Letter Sequence RAI |
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MONTHYEARML20304A4562020-10-30030 October 2020 Enclosures to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Request ML20304A4542020-10-30030 October 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. Project stage: Request ML20342A1802020-12-0606 December 2020 NRR E-mail Capture - Callaway - LIC-109 Acceptance Requested Licensing Action - Application to Adopt 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors EPID L-2020-LLA-0235 Project stage: Other ML21039A2222021-02-18018 February 2021 Audit Plan and Setup of Online Reference Portal for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Other ML21110A1232021-04-27027 April 2021 Audit Questions for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Project stage: Other ML21139A0222021-06-0909 June 2021 Audit Summary for License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Other ML21210A0272021-07-29029 July 2021 Evaluation of the Proposed Change Project stage: Request ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 Project stage: RAI ML21286A6802021-10-13013 October 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Request ML21356B5052021-12-22022 December 2021 Plan, Unit 1, Final Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Request ML21344A0052021-12-29029 December 2021 Issuance of Amendment No. 226 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants Project stage: Approval 2021-12-29
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Category:E-Mail
MONTHYEARML23362A0572023-12-28028 December 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - SUNSI Review of the Final Safety Analysis Report (FSAR) Revision OL-26 ML23338A0392023-12-0101 December 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Unacceptable with Opportunity to Supplement - Callaway - RR from Requirements of ASME BPV Code, Section Xl, Subsect IWL-Exam & Test-Unbonded Post Tensioning System - EPID L-2023-LLR-0061 ML23208A1052023-07-27027 July 2023 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Regulatory Audit Questions - LAR to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems ML23200A2982023-07-19019 July 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - Final Request for Additional Information (RAI) - Request for Approval of Oqam, Revision 36a - EPID L-2023-LLQ-0000 ML23121A0112023-04-28028 April 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Revise TS to Adopt TSTF-501-A Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control - EPID L-2023-LLA-0046 ML23114A2302023-04-24024 April 2023 NRR E-mail Capture - Regulatory Audit Question - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 ML23107A1812023-04-17017 April 2023 NRR E-mail Capture - Regulatory Audit Questions - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 ML23096A0072023-04-0505 April 2023 NRR E-mail Capture - Final Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Revise TS 5.5.16 for Permanent Extension of Integrated Leak Rate Testing - EPID L-2022-LLA-0165 ML23073A0262023-03-13013 March 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - SG Inspection Report Review - EPID L-2022-LRO-0143 ML23037A7092023-02-0606 February 2023 April 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23037A0022023-02-0303 February 2023 NRR E-mail Capture - Callaway - LAR to Adopt AST - EPID L-2021-LLA-0177 - Revised Schedule for Completion of the Project ML23026A0212023-01-24024 January 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Changes to TS for SFP - ML23010A2902023-01-10010 January 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Callaway Plant, Unit 1 - License Amendment Request to Clarify Support System Requirements for the RHR & Crac Systems - ML22346A0132022-12-0909 December 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of LAR to Revise TS 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies - EPID L-2022-LLA-0165 ML22322A0062022-11-17017 November 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) Callaway - LAR for Proposed Changes to TS and Exemption Request Use of Framatome Gaia Fuel - L-2022-LLA-0150 & L-2022-LLE-0030 ML22287A0952022-10-14014 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22280A1322022-10-0707 October 