Letter Sequence Acceptance Review |
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EPID:L-2024-LLR-0025, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (Approved, Closed) |
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MONTHYEARML24073A2342024-03-0606 March 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Request ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification Project stage: Request ML24103A1392024-04-12012 April 2024 NRR E-mail Capture - D.C. Cook Nuclear Plant, Unit Nos. 1 and 2 - Acceptance of License Amendment Request Regarding Adoption of 10 CFR 50.69 Project stage: Acceptance Review ML24116A0112024-04-25025 April 2024 Acceptance Review Determination for Proposed Alternative Request IR-4-13 Regarding Steam Generator Channel Head Drain Modification Project stage: Acceptance Review ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Approval ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification Project stage: Withholding Request Acceptance 2024-04-12
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Category:Acceptance Review Letter
MONTHYEARML24116A0112024-04-25025 April 2024 Acceptance Review Determination for Proposed Alternative Request IR-4-13 Regarding Steam Generator Channel Head Drain Modification ML24058A2322024-02-27027 February 2024 2/27/2024 E-mail from S. Sinha to R. Guzman P-8 Instrument Uncertainty in Support of LAR Framatome Gaia Fuel ML23317A0732023-11-13013 November 2023 Acceptance Review Determination - License Amendment Request Modification of TS SR 4.3.6.a ML23172A0752023-06-21021 June 2023 Acceptance Review Determination LAR to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23145A0052023-05-25025 May 2023 Acceptance Review Determination Exemption to Use Framatome Gaia Fuel Assemblies Containing Fuel Rods Fabricated with M5 Fuel Rod Cladding ML23038A0152023-02-0707 February 2023 Acceptance Review Determination LAR to Revise the Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures ML23024A1522023-01-24024 January 2023 Acceptance Review Determination LAR to Supplement Burnup Credit of Criticality Safety Analysis ML22292A3212022-10-19019 October 2022 Acceptance Review Determination for Alternative Request for Containment RSS Pump Periodic Verification Testing Program ML22123A0812022-05-0303 May 2022 Acceptance Review Determination for Proposed LAR for TS Change Applicable to TSTF-359, Increase Flexibility in Mode Restraints ML21348A7392021-12-14014 December 2021 E-mail - Acceptance Review Determination Alternative Request IR-4-09 for Use Alternative Brazed Joint Assessment Methodology for Class 3 Moderate Energy Piping ML21147A2982021-05-27027 May 2021 Correction to Projected Review Completion Date, ASME Section XI Inservice Inspection Program Relief Requests, Limited Coverage Examinations, Third Period, 3rd 10-year Inservice Inspection Interval (EPID L-2020-LLR-0081 to LLR-0088) ML21084A0042021-03-25025 March 2021 3/25/2021 E-mail, Acceptance Review Determination, Proposed License Amendment Request to Revise Shutdown Bank TS Requirements and Add Alternate Control Rod Position Monitoring Requirements ML21012A0442021-01-12012 January 2021 1/12/2021 E-mail Acceptance Review Determination, Alternative Requests RR-05-04 and IR-4-02 ML21011A2832021-01-11011 January 2021 1/11/2021 E-mail, Acceptance Review Determination, LAR Proposed License Amendment Request to Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A, Revision 1 ML20357A0282020-12-21021 December 2020 E-mail, Acceptance Review Determination, LAR Proposed License Amendment Request Measurement Uncertainty Recapture Power Uprate ML20350B8272020-12-15015 December 2020 (12/15/2020) E-mail from R. Guzman to S. Sinha - Acceptance Review Determination Proposed LAR to Revise MPS2 TSs for Steam Generator Inspection Frequency ML20337A2692020-12-0202 December 2020 12/2/20 E-mail, Acceptance Review Determination, LAR Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident (LBLOCA) ML20325A3762020-11-20020 November 2020 (11/20/2020) E-mail from