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Category:Letter type:NL
MONTHYEARNL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0213, Inservice Inspection Program Owner'S Activity Report for Outage 1R312023-03-21021 March 2023 Inservice Inspection Program Owner'S Activity Report for Outage 1R31 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-23-0011, Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only2023-01-0505 January 2023 Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, NL-22-0887, Cycle 32 Core Operating Limits Report2022-11-21021 November 2022 Cycle 32 Core Operating Limits Report NL-22-0884, Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-1012022-11-17017 November 2022 Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-101 NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0756, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02022-09-30030 September 2022 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis NL-22-0608, Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers2022-08-17017 August 2022 Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers NL-22-0552, Inservice Inspection Program Owner'S Activity Report for Outage 2R282022-07-28028 July 2022 Inservice Inspection Program Owner'S Activity Report for Outage 2R28 NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value NL-22-0361, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak.2022-06-20020 June 2022 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak. NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0388, Cycle 29 Core Operating Limits Report2022-05-31031 May 2022 Cycle 29 Core Operating Limits Report NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0340, Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical2022-05-10010 May 2022 Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations 2024-01-11
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-22-0361, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak.2022-06-20020 June 2022 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak. NL-21-1060, Units 1 and 2, Response to Request for Additional Information Related to License Amendment Request to Allow Elimination of the Encapsulation Vessels Around the First Containment Spray (CS) and Residual Heat Removal .2021-12-13013 December 2021 Units 1 and 2, Response to Request for Additional Information Related to License Amendment Request to Allow Elimination of the Encapsulation Vessels Around the First Containment Spray (CS) and Residual Heat Removal . NL-21-0020, Final Supplemental Response to NRC Generic Letter 2004-022021-03-23023 March 2021 Final Supplemental Response to NRC Generic Letter 2004-02 NL-21-0019, Response to Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-03-0202 March 2021 Response to Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NL-20-1273, Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for2020-11-20020 November 2020 Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for NL-20-0816, Response to Request for Clarification Regarding the Refueling Outage 1R29 Steam Generator Tube Inspection Report2020-07-17017 July 2020 Response to Request for Clarification Regarding the Refueling Outage 1R29 Steam Generator Tube Inspection Report NL-20-0636, Third Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate2020-05-29029 May 2020 Third Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate NL-20-0640, Response to Request for Additional Information for Exemption Request2020-05-27027 May 2020 Response to Request for Additional Information for Exemption Request NL-20-0550, Responses to NRC Requests for Additional Information License Amendment Request to Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint2020-05-20020 May 2020 Responses to NRC Requests for Additional Information License Amendment Request to Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint NL-20-0538, Second Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate2020-05-0808 May 2020 Second Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate NL-20-0458, Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate2020-04-22022 April 2020 Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate NL-20-0403, Response to Request for Additional Information Regarding License Amendment Request to Update the Spent Fuel Pool Criticality Safety Analysis and Revise Technical Specification (TS) 3.7.15 Spent Fuel Assembly Storage2020-04-13013 April 2020 Response to Request for Additional Information Regarding License Amendment Request to Update the Spent Fuel Pool Criticality Safety Analysis and Revise Technical Specification (TS) 3.7.15 Spent Fuel Assembly Storage NL-19-0676, Proposed Alternative FNP-ISI-ALT-05-04, Response to NRC Request for Additional Information2019-06-11011 June 2019 Proposed Alternative FNP-ISI-ALT-05-04, Response to NRC Request for Additional Information NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)2019-05-0303 May 2019 Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI) NL-19-0343, Relief Request FNP-ISI-RR-03: SNC Response to NRC Request for Additional Information2019-04-23023 April 2019 Relief Request