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway - License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-0 ML22278A0122022-10-0404 October 2022 NRR E-mail Capture - Draft - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-013 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22251A0122022-09-0707 September 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Application to Revise TS to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections - EPID L-2022-LLA-0110 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22216A0072022-07-0808 July 2022 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Draft Acceptance Review (Unacceptable for Review with Opportunity to Supplement) for Framatome Fuel Transition LAR and Exemption - EPIDs L-2022-LLA-0083 and L-2022-LLE-0019) ML22167A0252022-06-15015 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Revision to Radiological Emergency Response Plan Regarding Response & Notification Goals - EPID L-2022-LLA-0024 ML22157A0102022-06-0303 June 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood Ultimate Heat Sink Temporary Temperature Increase to 102.8 Degrees Fahrenheit ML22154A0122022-06-0202 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22151A0512022-05-27027 May 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22137A0292022-05-16016 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22096A0232022-04-0505 April 2022 NRR E-mail Capture - Callaway Plant - Final RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to GL 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML22089A0222022-03-29029 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LAR to Adopt TSTF-505 and TSTF-439 - Follow Up Clarifications for the Audit Questions - EPID L-2021-LLA-0197 ML22087A4022022-03-28028 March 2022 NRR E-mail Capture - Callaway - Draft RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to Generic Letter 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML22070A1362022-03-10010 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals - EPID L-2022-LLA-0024 ML22047A2312022-02-11011 February 2022 Email Between NRC NSIR and FEMA Regarding Callaway Sirens 021122 ML22003A0852022-01-0303 January 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Adopt TSTF-529, Clarify Use and Application Rules - EPID L-2021-LLA-0225 ML21334A5172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21335A0172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21308A0692021-11-0404 November 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Unit 1 - License Amendment Request - Adoption of Alternate Source Term and Revision of TSs - ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 ML21195A0252021-07-13013 July 2021 Email 7-13-21 Request for Information - Callaway EP Exercise Inspection - Sept 2021 ML21125A0452021-05-0404 May 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Plant, Unit 1 - License Amendment Request - Final Resolution to Address Concerns of GSI-191 - EPID L-2021-LLA-0059 ML21007A1622021-01-0606 January 2021 NRR E-mail Capture - Final - Request for Additional Information - (COVID-19) Callaway Plant, Unit 1 - Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs - EPID L-2021-LLE-0242 ML20342A1802020-12-0606 December 2020 NRR E-mail Capture - Callaway - LIC-109 Acceptance Requested Licensing Action - Application to Adopt 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors EPID L-2020-LLA-0235 ML20296A6332020-10-22022 October 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Exemption from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L 2020 Lle 0140 (Covid 19)) - Revised Completion Schedule ML20205L4252020-07-22022 July 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Acceptance of Requested Licensing Action Request for One-Time License Amendment to Defer Upcoming Steam Generator Inspection (EPID L-2020-LLA-0142)(COVID-19) ML20203M3682020-07-21021 July 2020 NRR E-mail Capture - Draft Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request - Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and 5.3.1.2 - EPID L-2020-LLA-0046 ML20162A1882020-06-10010 June 2020 Request for Supporting Information for the Callaway SPRA Audit Review - Draft Supplement ML20153A7902020-05-29029 May 2020 Emai: RFI for Callaway EP Program Inspection ML20133K6742020-05-11011 May 2020 05000483, Request for Information 2020-002 ML20099G2422020-04-0808 April 2020 NRR E-mail Capture - Acceptance Callaway Containment Tendon COVID-19 Relief Request ML20097C8362020-04-0606 April 2020 NRR E-mail Capture - Accepted: Callaway TS Change 5.3.1 LAR EPID: L-2020-LLA-0046 2023-07-27
