Letter Sequence Response to RAI |
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EPID:L-2021-LLA-0112, Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request (Approved, Closed) |
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MONTHYEARML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting Project stage: Meeting ML21165A4062021-06-14014 June 2021 Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request Project stage: Request PMNS20210910, Public Meeting with Exelon Generation Company, LLC (Exelon) to Discuss License Amendment Request Involving Spent Fuel Pool Cooling at Calvert Cliffs Nuclear Power Plant2021-07-13013 July 2021 Public Meeting with Exelon Generation Company, LLC (Exelon) to Discuss License Amendment Request Involving Spent Fuel Pool Cooling at Calvert Cliffs Nuclear Power Plant Project stage: Meeting ML21194A0632021-07-13013 July 2021 Tabulation of Proposed Changes in License Amendment Request Project stage: Other ML21201A0482021-07-19019 July 2021 Acceptance of Requested Licensing Action to Change Spent Fuel Pool Cooling Design Basis Project stage: Acceptance Review ML21200A0742021-07-20020 July 2021 Audit Plan in Support of Review of License Amendment Request Regarding Change Spent Fuel Pool Cooling Design Basis Project stage: Other ML21214A0202021-08-0909 August 2021 License Amendment Request to Change Spent Fuel Pool Cooling Design Basis Project stage: Other ML21225A3532021-08-13013 August 2021 Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request Supplement Project stage: Supplement ML21228A0742021-08-27027 August 2021 Summary of July 13, 2021, Meeting with Exelon Generation Company, LLC Concerning License Amendment Request for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Concerning Spent Fuel Pool Cooling Design Basis Change (L-2021-LLA-0112) Project stage: Meeting ML21287A0932021-10-0505 October 2021 Request for Additional Information: Calvert Cliffs 1 & 2 LAR to Revise Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Basis (EPID L-2021-LLA-0112) (Email) Project stage: RAI ML21298A0432021-10-25025 October 2021 Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request Project stage: Response to RAI ML21308A5072021-11-0404 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request Project stage: Supplement ML21334A3422021-11-30030 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request Project stage: Supplement ML21343A0122022-01-10010 January 2022 Regulatory Audit Summary Related to License Amendment Request to Modify the Licensing Basis of the Spent Fuel Pool and Shutdown Cooling System Project stage: Other ML21347A8642022-01-13013 January 2022 Issuance of Amendment Nos. 342 and 320 Modifying the Licensing Basis to Allow for Full Core Offload with No Shutdown Cooling Loop Available During Certain Refueling Outages Project stage: Approval 2021-07-13
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Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 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 ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23241A8432023-08-29029 August 2023 Enclosure 3 - Response to Request for Additional Information - Non-Proprietary Version ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23166A1052023-06-15015 June 2023 Response to Request for Additional Information Related to the License Amendment Request to Modify the Long-Term Coupon Surveillance Program ML23155A0012023-06-0404 June 2023 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request - One-Time Extension of the Control Room Emergency Ventilation System (C 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 ML21334A3422021-11-30030 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request 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 ML21308A5072021-11-0404 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request ML21298A0432021-10-25025 October 2021 Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request 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 ML21208A0072021-07-26026 July 2021 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-567 Rev 1, Add Containment Sump TS to Address GSI-191 Issues 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-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 ML20317A1122020-11-12012 November 2020 Final Response and Close-out to Generic Letter 2004-02 ML20280A5132020-10-0606 October 2020 Response to Request for Additional Information - End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20182A1102020-06-30030 June 2020 Response to Request for Additional Information to License Amendment Request - Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements Voltage ML20107F7652020-04-16016 April 2020 Response to Request for Additional Information to License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program 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 ML19282B7182019-10-0909 October 2019 Revised Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19277D1032019-10-0303 October 2019 Response to Request for Additional Information Revised - Final Response to Generic Letter 2004-02 ML19217A3372019-08-0606 August 2019 Response to RAI #6 Regarding the Application to Adopt 10 CFR 50.69 ML19217A1432019-08-0505 August 2019 Revised Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19200A2162019-07-19019 July 2019 Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19183A0122019-07-0101 July 2019 Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power ... 