Letter Sequence Response to RAI |
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MONTHYEARML20205L6032020-08-11011 August 2020 Letter, Individual SUNSI Notice, Revision to Technical Specification 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections Project stage: Other ML20205L6112020-08-13013 August 2020 FRN, Individual SUNSI Notice, Revision to Technical Specification 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections Project stage: Other RS-20-100, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections2020-08-19019 August 2020 Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections Project stage: Response to RAI ML20246G8652020-09-21021 September 2020 Issuance of Amendment Nos. 222 and 222 One-Time Extension of Unit No. 2 Steam Generator Inspections (COVID-19) Project stage: Approval 2020-08-13
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Similar Documents at Byron |
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Category:Letter type:RS
MONTHYEARRS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-117, 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-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-100, 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 RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. 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RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-057, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-04-0808 April 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-014, Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time2022-03-24024 March 2022 Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time RS-22-041, Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes2022-03-22022 March 2022 Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes RS-22-036, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-03-10010 March 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement 2024-06-28
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-117, 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 BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . 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 ML21320A2422021-11-16016 November 2021 Stations - Response to Request for Additional Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds 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 ML21225A0062021-08-13013 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 0 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 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-21-024, Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2021-03-16016 March 2021 Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-21-029, Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition2021-03-15015 March 2021 Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition RS-21-015, Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-182021-02-10010 February 2021 Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-18 RS-20-017, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-8852021-02-0101 February 2021 Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 RS-20-150, Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements2020-12-0101 December 2020 Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements RS-20-143, Response to Request for Additional Information Regarding Application to Revise Technical Specifications 3.8.1, AC Sources- Operating2020-11-20020 November 2020 Response to Request for Additional Information Regarding Application to Revise Technical Specifications 3.8.1, AC Sources- Operating RS-20-100, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections2020-08-19019 August 2020 Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections 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 RS-19-100, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended.2019-10-0707 October 2019 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended. 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RS-18-072, Response to Request for Additional Information Regarding 50.69 Amendment2018-06-13013 June 2018 Response to Request for Additional Information Regarding 50.69 Amendment 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-17-138, Stations - Response to Request for Additional Information Related to License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements'2017-10-25025 October 2017 Stations - Response to Request for Additional Information Related to License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements' RS-17-084, Response to Request for Additional Information for Byron Station and Braidwood Station Post Peening Relief Requests2017-07-14014 July 2017 Response to Request for Additional Information for Byron Station and Braidwood Station Post Peening Relief Requests RS-17-085, Response to Request for Additional Information Regarding Amendments to Remove Obsolete License and Technical Specification Items2017-06-29029 June 2017 Response to Request for Additional Information Regarding Amendments to Remove Obsolete License and Technical Specification Items RS-17-032, Response to Request for Additional Information Regarding the License Amendment Request to Utilize the TORMIS Computer Code Methodology2017-03-20020 March 2017 Response to Request for Additional Information Regarding the License Amendment Request to Utilize the TORMIS Computer Code Methodology 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-17-036, Response to Request for Additional Information Regarding Relief Request I4R-102017-02-24024 February 2017 Response to Request for Additional Information Regarding Relief Request I4R-10 RS-16-259, Response to Request for Additional Information for Relief Request I4R-10: Proposed Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval2016-12-29029 December 2016 Response to Request for Additional Information for Relief Request I4R-10: Proposed Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval RS-16-175, 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 the Near Term-Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-11-0202 