FNP-ISI-RR-03: SNC Response to NRC Request for Additional Information NL-19-0307, Response to NRC Request for Additional Information on Relief Request FNP-ISI-RR-022019-03-27027 March 2019 Response to NRC Request for Additional Information on Relief Request FNP-ISI-RR-02 NL-18-1514, Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift.2019-01-31031 January 2019 Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift. NL-17-2135, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program, Response to NRC Request for Additional Information2018-02-0909 February 2018 License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program, Response to NRC Request for Additional Information NL-17-2015, Response to NRC RAIs Regarding Decommissioning Funding Status Reports2018-01-22022 January 2018 Response to NRC RAIs Regarding Decommissioning Funding Status Reports NL-17-1443, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Final Response to NRC Requests for Additional Information2017-10-12012 October 2017 License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Final Response to NRC Requests for Additional Information NL-17-1367, Response to the Second Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-09-0707 September 2017 Response to the Second Request for Additional Information Regarding Alternative Source Term License Amendment Request NL-17-0480, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Responses to NRC Requests for Additional Information2017-06-22022 June 2017 License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Responses to NRC Requests for Additional Information NL-17-1067, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-06-0808 June 2017 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request NL-17-0643, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-05-23023 May 2017 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request NL-17-0774, Response to Request for Information Regarding License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems - Operating2017-05-15015 May 2017 Response to Request for Information Regarding License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems - Operating NL-17-0613, Response to Request for Additional Information Regarding Alternative Request FNP-ISI-ALT-20, Version 1.0, Regarding System Leakage Test2017-04-13013 April 2017 Response to Request for Additional Information Regarding Alternative Request FNP-ISI-ALT-20, Version 1.0, Regarding System Leakage Test NL-17-0512, Response to Request for Additional Information Regarding Alternative Request RR-PR-03 Version 1.0 for the Lnservice Testing Program Fifth 1 0-Year Interval2017-03-28028 March 2017 Response to Request for Additional Information Regarding Alternative Request RR-PR-03 Version 1.0 for the Lnservice Testing Program Fifth 1 0-Year Interval NL-16-2513, Response to Follow-up Request for Information Regarding Reactor Pressure Vessel Threads-in-Flange Examination Requirement2016-11-23023 November 2016 Response to Follow-up Request for Information Regarding Reactor Pressure Vessel Threads-in-Flange Examination Requirement NL-16-1830, Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1B of 1C2016-11-0303 November 2016 Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1B of 1C NL-16-1830, Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1C of 1C2016-11-0303 November 2016 Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1C of 1C ML16314A5052016-11-0303 November 2016 Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1B of 1C ML16214A0252016-07-25025 July 2016 Units 1 and 2 - Response to Request for Additional Information for TSTF-312 NL-16-0784, Units 1 and 2 - Response to Request for Additional Information for TSTF-312. Enclosure 2 Excerpts from Calculation SM-96-1064-0012016-07-25025 July 2016 Units 1 and 2 - Response to Request for Additional Information for TSTF-312. Enclosure 2 Excerpts from Calculation SM-96-1064-001 NL-16-0870, Units 1 and 2 Supplement to Response to Request for Additional Information for TS 3.3.5 Loss of Power Diesel Generator Start Instrumentation LAR2016-06-30030 June 2016 Units 1 and 2 Supplement to Response to Request for Additional Information for TS 3.3.5 Loss of Power Diesel Generator Start Instrumentation LAR NL-16-0628, Southern Nuclear Operating Company Response to Third Request for Additional Information Regarding Standard Emergency Plan: Cover Letter, Attachment 1 and Enclosures 1 - 102016-06-0909 June 2016 Southern Nuclear Operating Company Response to Third Request for Additional Information Regarding Standard Emergency Plan: Cover Letter, Attachment 1 and Enclosures 1 - 10 NL-16-0739, Corrected Response to Second Request for Additional Information Regarding Standard Emergency Plan2016-05-26026 May 2016 Corrected Response to Second Request for Additional Information Regarding Standard Emergency Plan NL-16-0572, Response to Request for Additional Information Regarding TSTF-432-A, Revision 12016-04-13013 April 2016 Response to Request for Additional Information Regarding TSTF-432-A, Revision 1 NL-16-0415, Response to Request for Additional Information for TS 3.3.5 Loss of Power Diesel Generator