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23200A2982023-07-19019 July 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - Final Request for Additional Information (RAI) - Request for Approval of Oqam, Revision 36a - EPID L-2023-LLQ-0000 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ML23163A1572023-06-0606 June 2023 In-service Inspection Request for Information ML23096A0072023-04-0505 April 2023 NRR E-mail Capture - Final Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Revise TS 5.5.16 for Permanent Extension of Integrated Leak Rate Testing - EPID L-2022-LLA-0165 ML23080A1382023-03-21021 March 2023 Notification of Inspection (NRC Inspection Report 05000483/2023003) and Request for Information ML23073A0262023-03-13013 March 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - SG Inspection Report Review - EPID L-2022-LRO-0143 ML23037A7092023-02-0606 February 2023 April 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23026A0212023-01-24024 January 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Changes to TS for SFP - ML22287A0952022-10-14014 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information ML22173A0562022-06-22022 June 2022 Information Request, Security IR 2022402 ML22167A0252022-06-15015 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Revision to Radiological Emergency Response Plan Regarding Response & Notification Goals - EPID L-2022-LLA-0024 ML22157A0572022-06-0606 June 2022 Notification of NRC Design Bases Assurance Inspection (Programs) (05000483/2022013) and Request for Information ML22154A0122022-06-0202 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22151A0512022-05-27027 May 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22137A0292022-05-16016 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22096A0232022-04-0505 April 2022 NRR E-mail Capture - Callaway Plant - Final RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to GL 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML21336A6392021-12-0202 December 2021 .05 Sec Doc Request ML21319A0062021-11-30030 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 ML21159A2352021-06-17017 June 2021 Notification of NRC Triennial Heat Exchanger/Heat Sink Performance Inspection (05000483/2021003) and Request for Information ML21130A5882021-05-11011 May 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions to Adopt a Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004 02 ML21088A3872021-03-30030 March 2021 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000483/2021002) and Request for Information ML21007A1622021-01-0606 January 2021 NRR E-mail Capture - Final - Request for Additional Information - (COVID-19) Callaway Plant, Unit 1 - Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs - EPID L-2021-LLE-0242 ML20203M3682020-07-21021 July 2020 NRR E-mail Capture - Draft Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request - Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and 5.3.1.2 - EPID L-2020-LLA-0046 ML20162A1882020-06-10010 June 2020 Request for Supporting Information for the Callaway SPRA Audit Review - Draft Supplement ML20280A5442020-03-25025 March 2020 Cwy 2020 PIR Request for Information ML20064B6582020-02-27027 February 2020 Second, Third, and Fourth Request for Information for Callaway Dba Teams Inspection 2020011 ML19317E6332019-11-13013 November 2019 Request for Supporting Information for the Callaway SPRA Audit Review ML19107A5152019-04-11011 April 2019 Cwy 2019410 RFI Cyber Security Gap ML19078A2932019-03-18018 March 2019 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000483/2019010) and Request for Information ML19023A2032019-01-22022 January 2019 Notification of NRC Triennial Heat Sink Performance Inspection (05000483/2019001) and Request for Information ML19009A3442019-01-0909 January 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Plant Class 1E LAR, L-2018-LLA-0062 