured as a dry bulb temperature, meaning the impacts from humidity are not accounted for as they are with WBGT. Low humidity impacts dry bulb temperatures positively, thus the WBGT will equate to a lower temperature than the measured U.S. Nuclear Regulatory Commission MNS-1 6-023 Enclosure 1 Page 2 of 3 dry bulb. Conversely, very high humidity (90-100%)
impacts dry bulb temperatures negatively, thus the WBGT will equate to a higher temperature than the measured dry bulb.During a loss of cooling event in the Control Room, there would not be an appreciable increase in humidity as temperature rises since mnost of the Control Room heat load is in the form of sensible heat. Latent heat, which drives humidity, accounts for only a fraction of the total room heat load. Thus, high humidity levels in the Control Room are not a concern for MNS or CNS.This means that the currently measured dry bulb temperature would be comparable to the WBGT, and there are no mandated stay time restrictions as long as the Control Room temperature remains 90°F or less.From a human factors perspective, based on the above considerations, the proposed change will have no adverse impact on Control Room Operators.
The effects of rising temperature in the Control Room should not impede the Operators' ability to take actions required to safely operate the nuclear power unit.Duke Energy also has readily available instruments that easily measure WBGT. These are available close to the Control Room and do not require any specific qualifications.
Their set-up and use are described in the "Heat and Cold Stress" procedure.
As such, an exact determination of Control Room WBGT can easily be determined.
In addition, Operator shifts are limited to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Supplemental staffing can be provided to allow Operators to periodically rotate during shifts if the need arises.NRC Question 2 The submittal indicates that the current licensed design temperature of the Control Room equipment is 90°F or less, verified every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This value was determined assuming that at least one train of the Control Room Area Chilled Water System was available for active removal of heat. When in the proposed Condition B, the ability to remove heat from the Control Room would be significantly reduced. Although it appears that the increased frequency of verification of Control Room temperature (i.e., every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) is meant to account for this, the submittal does not address why it is adequate.
Please provide a quantitative justification for the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> surveillance interval and how the 90°F limit remains valid given potentially increased Control Room heat-up rates.Duke Energy Response to Question 2 The four hour monitoring frequency of Control Room temperature when in the proposed Condition B was predominately based on remaining consistent with NRC approved TSTF-477 Rev.3 and draft TSTF-553.
As the Control Room is continuously occupied, any temperature changes would be immediately recognized by the Operators.
MNS and CNS have in place "Abnormal Procedures" (AP) to take mitigating actions when Control Room temperature reaches 80°F and take actions to shutdown the affected Units if temperature rises above 90°F.
U.S. Nuclear Regulatory Commission MNS-1 6-023 Enclosure 1 Page 3 of 3 The MNS AP is entered by Operators on symptoms such as: Control Room temperature increasing, chill water supply temperature increasing (alarms at 55°F), or Control Room supply air temperature increasing (alarms at 75°F). Once the AP is entered, MNS Control Room temperature is monitored continuously.
The CNS AP is entered by Operators on symptoms such as: Control Room temperature increasing, Control Room Air Handling Unit (AHU) low flow alarm, Control Room Chiller "off'alarm or "critical trouble" alarm. If the CNS Control Room reaches 80°F, temperature is monitored continuously until one train of Control Room Area Chilled Water System (CRACWS)is restored.In summary, MNS and CNS enter the applicable AP for "Control Room High Temperature" prior to any significant increase in Control Room temperature or early symptoms of CRACWS equipment malfunctions.
Once the APs are entered, Control Room temperature is continuously monitored with specific actions to be taken at 80°F and 90°F. These AP actions satisfy the intent of proposed Action B.1 and the associated Completion Time of four hours.As stated in Section 3.6 of the LAR, the most likely application of proposed Condition B and the associated Required Actions is when both CRACWS trains are inoperable but one train is functional with the ability to cool the Control Room. In this case, the Control Room temperature would remain constant at a normal value, and the 90°F limit is not challenged.