Start Instrumentation LAR2016-04-11011 April 2016 Response to Request for Additional Information for TS 3.3.5 Loss of Power Diesel Generator Start Instrumentation LAR NL-16-0098, Response to Request for Additional Information for Adoption of Technical Specifications Task Force Traveler 3122016-03-0303 March 2016 Response to Request for Additional Information for Adoption of Technical Specifications Task Force Traveler 312 NL-16-0169, Southern Nuclear Operating Company Response to First Request for Additional Information Re Standard Emergency Plan. Attachment 1: SNC Response to NRC RAI-1 Fleet Standard Emergency Plan and Enclosure 1: Evaluation of Proposed Changes Encl2016-02-17017 February 2016 Southern Nuclear Operating Company Response to First Request for Additional Information Re Standard Emergency Plan. Attachment 1: SNC Response to NRC RAI-1 Fleet Standard Emergency Plan and Enclosure 1: Evaluation of Proposed Changes Enclos ML16060A3282016-02-17017 February 2016 Southern Nuclear Operating Company Response to First Request for Additional Information Re Standard Emergency Plan. Attachment 1: SNC Response to NRC RAI-1 Fleet Standard Emergency Plan and Enclosure 1: Evaluation of Proposed Changes Enclos NL-15-2222, Response to Request for Additional Information for RHR Autoclosure Interlock Function Elimination LAR2016-01-28028 January 2016 Response to Request for Additional Information for RHR Autoclosure Interlock Function Elimination LAR NL-16-0086, Units 1 and 2 - Response to Third Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 22016-01-28028 January 2016 Units 1 and 2 - Response to Third Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 2 NL-15-2062, Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 22015-11-25025 November 2015 Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 2 2023-08-23
[Table view] |
Text
Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 SOUTHERN << \
Fax 205.992.7601 NUCLEAR A SOUTHERN COMPANY JAN 2 8 2016 Docket Nos.: 50-348 NL-15-2222 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Units 1 and 2 Response to Request for Additional Information for RHR Autoclosure Interlock Function Elimination LAR Ladies and Gentlemen:
By letter dated August 31, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15261A673) Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) to eliminate the Residual Heat Removal (RHR) autoclosure interlock and its associated Surveillance Requirement for Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2.
By letter dated December 17,2015, the Nuclear Regulatory Commission (NRC) sent SNC a request for additional information (RAI). The enclosure to this letter provides the SNC response to the NRC RAI.
This letter contains no new NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
U.S. Nuclear Regulatory Commission NL-15-2222 Page2 Mr. C. R. Pierce states he is Regulatory Affairs Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.
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-.f C. R. Pierce ~~/
Regulatory Affairs Director
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CRP/JMC/Iac Sworn to and subscribed before me this Jg day of ~ .. a ~ '2016.
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Notary Public
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My commission expires: /0 ;l.o t '1
Enclosure:
Response to Request for Additional Information cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President - Farley Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. L. D. Wert, Regional Administrator (Acting)
Mr. S. A. Williams, NRR Project Manager- Farley Mr. P. K. Niebaum, Senior Resident Inspector- Farley Alabama Department of Public Health Dr. D. E. Williamson, State ~ealth Officer
Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Request for Additional Information for RHR Autoclosure Interlock Function Elimination LAR Enclosure Response to Request for Additional Information
Enclosure to NL-15-2222 Response to Request for Additional Information By letter dated August 31, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15261A673) Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) to eliminate the Residual Heat Removal (AHA) autoclosure interlock and its associated Surveillance Requirement for Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2. By letter dated December 17,2015, the Nuclear Regulatory Commission (NRC) sent SNC a request for additional information (RAI). The enclosure to this letter provides the SNC response to the NRC RAI.
Request For Additional Information #1 Section 2.3, "Procedural Changes," of the WCAP-11736, "Residual Heat Removal System Autoclosure Interlock Removal Report for the Westinghouse Owners Group," NRC staff safety evaluation report (SEA) states that WCAP-11736 proposes generic procedural requirements. The SEA also states that 11the staff agrees with this generic guidance assuming a surveillance procedure for the
[Residual Heat Removal (RHR) System] suction valve alarms is added to ensure these alarms remain operable ... Provide a description of the mentioned surveillance procedure for the new RHR System suction valve alarm at Farley.