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 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 ML18316A0342018-11-12012 November 2018 Response to Request for Additional Information: Proposed Changes to Technical Specification 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to 14 ... ML18283A0342018-10-10010 October 2018 Supplement to Final Response to Generic Letter 2004-02, Dated August 13, 2018 ML18239A2602018-08-27027 August 2018 Supplement to Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk .. ML18201A4062018-06-21021 June 2018 Plants, Units 1 and 2 - Exelon'S Response to NRC Questions ML18172A1452018-06-21021 June 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed ... NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. 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) ML18047A1242018-02-16016 February 2018 Relief Requests Associated with Fifth Ten-Year Lnservice Testing Interval: Supplement 1 - Response to Request for Additional Information ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 ML18018B3402018-01-18018 January 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times. ML18011A6652018-01-11011 January 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times. RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 ML17081A3032017-03-22022 March 2017 Response to Request for Additional Information to License Amendment Request - Control Room Emergency Ventilation System 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-17-003, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-01-0505 January 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML16246A2022016-09-0101 September 2016 Response to Request for Additional Information Regarding Relief Request for Dissimilar Metal Butt Weld Examinations 2023-08-29
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200 Exelon Way 200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10CFR50.90 October 25, 2021 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 Docket Nos. 50-317 and 50-318
Subject:
Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request
References:
- 1. Letter from David P. Helker (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request, dated June 14, 2021 (ADAMS Accession No. ML21165A406)
- 2. Letter from Michael Marshall, U.S. Nuclear Regulatory Commission to David P. Rhoades, Exelon Generation Company, LLC, Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Audit Plan in Support of Review of License Amendment Request Regarding Change Spent Fuel Pool Cooling Design Basis (EPID L-2021-LLA-0112), dated July 20,2021 (ADAMS Accession No. ML21200A074)
- 3. Letter from David P. Helker (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, " Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request Supplement, dated August 13, 2021 (ADAMS Accession No. ML21225A353)
- 4. Email from Andrea Mayer, U.S. Nuclear Regulatory Commission, to Francis J Mascitelli, Exelon Generation Company, LLC, " Request for Additional Information: Calvert Cliffs 1 & 2 LAR to Revise Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Basis (L-2021-LLA-0112)," dated October 5, 2021 (ADAMS Accession No. ML21287A093)
In accordance with 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, Exelon Generation Company, LLC (Exelon) requested changes to the Spent Fuel Pool and Shutdown Cooling Licensing Design Basis of the Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (CCNPP) (Reference 1).
The original proposed changes would revise the Updated Final Safety Analysis Report (UFSAR) Section 9.4, Spent Fuel Pool Cooling System, design basis to allow for partial and full core offloads without being supplemented with one train of the Shutdown Cooling (SDC) system. In addition, the Spent Fuel Pool temperature would be allowed to increase from a
CCNPP RAI Response to SPFC-SDC Systems LAR October 25, 2021 Page 2 maximum of 120 °F and 130 °F for partial and full core offloads, respectively, to a maximum of 150°F under certain conditions.
On July 20, 2021 NRC announced an Audit Plan to review License Amendment Request (LAR) referenced supporting calculations (Reference 2).
On August 13, 2021 Exelon supplemented the Reference 1 License Amendment Request (LAR) to reduce the LAR scope (Reference 3). The scope of the request was revised to include only full core offloads during refueling outages conducted when the spent fuel pool cooling system (SFPC) service water temperature can be maintained below 50 °F and the SDC system is unavailable to assist the SFPC system, if required.
On October 5, 2021 NRC issued a Request for Additional Information regarding spent fuel pool wall stresses (Reference 4) in order to complete their Audit Review of the LAR supporting calculations.
The attachment to this letter contains the NRC's Request for Additional Information (RAI) followed by Exelon's response.
Exelon has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC in References 1 and 3. Exelon has concluded that the information provided in this response does not affect the bases for concluding that the proposed license amendments do not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92. In addition, Exelon has concluded that the information in this response does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendments.
There are no regulatory commitments contained in this response.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), Exelon is notifying the State of Maryland of this response to a request for additional information by transmitting a copy of this letter and its attachment to the designated State Official.
Should you have any questions concerning this submittal, please contact Frank Mascitelli at (610) 765-5512.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 25th day of October 2021.