November 2016 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 the Near Term-Task Force Review of Insights from the Fukushima Dai-ichi Accident RS-16-195, Supplemental Information for the Fourth Inservice Inspection Interval Relief Request 14R-082016-09-29029 September 2016 Supplemental Information for the Fourth Inservice Inspection Interval Relief Request 14R-08 RS-16-122, 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 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 Fukushima Dai-ichi Accident 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-16-079, Response to Request for Additional Information Regarding the Request for Exemption from 10 CFR 50.55a, Codes and Standards, Paragraph (h)(2), Protection Systems, Including Change to Request NRC Approval Under 10 CFR 50.55a..2016-04-11011 April 2016 Response to Request for Additional Information Regarding the Request for Exemption from 10 CFR 50.55a, Codes and Standards, Paragraph (h)(2), Protection Systems, Including Change to Request NRC Approval Under 10 CFR 50.55a.. RS-16-078, Clarification to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-04-0404 April 2016 Clarification to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds RS-16-067, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-22022 March 2016 Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds RS-16-045, Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-02-11011 February 2016 Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds RS-16-039, Response to Request for Additional Information Regarding the Request for Exemption from 10 CFR 50.55a, Codes and Standards, Paragraph (h)(2), Protection Systems.2016-01-29029 January 2016 Response to Request for Additional Information Regarding the Request for Exemption from 10 CFR 50.55a, Codes and Standards, Paragraph (h)(2), Protection Systems. RS-15-319, Responds to Request for Additional Information Regarding Relief Request RP-1 Associated with the Fourth Inservice Testing Interval2015-11-30030 November 2015 Responds to Request for Additional Information Regarding Relief Request RP-1 Associated with the Fourth Inservice Testing Interval 2024-08-09
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Text
4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 65 7 2000 Office RS-20-100 10 CFR 50.90 August19,2020 U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, "Steam Generator (SG) Program ,"
for a One-Time Deferral of Steam Generator Tube Inspections
References:
- 1) Letter from D. Murray (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Application for Revision to TS 5.5.9, 'Steam Generator (SG) Program ,' for a One-Time Deferral of Steam Generator Tube Inspections," dated July 10, 2020 (ADAMS Package Accession No .
ML20196L732))
- 2) Email from J. Wiebe (U.S. Nuclear Regulatory Commission) to L.A. Simpson (Exelon Generation Company, LLC), "Preliminary RAls for Byron , Unit 2, Amendment to Defer SIG Inspections," dated August 10, 2020 By application dated July 10, 2020 (Reference 1), Exelon Generation Company, LLC (EGC) requested an amendment to the Technical Specifications (TS) for Renewed Facility License Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron) . The proposed changes would allow a one-time deferral of the steam generator tube inspections required in Section 5.5 .9.d.3, "Steam Generator (SG) Program," of the TS for Byron, Units 1 and 2. Although the proposed change only affects Byron Unit 2, Reference 1 and this submittal are docketed for Byron Station , Units 1 and 2, since the TS are common to Units 1 and 2 for Byron.
The proposed changes were submitted in response to social distancing recommendations by the United States Centers for Disease Control and Prevention, which have been issued as a defensive measure against the spread of the Coronavirus Disease 2019 (COVID-19).
In NRC email dated August 10, 2020 (Reference 2), the NRC determined that additional information is needed to complete its review. The Attachment to this letter provides the requested information.
August19,2020 U.S. Nuclear Regulatory Commission Page 2 EGC has reviewed the information supporting the No Significant Hazards Consideration and the Environmental Consideration that was previously provided to the NRC in Attachment 1 of the Reference 1 letter. The additional information provided in this submittal does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration. This additional information also does not affect the conclusion that there is no need for an environmental assessment to be prepared in support of the proposed amendment.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b),
EGC is providing a copy of this letter and its attachment to the State of Illinois.
This letter contains no regulatory commitments. Should you have any questions concerning this submittal, please contact Ms. Lisa Simpson at (630) 657-2815.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 19th day of August 2020 .
Respectfully, Kusuma wat i Digita lly signed by Kusumaw atim urray, Putri murray, Putn.
DN: cn = Kusumawatimurray, Putri Date: 2020.08. 19 11:49:41
- 05'00' Putri D. Kusumawati Murray Sr. Manager - Licensing Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - Byron Station Illinois Emergency Management Agency - Division of Nuclear Safety
ATTACHMENT Response to Request for Additional Information By application dated July 10, 2020 (Reference 1), Exelon Generation Company, LLC (EGC) requested an amendment to the Technical Specifications (TS) for Renewed Facility License Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron) . This proposed amendment request would modify Technical Specifications (TS) 5.5 .9, "Steam Generator (SG) Program ," for a one-time revision to the frequency for SG tube inspections. The requested TS amendments support deferral of the TS required inspections until the next Unit 2 refueling outage.
By email dated August 10, 2020 (Reference 2), the NRC determined that additional information is needed to complete its review. This attachment provides the requested information .