SNC Response to RAI #1 A new annunciator response procedure (ARP) will be prepared for Farley Nuclear Plant, Units 1 and 2 for the alarm that will be added in the Main Control Room.
The LAR states in section 3.0, Technical Evaluation, that an alarm will be added to each RHR suction isolation valve which will actuate if the valve is open and the reactor coolant system (RCS) pressure is greater than the open permissive setpoint and less than the RHR system design pressure minus the RHR pump head pressure at minimum flow.
SNC intends to prepare the procedure to be consistent with the generic procedural requirements in WCAP-11736, as applicable to FNP. In addition, Vogtle Electric Generating Plant (VEGP) Units 1 and 2, another SNC Westinghouse NSSS plant, submitted a similar LAR in 1991 to eliminate their AHA autoclosure interlock. FNP will use the VEGP ARP as a template when preparing the ARP for FNP. The procedure will be entered when an AHA suction isolation valve is open and RCS pressure is above the alarm setpoint.
There are no automatic actions associated with this alarm. The actions that will be required by the ARP that the operator should take, are, at a minimum, as follows:
- 1. Check RCS pressure.
- 2. If a Reactor Coolant Pump (RCP) was inadvertently started, secure the RCP as necessary.
- 3. If the RCS is water solid, lower RCS pressure by adjusting Charging and Letdown.
- 4. If a steam bubble exists in the pressurizer, lower RCS pressure by operating pressurizer spray and/or auxiliary spray valves as necessary.
E- 1
Enclosure to NL-15-2222 Response to Req~:~est for Additional Information
- 5. If one or more RHR suction valves were inadvertently left open, close applicable valve(s).
An item has been entered into the FNP corrective action program to track preparation of the new ARP.
Request For Additional Information #2 The license amendment request discusses a new alarm that will actuate if any RH R System suction isolation valve is open and the reactor coolant system pressure is greater than the open permissive setpoint and less than the RHR System design pressure minus the RHR pump head pressure at minimum flow.
NUREG-0800, Branch Technical Position (BTP) 5-4, "Design Requirements of the Residual Heat Removal System," contains an RHR System isolation requirement that states: "The valves should have independent diverse interlocks to protect against one or both valves being open during a [reactor coolant system] increase above the design pressure of the RHR system, to the extent that such interlocks will not degrade high system reliability during shutdown operations (see Generic Letter 88-17)." Additionally, Section 2.5, "Safety Function of the Autoclosure Interlock," of the WCAP-11736 SER also highlights this concern: "The ACI function is to preclude conditions that could lead to a LOCA outside of containment, Event V, due to operator error. The sequence that concerns the staff in particular is that case in which the operator closes one of the isolation valves and not the other... "
- a. Since a level of diversity is being removed by removing the ACI, how will plant procedures ensure that operators will take appropriate action when the alarm is received in the control room?
- b. What additional operator training will be required prior to implementation of the revised Technical Specifications?
- a. Plant operators are trained to respond to alarms by using the guidance in the applicable annunciator response procedures. The ARP will include operator actions to take when the alarm is received. A list of the potential actions that will be included in the ARP is provided in the SNC response to RAI #1 above.
- b. Pending approval of the associated LAR, all operators will be trained on the removal of the RHR autoclosure interlock, which will include training on the new alarm and any associated procedure changes.
Request For Additional Information #3 The RHR System provides a low temperature overpressure protection safety function during shutdown and refueling operations by providing pressure relief to the pressure relief tank inside containment. Previously, power lockout of the RHR System containment isolation valves was implemented at FNP to reduce the E-2
Enclosure to NL-15-2222 Response to Request for Additional Information frequency of inadvertent valve closure due to the presence of the ACI. With the removal of the ACI circuitry, FNP is also removing the requirement to lockout power to the AHA System containment isolation valves below a reactor coolant system temperature of 180 degrees Fahrenheit as discussed in the license amendment request. LCO 3.4.12, "Low Temperature Overpressure Protection (L TOP) System," requires that two AHA suction relief valves with setpoints less than or equal to 450 pounds per square inch gauge be available or alternatively that the reactor coolant system be depressurized with a reactor coolant system vent greater than or equal to 2.85 square inches in Modes 4, 5, and 6. The presence of LCO 3.4.12 does not inherently prevent the closure of the two AHA suction relief valves during Modes 4, 5, and 6; appropriate plant procedures are also required to ensure that the LCO will be met. With power no longer being removed and manual valve closure possible, describe plant procedures associated with the control of the RH A suction relief valves to provide assurance that inadvertent isolation will not occur during Modes 4, 5, and 6.