Respectfully, David P. Helker Sr. Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information
CCNPP RAI Response to SPFC-SDC Systems LAR October 25, 2021 Page 3 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, CCNPP Project Manager [CCNPP] USNRC S. Seaman, State of Maryland
ATTACHMENT Calvert Cliffs Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 Docket Nos. 50-317 and 50-318 Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request Response to NRC Request for Additional Information
Attachment SFPC-SDC Systems Licensing Design Basis LAR Response to NRC Request for Additional Information Page 1 of 4
References:
- 1. Letter from David P. Helker (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request, dated June 14, 2021 (ADAMS Accession No. ML21165A406)
- 2. Letter from Michael Marshall, U.S. Nuclear Regulatory Commission to David P. Rhoades, Exelon Generation Company, LLC, Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Audit Plan in Support of Review of License Amendment Request Regarding Change Spent Fuel Pool Cooling Design Basis (EPID L-2021-LLA-0112), dated July 20,2021 (ADAMS Accession No. ML21200A074)
- 3. Letter from David P. Helker (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, " Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request Supplement, dated August 13, 2021 (ADAMS Accession No. ML21225A353)
- 4. Email from Andrea Mayer, U.S. Nuclear Regulatory Commission, to Francis J Mascitelli, Exelon Generation Company, LLC, " Request for Additional Information: Calvert Cliffs 1 & 2 LAR to Revise Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Basis (L-2021-LLA-0112)," dated October 5, 2021 (ADAMS Accession No. ML21287A093).
By letter dated June 14, 2021, Reference 1, as supplemented by letter dated August 13, 2021, Reference 3, (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML21165A406 and ML21225A353, respectively), Exelon Generation Company, LLC (Exelon) submitted a license amendment request (LAR) to revise the Updated Final Safety Analysis Report (UFSAR) and the Technical Requirements Manual for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (CCNPP), to allow for a full core offload in the spent fuel pool (SFP) without being supplemented with one train of the Shutdown Cooling (SDC) system. The proposed amendment also includes a change in the calculational methodology used in the SFP heat-up analysis.
From July 6 to August 29, 2021, the NRC staff conducted a regulatory audit to review licensee calculations supporting the LAR to determine if additional information contained in the analyses performed in support of the requested change is needed to support or develop conclusions for the staffs safety evaluation. An audit plan was issued by the NRC staff by letter dated July 20, 2021, Reference 2 (ADAMS Accession No. ML21200A074).
The Nuclear Regulatory Commission (NRC) staff has determined, during the regulatory audit, that additional information is needed to complete its review of the request (Reference 4). The NRC Request for Additional Information (RAI) is shown in italic text followed by Exelons response.
Attachment SFPC-SDC Systems Licensing Design Basis LAR Response to NRC Request for Additional Information Page 2 of 4 REQUEST FOR ADDITIONAL INFORMATION RAI 3.3-1 Regulatory Basis:
Calvert Cliffs UFSAR Appendix 1C states, in part, Calvert Cliffs was designed and constructed to meet the intent of the draft (proposed) Generic Design Criteria (GDC) for Nuclear Power Plants, which were published by the Atomic Energy Commission in July 1967.
Draft GDC 1 requires that seismic Category 1 structures, systems, and components (SSCs) (e.g., SFP) shall be identified and then designed, fabricated, and erected to quality standards that reflect the importance of the safety function to be performed.
Draft GDC 2 requires, in part, that seismic Category 1 SSCs be designed to withstand, without loss of the capability to protect the public, the additional forces that might be imposed by natural phenomena such as earthquakes, tornadoes, flooding conditions, winds, ice, and other local site effects.
Background:
The proposed LAR, as supplemented, requests to revise the UFSAR Section 9.4, Spent Fuel Pool Cooling System, design basis to raise the maximum allowable SFP water temperature from 130oF to 150oF for full core offloads in certain refueling outages, and 212oF in the case of total loss of the SFP cooling with 1830 fuel assemblies in the pool. LAR Section 3.3, Structural Integrity of SFP, states that the current licensing basis for the SFP structural analysis accommodates the increased SFP allowable maximum temperature of 150°F and 212°F based on Reference 11 of the LAR (i.e., engineering calculation CA09085, Rev 0000, Spent Fuel Pool).
The NRC staff reviewed the UFSAR Sections 5.6.1, 6.3.5.1, and 9.4.4, and Appendix 5A, and found that the SFP was designed for the loads and conditions as shown in UFSAR Table 5-6 in accordance with American Concrete Institute (ACI) 318-63, Building Code Requirements for Reinforced Concrete, as well as the most severe of the load combination equations in UFSAR Appendix 5A.3.1.8. UFSAR Section 5.6.1.6 also states that the maximum thermal stresses developed in the spent fuel pool walls under the most adverse conditions will be in the range of 950 psi, compressive, and in the range of 7,500 psi, tension, in the reinforcing steel.