References :
- 1) Letter from D. Murray (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Application for Revision to TS 5.5.9, 'Steam Generator (SG) Program,'
for a One-Time Deferral of Steam Generator Tube Inspections," dated July 10, 2020
- 2) Email from J. Wiebe (U .S. Nuclear Regulatory Commission) to L.A. Simpson (Exelon Generation Company, LLC), "Preliminary RAls for Byron, Unit 2, Amendment to Defer SIG Inspections," dated August 10, 2020
- 3) EC 632009, Revision 0, "Foreign Object Operational Assessment to Support B2R22 Deferral LAR," dated July 2020 NRC RAI 1 Table 4, "Byron B2R20 Foreign Objects Remaining in SGs Based on Visual Inspection ," in , "Description and Assessment," of the application , provides details for six foreign objects (FOs) that were found during visual inspections during Byron Unit 2 Refueling Outage 20 (B2R20). While reviewing the Byron Unit 2 SG tube inspection report for B2R20 dated April 5, 2018 (ADAMS Accession No. ML18095A116), the NRC staff noted on page 9 that the tube in Row 35, Column 22 (R35C22) in SG 2A and the tube in R40C52 in SG 2D "were preventatively plugged due to the FO that caused the wear is still present that may cause continued tube wear." The SG tube inspection report also stated that the foreign object wear in these tubes were newly reported in B2R20. Based on the statements in the SG tube inspection report for B2R20 , identify whether the presence of the FOs impacting these tubes were visually confirmed. If they were visually confirmed, provide justification for not including these FOs in Table 4 of Attachment 1 in the application. Provide justification that the FO analysis in the application is still valid if it only accounts for six of the eight FOs remaining in the SGs from B2R20.
EGC Response to NRC RAI 1 The two tubes preventatively plugged during B2R20 for foreign object wear (i.e., R35C22 in SG 2A and R40C52 in SG 2D) both had an assumed FO present at the wear location, which was just below the fifth tube support plate (i .e., tube support plate (TSP) Location 05H).
These two tubes are located several tubes into the bundles, which negatively impacted their accessibility. The Possible Loose Parts (PLPs) detected by eddy current in these tubes were not accessible for visual inspection during B2R20; therefore , they were not included in Table 4, "Byron B2R20 Foreign Objects Remaining in SGs Based on Visual Examination ," in Page 1 of 5
ATTACHMENT Response to Request for Additional Information of Reference 1. Support 05H is the third support structure above the secondary side handhole on the Hot Leg top of tubesheet. The nearest secondary side access handholes in the Byron Unit 2 SGs are located at the pre-heater section (Cold Leg) and at the top of tubesheet on the Hot Leg side. It is general industry practice not to pursue visual confirmation or removal of PLPs at the upper tube supports unless significant damage has occurred due to a FO . In these cases, to achieve access, it may be necessary to cut a hole into the SG vessel wall and inner wrapper.
Based on +Point' 1 eddy current, it was determined that both FOs were located just below 05H TSP and are positioned within the quatrefoil flow holes of the two tubes that were plugged in B2R20; therefore, they do not pose any risk to the surrounding tubes. To verify this, all tubes surrounding the tubes with the FOs (24 tubes for each FO) were inspected during B2R20 with the +Point' probe and confirmed there was no contact of the FOs with any adjacent tubes. The circumferential extent of the wear flaw within a quatrefoil lobe is limited to less than 90 degrees; therefore, there is no risk of the tube severing and affecting the surrounding tubes. Based on these as-left conditions, the FO analysis summarized in Reference 1 is still valid, as FO wear to inservice tubes from these two remaining TSP FOs is not expected. In addition, the revised 3-cycle Operational Assessment for FO wear (Reference 3) considers the possibility that new FO wear indications at TSPs similar to those detected in B2R20 could occur (either via new FOs entering the SGs or existing FOs potentially "relocating" from their current plugged tube locations). These hypothetical new FO wear indications at TSPs, even if actively growing at a conservative growth rate (i.e., 17.5%TW/cycle) for three operating cycles, were evaluated to not exceed the Condition Monitoring limit.