SNC Response to RAI #3 The standard operating procedure (SOP) for the FNP AHA system states in multiple places:
When the temperature of any RCS Cold leg is at or below 275°F, then two AHA relief valves with lift settings of less than or equal to 450 psig shall be operable and their isolation valves, Q1 E11 MOV8701 A & Q1 E11 MOV8701 B and Q1 E11 MOV8702A & Q1 E11 MOV8702B shall be open.
Note that this SOP is used to align the AHA system as directed by the applicable unit operating procedure to meet LCO 3.4.12, "L'ow Temperature Overpressure Protection (LTOP) System," when the AHA relief valves are used for low temperature overpressure protection. Conditions 0 and E of TS 3.4.12 address one and two inoperable AHA relief valves, respectively. Required Actions 0.1, 0.2, 0.3, and E.1 identify the actions to be taken to provide low temperature overpressure protection if the AHA relief valves are inoperable.
In addition, existing surveillance test procedures ensure the Surveillance Requirements (SA) are met forTS 3.4.12, "Low Temperature Overpressure Protection (LTOP) System," to verify AHA suction isolation valves are open for each required AHA suction relief valve every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in the applicable modes. If two AHA suction relief valve paths are not operable, there is a SA to verify an RCS vent ~ 2.85 square inches exists every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for unlocked open vent valve(s) or every 31 days for locked open vent valve(s).
Operators are trained to comply with procedures and the requirements of Technical Specifications. The elimination of the AHA autoclosure interlock will require multiple procedure changes, in addition to the new alarm ARP. There will be changes to the AHA standard operating procedures, unit operating procedures for shutdown to cold shutdown and unit operating procedures for startup from cold shutdown as a result of the AHA autoclosure interlock elimination LAR approval. The procedure changes will ensure that the AHA suction isolation valves are not inappropriately closed in Modes 4, 5 or 6.
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Enclosure to NL-15-2222 Response to Request for Additional Information It is desirable to maintain power to the RHA suction isolation valves in the shutdown modes to improve the capability of the operators to isolate RHA from the RCS in the event of a leak in the AHA system. Operations personnel or any SNC personnel do not manipulate any valve without procedural guidance; therefore, the potential of the AHA suction isolation valves being inadvertently isolated is not expected to occur. An item has been entered into the FNP corrective action program to track all procedure changes associated with the AHA autoclosure interlock elimination.
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Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 SOUTHERN << \
Fax 205.992.7601 NUCLEAR A SOUTHERN COMPANY JAN 2 8 2016 Docket Nos.: 50-348 NL-15-2222 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Units 1 and 2 Response to Request for Additional Information for RHR Autoclosure Interlock Function Elimination LAR Ladies and Gentlemen:
By letter dated August 31, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15261A673) Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) to eliminate the Residual Heat Removal (RHR) autoclosure interlock and its associated Surveillance Requirement for Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2.
By letter dated December 17,2015, the Nuclear Regulatory Commission (NRC) sent SNC a request for additional information (RAI). The enclosure to this letter provides the SNC response to the NRC RAI.
This letter contains no new NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
U.S. Nuclear Regulatory Commission NL-15-2222 Page2 Mr. C. R. Pierce states he is Regulatory Affairs Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.
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-.f C. R. Pierce ~~/
Regulatory Affairs Director
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CRP/JMC/Iac Sworn to and subscribed before me this Jg day of ~ .. a ~ '2016.