During the regulatory audit, the staff found in engineering calculation CA09085 that: a) The SFP walls were analyzed for thermal loads in accordance with methods presented in ACI 505; b) Under normal conditions, the interior wall temperature was 150oF and the maximum calculated thermal stress was 996 psi for concrete and 11,410 psi for reinforcing steel; c) After prolonged outage of the cooling system, the
Attachment SFPC-SDC Systems Licensing Design Basis LAR Response to NRC Request for Additional Information Page 3 of 4 interior wall temperature could reach 212oF and the maximum calculated thermal stress was 1,681 psi for concrete and 25,600 psi for reinforcing steel.
It appears that the maximum calculated thermal stresses for concrete and reinforcing steel in the CA09085 are higher than the maximum thermal stresses presented in Section 5.6.1.6 of the UFSAR. Accordingly, it is not clear how the code acceptance criteria were met for these load combinations including thermal load used for the SFP walls and liner.
Request:
- 1. Clarify and correct the discrepancy between thermal stresses reported in the UFSAR and those in the CA09085.
- 2. Describe, with quantitative results, how the structural acceptance criteria were met for the SFP walls and its liner for the controlling load combinations including thermal loads.
Exelon Response:
CA09085 was performed using several differing methodologies that were appropriate for the timeframe associated with CCNPP design (1970 to 1977). These methods were performed using two different bounding temperature differentials of 100°F and 60°F. The results for the two methods, at the two differential temperatures, were similar and showed that the concrete and reinforcing steel stresses were within the working stress design allowables of 1,350 psi for 3,000 psi concrete and 20,000 psi for the reinforcing steel (ACI 318-63).
The first method is described in the Reinforced Concrete Design Handbook (Reynolds) that is shown on page 107. Pages 107 and 108 are reproduced and included in the analysis, CA09085, as pages 48 and 49. This method was used to encompass the 150°F SFP water temperature that has been listed as far back as the Preliminary Safety Analysis Report (PSAR) for CCNPP.
The second stress methodology begins on page 53 in the analysis, CA09085, and lists data for the materials, including concrete and steel. This methodology assumes the concrete slab is a plate and the stresses are based on Timoshenko, Chapter 2, Section 14 Thermal Stresses in Plates with Clamped Edges. This was an alternate method that was used to encompass the 120°F SFP water temperature that has been listed as far back as the PSAR for CCNPP.
The results for the two different methods range from 825 psi to 918 psi for the concrete and 7,400 to 7,830 for the reinforcing steel (pages 51 and 58 of CA09085).
These values form the basis for the current UFSAR Section 5.6.1.6 statement: The maximum thermal stresses developed in the spent fuel pool walls under the most
Attachment SFPC-SDC Systems Licensing Design Basis LAR Response to NRC Request for Additional Information Page 4 of 4 adverse conditions will be in the range of 950 psi, compressive, and in the range of 7500 psi, tension, in the reinforcing steel.
The stresses noted in the background of the RAI are an excerpt from page 50 of CA09085. Further research into the history of CA09085 has determined that the statements on page 50 of this calculation do not appear to apply to the design basis for CCNPP as originally thought. The reason for their inclusion in the calculation could not be ascertained and would be merely speculation at this point.
The differential temperature range in the current CA09085 methodology, namely 60°F to 100°F, would cover the anticipated normal operating range of the SFP up to the maximum assumed value of 150°F assuming a conservatively low Auxiliary Building temperature of 60°F. The 212°F maximum SFP temperature that would result in the unlikely event of losing both trains of SFP cooling with 1830 bundles in the pool, remains below the allowable stresses using method 1. Note however, that this scenario is considered a short-term temperature transient event that has been historically treated as acceptable for steel reinforced concrete structures. Using the method 1 of analysis as described above, the stresses seen at the SFP at 212°F are 1,254 psi for the concrete and 11,902 psi for the reinforced steel. These stresses are acceptable when compared to the allowables outlined in ACI 318-63.
Below are the results of the different methods compared to the allowables of 1,350 psi for 3,000 psi concrete and 20,000 psi for the reinforcing steel (ACI 318-63):
Method 1 (T = 100F) (Reinforced Concrete Design Handbook - Reynolds)
Concrete - 825 psi (compressive)
Reinforcing steel - 7,830 psi (tensile)
Method 2 (T = 60F) (Timoshenko / Advance Reinforced Concrete (Dunham))
Concrete - 918 psi (compressive)
Reinforcing steel - 7,400 psi (tensile)
Reinforcing steel - 14,200 psi (Compressive)