NRC RAI 2 On page 21 of Attachment 1 of the application, you state that there are 12 tube support plate (TSP) wear indications and five drilled support plate (DSP) wear indications in the Byron Unit 2 SGs. In Note 2 of Table 7, "Summary of Input Parameters and OA [Operational Assessment]
Results for Mechanical Wear at Structures," on page 22 of Attachment 1, you state that there are 13 TSP paired indications and 10 DSP paired indications for B2R18 and B2R20 combined. Provide clarification of the type of TSP and DSP wear indications reported on page 21 (i.e., single or paired wear indications) and confirm the reported numbers.
EGC Response to NRC RAI 2 Page 21 of Attachment 1 of Reference 1 states that there are 12 TSP wear indications and five DSP wear indications in the Byron Unit 2 SGs. These counts are correct for projecting growth of the TSP and DSP wear indications returned to service after B2R20. Note that one tube with two TSP wear indications was removed from service by plugging in B2R20.
In Note 2 of Table 7, "Summary of Input Parameters and OA [Operational Assessment] Results for Mechanical Wear at Structures," on page 22 of Attachment 1 of Reference 1, it states that there are 13 TSP paired indications and 10 DSP paired indications for B2R18 and B2R20 combined. Subtracting single (new and unpaired) indications found in B2R18 and B2R20, EGC 1
+Point is a trademark or registered trademark of Zetec, Inc. , its subsidiaries and/or affiliates in the United States of America and may be registered in other countries through the world. All rights reserved. Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners.
Page 2 of 5
ATTACHMENT Response to Request for Additional Information confirms there are 13 TSP paired indications for B2R18 and B2R20 combined, as reported in Note 2 of Table 7 on page 22 of Attachment 1 of Reference 1. The 1O DSP paired indications for B2R18 and B2R20 combined that were reported in Note 2 of the same table was overstated due to the inadvertent counting of two legacy FO wears near a DSP. The correct count of DSP paired indications for B2R18 and B2R20 combined is 8.
The table below provides a clarification of the type (i.e., TSP and DSP) and count of paired wear indications from the B2R18 and B2R20 refueling outages combined reported in Note 2 of Table 7 on page 22 of Attachment 1 of Reference 1.
B2R20 B2R18 B2R18 + B2R20 Description
___ (~~~-?_99_~~!.!.~)____ ___ (~~g;_gs_!~~-!.?L . .J~9.!~_?_, T_~_t?J~.?.L TSP DSP TSP DSP TSP DSP Wear Wear Wear Wear Wear Wear Total# of Support Wear Indications 74 14 1 5 4 NR NR Reported
- of Repeat Indications "Paired" to a Wear Indication from Prior 84 4 5 4 13 83
_______________________l_~-~-P.~~!~~~---------------------- --------------- --------------- --------------- --------------- --------------- ---------------
- of "Single" (New and Unpaired) 52 1 2 0 NR NR Indications Notes:
(1) Fourteen is the number of TSP wear indications reported in B2R20. However, Page 21 of Attachment 1 of Reference 1 states, "There are 12 TSP wear indications in the Byron Unit 2 SGs." This count is based on the number of remaining indications returned to service after B2R20 as one tube, SG 2C R49C65, with two TSP wear indications, was plugged during B2R20.
(2) Includes two "unpaired" indications that were identified at locations where prior TSP wear was reported in B2R18. This is due to the sizing technique from B2R18 to B2R20 being changed from bobbin to +Point'. Two tubes that each had a single TSP wear indication reported in B2R18 subsequently had wear detected at two separate quatrefoil lands at the same support locations in B2R20 (SG 2B R46C50 and SG 2C R49C65).
(3) Previously reported as 10 DSP paired indications in Note 2 to Table 7 of Attachment 1 of Reference 1. The updated count of paired DSP wear indications in Note 2 from 10 to eight does not affect the bounding degradation growth rates observed for DSP wear reported in Table 7 of Attachment 1 of Reference 1 and used in the 3-cycle Operational Assessment.
(4) There was one additional repeat TSP wear indication identified in B2R20 (14% TW), which was also detected in B2R18 (13%TW) but was not reported in ML15051A312 (i.e ., tube SG 2B R49C73) . There is no impact on the B2R20 or B2R18 operational assessments as a result of this omission of one TSP wear indication in B2R18. EGC has documented this issue in the corrective action program.
