Letter Sequence Response to RAI |
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CAC:MF8700, Implement 10 CFR 50, Appendix J, Option B (Approved, Closed) CAC:MF8701, Implement 10 CFR 50, Appendix J, Option B (Approved, Closed) |
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MONTHYEARRS-16-191, License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-10-26026 October 2016 License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Project stage: Request ML16350A0742016-12-15015 December 2016 Acceptance for Review of Application Concerning Extension of Type a and Type C Leak Rate Test Frequencies Project stage: Acceptance Review RS-17-024, Supplement to License Amendment Request for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Regarding Hardened Containment Vent System Modifications and Installation of Primary Containment Isolation Valves2017-02-16016 February 2017 Supplement to License Amendment Request for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Regarding Hardened Containment Vent System Modifications and Installation of Primary Containment Isolation Valves Project stage: Supplement ML17151A3822017-06-0505 June 2017 Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Leak Rate Test Frequencies Project stage: RAI ML17164A1152017-06-15015 June 2017 Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Leak Rate Test Frequencies Project stage: RAI RS-17-098, Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch)2017-07-17017 July 2017 Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch) Project stage: Response to RAI RS-17-099, Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch)2017-08-0808 August 2017 Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch) Project stage: Response to RAI RS-17-131, Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals2017-09-27027 September 2017 Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals Project stage: Supplement RS-17-133, Additional Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals2017-10-0303 October 2017 Additional Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals Project stage: Supplement RS-17-157, Supplemental Information Regarding the Third Interval Containment Inservice Inspection (Cisi) Schedule for LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals2017-11-0808 November 2017 Supplemental Information Regarding the Third Interval Containment Inservice Inspection (Cisi) Schedule for LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals Project stage: Supplement ML17283A0852017-11-16016 November 2017 Issuance of Amendment Nos. 226 and 212 - Revise Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Leak Rate Test Frequencies (CAC MF8700 and MF8701; L-2016-LLA-0021) Project stage: Approval 2017-02-16
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Category:Letter
MONTHYEARIR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 ML23354A2902024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information IR 05000373/20230032023-11-0909 November 2023 County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001 ML23286A2602023-11-0808 November 2023 Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report IR 05000373/20234012023-11-0707 November 2023 County Station Security Baseline Inspection Report 05000373/2023401 and 05000374/2023401 RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000374/20230102023-10-11011 October 2023 NRC Inspection Report 05000374/2023010 IR 05000373/20233012023-09-15015 September 2023 Errata to NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor ML23212A9012023-08-0303 August 2023 Regulatory Audit Report to Support the Review of the Amendments to Relocation of the Pressure Temperature Limit Curves to the Pressure and Temperature Limits Report IR 05000373/20230022023-08-0101 August 2023 County Station - Integrated Inspection Report 05000373/2023002 and 05000374/2023002 ML23208A3182023-07-27027 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis ML23192A5272023-07-12012 July 2023 NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 ML23186A2062023-07-0606 July 2023 Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000374/2023010 ML23181A1502023-06-30030 June 2023 Combined Response to Request for Additional Information and Supplemental Information in Support of LAR to Relocate Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000373/20230112023-06-26026 June 2023 County Station - Quadrennial Fire Protection Team Inspection Report 05000373/2023011 and 05000374/2023011 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167A0352023-06-16016 June 2023 Registration of Use of Cask to Store Spent Fuel ML23171A9562023-06-12012 June 2023 Post Exam Ltr RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000373/20230012023-05-10010 May 2023 County Station - Integrated Inspection Report 05000373/2023001 and 05000374/2023001 ML23123A2202023-05-0303 May 2023 Relief Request I4R-14 for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23121A1612023-05-0101 May 2023 Information Meeting (Open House) with a Question-and-Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of LaSalle County Station, Units 1 and 2 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23107A1822023-04-18018 April 2023 Operator Licensing Examination Approval Lasalle County Station, May 2023 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000373/20220062023-03-0101 March 2023 Annual Assessment Letter for LaSalle County Station, Units 1 and 2 (Report 05000373/2022006 and 05000374/2022006) RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station ML23024A1372023-02-0303 February 2023 Request for Withholding Information from Public Disclosure for LaSalle County Station, Unit Nos. 1 and 2 ML23031A1972023-01-31031 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information, Inspection Report Nos. 05000373/2023011 and 05000374/2023011 IR 05000373/20220042023-01-31031 January 2023 County Station - Integrated Inspection Report 05000373/2022004 and 05000374/2022004 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 2024-01-05
