Letter Sequence Response to RAI |
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EPID:L-2019-LLA-0281, License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances (Approved, Closed) |
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MONTHYEARML19346E5362019-12-11011 December 2019 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances Project stage: Request ML20015A4992020-01-15015 January 2020 Acceptance of Requested Licensing Action Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances Project stage: Acceptance Review ML20052E9852020-02-28028 February 2020 Audit Plan in Support of Review of License Amendment Request to Revise Technical Specification Surveillance Requirements Relating to Emergency Diesel Generator Project stage: Other ML20157A0782020-06-0505 June 2020 Request for Additional Information Regarding License Amendment Request Concerning Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances Project stage: RAI ML20167A2532020-06-15015 June 2020 Second Request for Additional Information Regarding License Amendment Request Concerning Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances Project stage: RAI 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 Project stage: Response to RAI ML20174A0592020-06-30030 June 2020 Regulatory Audit Summary Regarding License Amendment Request for Revision to Technical Specification Surveillance Requirements Relating to Emergency Diesel Generator Project stage: Other ML20273A0882020-11-0909 November 2020 Issuance of Amendment Nos. 338 and 316 Revise Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances Project stage: Approval 2020-02-28
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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 Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.90 June 30, 2020 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 to License Amendment Request - Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances (using WCAP-17308 methodology)
References:
- 1. Letter from Shannon Rafferty-Czincila (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "License Amendment Request - Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances (using WCAP-17308 methodology), dated December 11, 2019 (ML19346E536)
- 2. Electronic mails from Michael Marshall (Senior Project Manager, U.S.
Nuclear Regulatory Commission) to Frank Mascitelli (Exelon), Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Two Requests for Additional Information dated June 5, 2020 and June 15, 2020; and One Request for Confirmatory Information dated June 15, 2020; all regarding License Amendment Request concerning Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances.
By letter dated December 11, 2019 (Reference 1), Exelon Generation Company, LLC (Exelon; licensee) submitted a License Amendment Request (LAR) for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs). The proposed amendments would revise certain frequency and voltage acceptance criteria for steady-state emergency diesel generator surveillance testing in Calvert Cliffs Technical Specification Section 3.8.1, AC Sources -
Operating. The calculations supporting the request were revised using methodology described in WCAP-17308-NP-A, Rev. 0, "Treatment of Diesel Generator (DG) Technical Specification Frequency and Voltage Tolerances, dated July 2017.
Response to RAI and RCI for License Amendment Request For EDG SR Frequency and Voltage Tolerances June 30, 2020 Page 2 By three electronic mails (Reference 2), the NRC identified areas where additional and confirmatory information was necessary.
The attachment to this letter contains the NRC's requests for additional information (RAI) and request for confirmatory information (RCI) immediately followed by Exelon's response.
Exelon has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1.
Exelon has determined that the information attached to this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. Furthermore, the information attached to this letter 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 amendment.
There are no new regulatory commitments contained in this response. If you should have any questions regarding 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 30th day of June 2020.
Respectfully, David P. Helker Sr. Manager, Licensing Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information and Request for Confirmatory Information cc: NRC Regional Administrator, Region I NRC Senior Resident Inspector, CCNPP NRC Project Manager, NRR, CCNPP S. Seaman, Maryland Department of Natural Resources
ATTACHMENT Response to Request for Additional Information and Request for Confirmatory Information License Amendment Request Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances (using WCAP-17308 methodology)
Docket Nos. 50-317 and 50-318
Attachment Response to RAI and RCI License Amendment Request Proposed Changes to Technical Specification (TS) 3.8.1, EDG SR Frequency and Voltage Tolerances Page 1 of 5 By letter dated December 11, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19346E536), Exelon Generation Company, LLC (Exelon; licensee) submitted license amendment requests (LAR) for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs). The proposed amendments would revise certain frequency and voltage acceptance criteria for steady-state emergency diesel generator surveillance testing in Calvert Cliffs Technical Specification Section 3.8.1, AC Sources -
Operating. The calculations supporting the request were revised using methodology described in WCAP-17308-NP-A, Rev. 0, "Treatment of Diesel Generator (DG) Technical Specification Frequency and Voltage Tolerances, dated July 2017.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the LAR and made available by Exelon during regulatory audit performed by the NRC staff between March 16 and April 24, 2020 (ADAMS Accession No. ML20052E985) and has determined that additional information is needed to complete its review. The request for additional information (RAI #1) was discussed with Exelon on May 27, 2020. The request for additional information (RAI #2) was discussed with Exelon on May 27 and June 12, 2020.