Page 3 of 5
ATTACHMENT Response to Request for Additional Information NRC RAI 3 There appears to be a several typographical errors in Attachment 1 of the application which are identified below.
EGC Response to NRC RAI 3 The following responses are provided as correction to the typographical errors identified in Reference 1.
NRC RAI 3.a
- a. Section 3.2.3.d, "Operational Assessment Summary for All Degradation Mechanisms, Including Predicted Margin to the Tube Integrity Performance Criteria at B2R23 (October 2021 ),"consistently states that B2R23 is in October 2021, however, it is the NRC staffs understanding that B2R23 is in April 2022. Provide confirmation that B2R23 is in April 2022. In addition, provide clarification whether the approximately 52 effective full power months, also referenced in this section, is based on October 2021 or April 2022 .
EGC Response to NRC RAI 3.a Byron refueling outage B2R23 is scheduled in April 2022 , which is approximately 18 months following the fall 2020 refueling outage (B2R22). All instances where "October 2021" is stated in the EGC application dated July 10, 2020 (Reference 1) are typographical errors; these should instead state "April 2022," which is the month and year in which B2R23 is scheduled to begin.
In addition , the approximately 52 effective full power months referenced in Section 3.2.3 .d of of Reference 1 is based on April 2022 (B2R23). The corrected statement is as follows:
In summary, using the deterministic method, which is considered to be the most conservative OA approach, tubes with any of the three existing structural support mechanical wear mechanisms can safely operate for three cycles (approximately 52 EFPM) until April 2022 without challenging the tube integrity limits for each type of wear.
NRC RAI 3.b
- b. On page 18, you state that the structural integrity performance criteria will be satisfied at B2R23 for existing and potential degradation and that the "accident-induced leakage performance criteria (AILPC) for the limiting accident condition will be met for the end of Cycle 22 condition." The NRC staff believes that you intended to state that the AILPC for the limiting accident condition will be met for the end of Cycle 23 condition . Please confirm that the AILPC will be met for the end of Cycle 23 condition.
Page 4 of 5
ATTACHMENT Response to Request for Additional Information EGC Response to NRC RAI 3.b EGG confirms that the AILPC for the limiting accident condition will be met for the end of Cycle 23 condition. Including "end of Cycle 22" in this statement of Reference 1 was a typographical error. The corrected statement is as follows:
Accident-induced leakage performance criteria (AILPC) for the limiting accident condition will be met for the end of Cycle 23 condition .
NRC RAI 3.c
- c. Note 3 to Table 6, "Summary of Operational Assessment (Exam Scope, Results, and Margins) for Potential SCC [Stress Corrosion Cracking] Degradation Mechanisms for 3 Cycle Operation to B2R23 (October 2021 ),"on page 20, states that "no primary-to-secondary leakage was reported during Cycle 21 and is not expected for Cycle 22."
Confirm whether or not that you intended to state that there was no primary-to-secondary leakage reported during Cycles 21 and 22 and is not expected for Cycle 23 .
EGC Response to NRC RAI 3.c Table 6, "Summary of Operational Assessment (Exam Scope, Results, and Margins) for Potential SCC Degradation Mechanisms for 3 Cycle Operation to B2R23," contains typographical errors. The title of Table 6 should reference "April 2022" instead of "October 2021 ." In addition, Note 3 to Table 6 contains a typographical error regarding Cycle 22 . The corrected Note 3 is as follows:
(3) No primary-to-secondary leakage was reported during Cycle 21. to date for Cycle 22.
and is not expected for Cycle 23.
NRC RAI 3.d
- d. On page 24, you state "should a loose part be present in the hot leg or cold leg primary bowl during operating Cycle 22, Byron Unit 2 will take appropriate action to minimize any damage to the Steam Generators." Confirm whether or not that you intended to state should a loose part be present in the hot leg or cold leg primary bowl during operating Cycle 23 .
EGC Response to NRC RAI 3.d The use of "Cycle 22" in the discussion regarding the Loose Parts Detection System of the Steam Generations contained a typographical error; it should have stated "Cycle 23." The corrected statement is as follows:
Should a loose part be present in the hot leg or cold leg primary bowl during the remainder of Cycle 22 or operating Cycle 23, Byron Unit 2 will take appropriate action to minimize any damage to the Steam Generators.
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