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-083, Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical2022-06-17017 June 2022 Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical RS-22-033, Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0303 March 2022 Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-085, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016)2021-08-17017 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016) NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments RS-21-055, Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended.2021-05-10010 May 2021 Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended. JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting RS-21-050, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-16016 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) RS-21-045, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-0707 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) RS-21-040, Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-03-31031 March 2021 Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-21-027, Response to Request for Additional Information Regarding Request for Exemption from Pre-Access Drug and Alcohol Testing Requirements in 10 CFR 26.652021-02-21021 February 2021 Response to Request for Additional Information Regarding Request for Exemption from Pre-Access Drug and Alcohol Testing Requirements in 10 CFR 26.65 ML21022A1302021-01-22022 January 2021 Response to Request for Additional Information Regarding the License Amendment Request to Adopt 10 CFR 50.69 RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)2020-10-29029 October 2020 Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018) RS-20-133, Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.692020-10-16016 October 2020 Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69 RS-20-104, Supplement to the Request for a License Amendment Technical Specification 3.7.3, Ultimate Heat Sink2020-09-11011 September 2020 Supplement to the Request for a License Amendment Technical Specification 3.7.3, Ultimate Heat Sink RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants RS-19-052, Supplement to the Response to Request for Additional Information Regarding License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High ..2019-04-24024 April 2019 Supplement to the Response to Request for Additional Information Regarding License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High .. RS-19-019, Response to Request for Additional Information Regarding Relief Request 13R-152019-04-0202 April 2019 Response to Request for Additional Information Regarding Relief Request 13R-15 JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements RS-18-097, Response to Request for Additional Information and Supplemental Information-License Amendment.2018-07-27027 July 2018 Response to Request for Additional Information and Supplemental Information-License Amendment. RS-18-086, Response to Request for Additional Information Regarding License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System2018-07-16016 July 2018 Response to Request for Additional Information Regarding License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System RS-18-078, Supplemental Information Related to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-06-18018 June 2018 Supplemental Information Related to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) RS-18-014, Supplement to Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits2018-01-25025 January 2018 Supplement to Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits RS-17-147, Response to Request for Additional Information Regarding LaSalle County Station Fourth Inservice Inspection Interval Relief Request 14R-012017-11-10010 November 2017 Response to Request for Additional Information Regarding LaSalle County Station Fourth Inservice Inspection Interval Relief Request 14R-01 RS-17-146, Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis2017-10-19019 October 2017 Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis RS-17-099, Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch)2017-08-0808 August 2017 Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch) RS-17-101, Response to Request for Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis2017-07-28028 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis RS-17-102, Response to Request for Supplemental Information Regarding Fourth Inservice Inspection Interval Relief Request 14R-012017-07-20020 July 2017 Response to Request for Supplemental Information Regarding Fourth Inservice Inspection Interval Relief Request 14R-01 RS-17-098, Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch)2017-07-17017 July 2017 Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch) RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-010, Response to Request for Additional Information Regarding LaSalle County Station Alternative Request RV-01 for the Lnservice Testing Program Fourth 10-Year Interval2017-02-0909 February 2017 Response to Request for Additional Information Regarding LaSalle County Station