Letter Sequence Other |
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EPID:L-2020-LLA-0242, Proposed License Amendment Request, Addition of Analytical Methodology to the Core Opera Ting Limits Report for a Full Spectrum Loss of Coolant Accident (Fsloca) Gamma Energy Redistribution Information (Approved, Closed) |
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MONTHYEARRS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2020-02-28028 February 2020 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) Project stage: Request ML20063L2822020-02-28028 February 2020 Application of Westinghouse Full Spectrum LOCA Evaluation Model Project stage: Other ML20244A3362020-08-31031 August 2020 Proposed License Amendment Request, Addition of Analytical Methodology to the Core Opera Ting Limits Report for a Full Spectrum Loss of Coolant Accident (Fsloca) Gamma Energy Redistribution Information Project stage: Request ML20310A3242020-11-0505 November 2020 Proposed License Amendment Request, Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident (LBLOCA) Project stage: Request 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) Project stage: Acceptance Review ML21105A1152021-04-15015 April 2021 Request for Additional Information (e-mail Dated 4/15/2021) Proposed LAR for Addition of Analytical Methodology to the Core Operating Limits Report for a LBLOCA Project stage: RAI ML21140A2992021-05-20020 May 2021 Response to Request for Additional Information for Proposed License Amendment Request to Add an Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident Project stage: Response to RAI ML21201A1712021-06-24024 June 2021 4 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses Project stage: Request 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 Project stage: Withholding Request Acceptance ML21227A0002021-10-0505 October 2021 Issuance of Amendment No. 279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident Project stage: Approval 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 Project stage: Other 2021-10-19
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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: Guzman, Richard To: Shayan.Sinha@dominionenergy.com
Subject:
RE: [Identification and Correction in SE] Millstone Power Station, Unit No. 3 - Issuance of Amendment No. 279 Re: Addition of Analytical Methodology to the COLR for a Large Break Loss-of-Coolant Accident (EPID L-2020-LLA-0242)
Date: Tuesday, October 19, 2021 4:05:23 PM
- Shayan, Thanks for providing your feedback on the subject license amendment issued on October 5, 2021. The staff has reviewed your comments dated October 13, 2021 (message below) and acknowledges there were a few inaccuracies in the safety evaluation (SE), resulting in the need for clarification as follows:
- 1. [DENC Comment] The SE accurately states that Dominion did not utilize the FSLOCA methodology to demonstrate compliance with 10 CFR 50.46 (b)(5). However, Dominion believes that the characterizations that the ASTRUM methodology addresses 10 CFR 50.46(b)(5) & long term core cooling are not representative of the MPS3 FSAR. The second-to-last paragraph of the Enclosure 2 SE, Section 3.3 (page 8) references MPS3 FSAR Section 15.6.5.2.6. This referenced MPS3 FSAR Section clarifies (emphasis added):
The actions, automatic or manual, that are currently in place at these plants to maintain long term cooling remain unchanged with the application of ASTRUM methodology (WCAP-16009-P-A).
In other words, the actions mentioned above demonstrate compliance with 10 CFR 50.46(b)(5) rather than application of the ASTRUM methodology. MPS3 Stretch Power Uprate (SPU) LAR, Attachment 5, Section 2.8.5.6.3.2.5.2 and MPS3 Measurement Uncertainty Recapture (MUR)
LAR, Attachment 4, Page 57/162 (item #28) provide more detail on the actions to maintain long term cooling. The linkage between 50.46(b)(5) compliance and the ASTRUM methodology appears in the SE Section 3.3 paragraph cited above, Section 3.4 (page 8) and the second bullet of Section 3.5 (page 15).
NRC Staff Response: The NRC staff acknowledges the error in the SE; characterizing that the ASTRUM methodology application demonstrates compliance with 10 CFR 50.46(b)(5) and long term cooling is incorrect and inconsistent with the referenced FSAR Section 15.6.5.2.6. The NRC staff is also in agreement that the referenced FSAR section 15.6.5.2.6 (ADAMS Accession No. ML21201A171), the stated SPU LAR section (ADAMS Accession No. ML072000400) and the MUR LAR section (ADAMS Accession No. ML20324A703) as explained and underscored in your 10/13/2021 comments is the correct rationale for clarifying the identified inaccuracy.
- 2. [DENC Comment] SE Section 3.2 (page 5), first and third paragraphs under Methodology note that the FSLOCA methodology is applicable to 2-loop PWRs with cold leg injections. However, the FSLOCA Topical Report (WCAP-16996) states that the methodology is applicable to 3- and 4-loop PWRs with cold leg injections.