ML18355A4882018-12-20020 December 2018 NRR E-mail Capture - Formal Release of RAI Ref: Callaway Plant EAL Changes, L-2018-LLA-0239 ML18331A2052018-11-27027 November 2018 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Relief Request EPID L-2018-LLR-0051 ML18025B4672018-01-24024 January 2018 NRR E-mail Capture - Request for Extension of Due Date for RAI Response ML17304B1912017-10-31031 October 2017 NRR E-mail Capture - Requests for Additional Information Concerning Callaway License Amendment - Thermal Overload Protection ML17142A1352017-05-19019 May 2017 Notification of NRC Design Bases Assurance Inspection (05000483/2017007) and Initial Request for Information ML17115A0622017-04-25025 April 2017 NRR E-mail Capture - Requests for Additional Information -- Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report CAC MF8463 ML17038A2292017-02-0707 February 2017 NRR E-mail Capture - RAI Formal Release for Callaway SG Tube Inspection Report, MF8474 ML16111B3222016-04-20020 April 2016 Notification of Evaluations of Changes, Tests, and Experiments, and Permanent Plant Modifications Inspection (05000483/2016007) and Request for Information ML15316A1532015-11-12012 November 2015 Request for Additional Information Email, Relief Request 13R-11 (Pressurizer Welds) from Code Case N-460 Requirements, Third 10-Year Inservice Inspection Interval ML15096A0942015-04-0606 April 2015 Notification of Inspection (NRC Inspection Report 05000483/2015003) and Request for Information ML14353A1172014-12-22022 December 2014 Request for Additional Information, Round 3, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14294A7752014-10-28028 October 2014 Request for Additional Information, Round 2, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14203A0632014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Rv ISI Frequency from 10 to 20 Years, Third 10-Year ISI Interval ML14178A8232014-07-0101 July 2014 Request for Additional Information, License Amendment Request to Revise Final Safety Analysis Report- Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ULNRC-06117, Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses2014-04-24024 April 2014 Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses ML14114A1102014-04-24024 April 2014 License Revewal Application, Request for Additional Information (RAI) Set 31 Responses 2023-07-19
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Text
From: Chawla, Mahesh Sent: Tuesday, September 14, 2021 5:11 PM To: 'Elwood, Thomas B' Cc: Dixon-Herrity, Jennifer; Havertape, Joshua; Circle, Jeff; Pascarelli, Robert; Wu, De; Grenier, Bernard; Tetter, Keith; Rosenberg, Stacey; Quinlan, Kevin; Heeszel, David; Hayes, Barbara; Lee, Brian; Nold, David; Robinson, Jay; Jenkins, Joel; Ashcraft, Joseph; Hsu, Kaihwa; Farnan, Michael; Pettis, bob; Cumblidge, Stephen; Goel, Vijay
Subject:
FINAL - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Adopt 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors"- EPID L-2020-LLA-0235 Attachments: Callaway 50.69 RAIs.docx
Dear Mr. Elwood,
By application dated October 30, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20304A454), Union Electric Company, dba Ameren Missouri (the licensee), submitted a license amendment request for Callaway Plant, Unit No. 1 (Callaway). The proposed amendment would modify the Callaway licensing basis by the addition of a license condition (i.e., License Condition 2.C.(19)), to allow for the implementation of the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors. On February 18, 2021 (ADAMS Accession No. ML21039A222), the U.S.
Nuclear Regulatory Commission (NRC) staff issued an audit plan that conveyed the intent to conduct a regulatory audit to support its review of the subject license amendment. The NRC staff and the representatives of Ameren Missouri, participated in the regulatory audit, conducted from May 11, 2021 through May 13, 2021. The NRC issued an audit summary in a letter dated June 9, 2021 (ADAMS Accession No. ML21139A022). The licensee provided additional/revised information in a supplement dated July 29, 2021 (ADAMS Accession No. ML21210A025). The NRC staff has reviewed the supplemental information provided after completion of the regulatory audit, and has determined that the attached additional information is required in order to complete the review of the subject LAR.