For CNS NRC Question 3 The submittal indicates that the current licensed design temperature of the Control Room equipment is 90°F or less. The submittal also indicates that, while the temperature control band for MNS is 75°F to 900°F, the band for CNS is 72°F to 850°F. Please clarify the apparent discrepancy between the CNS licensing basis and system design.Duke Energy Response to Question 3 The current licensed design temperature for the CNS Control Room is 90°F. This is the Technical Specification (TS) limit as defined in CNS TS 3.7.11. This represents the temperature at which CNS will take action to shut down both Units. The 90°F limit does not represent the maximum temperature at which equipment in the Control Room will operate, nor does it represent the temperature at which CNS operates the Control Room. The CRACWS "design set point" (temperature at which the Control Room is maintained) is 74°F. In a large system, however, there is always a range of temperatures over which a system will operate. The submittal addresses this potential range by using the values stated in the Technical Specification Bases for CNS TS 3.7.11 which is 72 0 F -85°F.Although the operating range of 72°F- 85°F is the administrative limit, 90°F remains the TS limit as defined in CNS TS 3.7.11. It should be noted that CNS maintains the Control Room at 740°F.Actions will be taken anytime the Control Room temperature reaches 80 0 F or above. This provides margin to the LCO limit of 900°F.
DUKE Steven D. Capps~ Vice President ENERGY° McGuire Nuclear Station Duke Energy MG01VP I112700 Hagers Ferry Road Huntersville, NC 27078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com Serial No. MNS-16-023 March 16, 2016 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Duke Energy Carolinas, LLC (Duke Energy)McGuire Nuclear Station (MNS), Units 1 and 2 Docket Numbers 50-369 and 50-370, Renewed Facility Operating License NPF-9 and NPF-17 Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Renewed Facility Operating License NPF-35 and NPF-52 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications
REFERENCES:
- 1. Letter from Steven D. Capps (Duke Energy) to NRC (Serial: MNS-16-002), dated January 7, 2016 (ADAMS Accession Number ML16029A077), Proposed Technical Specifications (TS) Amendment TS 3. 7.10, "Con trol Room Area Chilled Water System" (MNS), and TS 3. 7.11, "Control Room Area Chilled Water System" (CNS)2. NRC letter from G. Edward Miller to Steven D. Capps (Duke Energy), dated March 1, 2016 (ADAMS Accession Number ML1 6055A333), McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2 -Supplemental Information Needed For Acceptance of Requested Licensing Action RE: License Amendment Request for Control Room Chilled Water System Technical Specifications (TAC Nos.MF7224, MF7225, MF7226, and MF7227)
U.S. Nuclear Regulatory Commission MNS-1 6-023 Page 2 By letter dated January 7, 2016 (Reference 1), Duke Energy submitted a License Amendment Request (LAR) for Technical Specifications (TS) TS 3. 7.10, "Con trol Room Area Chilled Water System" (MNS), and TS 3.7.11, "Control Room Area Chilled Water System" (CNS).The NRC staff reviewed the LAR and determined that supplemental information is needed regarding the acceptability of the proposed LAR in terms of regulatory requirements and the protection of public health and safety and the environment.
By letter dated March 1, 2016 (Reference 2), the supplemental information was requested.
The supplemental information requires submission by March 17, 2016. The Duke Energy responses to the supplemental information are provided in the Enclosure to this letter.The conclusions of the original Significant Hazards Consideration and Environmental Considerations contained in the January 7, 2016, LAR (Reference
- 1) are unaffected as a result of this supplemental response.Pursuant to 10 CER 50.91, a copy of this LAR supplement is being provided to the appropriate States of North and South Carolina officials.
There are no regulatory commitments contained in this letter or its enclosure.
If you have any questions or need additional information on this matter, please contact Lee A. Hentz at (980) 875-4187.I declare under penalty of perjury that the foregoing is true and correct. Executed on March 16, 2016.Sincerely, Steven D.