The Request for Confirmatory Information (RCI #1) for one of the documents reviewed during the audit to confirm it is correct and the information is applicable to the LAR was discussed with Exelon on May 27 and June 12, 2020. It was subsequently agreed that Exelon would provide a response to all three requests by July 5, 2020.
REQUEST FOR ADDITIONAL INFORMATION RAI #1 Section 50.36, Technical specifications, of Title 10 of the Code of Federal Regulations (10 CFR) describe the requirements related to the content of the technical specifications (TS). Pursuant to 10 CFR 50.36(c), TS are required to include item surveillance requirements (SR). Surveillance requirements relating to test, calibration, or inspection need to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. The proposed changes in this LAR relate to the SRs.
- 1. On Page 9 of Attachment 1 of the LAR, the licensee stated:
Motor operated valves [MOVs] were evaluated in Appendix D to CA10309. WCAP-17308 determined that there were four potential effects on MOVs due to EDG [emergency diesel generator] frequency and voltage tolerance that need evaluation. The first consideration is the increased inertia of the motor due to increased EDG frequency. The second is the potential effect of higher pump motor frequency on the differential pressure across the MOVs. The third is the impact of decreased voltage below nominal on the motor operator capability. The fourth is increased stroke time. Appendix D to CA10309 evaluated all safety-related, EDG-powered MOVs and determined that no issues exist at the proposed new TS SR frequency and voltage uncertainty values.
Attachment Response to RAI and RCI License Amendment Request Proposed Changes to Technical Specification (TS) 3.8.1, EDG SR Frequency and Voltage Tolerances Page 2 of 5 Please provide a brief explanation of the methods and acceptance criteria for each of the above-mentioned potential effects on the MOVs at the proposed new TS SR frequency and voltage uncertainty values that led to the conclusion that no issues exist.
Exelons Response
- 1. Increased inertia of the motor due to increased EDG frequency:
Increasing the EDG frequency and voltage increases the MOV motor speed. This, in turn, increases the kinetic energy in the motor operator. For torque seated valves, the obturator contacts the seat, which has some flexibility, and motor torque increases from the time of the contact until tripping of the motor. After the motor trips, the kinetic energy of the moving actuator components must be absorbed by the valve and actuator. This absorbed energy is manifested in increased seating load.
The increased seating load has impact on the MOV evaluation. First, the increased load must be compared to the valve and actuator load limits. On wedging type valves, the increased wedging force results in increased pull out forces. The actuator motor must generate additional torque to overcome the increased pullout load. The valve and actuator must withstand these increased pullout loads.
- 2. Potential effect of higher pump motor frequency on the differential pressure across the MOVs:
There are two ways of accommodating EDG voltage and frequency variation in the system hydraulic calculations. The first is to change the In-Service Test (IST) allowable limits so that the pumps could operate outside of the range currently allowed by the IST program. That would require review of the hydraulic and perhaps accident analyses that are based on the pump curves. This would also require reviewing the differential pressure (dP) used to establish the required operating forces and torques for the valves in the GL 96-05 program.
The second method is to determine new IST limits, and ensure that these limits are within the bounds of the existing hydraulic and accident analyses. This methodology ensures that there are no changes to system design calculations.
The evaluation of the safety-related pumps conducted in Appendix C of CA10309 assumes that there is no change to the existing pump hydraulic and accident analyses as a result of the EDG frequency and voltage tolerance. Therefore, the design dP across the MOVs will not be increased due to increased EDG frequency.
- 3. Impact of decreased voltage below nominal on the motor operator capability:
Using references in CA10309 Appendix D, reference 5.3.2 (E-90-038 MOV Min Voltages) evaluates the MOV terminal voltages for Units 1 and 2 using as input
Attachment Response to RAI and RCI License Amendment Request Proposed Changes to Technical Specification (TS) 3.8.1, EDG SR Frequency and Voltage Tolerances Page 3 of 5 MCC voltages calculated within Reference 5.3.3 (CA07772 - AC Load Flow). Per Section 6.3.2 of Reference 5.3.3 the MCC voltages supplied to Reference 5.3.2 are based on the upstream Class 1E 4kV buses being at the Transient Undervoltage Relay (TUR) minimum dropout voltage of 3,630 V. As the minimum acceptable steady state EDG operating voltage, per Technical Specifications, is 4,060 V (i.e. >
3,630 V) the existing MOV voltage drop analyses within Reference 5.3.2 remain bounding and thus no further evaluation is required.
- 4. Increased stroke time:
WCAP-17308 provides methodology for determining the impact of MOV motor speed change on stroke time. Per the WCAP, a slightly faster stroke time will not have an adverse impact on valve performance. Therefore, only increases in stroke times were considered in the evaluation in CA10309. The change in stroke time is determined by first calculating the change in motor speed as a result of the change uncertainty in diesel generator frequency.