R. Guzman to S. Sinha - Acceptance Review, Unacceptable with Opportunity to Supplement Proposed LAR to Revise MPS2 TSs for Steam Generator Inspection Frequency ML20287A3372020-10-13013 October 2020 Acceptance Review Determination: ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations, Third Period, 4th 10-year Inservice Inspection Interval (EPID L-2020-LLR-0129 and LLR-0130) ML20224A0702020-08-11011 August 2020 Acceptance Review Determination (E-mail Dated 8/11/2020) Alternative Request RR-05-06 Insepection Interval Extension for SG Pressure-Retaining Welds and Full-Penetration Welded Nozzles ML20198M3742020-07-16016 July 2020 Acceptance Review Determination: ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations, Third Period, 3rd 10-year Inservice Inspection Interval (EPID L-2020-LLR-0081 to LLR=0088) ML20142A4682020-05-21021 May 2020 Acceptance Review Determination (E-mail Dated 5/21/2020) Proposed Technical Specification Change to Battery Surveillance Requirements ML20092K9572020-04-0101 April 2020 Acceptance Review Determination (E-mail Dated 4/1/2020) LAR to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20079M4772020-03-19019 March 2020 Acceptance Review Determination (E-mail Dated 3/19/2020) ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations (EPID L-2020-LLR-0024 to LLR-0026) ML20079M6752020-03-19019 March 2020 Acceptance Review Determination (E-mail Dated 3/19/2020) ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations (EPID L-2020-LLR-0027 to LLR-0032) ML20021A3772020-01-21021 January 2020 Acceptance Review Determination (E-mail 1/21/2020) Alternative Request RR-05-05 ML20021A3782020-01-21021 January 2020 Acceptance Review Determination (E-mail 1/21/2020) LAR to Revise TS 6.25 ML19304B1542019-10-31031 October 2019 Acceptance Review Determination (E-mail 10/31/19) Extension of TS 3.8.1.1 Allowed Outage Time ML19295C8342019-10-22022 October 2019 Acceptance Review Determination (E-mail 10/22/19) Alternative Request RR-05-03 Extension of ASME Code Case N-770-2 RCP Nozzle DM Butt Welds ML19277B9082019-10-0707 October 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time ML19249B5482019-09-0606 September 2019 Acceptance Review Determination (E-mail 9/6/19) - Revised TS Limits for Primary and Secondary Coolant Activity ML19249B5972019-09-0606 September 2019 Acceptance Review Determination (E-mail 9/6/19) LAR to Revise Integrated Leak Rate Test ML19126A3232019-05-0606 May 2019 Acceptance Review Determination (E-mail 5/6/19) Proposed Alternative Request RR-05-01, VT-2 Pressure Testing Requirements for the Lower Portion of the RPV ML19126A3252019-05-0606 May 2019 Acceptance Review Determination (E-mail 5/6/19) Proposed Alternative Requests RR-05-02, Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML19126A3262019-05-0606 May 2019 Acceptance Review Determination (E-mail 5/6/19) Proposed Alternative Request IR-4-01, Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML19122A3032019-05-0202 May 2019 Acceptance Review Determination (e-mail 5/2/19) License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 ML19087A0692019-03-28028 March 2019 Acceptance Review Determination (E-mail 3/28/19) Proposed Alternative Request IR-3-39 ML19058A8622019-02-27027 February 2019 Acceptance Review Determination (E-mail 2/27/19), LAR Proposed Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of SSCs for Nuclear Power Plants ML19036A9022019-02-0505 February 2019 Acceptance of Amendment Request Revising Emergency Action Level Schemes ML18186A4282018-07-0505 July 2018 Acceptance Review Determination (E-mail 7/5/2018), Proposed Alternative Request P-06 for 'C' Charging Pump Test ML18163A1732018-06-12012 June 2018 Acceptance Review Determination (E-mail 6/12/2018), LAR Regarding Proposed TS Changes to Spent Fuel Storage and New Fuel Storage ML18127A0232018-05-0707 May 2018 Acceptance Review Determination (E-mail 5/7/2018), LAR to Revise TS Action Statement for Loss of Control Building Inlet Ventilation Rad Monitor Instrumentation Channels ML18078A0072018-03-19019 