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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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Richard Emch - Need for Conference Call on SAMA RA! Responses Page 1 From: Richard Emch To: Edward_Annino~dom.com; Rich Gallagher; William_RWatson~dom.com Date: 9/2104 12:12PM
Subject:
Need for Conference Call on SAMA RAI Responses Rich, Ed & Bill, Attached is a list of questions to be used as an agenda for a conference call to discuss your responses to the SAMA RAls. We are proposing to conduct the conference call on Wednesday, September 8.
I am out of the office this week; if you want to talk to me about these questions or to set up the call, call me on my cell phone at 301-526-8716.
Rich Emch CC: John Tappert; JXD10; Leslie Fields; Robert Palla
Richard Emch - Followup~uestionsonMNPSRAlresponsesU2andU3.wpd Page-1 1 Page 1II Richard Emch FollowupQuestionsonMN PSRAiresponsesU2andU3.wpd QUESTIONS ON RESPONSES TO MNPS RAls
- 1. (U2 & U3) Different revisions of the PRA were used for the identification of SAMAs and the quantification of benefits. The response to RAI 6a lists the highest importance basic events from the PRA used for SAMA identification (Rev. 2 for U2; 10/99 for U3) and the importance of the same basic events from the PRA used for quantification (Rev. 3 for U2; 10/02 for U3). Confirm that the highest importance events from the later PRA are included in the list. If not, identify those basic events and the SAMAs that address those events.
- 2. (U2) The response to RAI 1b (p. 5) mentions results of a PRA model more recent than the version used for SAMA quantification. Confirm the existence of this update, identify the major changes (models/assumptions and results/risk profile), and discuss any potential impact on the SAMA analysis.
- 3. (U2) Relative to peer review F&O AS-5 (Item A.2 in Table 2), confirm that manual control of AFW after loss of air or loss of DC is credited in the PRA. (For example, is success in manual AFW control included in the top success branch in the event tree provided in response to RAI 2c?) If so, what is the failure probability and its importance? Is unavailability of indications due to dependency on power considered in determining this HEP? How was the evaluation of SAMA 113 performed in response to RAI 6g (i.e., what events were revised)?
- 4. (U3) Relative to Level A peer review F&Os SY-4 and HR-1 (Items A.2 and A.3 in Table 2), please provide a more detailed discussion and support for the conclusion that the incorporation of model changes in response to this F&O will have a negligible impact on the SAMA analysis.
- 5. (U3) Relative to peer review F&O TH-8 (Item B.19 in Table 2), the impact in Table 2 says that the DWST will provide only 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of water for the AFW pumps. Considering the high importance of the AFW system (the AFW is involved in 3 of the top 4 CDF sequences and the turbine driven AFW pump has a FV importance of 0.235), and the potential for a dependancy between operator action to initiate bleed and feed, justify further why the failure to provide alternate sources of water for the AFW after the DWST is emptied has a negligible impact on the SAMA analysis.
- 6. (U3) The date provided for Rev. 4 is 10/99. The ER states that the WOG peer review took place in 9/99. What version of the PRA was used in the peer review? The ER implies that it was the version used for the SAMA analysis (10/99). Table G.2-1 indicates a 8/99 version, but this is not included in the response to RAI Id. Please clarify.
- 7. (U2 & U3) The truncation value used has a significant impact on the CDF. Please provide the truncation values used for obtaining the CDFs given for U2 PRA Revisions 0, 1, and 2, and U3 PRA Revisions 0 (12/95), 2, and 3.
- 8. (U2 & U3) Of all of the PRA changes listed in response to RAI 1d, indicate which ones (1 or 2) were the major contributors to the changes in CDF from one revision to the next.
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Richard Emch - FollowupQuestionsonMNPSRAiresponsesU2andU3.wpd Page 21
- 9. (U2) What is meant by the last sentence in the description of the Rev. 0 and Rev. 1 PRAs?
- 10. (U2) Describe the sequences identified as COOL in the response to RAI 1e.
- 11. (U3) Regarding the 10/02 revision of the PRA, the response to RAI le indicates a total CDF (excluding internal flooding) of 2.57E-5 with a truncation value of 1E-1 1. The response to RAI 1d gives a value of 2.04E-5 with a truncation value of 1E-9. The ER provides a value of 2.88E-5 and states that a truncation value of 1E-1 1 was used.
Please explain.
- 12. (U2) The second paragraph of the response to RAI 1h states "The Level 2 portion of the IPE PRA for Millstone Unit 2 has not been updated but there has been some modifications of the individual bin definitions for consistency between the Unit 2 and Unit 3 PRAs." However, page E-F-23 of the ER states 'Recent experimental results have shown that certain outcomes on the containment event tree are much less likely than previously thought. These changes were incorporated into the Level 2 model." These statements appear inconsistent. Please clarify and describe in more detail what was done.
- 13. (U2) An example of how the RC and PDS conversions were made, and how Table F.2-4 was generated would help explain some remaining confusion regarding the conversion process. Take new RC M6, for example. According to Table 1h-3 in the RAI responses, RC M6 is composed of IPE RCs E-LM-R and E-MH-R. In the IPE (Table 4.9-5 of the IPE), TLCH contributes 0.04% and 37.7% to these two RCs. However, in the revised PRA (Table F.2-4 of the ER) TLCH contributes 73.8% of RC M6. It is noted that a number of IPE PDSs are not Included in Tables 1h-1 and F.2-4 (for example, TEHA, TEHB, and TEHC, which are the dominant PDS in the IPE. Where are they assigned and is this the source of the difference noted above?
- 14. (U3) Given that the original Table G.2-4 is incorrect (according to the response to RAI 2.c) and results in incorrect (but high) frequencies in several release categories, is the increase in CDF used in the cost benefit analysis also in error?
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