NRC Staff Response: The staff agrees; this was a typo and should have been 3-loop instead of 2-loop as follows:
The previous NRC-approved best-estimate LBLOCA analysis
(Westinghouse) methodology described in WCAP-16009-P-A (Reference 6) is termed the Automated Statistical Treatment of Uncertainty Method (ASTRUM) EM. This methodology is applicable to the Westinghouse-designed (a) 3-loop and 4-loop PWRs with ECCS injection into the reactor coolant system (RCS) cold legs and
- 3. [DENC Comment] Minor comment on SE Section 3.0 (page 4), bullet (b) says that the Staff evaluated whether the regulations in Section 2.3 were satisfied, but Section 2.3 covers regulatory requirements and guidance.
NRC Staff Response: The NRC staff agrees this is a minor comment as the word regulations was intended to refer to the applicable regulatory requirements and guidance listed in Section 2.3. Please note however, the first sentence of Section 2.3 states, the NRC staff considered the following regulations during its review of the proposed changes, which is not inconsistent with the subsequent use of the word regulations in Section 3.0.
- 4. [DENC Comment] Minor comment on SE Section 3.1 (page 4), the third paragraph says that WCAP-12945-P-A was superseded, however the term replaced is recommended instead.
WCAP-12945 is not superseded in the sense that it is no longer a valid document, it is simply not currently used at MPS3.
NRC Staff Response: The NRC staff agrees this is a minor comment and the word replaced is the more optimal term (instead of superseded) for the reasons stated in your 10/13/2021 message (i.e., WCAP-12945 remains a valid document, but not currently used at MPS3).
The identified discrepancies above are considered minor and do not warrant a formal correction letter as the license and TS pages are not impacted and the staffs technical basis and safety conclusions in the safety evaluation are not impacted as originally issued in Amendment No. 279. Please consider this e-mail communication as documentation of the inaccuracies and/or minor errors as stated above. This communication will be added to ADAMS as an official agency record. If you have any questions or concerns on this matter, please contact me.
Thank you, Rich Guzman Sr. PM, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov From: Shayan.Sinha@dominionenergy.com <Shayan.Sinha@dominionenergy.com>
Sent: Wednesday, October 13, 2021 3:01 PM To: Guzman, Richard <Richard.Guzman@nrc.gov>
Subject:
[External_Sender] FW: Millstone Power Station, Unit No. 3 - Issuance of Amendment No.
279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident (EPID L-2020-LLA-0242)
- Rich, Dominion had some feedback on the subject SE for the MPS3 FSLOCA LAR - please see below:
- 1. The SE accurately states that Dominion did not utilize the FSLOCA methodology to demonstrate compliance with 10 CFR 50.46 (b)(5). However, Dominion believes that the characterizations that the ASTRUM methodology addresses 10 CFR 50.46(b)(5) & long term core cooling are not representative of the MPS3 FSAR. The second-to-last paragraph of the Enclosure 2 SE, Section 3.3 (page 8) references MPS3 FSAR Section 15.6.5.2.6. This referenced MPS3 FSAR Section clarifies (emphasis added):
The actions, automatic or manual, that are currently in place at these plants to maintain long term cooling remain unchanged with the application of ASTRUM methodology (WCAP-16009-P-A).
In other words, the actions mentioned above demonstrate compliance with 10 CFR 50.46(b)
(5) rather than application of the ASTRUM methodology. MPS3 Stretch Power Uprate (SPU)
LAR, Attachment 5, Section 2.8.5.6.3.2.5.2 and MPS3 Measurement Uncertainty Recapture (MUR) LAR, Attachment 4, Page 57/162 (item #28) provide more detail on the actions to maintain long term cooling. The linkage between 50.46(b)(5) compliance and the ASTRUM methodology appears in the SE Section 3.3 paragraph cited above, Section 3.4 (page 8) and the second bullet of Section 3.5 (page 15).
- 2. SE Section 3.2 (page 5), first and third paragraphs under Methodology note that the FSLOCA methodology is applicable to 2-loop PWRs with cold leg injections. However, the FSLOCA Topical Report (WCAP-16996) states that the methodology is applicable to 3- and 4-loop PWRs with cold leg injections.
- 3. Minor comment on SE Section 3.0 (page 4), bullet (b) says that the Staff evaluated whether the regulations in Section 2.3 were satisfied, but Section 2.3 covers regulatory requirements and guidance.
- 4. Minor comment on SE Section 3.1 (page 4), the third paragraph says that WCAP-12945-P-A was superseded, however the term replaced is recommended instead. WCAP-12945 is not superseded in the sense that it is no longer a valid document, it is simply not currently used at MPS3.
If you have any questions or need to discuss further, please let me know.
- Thanks, Shayan Sinha