Enclosure:
Response to Supplemental Information U.S. Nuclear Regulatory Commission MNS-1 6-023 Page 3 cc: (with enclosure)
Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission
-Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1 257 G.A. Hutto Ill (Catawba)Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station J. Zeiler Senior Resident Inspector (McGuire)U.S. Nuclear Regulatory Commission McGuire Nuclear Station G.E. Miller NRC Project Manager (McGuire)U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A 111555 Rockville Pike Rockville, MD 20852-2738 J.A. Whited Project Manager (Catawba)U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 B1A 11555 Rockville Pike Rockville, MD 20852-2738 S.E. Jenkins Manager Radioactive
& infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.Columbia, SC 29201 W.L. Cox, IlI Section Chief, Division of Environmental Health Radiation Protection Section North Carolina Department of Environment and Natural Resources 1645 Mail Service Center Raleigh, NC 27699 U.S. Nuclear Regulatory Commission M NS-1 6-023 Enclosure 1 Page 1 of 3 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications By letter dated January 7, 2016 (Agencywide Documents Access and Management System Accession No. ML 16029A077), Duke Energy Carolinas, LLC (Duke Energy or the licensee), submitted a license amendment request for McGuire Nuclear Station, Units 1 and 2 (MNS 1 and 2) and Catawba Nuclear Station, Units 1 and 2 (CNS 1 and 2). The proposed amendment would modify the Control Room Area Chilled Water System Technical Specifications to allow a finite time to address a loss of both trains provided Control Room temperature remains below 90°F.The NRC staff has reviewed your application and concluded that the information delineated below is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment.
For MNS and CNS NRC Question 1 With both trains of the Control Room Area Chilled Water System inoperable, the effects of heat stress due to the rising temperature, under some circumstances, may impede the operators' ability to take actions required to safely operate the nuclear power unit. From a human factors perspective, please describe any effects that the proposed change may have on the control room operators.
In this description, include a justification that any impacted persons will still be able to successfully perform their job role.Duke Energy Response to Question 1 This question was further clarified during the March 1, 2016, conference call between the NRC Staff and Duke Energy: "What would be the impact on the Control Room Operators if the Control Room remained at or near 90°F for the duration of the proposed Condition B Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />." Duke Energy has in place an Administrative Procedure, "Heat and Cold Stress," based on an industry standard, that evaluates activities which expose workers to adverse environmental conditions and provides means and methods to avoid heat stress related health incidents.
Control Room activities can be considered "Light work: sitting or standing with moderate arm or trunk movement, monitoring equipment, minimal walking." Per the Procedure's "Stay Time Chart," there are no stay time limits for light work up to a wet bulb globe temperature (WBGT) of 90°F. Stay time is defined as the recommended amount of time that a worker is expected to safely work in a moderate to high heat environment.
Control Room temperature is measured as a dry bulb temperature, meaning the impacts from humidity are not accounted for as they are with WBGT. Low humidity impacts dry bulb temperatures positively, thus the WBGT will equate to a lower temperature than the measured U.S. Nuclear Regulatory Commission MNS-1 6-023 Enclosure 1 Page 2 of 3 dry bulb. Conversely, very high humidity (90-100%)
impacts dry bulb temperatures negatively, thus the WBGT will equate to a higher temperature than the measured dry bulb.During a loss of cooling event in the Control Room, there would not be an appreciable increase in humidity as temperature rises since mnost of the Control Room heat load is in the form of sensible heat. Latent heat, which drives humidity, accounts for only a fraction of the total room heat load. Thus, high humidity levels in the Control Room are not a concern for MNS or CNS.This means that the currently measured dry bulb temperature would be comparable to the WBGT, and there are no mandated stay time restrictions as long as the Control Room temperature remains 90°F or less.From a human factors perspective, based on the above considerations, the proposed change will have no adverse impact on Control Room Operators.
The effects of rising temperature in the Control Room should not impede the Operators' ability to take actions required to safely operate the nuclear power unit.Duke Energy also has readily available instruments that easily measure WBGT. These are available close to the Control Room and do not require any specific qualifications.