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Notary Public
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Enclosure:
Response to Request for Additional Information cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President - Farley Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. L. D. Wert, Regional Administrator (Acting)
Mr. S. A. Williams, NRR Project Manager- Farley Mr. P. K. Niebaum, Senior Resident Inspector- Farley Alabama Department of Public Health Dr. D. E. Williamson, State ~ealth Officer
Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Request for Additional Information for RHR Autoclosure Interlock Function Elimination LAR Enclosure Response to Request for Additional Information
Enclosure to NL-15-2222 Response to Request for Additional Information By letter dated August 31, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15261A673) Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) to eliminate the Residual Heat Removal (AHA) autoclosure interlock and its associated Surveillance Requirement for Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2. By letter dated December 17,2015, the Nuclear Regulatory Commission (NRC) sent SNC a request for additional information (RAI). The enclosure to this letter provides the SNC response to the NRC RAI.
Request For Additional Information #1 Section 2.3, "Procedural Changes," of the WCAP-11736, "Residual Heat Removal System Autoclosure Interlock Removal Report for the Westinghouse Owners Group," NRC staff safety evaluation report (SEA) states that WCAP-11736 proposes generic procedural requirements. The SEA also states that 11the staff agrees with this generic guidance assuming a surveillance procedure for the
[Residual Heat Removal (RHR) System] suction valve alarms is added to ensure these alarms remain operable ... Provide a description of the mentioned surveillance procedure for the new RHR System suction valve alarm at Farley.
SNC Response to RAI #1 A new annunciator response procedure (ARP) will be prepared for Farley Nuclear Plant, Units 1 and 2 for the alarm that will be added in the Main Control Room.
The LAR states in section 3.0, Technical Evaluation, that an alarm will be added to each RHR suction isolation valve which will actuate if the valve is open and the reactor coolant system (RCS) pressure is greater than the open permissive setpoint and less than the RHR system design pressure minus the RHR pump head pressure at minimum flow.
SNC intends to prepare the procedure to be consistent with the generic procedural requirements in WCAP-11736, as applicable to FNP. In addition, Vogtle Electric Generating Plant (VEGP) Units 1 and 2, another SNC Westinghouse NSSS plant, submitted a similar LAR in 1991 to eliminate their AHA autoclosure interlock. FNP will use the VEGP ARP as a template when preparing the ARP for FNP. The procedure will be entered when an AHA suction isolation valve is open and RCS pressure is above the alarm setpoint.
There are no automatic actions associated with this alarm. The actions that will be required by the ARP that the operator should take, are, at a minimum, as follows:
- 1. Check RCS pressure.
- 2. If a Reactor Coolant Pump (RCP) was inadvertently started, secure the RCP as necessary.
- 3. If the RCS is water solid, lower RCS pressure by adjusting Charging and Letdown.
- 4. If a steam bubble exists in the pressurizer, lower RCS pressure by operating pressurizer spray and/or auxiliary spray valves as necessary.
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Enclosure to NL-15-2222 Response to Req~:~est for Additional Information
- 5. If one or more RHR suction valves were inadvertently left open, close applicable valve(s).
An item has been entered into the FNP corrective action program to track preparation of the new ARP.
Request For Additional Information #2 The license amendment request discusses a new alarm that will actuate if any RH R System suction isolation valve is open and the reactor coolant system pressure is greater than the open permissive setpoint and less than the RHR System design pressure minus the RHR pump head pressure at minimum flow.
NUREG-0800, Branch Technical Position (BTP) 5-4, "Design Requirements of the Residual Heat Removal System," contains an RHR System isolation requirement that states: "The valves should have independent diverse interlocks to protect against one or both valves being open during a [reactor coolant system] increase above the design pressure of the RHR system, to the extent that such interlocks will not degrade high system reliability during shutdown operations (see Generic Letter 88-17)." Additionally, Section 2.5, "Safety Function of the Autoclosure Interlock," of the WCAP-11736 SER also highlights this concern: "The ACI function is to preclude conditions that could lead to a LOCA outside of containment, Event V, due to operator error. The sequence that concerns the staff in particular is that case in which the operator closes one of the isolation valves and not the other... "
- a. Since a level of diversity is being removed by removing the ACI, how will plant procedures ensure that operators will take appropriate action when the alarm is received in the control room?
- b. What additional operator training will be required prior to implementation of the revised Technical Specifications?