The attached RAIs were sent to you via email on September 2, 2021 as the draft RAIs and requested you to set up a clarification call with the NRC staff. On September 14, 2021 you informed NRC that your staff understands the requested information and has determined that there is no need for a clarification call with the NRC staff. You have also agreed to provide the supplemental response to the requested information within 30 calendar days of the receipt of this email. Thanks Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ph: 301-415-8371
OFFICE DORL/LPL4/PM DORL/LPL4/BC JDixon-NAME MChawla Herrity DATE 9/14/2021 9/14/2021
Hearing Identifier: NRR_DRMA Email Number: 1347 Mail Envelope Properties (SA1PR09MB8415A687B9B1E78AA66851B1F1DA9)
Subject:
FINAL - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Adopt 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors"- EPID L-2020-LLA-0235 Sent Date: 9/14/2021 5:11:18 PM Received Date: 9/14/2021 5:11:19 PM From: Chawla, Mahesh Created By: Mahesh.Chawla@nrc.gov Recipients:
"Dixon-Herrity, Jennifer" <Jennifer.Dixon-Herrity@nrc.gov>
Tracking Status: None "Havertape, Joshua" <Joshua.Havertape@nrc.gov>
Tracking Status: None "Circle, Jeff" <Jeff.Circle@nrc.gov>
Tracking Status: None "Pascarelli, Robert" <Robert.Pascarelli@nrc.gov>
Tracking Status: None "Wu, De" <De.Wu@nrc.gov>
Tracking Status: None "Grenier, Bernard" <Bernard.Grenier@nrc.gov>
Tracking Status: None "Tetter, Keith" <Keith.Tetter@nrc.gov>
Tracking Status: None "Rosenberg, Stacey" <Stacey.Rosenberg@nrc.gov>
Tracking Status: None "Quinlan, Kevin" <Kevin.Quinlan@nrc.gov>
Tracking Status: None "Heeszel, David" <David.Heeszel@nrc.gov>
Tracking Status: None "Hayes, Barbara" <Barbara.Hayes@nrc.gov>
Tracking Status: None "Lee, Brian" <Brian.Lee@nrc.gov>
Tracking Status: None "Nold, David" <David.Nold@nrc.gov>
Tracking Status: None "Robinson, Jay" <Jay.Robinson@nrc.gov>
Tracking Status: None "Jenkins, Joel" <Joel.Jenkins@nrc.gov>
Tracking Status: None "Ashcraft, Joseph" <Joseph.Ashcraft@nrc.gov>
Tracking Status: None "Hsu, Kaihwa" <Kaihwa.Hsu@nrc.gov>
Tracking Status: None "Farnan, Michael" <Michael.Farnan@nrc.gov>
Tracking Status: None "Pettis, bob" <Robert.Pettis@nrc.gov>
Tracking Status: None "Cumblidge, Stephen" <Stephen.Cumblidge@nrc.gov>
Tracking Status: None "Goel, Vijay" <Vijay.Goel@nrc.gov>
Tracking Status: None
"'Elwood, Thomas B'" <TElwood@ameren.com>
Tracking Status: None Post Office: SA1PR09MB8415.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 2320 9/14/2021 5:11:19 PM Callaway 50.69 RAIs.docx 31721 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
CALLAWAY PLANT, UNIT NO. 1 LICENSE AMENDMENT TO ADOPT 10 CFR 50.69 RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS REQUEST FOR ADDITIONAL INFORMATION By application dated October 30, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20304A454), Union Electric Company, dba Ameren Missouri (the licensee), submitted a license amendment request (LAR) for Callaway Plant, Unit No. 1 (Callaway). The proposed amendment would modify the Callaway licensing basis by the addition of a license condition (i.e., License Condition 2.C.(19)), to allow for the implementation of the provisions of Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors. On February 18, 2021 (ADAMS Accession No. ML21039A222), the U.S. Nuclear Regulatory Commission (NRC) staff issued an audit plan that conveyed the intent to conduct a regulatory audit to support its review of the subject license amendment. The NRC staff and the representatives of Ameren Missouri, participated in the regulatory audit, conducted from May 11, 2021 through May 13, 2021. The NRC issued an audit summary in a letter dated June 9, 2021 (ADAMS Accession No. ML21139A022). The licensee provided additional/revised information in a supplement dated July 29, 2021 (ADAMS Accession No. ML21210A025). The NRC staff has reviewed the supplemental information provided after completion of the regulatory audit, and has determined that additional information is required in order to complete the review of the subject LAR. Please arrange a clarification teleconference with the NRC staff at your earliest possible.
RAI 01 - Use of Mean Core Damage Frequency and Large Early Release Frequency Values and Consideration of the State of Knowledge Correlation Regulatory Guide (RG) 1.174, Revision 3, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, dated January 2018 (ADAMS Accession No ML17317A256) and Section 6.4 of NUREG-1855, Revision 1, Guidance on the Treatment of Uncertainties Associated with PRAs [Probabilistic Risk Assessments] in Risk-Informed Decisionmaking, dated March 2017 (ADAMS Accession No. ML17062A466), for a Capability Category II risk evaluation, indicate that the mean values of the risk metrics (total and incremental values) need to be compared against the risk acceptance guidelines. The mean values referred to are the means of the probability distributions that result from the propagation of the uncertainties on the PRA input parameters and model uncertainties explicitly reflected in the PRA models. In general, the point estimate core damage frequency (CDF) and large early release frequency (LERF) obtained by quantification of the cutset probabilities using mean values for each basic event probability does not produce a true mean of the CDF and LERF. Under certain circumstances, a formal propagation of uncertainty may not be required if it can be demonstrated that the state of knowledge correlation (SOKC) is unimportant (i.e., the risk results are well below the acceptance guidelines). of the updated LAR, in response to Audit Question APLA/APLC 05 Part (c) provides updated quantification results based on PRA update 9.01 using mean values which account for the SOKC showing the total CDF and LERF meet the RG 1.174 risk acceptance guidelines. However, the updated LAR did not state whether fire, seismic and wind PRA Enclosure
parameters that should be correlated to account for SOKC were included such as circuit failure probabilities, suppression probabilities, and ignition frequencies for the fire PRA. The response also states that the mean values are conservative because of the inability to fully post-process with ACUBE [advanced cutset upper bound estimator]. It is not clear how this conservatism (i.e., that the mean values are 19 and 27 percent higher than the point estimate values for CDF and LERF respectively) will be addressed for the 10 CFR 50.69 program, given that it would appear to impact to 10 CFR 50.69 risk-informed categorization. Therefore, address the following:
a) Identify the parameters derived from the same data (other than for same type code data) that were correlated for the fire, seismic, and high wind PRAs, and justify that these parameters are sufficient to estimate the SOKC.
b) Discuss how the SOKC will be treated for the 10 CFR 50.69 program consistent with NUREG-1855, Revision 1, when the risk increase associated with SOKC is considered.
RAI 02 - Treatment of Sensitive Electronics in the Fire PRA RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities, states NRC reviewers, [will] focus their review on key assumptions and areas identified by peer reviewers as being of concern and relevant to the application. The relatively extensive and detailed reviews of fire PRAs undertaken in support of LARs to transition to National Fire Protection Association (NFPA)-805, Performance-Based Standard for Light Water Reactor Electric Generating Plants, determined that implementation of some of the complex fire PRA methods often used non-conservative and over-simplified assumptions to apply the method to specific plant configurations. Some of these issues were not always identified in facts and observations (F&Os) by the peer review teams but are considered potential key assumptions by the NRC staff because using more defensible and less simplified assumptions could substantively affect the fire risk and fire risk profile of the plant.
LAR Section 3.2.2 states that the numerous new or revised fire PRA guidance documents issued since Callaway was approved to implement NFPA-805 are being addressed through the PRA maintenance and update process. With regards to use of Frequently Asked Question (FAQ)13-0004, Clarifications on Treatment of Sensitive Electronics (ADAMS Accession No. ML13322A085), Attachment 8 of the updated LAR states that [w]ithout explicitly citing FAQ 13-0004 for the treatment of sensitive electronics, the fire PRA does implement the salient conclusion that a generic screening heat flux damage threshold for thermoset cables, as observed on the outer surface of the cabinet, can be used as a conservative surrogate for assessing the potential for thermal damage to solid-state and sensitive electronics within an electrical panel (cabinet). The LAR, however, does not address the two caveats cited in FAQ 13-0004 that can invalidate this approach which are (1) sensitive electronics mounted on the surface of the cabinet where it can be exposed to the convective or radiant energy of a fire, and (2) the presence of a louver or other typical ventilation means. It appears to the NRC staff that this source fire PRA modeling uncertainty could have the potential to impact the application.
Therefore, address the following:
a) Explain how sensitive electronics are modeled in the fire PRA for sensitive electronics cabinet configurations (i.e., wall mounted electronics or ventilation) that invalidate the FAQ 13-0004 approach described in the LAR (i.e., using the heat flux damage threshold for thermoset cables for sensitive electronics inside a cabinet). Include confirmation that the approach is consistent with the guidance in FAQ 13-0004.
b) If the approach cannot be confirmed to be consistent with the guidance in FAQ 13-0004, then, justify that it has an inconsequential impact on 10 CFR 50.59 risk-informed categorization. Alternatively, explain how the uncertainty associated with this modelling treatment will be addressed in the 10 CFR 50.69 program.
RAI 03 - Seismic PRA Modeling RG 1.174, Revision 3, states, in part, that the plant-specific PRA supporting the licensees proposals has been demonstrated to be acceptable.
Review of PRA-SEISMIC-QUANT (described in Audit Question APLA/APLC-03 Response in , Attachment 8 to the LAR supplement dated July 29, 2021), Table 4-2 indicates that the highest ACUBE conditional core damage probability (CCDP) is 0.9 and its note (2) states that the value in the column includes the plant availability factor (PAF) of 0.9. However, Table 4-3 shows that ACUBE conditional large early release probability (CLERP) is close to 1.
It is not clear why the value in the column does not include the PAF of 0.9, since they are very similarly calculated as a ratio of either ACUBE CDF or ACUBE LERF to seismic frequency. In addition, on page 54 it says that both CCDP and CLERP approach the PAF of 0.9 for the last hazard interval bin. However, Figures 4-3, 4-4, and 4-5 do not demonstrate this. Instead, Figures 4-3 and 4-5 show CCDP more than 0.9, while Figures 4-4 and 4-5 show CLERP is close to 1.
The last bin for seismic CDF represents 0.88 g peak ground acceleration, covering a seismic hazard from 0.8 to 10 g. Provide a sensitivity study to demonstrate no impact on the final seismic CDF when this bin is divided into several sub-bins (for example, 0.8-1.0 g, 1.0-1.2 g, 1.2-1.4 g, 1.4-1.6 g, 1.6-2.0 g and 2.0-10 g).
RAI 04 - Seismic Fragility Analysis Uncertainty Section 5 of Nuclear Energy Institute (NEI) 00-04, 10 CFR 50.69 SSC [Structure, System, and Component] Categorization Guideline, provides guidance for performing sensitivity studies for each PRA model to address the uncertainty associated with those models. Specifically, Sections 5.1, 5.2, and 5.3 provide guidance for such sensitivities for the internal events, fire and seismic PRA, respectively. The sensitivity studies are performed to ensure that assumptions and sources of uncertainty (e.g., human error, common cause failure, and maintenance probabilities) do not mask importance of components.
The high seismic CDF and LERF values relative to the CDF and LERF values from the other hazards including internal events suggest that the uncertainty in seismic PRA modeling involving the level of detail used to model fragility could potentially impact 10 CFR 50.69 risk-informed categorization. It is not clear from the discussion provided in Attachment 8 of the updated LAR in response to Audit Question APLC 04 on the level of fragility analyses performed for four dominant CDF and LERF importance contributors (i.e., seismically induced loss of offsite power, failure of service water, failure of steam generator supports and soil failure) whether the Callaway seismic CDF and LERF values could be further reduced by further refining the fragility analyses for other SSCs. NRC staff observes that since the point estimate seismic CDF of 5.59E-05 per year presented in Section 6 of the Callaway seismic PRA report dated July 10, 2020 (ADAMS Accession No. ML20192A244) the calculated point estimate seismic CDF value has been reduced to 4.01E-05 based on refinements according to of the updated 10 CFR 50.69 LAR. An overly conservative seismic PRA model
could skew the integrated importance measures calculated for 10 CFR 50.69 categorization.
Importance measures provide a relative measure of risk importance and, therefore, if the importance of certain SSCs is significantly overestimated, then the importance of other SSCs will be underestimated. In light of these observations, address the following:
a) Justify that not using more refined fragility analysis for certain important SSCs will not have a consequential impact on 10 CFR 50.69 risk-informed categorization. Include in the discussion how the SSC fragility analysis for important SSCs beyond just the top four contributors is performed.
b) If it cannot be justified that using more refined fragility analysis for certain important SSCs will not have a consequential impact on 10 CFR 50.69 categorization, then explain how this modeling uncertainty will be addressed for the 10 CFR 50.69 program.