Their set-up and use are described in the "Heat and Cold Stress" procedure.
As such, an exact determination of Control Room WBGT can easily be determined.
In addition, Operator shifts are limited to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Supplemental staffing can be provided to allow Operators to periodically rotate during shifts if the need arises.NRC Question 2 The submittal indicates that the current licensed design temperature of the Control Room equipment is 90°F or less, verified every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This value was determined assuming that at least one train of the Control Room Area Chilled Water System was available for active removal of heat. When in the proposed Condition B, the ability to remove heat from the Control Room would be significantly reduced. Although it appears that the increased frequency of verification of Control Room temperature (i.e., every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) is meant to account for this, the submittal does not address why it is adequate.
Please provide a quantitative justification for the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> surveillance interval and how the 90°F limit remains valid given potentially increased Control Room heat-up rates.Duke Energy Response to Question 2 The four hour monitoring frequency of Control Room temperature when in the proposed Condition B was predominately based on remaining consistent with NRC approved TSTF-477 Rev.3 and draft TSTF-553.
As the Control Room is continuously occupied, any temperature changes would be immediately recognized by the Operators.
MNS and CNS have in place "Abnormal Procedures" (AP) to take mitigating actions when Control Room temperature reaches 80°F and take actions to shutdown the affected Units if temperature rises above 90°F.
U.S. Nuclear Regulatory Commission MNS-1 6-023 Enclosure 1 Page 3 of 3 The MNS AP is entered by Operators on symptoms such as: Control Room temperature increasing, chill water supply temperature increasing (alarms at 55°F), or Control Room supply air temperature increasing (alarms at 75°F). Once the AP is entered, MNS Control Room temperature is monitored continuously.
The CNS AP is entered by Operators on symptoms such as: Control Room temperature increasing, Control Room Air Handling Unit (AHU) low flow alarm, Control Room Chiller "off'alarm or "critical trouble" alarm. If the CNS Control Room reaches 80°F, temperature is monitored continuously until one train of Control Room Area Chilled Water System (CRACWS)is restored.In summary, MNS and CNS enter the applicable AP for "Control Room High Temperature" prior to any significant increase in Control Room temperature or early symptoms of CRACWS equipment malfunctions.
Once the APs are entered, Control Room temperature is continuously monitored with specific actions to be taken at 80°F and 90°F. These AP actions satisfy the intent of proposed Action B.1 and the associated Completion Time of four hours.As stated in Section 3.6 of the LAR, the most likely application of proposed Condition B and the associated Required Actions is when both CRACWS trains are inoperable but one train is functional with the ability to cool the Control Room. In this case, the Control Room temperature would remain constant at a normal value, and the 90°F limit is not challenged.
For CNS NRC Question 3 The submittal indicates that the current licensed design temperature of the Control Room equipment is 90°F or less. The submittal also indicates that, while the temperature control band for MNS is 75°F to 900°F, the band for CNS is 72°F to 850°F. Please clarify the apparent discrepancy between the CNS licensing basis and system design.Duke Energy Response to Question 3 The current licensed design temperature for the CNS Control Room is 90°F. This is the Technical Specification (TS) limit as defined in CNS TS 3.7.11. This represents the temperature at which CNS will take action to shut down both Units. The 90°F limit does not represent the maximum temperature at which equipment in the Control Room will operate, nor does it represent the temperature at which CNS operates the Control Room. The CRACWS "design set point" (temperature at which the Control Room is maintained) is 74°F. In a large system, however, there is always a range of temperatures over which a system will operate. The submittal addresses this potential range by using the values stated in the Technical Specification Bases for CNS TS 3.7.11 which is 72 0 F -85°F.Although the operating range of 72°F- 85°F is the administrative limit, 90°F remains the TS limit as defined in CNS TS 3.7.11. It should be noted that CNS maintains the Control Room at 740°F.Actions will be taken anytime the Control Room temperature reaches 80 0 F or above. This provides margin to the LCO limit of 900°F.