March 2018 Acceptance Review Determination (E-mail), Inservice Testing Program for Pumps, Valves, and Snubbers, Fifth and Fourth 10-Year Interval Updates (EPID: L-2018-LLR-0011 to L-2018-LLR-0022) ML18078A0042018-03-19019 March 2018 Acceptance Review Determination (E-mail), Proposed Alternative Request RR-04-27 and IR-3-38 Use of Encoded Paut in Lieu of Rt ML17313A1602017-11-0909 November 2017 Acceptance Review Determination Regarding License Amendment Request to Revise the Integrated Leak Rate Test (Type a) and Type C Test Intervals ML17202A0062017-07-21021 July 2017 Acceptance Review Determination Regarding License Amendment Request to Revise the Company Name ML16354B5972016-12-19019 December 2016 Acceptance Review Determination - LAR to Revise TS Surveillance Requirement 4.1.3.1.2 for CEA-39 ML16335A2772016-11-30030 November 2016 Acceptance Review Determination - 2016/11/30 E-Mail from R. Guzman to W.C Raft Proposed Exemption from Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability ML16308A1932016-11-0303 November 2016 Acceptance Review Determination - 2016/11/03 E-Mail from R.Guzman to W.Craft Alternative Requests RR-04-24 and IR-3-30, Elimination of RPV Threads in Flange Examination (CAC Nos. MF8468/MF8469) ML16223A9392016-08-10010 August 2016 Acceptance Review Determination - 2016/08/10 E-mail from R.Guzman to W.Craft Exemption Request for Use of Axiom Cladding Material in Lead Test Assemblies (MF8120) 2024-04-25
[Table view] Category:E-Mail
MONTHYEARML24213A2602024-07-31031 July 2024 Request for Additional Information LAR to Support Implementation of Framatome Gaia Fuel ML24116A0112024-04-25025 April 2024 Acceptance Review Determination for Proposed Alternative Request IR-4-13 Regarding Steam Generator Channel Head Drain Modification ML24115A2622024-04-24024 April 2024 Acceptance Review Determination for Proposed Alternative Request IR-4-14 Regarding Pressurizer and Steam Generator Pressure-Retaining Welds and Full-Penetration Welded Nozzles ML24114A3192024-04-23023 April 2024 Acceptance Review Determination LAR to Extend Inspection Interval for Reactor Coolant Pump Flywheels (TSTF-421) Using the CLIIP ML24113A2502024-04-22022 April 2024 Request for Additional Information (e-mail 4/22/2024) License Renewal Commitment for Aging Management Program of Alloy 600 Components ML24092A1082024-04-0101 April 2024 3R22 RFO ISI Owners Activity Report Extension - NRC Staff Acknowledgement Email (4/1/2024) ML24065A3112024-03-0505 March 2024 Request for Additional Information (Redacted) (03/05/2025 E-mail from R. Guzman to S. Sinha) Framatome Gaia Fuel LOCA LAR ML24058A2322024-02-27027 February 2024 2/27/2024 E-mail from S. Sinha to R. Guzman P-8 Instrument Uncertainty in Support of LAR Framatome Gaia Fuel ML24032A4702024-02-0101 February 2024 Change in Estimated Review Schedule Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC ML24024A2452024-01-24024 January 2024 1/24/2024 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in SE for Amendment No. 288 - Revision to Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures ML24024A0202024-01-24024 January 2024 Correction to Safety Evaluation Associated Wit Amendment No. 288 - Revision to Applicability Term for RCS Heat-Up and Cooldown Pressure-Temperature Limitations Figures ML23326A0132023-11-22022 November 2023 Acceptance Review Determination LAR to Support Implementation of Framatome Gaia Fuel ML23318A0952023-11-14014 November 2023 Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel ML23317A0732023-11-13013 November 2023 Acceptance Review Determination - License Amendment Request Modification of TS SR 4.3.6.a ML23297A2312023-10-24024 October 2023 E-mail to File - Summary of September 13, 2023, Meeting with Dominion to Discuss Proposed LAR to Support Cycle Reloads Using Framatome Gaia Fuel ML23265A2302023-09-22022 September 2023 Acceptance Review Determination - License Amendment Request Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC ML23258A0552023-08-31031 August 2023 Setup of Online Reference Portal