Alternative Request RV-01 for the Lnservice Testing Program Fourth 10-Year Interval RS-16-244, Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings2016-12-12012 December 2016 Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings RS-16-176, County, 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 Fukushima Dai-ic2016-12-0101 December 2016 County, 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 Fukushima Dai-ich RS-16-125, Spent Fuel Pool Evaluation Supplemental 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 Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental 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 Fukushima Dai-ichi Accident RS-16-159, County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings2016-07-28028 July 2016 County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings RS-16-144, Response to Request for Additional Information on Severe Accident Mitigation Alternatives for License Renewal Environmental Review Dated July 6, 20162016-07-11011 July 2016 Response to Request for Additional Information on Severe Accident Mitigation Alternatives for License Renewal Environmental Review Dated July 6, 2016 RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure RS-16-076, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2016-04-11011 April 2016 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. 2023-07-24
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4300 Winfic:lcl f!o;id Warrenville, IL 6055!i ,. ........... Exelon Generation
.. ,, 630 657 2000 Of rice RS-17-098 10 CFR 50.90 July 17, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type A and Type C Containment Leak Rate Test Intervals (SBPB Branch)
References:
- 1) Letter from D. M. Gullatt (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "License Amendment Request to Revise Technical Specifications 5.5.13, 'Primary Containment Leakage Rate Testing Program,'
for Permanent Extension of Type A and Type C Leak Rate Test Frequencies," dated October 26, 2016 (ADAMS Accession No. ML 16300A200)
- 2) Letter from B. Vaidya (U.S. Nuclear Regulatory Commission) to 8. C. Hanson (Exelon Generation Company, LLC), "LaSalle County Station, Units 1 and 2, Request for Additional Information Regarding License Amendment Request for Extension of Type A and Type C Leak Rate Test Frequencies (CAC Nos. MF8700 and MF8701)," dated June 15, 2017 (ADAMS Accession No. ML17164A 115) In Reference 1, Exelon Generation Company, LLC (EGC) submitted an amendment request for LaSalle County Station (LSCS), Units 1 and 2. The proposed amendment would revise Technical Specifications (TS) 5.5.13, "Primary Containment Leakage Rate Testing Program," to allow for the permanent extension of the Type A integrated leak rate testing (ILRT) and Type C leak rate testing frequencies.
In Reference 2, the U.S. Nuclear Regulatory Commission (NRG) requested additional information related to its review of Reference
- 1. The requested information is provided in Attachment 1 of this letter. There are no regulatory commitments contained within this letter.
July 17, 2017 U.S. Nuclear Regulatory Commission Page2 Should you have any questions concerning this letter, please contact Ms. Lisa A. Simpson at {630) 657-2815.
Respectfully, David M. Gullatt Manager -Licensing Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector, LaSalle County Station Illinois Emergency Management Agency -Division of Nuclear Safety ATIACHMENT1 Response to Request for Additional Information By letter to the Nuclear Regulatory Commission (NRG) dated October 26, 2016 (Reference 1 ), Exelon Generation Company, LLC (EGG) requested a license amendment to revise the Technical Specifications 5.5.13, "Primary Containment Leakage Rate Testing Program," for LaSalle County Station, Units 1 and 2, to allow for the permanent extension of the Type A integrated leak rate testing and Type C leak rate testing frequencies.
In a letter dated June 15, 2017, the NRG requested additional information to complete its review of the proposed LAA.
SBPB RAl-1 Referring to Table 3.2.5-1 "LSCS Unit 1 Type A Test History" and Table 3.2.5-2 "LSCS Unit 2 Type A Test History" of Attachment 1 to the submittal, please provide past Type A integrated leak rate testing (ILRT) results. a. Provide a breakdown of the results into "As-found minimum leakage rate" and "As-left maximum leakage rate," to enable the NRG staff evaluation of the results against performance criteria and restart acceptance criteria.
As discussed during a clarification call between the NRG and Exelon Generation Company, LLC (EGG) on June 14, 2017, the response to SBPB RAl-1 will include the results from the past two Type A ILRTs for LSCS Unit 1 and Unit 2. EGC Response 1994 LSCS Unit 1 I LAT As-Found:
The as-found leakage rate at the 95% upper confidence limit (UCL) was 0.266 wt.%/day.
The as-found leakage rate is the sum of the 95% UCL (0.1685 wt.%/day) plus the non-vented pathways (0.0335 wt.%/day) plus the as-found adjustment (0.064 wt.%/day), which takes into account the improvements made to Type B and C pathways during the Type A outage in advance of the conduct of the ILRT. The as-found leakage rate was less than the acceptance criteria of 1.0 La (0.635 Wt.%/day).
As-Left: The as-left leakage rate at the 95% UCL was 0.202 wt.%/day.
The as-left leakage rate is the sum of the 95% UCL (0.1685 wt.%/day) plus the non-vented pathways (0.0335 wt.%/day).
There were no significant leaks requiring pathways to be isolated during the performance of the ILRT. The as-left leakage rate was less than the acceptance criteria of 0.75 La (0.47625 wt.%/day).
Page 1 of 9 ATTACHMENT 1 Response to Request for Additional Information 2008 LSCS Unit 1 I LRT As-Found:
The as-found leakage rate at the 95% UCL is 0.47044 wt.%/day.
The as-found leakage rate is the sum of the 95% UCL (0.4213 wt.%/day) plus the non-vented pathways (0.04914 wt.%/day).
The as-found leakage rate was less than the acceptance criteria of 1.0 La (0.635 wt. %/day). As-Left: The as-left leakage rate at the 95% UCL is 0.47044 wt.%/day.
The as-left leakage rate is the sum of the 95% UCL (0.4213 wt.%/day) plus the non-vented pathways (0.04914 wt.%/day).
There were no significant leaks requiring pathways to be isolated during the performance of the ILRT. The as-left leakage rate was less than the acceptance criteria of 0.75 La (0.47625 wt.%/day).
1993 LSCS Unit 2 ILRT As-Found:
The as-found leakage rate at the 95% UCL was 0.4273 wt.%/day.
The as-found leakage rate is the sum of the as-left leak rate (0.3164 wt.%/day), plus the non-vented pathways (0.0315 wt.%/day), and the back-correction leak rate (0.0794 wt.%/day) which takes into account the improvements made to Type B and C pathways during the Type A outage in advance of the conduct of the ILRT. The as-found leakage rate was less than the acceptance criteria of 1.0 La (0.635 wt.%/day).
As-Left: The as-left leakage rate at the 95% UCL was 0.3164 wt. %/day. The as-left leakage rate is the sum of the calculated leakage rate of 0.28486 wt. %/day plus the leakage rate of all non-vented penetrations which is 0.0315 wt.%/day.
There were no significant leaks requiring pathways to be isolated during the performance of the ILRT. The as-left leakage rate was less than the acceptance criteria of 0.75 La (0.47625 wt.%/day).
2009 LSCS Unit 2 ILRT As-Found:
The as-found leakage rate at the 95% UCL is 0.3863 wt.%/day.
The as-found leakage rate is the sum of the 95% UCL (0.3547 wt%/day) plus the non-vented pathways (0.03158 wt.%/day).
The as-found leakage rate was less than the acceptance criteria of 1.0 La (0.635 wt.%/day).
Page 2 of 9 ATTACHMENT 1 Response to Request for Additional Information As-Left: The as-left leakage rate at the 95% UCL is 0.3863 wt.%/day.
The as-left leakage rate is the sum of the 95% UCL (0.3547 wt.%/day) plus the non-vented pathways (0.03158 wt.%/day).
There were no significant leaks requiring pathways to be isolated during the performance of the ILRT. The as-left leakage rate was less than the acceptance criteria of 0.75 La (0.47625 wt.%/day).
- b. Technical Specification (TS) 5.5.13 states that the peak calculated primary containment pressure for the design basis loss of cooling accident of Pa (pressure absolute), at 42.6 pounds per square inch gauge (psig). Section 9.2.3 "Extended Test Intervals" of Nuclear Energy Institute (NEI) 94-01, Revision 2-A, states that "in the event where previous Type A tests were performed at reduced pressure (as described in 1 O CFR 50, Appendix J, Option B), at least one of the two.consecutive periodic Type A tests shall be performed at peak accident pressure (Pa)." Provide the actual ILRT pressures employed during the last recent Type A tests for both LSCS units. EGC Response Note that Part B of SBPB -RAI -1 equates Pa to both "pressure absolute" and to "peak accident pressure." EGC's response is aligned with the TS 5.5.13 definition for Pa as the peak calculated primary containment pressure.
The pressures employed during the last recent Type A tests for both LSCS Units 1 and 2 are as follows:
- Final containment pressure during the LSCS Unit 1 2008 ILRT was 42.48 psig, which was greater than the minimum required pressure of 39.9 psig
- Final containment pressure during the LSCS Unit 2 2009 ILRT was 41.26 psig, which was greater than the minimum required pressure of 39.9 psig. Both the Unit 1 2008 ILRT and the Unit 2 2009 ILRT were performed in accordance with ANSI/ANS 56.8-1994.
The standard requires the Type A test pressure not be less than 0.96 Pac (accident pressure) nor exceed Pd (design pressure).
Calculated peak containment accident pressure at the time of the tests was 39.9 psig. The LSCS drywell design pressure is 45 psig. Therefore, the tests met the test pressure criteria specified in ANSI/ANS 56.8-1994.
Note: LSCS TS 5.5.13 states the peak calculated primary containment pressure for the design basis loss of cooling accident, Pa, is 42.6 pounds per square inch gauge (psig). This pressure is higher than the Pa used during the 2008 LSCS Unit 1 and 2009 LSCS Unit 2 ILRTs as a result of a TS change in January 2015 to resolve a non-conservative TS. Amendment Nos. 212 (LSCS Unit 1) and 198 (LSCS Unit 2) changed the peak calculated primary containment internal pressure value from 39.9 psig to 42.6 psig. Page 3 of 9 ATIACHMENT1 Response to Request for Additional Information SBPB RAl-2 In Table 3.7.1-1 "NEI 94-01Revision2-A Limitations and Conditions" of Attachment 1 to the submittal, it states that: LSCS will utilize the definition in NEI 94-01 Revision 3-A, Section 5.0. This definition has remained unchanged from Revision 2-A to Revision 3-A of NEI 94-01. Tables 3.2.5-1 and 3.2.5-2 provided the historical ILRT results for Units 1 and 2. Provide the definition of "performance leakage rate" used in Tables 3.2.5-1 and 3.2.5-2 during historical ILRT results for LSCS Units 1 and 2, with a comparison and/or a conclusion that it is consistent with the definition in NEI 94-01, Revisions 2-A and 3-A, which includes the clarification provided in the NRC's safety evaluation (SE). EGC Response The definition of "performance leakage rate" was first introduced in NEI 94-01, Revision O following the addition of Option B to 1 O CFR 50 Appendix J. On March 11, 1996, the NRG issued Amendment Nos 11 O (LSCS Unit 1) and 95 (LSCS Unit 2) which revised TS 5.5.13 to incorporate 1 O CFR Part 50, Appendix J, Option B at LSCS. Therefore, 1982, 1986, 1989, 1993 and 1994 Unit 1 ILRTs along with the 1983, 1987, 1990, 1992, and 1993 Unit 2 ILRTs were not performed under the performance-based standard as they were performed prior to the adoption of Appendix J, Option B. The definition of performance leakage rate has remained unchanged from NEI 94-01, Revisions 0, 2-A, and 3-A. As noted in Section 3.1.1.1 of the NRG Safety Evaluation for NEI 94-01 Revision 2-A dated June 25, 2008, the "performance leakage rate" definition is different from that of ANSI/ANS 56.8-2002.
The definition contained in NEI 94-01 Revisions 0, 2-A and 3-A is more inclusive as it considers excessive leakage in the performance determination.
The following definition was used to calculate the 2008 Unit 1 ILRT and 2009 Unit 2 ILRT performance leakage rate: The performance criteria for Type A test allowable leakage is less than 1.0 La. This allowable leakage rate is calculated as the sum of the Type A UCL and As-Left MNPLR leakage rate for all Type Band Type C pathways that were in service, isolated or not lined up in their test position (i.e., drained and vented to containment atmosphere) prior to performing the Type A test. In addition, leakage pathways that were isolated during performance of the test because of excessive leakage must be factored into the performance determination.
If the leakage can be determined by a local leakage rate test, the As-Found MNPLR for that leakage path must also be added to the Type A UCL. If the leakage cannot be determined by local leakage rate testing, the performance criteria are not met. The 2008 Unit 1 ILRT performance leakage rate was 0.470 wt.%/day, well below the 1.0 La limit of 0.635 wt.%/day.
The included penalty for isolated pathways during the Unit 1 2008 ILRT performance was 0.049 wt.%/day.
The 2009 Unit 2 ILRT performance leakage rate was 0.386 wt.%/day, which was below the 1.0 La limit of 0.635 wt.%/day.
The included penalty for isolated pathways during the Unit 2 2009 ILRT performance was 0.032 wt.%/day.
Page 4 of 9 ATTACHMENT 1 Response to Request for Additional Information SBPB RAl-3 In Table 3.7.1.1 of Attachment 1 to the submittal, the licensee indicates that" ... there are no major modifications planned." Section 9.2.4 of NEI Topical Report 94-01, Revision 2, indicates that Type A testing is required after major modifications to the containment, or upon approval by the NRG, the licensee may perform a short duration structural test of the containment.