- a. Plant operators are trained to respond to alarms by using the guidance in the applicable annunciator response procedures. The ARP will include operator actions to take when the alarm is received. A list of the potential actions that will be included in the ARP is provided in the SNC response to RAI #1 above.
- b. Pending approval of the associated LAR, all operators will be trained on the removal of the RHR autoclosure interlock, which will include training on the new alarm and any associated procedure changes.
Request For Additional Information #3 The RHR System provides a low temperature overpressure protection safety function during shutdown and refueling operations by providing pressure relief to the pressure relief tank inside containment. Previously, power lockout of the RHR System containment isolation valves was implemented at FNP to reduce the E-2
Enclosure to NL-15-2222 Response to Request for Additional Information frequency of inadvertent valve closure due to the presence of the ACI. With the removal of the ACI circuitry, FNP is also removing the requirement to lockout power to the AHA System containment isolation valves below a reactor coolant system temperature of 180 degrees Fahrenheit as discussed in the license amendment request. LCO 3.4.12, "Low Temperature Overpressure Protection (L TOP) System," requires that two AHA suction relief valves with setpoints less than or equal to 450 pounds per square inch gauge be available or alternatively that the reactor coolant system be depressurized with a reactor coolant system vent greater than or equal to 2.85 square inches in Modes 4, 5, and 6. The presence of LCO 3.4.12 does not inherently prevent the closure of the two AHA suction relief valves during Modes 4, 5, and 6; appropriate plant procedures are also required to ensure that the LCO will be met. With power no longer being removed and manual valve closure possible, describe plant procedures associated with the control of the RH A suction relief valves to provide assurance that inadvertent isolation will not occur during Modes 4, 5, and 6.
SNC Response to RAI #3 The standard operating procedure (SOP) for the FNP AHA system states in multiple places:
When the temperature of any RCS Cold leg is at or below 275°F, then two AHA relief valves with lift settings of less than or equal to 450 psig shall be operable and their isolation valves, Q1 E11 MOV8701 A & Q1 E11 MOV8701 B and Q1 E11 MOV8702A & Q1 E11 MOV8702B shall be open.
Note that this SOP is used to align the AHA system as directed by the applicable unit operating procedure to meet LCO 3.4.12, "L'ow Temperature Overpressure Protection (LTOP) System," when the AHA relief valves are used for low temperature overpressure protection. Conditions 0 and E of TS 3.4.12 address one and two inoperable AHA relief valves, respectively. Required Actions 0.1, 0.2, 0.3, and E.1 identify the actions to be taken to provide low temperature overpressure protection if the AHA relief valves are inoperable.
In addition, existing surveillance test procedures ensure the Surveillance Requirements (SA) are met forTS 3.4.12, "Low Temperature Overpressure Protection (LTOP) System," to verify AHA suction isolation valves are open for each required AHA suction relief valve every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in the applicable modes. If two AHA suction relief valve paths are not operable, there is a SA to verify an RCS vent ~ 2.85 square inches exists every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for unlocked open vent valve(s) or every 31 days for locked open vent valve(s).
Operators are trained to comply with procedures and the requirements of Technical Specifications. The elimination of the AHA autoclosure interlock will require multiple procedure changes, in addition to the new alarm ARP. There will be changes to the AHA standard operating procedures, unit operating procedures for shutdown to cold shutdown and unit operating procedures for startup from cold shutdown as a result of the AHA autoclosure interlock elimination LAR approval. The procedure changes will ensure that the AHA suction isolation valves are not inappropriately closed in Modes 4, 5 or 6.
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Enclosure to NL-15-2222 Response to Request for Additional Information It is desirable to maintain power to the RHA suction isolation valves in the shutdown modes to improve the capability of the operators to isolate RHA from the RCS in the event of a leak in the AHA system. Operations personnel or any SNC personnel do not manipulate any valve without procedural guidance; therefore, the potential of the AHA suction isolation valves being inadvertently isolated is not expected to occur. An item has been entered into the FNP corrective action program to track all procedure changes associated with the AHA autoclosure interlock elimination.
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