The change in stroke time is then calculated by the ratio of the change in motor speed to the nominal motor speed, which is equal to the ratio of the uncertainty in diesel generator frequency to the nominal diesel generator frequency.
As such, MOV stroke time will be increased by no greater than 1.25% as a result of the maximum diesel generator frequency tolerance. In order to determine how this impacts available margin on stroke time, Attachment 3 of CA10309 Appendix D increases the MOVs reference stroke times 1.25% and compares that value to the maximum allowable stroke time. Per Attachment 3, all stroke times are still below the maximum allowable. Therefore, there is no adverse impact on MOV stroke times as a result of the diesel generator frequency and voltage tolerance.
Acceptance Criteria:
MOVs are determined to be acceptable if the revised torque and thrust caused by the increased EDG voltage and frequency are less than the maximum allowable torque and thrust for the MOV. In order to meet the acceptance criteria for stroke time, the stroke times from recent MOV test results must remain within the stroke time requirement after accounting for the effects of frequency and voltage tolerances.
RAI #2 Section 50.36, Technical specifications, of Title 10 of the Code of Federal Regulations (10 CFR) describe the requirements related to the content of the technical specifications (TS). Pursuant to 10 CFR 50.36(c), TS are required to include item surveillance requirements (SR). Surveillance requirements relating to test, calibration, or inspection need to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. The proposed changes in this LAR relate to the SRs.
Attachment Response to RAI and RCI License Amendment Request Proposed Changes to Technical Specification (TS) 3.8.1, EDG SR Frequency and Voltage Tolerances Page 4 of 5
- 2. The lower discharge pressures resulting from the proposed low-end frequency tolerance (59.25 Hertz) could cause low pressure switches to trip. Similarly, the higher discharge pressure resulting from the proposed high-end frequency tolerance (60.75 Hertz) could cause relief valves to lift on affected discharge piping. The licensee did not provide information that addresses whether the proposed frequency tolerance change could cause low pressure switches associated with affected pumps (if equipped) to trip or relief valves located on the discharge piping of affected pumps to lift.
Please discuss whether or not any low pressure switches associated with affected pumps will trip or whether any relief valves located on the discharge piping of affected pumps will lift due to the pressures at the low-end (59.25 Hertz) and high-end (60.75 Hertz) proposed frequency tolerance. If a low pressure switch could trip or a relief valve could lift, explain how the affected pumps will continue to perform their design functions.
Exelon Response The required changes to the IST limits take into account the impacts of EDG frequency and voltage tolerance on safety-related pumps. By operating within the IST limits established in Appendix C of CA10309, all safety-related pumps will remain within the analytical limits when the EDG is operating at the extreme limits for its frequency and voltage tolerance band. Operation within the analytical limits ensures that the affected pumps will operate within the limits of low pressure switches and any relief valves in the discharge piping.
Therefore, operating at the extreme limits of the new EDG frequency and voltage tolerance will not cause an adverse impact on the operation of the affected pumps.
REQUEST FOR CONFIRMATORY INFORMATION RCI #1 Insufficient net positive suction head (NPSH) margin can result in pump cavitation and pump performance degradation. Changes in pump frequency affect the available and required NPSH. The proposed frequency tolerance could affect the available and required NPSH of the affected pumps. The submittal does not provide information to describe how the proposed frequency tolerance affects available and required NPSH for the analyzed pumps.
In the NRC staffs audit of Appendix C, Adjustment of Pump IST [Inservice Testing]
Acceptance Criteria and Comparison to Existing Test Results, to Analysis Number CA10309, Revision 0000, Evaluation of Fans, Pumps, and MOVs [Motor Operated Valves]
for the Effects of Emergency Diesel Generator [EDG] Voltage and Frequency Variations, which evaluated the EDG-powered pumps by determining and comparing new IST limits for the pumps based on the methodology specified in WCAP-17308-NP-A, Rev. 0, the staff inferred from the calculations that all affected pumps fall within analytical limits, and thus have sufficient NPSH margin after the proposed frequency and voltage tolerance change.
Attachment Response to RAI and RCI License Amendment Request Proposed Changes to Technical Specification (TS) 3.8.1, EDG SR Frequency and Voltage Tolerances Page 5 of 5 Please confirm the NRC staff's understanding that the analysis demonstrates sufficient NPSH margin for the affected pumps and the applicability of this information to the LAR.
Exelon Response:
The NRC staffs understanding, as stated above, is correct. Operation of the pumps within the new IST limits will ensure that the affected pumps will operate within the analytical limits and therefore, have sufficient NPSH margin for proper pump operation.