For minor modifications or modifications to the pressure boundary, a local leak rate test (LLRT) was indicated.
As the LSGS, Unit 1 and 2, containments have been in service for more than 40 years, provide a summary of all significant modifications to the Units 1 and 2 containments since the last ILRTs and the subsequent post-modification testing. The summary should discuss the extent to which actions were completed consistent with the NRG staff limitations and conditions in the staff SE dated June 25, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081140105), which endorsed NEI 94-01, Revision 2. EGC Response:
No significant modifications requiring post-modification testing have been performed on the primary containments at LSGS Unit 1 or Unit 2 since the 2008 Unit 1 and 2009 Unit 2 ILRTs. SBPB RAl-4 Table 3.4.5-3 "LSGS Unit 1 Type B and Type G LLRT Program Implementation Review" and Table 3.4.5-4 "LSGS Unit 2 Type B and Type G LLRT Program Implementation Review" of Attachment 1 to the submittal, identified components that were on extended intervals and have not demonstrated acceptable performance during the last two outages for Unit 1 (L 1R15-2014 and L1R16-2016) and Unit 2 (L2R14-2013 and L2R15-2015).
Provide the "As-found" and "As-left" maximum pathway leakage rate and minimum pathway leakage values, respectively, for the penetrations associated with the failed components.
EGC Response The following table shows the MNPLR and MXPLR for the penetrations associated with the failed components displayed in Table 3.4.5-3, "LSGS Unit 1 Type Band Type G LLRT Program Implementation Review," and Table 3.4.5-4 "LSGS Unit 2 Type Band Type G LLRT Program Implementation Review," of Attachment 1 to the submittal.
Page 5 of 9 ATTACHMENT 1 Response to Request for Additional Information L1R15-2014 As-Found As-Left Measured Measured Leak As-Leak Rate Found Rate As-Left As-Left Penetration Valves Description (SCFH) MNPLR (SCFH) MNPLR MXPLR 1 E12-FOOS RHR 596 1.05 M-7 1 E12-SHUTDOWN 0.52 0.52 1.05 F009 COOLING 0.52 0.52 1 E12-SUCTION F460 0 0 L 1 R16 -2016 As-Found As-Left Measured Measured Leak As-Leak Rate Found Rate As-Left As-Left Penetration Valves Description (SCFH) MNPLR (SCFH) MNPLR MXPLR M-45 1C51-TIP BALL 19.8 19.8 19.8 19.8 19.8 J004E VALVE E 1 E51-RCIC TURBINE M-101 F080 EXHAUST Note 1 Note 1 1.75 0.88 1.75 1 E51-VACUUM F086 BREAKER :> ';;\,, :' ,,,:<;:::;;., **, ..
,, \' ,,, , \' , 'c;::;,\ >>: C.\. , , ... . *.' , , *. '** ;:;)*, , " ... ;.: ; *, :". " ; : : < ' >.:. *:*, ,:;,, ;;:;'J:i/
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'*::*. ' :;<<.,, ' L2R15-2015 As-Found As-Left Measured Measured Leak As-Leak Rate Found Rate As-Left Penetration Valves Description (SCFH) MNPLR (SCFH) MNPLR 2C51-TIP BALL M-42 J004C VALVE C 15.53 15.53 15.53 15.53 2RF012 DRYWELL 17.23 3.62 M-98 2RF013 FLOOR DRAIN 15.6 15.6 15.6 3.62 SUMP Note 1: The test of M-101 is performed between the two containment isolation valves, 1 E51-F080 and 1 E51-F086.
Due to excessive leakage past 1 E51-F086, a satisfactory leakage test of the penetration could not be performed.
Following repair of 1 E51-F086, a successful test of the penetration was performed with a measured leakage rate of 1.75 SCFH. Page 6 of 9 As-Left MXPLR 15.53 15.6 ATIACHMENT1 Response to Request for Additional Information SBPB RAl-5 Provide a total count of Type Band Type C components at LSCS, Units 1 and 2, and how many of them are currently on extended petiormance-based test intervals of 120 months for Type B and 60 months for Type C. EGC Response The percentage of the total number of LSCS Unit 1 Type B tested components that are on extended performance-based test intervals is 91 % (i.e., 98 of 108 total Type B tests). The percentage of the total number of LSCS Unit 2 Type B tested components that are on extended petiormance-based test intervals is 88% (i.e., 78 of 89 total Type B tests). Note: The LSCS Type B testing schedule is conservative, in that, only one component at Unit 2 has been extended to the maximum allowed 120-month test interval.
The totals listed above are for varying frequencies beyond 30 months. The following is a breakdown of the component totals on the various extended test frequencies.
Unit 1: Five-Year Test Frequency:
8 components Six-Year Test Frequency:
5 components Eight-Year Test Frequency:
72 components Nine-Year Test Frequency:
13 components Unit 2: Four-Year Test Frequency:
1 component Five-Year Test Frequency:
7 components Six-Year Test Frequency:
5 components Eight-Year Test Frequency:
57 components Nine-Year Test Frequency:
7 components Ten-Year Test Frequency:
1 component The percentage of the total number of LSCS Unit 1 Type C tested components that are on 60-month extended petiormance-based test intervals is 65% (i.e., 95 of 147 total Type C tests). The percentage of the total number of LSCS Unit 2 Type C tested components that are on 60-month extended performance-based test intervals is 59% (i.e., 86 of 147 total Type C tests). Note: The remaining Type C components which are on either a fixed 30-month (i.e., Regulatory Guide 1.163 components) interval or an interval between 30 and 60-months are established and
- maintained under administrative controls in accordance with the LSCS Appendix J Program. Page 7 of 9 ATTACHMENT 1 Response to Request for Additional Information SBPB RAl-6 In supplemental letter dated February 16, 2017, EGC stated that two new primary containment isolation valves (PCIVs) will be added to the 10 CFR Part 50, Appendix J, program at each of LPCS, Units 1 and 2. The valves are being added in response to the NRC issued Order EA-13-109, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions, 11 to all operating boiling-water reactor licenses with Mark I and Mark II containments.
Provide details regarding post-modification Appendix J leak rate testing of the subject penetrations that would be conducted prior to resuming power operations after the new PC IVs are installed during the spring 2017 refueling outage for Unit 2 and the spring refueling outage of 2018 for Unit 1, including the acceptance criteria of the test results, including information if a new opening through the primary containment is required or an existing opening would suffice. EGC Response A modification was completed at LSCS Unit 2 to install a hardened containment vent system in response to NRC Order EA-13-109 during refueling outage L2R16 in February 2017. The modification added two new primary containment isolation valves (PCIVs): 2PC009A and 2PC01 OA. This penetration modification taps into existing containment penetration M-104 located between the suppression pool and the drywall and is between existing PCIVs 2PC001A and 2PC003A. As a result, the installation of the hardened containment vent system and associated PCIVs did not require a new opening through the primary containment.
The local leak rate test is performed between the two PCIVs and is administratively controlled by procedure LTS-100-57, "Hardened Containment Isolation Valves Local Leak Rate Test 2PC009A and 2PC010A," with the acceptance criteria below 30.0 standard cubic feet per hour (SCFH). The local leak rate test of the penetration was completed on February 16, 2017 with the following results:
- As-Found MNPLR: 0.655 SCFH
- As-Left MXPLR: 1.310 SCFH A similar hardened containment vent system will be installed for LSCS Unit 1 with the same configuration as defined above and is scheduled for installation during the L 1R17 refueling outage in February 2018. The local leak rate test will be administratively controlled by procedure LTS-100-57, with the acceptance criteria below 30.0 SCFH. Page 8 of 9 ATIACHMENT1 Response to Request for Additional Information REFERENCES
- 1) Letter from D. M. Gullatt (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "License Amendment Request to Revise Technical Specifications 5.5.13, 'Primary Containment Leakage Rate Testing Program,'
for Permanent Extension of Type A and Type C Leak Rate Test Frequencies," dated October 26, 2016 (ADAMS Accession No. ML 16300A200)
- 2) Letter from B. Vaidya (U.S. Nuclear Regulatory Commission) to B. C. Hanson, "LaSalle County Station, Units 1 and 2, Request for Additional Information Regarding License Amendment Request for Extension of Type A and Type C Leak Rate Test Frequencies (CAC Nos. MFB700 and MF8701)," dated June 15, 2017 (ADAMS Accession No. ML 17163A422)
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