and Audit Plan for the NRC Staff'S Review of LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies (08/31/2023 e-mail) ML23199A2832023-07-18018 July 2023 Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits ML23172A0752023-06-21021 June 2023 Acceptance Review Determination LAR to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23145A0052023-05-25025 May 2023 Acceptance Review Determination Exemption to Use Framatome Gaia Fuel Assemblies Containing Fuel Rods Fabricated with M5 Fuel Rod Cladding ML23145A0042023-05-25025 May 2023 Acceptance Review Determination LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies ML23115A3022023-04-24024 April 2023 4/24/2023 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Issuance of Amendments Adoption of TSTF-359, Increase Flexibility in Mode Restraints ML23089A1882023-03-29029 March 2023 Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report ML23067A2162023-03-0707 March 2023 NRR E-mail Capture - RAI for North Anna, 1 & 2, Surry 1 & 2, Millstone, 2 & 3, Request for Approval of App. F Fleet Report DOM-NAF-2-P, Qual of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion VIPRE-D Computer Code ML23038A0152023-02-0707 February 2023 Acceptance Review Determination LAR to Revise the Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures ML23024A1522023-01-24024 January 2023 Acceptance Review Determination LAR to Supplement Burnup Credit of Criticality Safety Analysis ML23018A0352023-01-17017 January 2023 NRR E-mail Capture - Acceptance Review for Fleet Report Re Appendix F of DOM-NAF-2-P (L-2022-LLT-0003) ML22320A5752022-11-16016 November 2022 E-mail to File - Summary of October 18, 2022, Meeting with Dominion to Discuss Requested Actions for Implementing Framatome Gaia Fuel ML22298A2052022-10-25025 October 2022 Acceptance Review Determination for Alternative Request for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles ML22292A3212022-10-19019 October 2022 Acceptance Review Determination for Alternative Request for Containment RSS Pump Periodic Verification Testing Program ML22297A1802022-10-0707 October 2022 Email Acknowledgement to Dominion Energy Nuclear Decommissioning Trust Fund Disbursement 30 Day Notification for Millstone Power Station Unit 1: Docket No 50-245 ML22278A0932022-10-0505 October 2022 E-mail to File - Summary of September 7, 2022, Meeting with Dominion to Discuss Proposed Supplement to the Spent Fuel Pool Criticality Safety Analysis (EPID L-2022-LRM-0059 ML22272A0332022-09-29029 September 2022 Memo E-mail to File - Summary of August 29, 2022, Meeting with Dominion to Discuss Proposed Alternative Request Post-peening follow-up Volumetric Exam of RPV Head Penetration Nozzle ML22252A1772022-09-0909 September 2022 Memo E-mail to File - Summary of August 9, 2022, Meeting with Dominion to Discuss Proposed Alternative Reqeust Recirculation Spray Pump Flow Testing (EPID L:2022-LRM-0057) ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML22174A3552022-06-23023 June 2022 NRR E-mail Capture - Acceptance Review for Dominion Fleet LAR to Implement TSTF-554 (L-2022-LLA-0078) ML22123A0812022-05-0303 May 2022 Acceptance Review Determination for Proposed LAR for TS Change Applicable to TSTF-359, Increase Flexibility in Mode Restraints ML22069A7192022-03-10010 March 2022 E-mail from R. Guzman to S. Sinha - Millstone Unit 3 Steam Generator Outage Conference Call ML22020A4122022-01-11011 January 2022 1/11/2022 State Consultation E-mail, R. Guzman to J. Semancik Millstone Power Station, Unit 3 Planned Issuance of Amendment to Clarify Shutdown Bank TS and Add Alternate Control Rod Position Monitoring Requirements ML21348A7392021-12-14014 December 2021 E-mail - Acceptance Review Determination Alternative Request IR-4-09 for Use Alternative Brazed Joint Assessment Methodology for Class 3 Moderate Energy Piping ML21347A9412021-12-13013 December 2021 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Safety Evaluation for Amendment No. 280 Measurement Uncertainy Recapture Power Uprate ML21334A1922021-11-30030 November 2021 NRR E-mail Capture - Audit Plan for Reactor Core Thermal-Hydraulics Using the VIPRE-D Appendix E Review ML21326A1502021-11-22022 November 2021 NRR E-mail Capture - Acceptance Review for Relocation of Unit Staff Requirements to the QAPD LAR (L-2021-LLA-0195) ML21306A3302021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review for TSTF-569 LAR ML21297A0072021-10-19019 October 2021 E-mail from R. Guzman to S. Sinha - Acknowledgemnt of Error in SE for Millstone Power Station, Unit 3, Amendment No. 279 Addition of Analytical Methodology to the COLR for LBLOCA ML21286A7372021-10-13013 October 2021 Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR ML21223A3042021-08-11011 August 2021 Request for Withholding Information from Public Disclosure Proposed LAR to Add an Analytical Methodology to the COLR for a Large Break LOCA ML21200A2562021-07-19019 July 2021 7/19/2021 E-mail Pressurizer Steam Space Line Classification ML21195A2442021-07-13013 July 2021 NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code 2024-07-31
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From: Richard Guzman To: Shayan Sinha Cc: RidsNRRLIC109 Resource; Hipo Gonzalez
Subject:
Millstone Power Station, Unit 3 - Acceptance Review Determination for Proposed Alternative Request IR-4-13 Regarding Steam Generator Channel Head Drain Modification (EPID: L-2024-LLR-0025)
Date: Thursday, April 25, 2024 7:09:51 AM
Mr. Sinha,
By letter dated April 1, 2024 (ADAMS Accession No. ML24093A102), Dominion Energy Nuclear Connecticut, Inc. (the licensee) submitted alternative request IR-4-13 for Millstone Power Station, Unit No. 3 (MPS3), in support of performing modifications on the steam generator (SG) channel head drain connection on each SG in accordance with American Society of Mechanical Engineers (ASME) Code Case N-839. The proposed alternative requests relief from the code case requirements to use a 48-hour hold time and volumetric inspection method for final examination. The licensee proposes to perform progressive surface exams with the Liquid Dye Penetrant Examination (PT) process as an alternative to the final volumetric inspection. The proposed alternative is requested on the basis that compliance with the specified ASME Code Case examination requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety in accordance with Title 10 of the Code of Federal Regulations (10 CFR) section 50.55a(z)(2). The SG head drain modifications are scheduled to take place during the spring 2025 MPS3 refueling outage.
The purpose of this e-mail is to provide the results of the Nuclear Regulatory Commission (NRC) staffs acceptance review of this alternative request.The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the submittal has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff has reviewed the licensees submittal and concludes that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment.Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review.If additional information is needed, you will be advised by separate correspondence.
Based on the information provided in the submittal, the NRC staff has estimated that the review of the alternative request will take approximately 190 hours0.0022 days <br />0.0528 hours <br />3.141534e-4 weeks <br />7.2295e-5 months <br /> to complete.The NRC staff expects to complete this review by April 1, 2025.If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%),
the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager. These estimates are based on the NRC staffs initial review of the application and they could change, due to several factors including requests for additional information and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.
Please contact me if you have any questions. A copy of this email will be made publicly available in ADAMS.
- Thanks,
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Rich Guzman Sr. PM, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-10H17 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov