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| | issue date = 02/15/2019 | | | issue date = 02/15/2019 |
| | title = Memo E-mail to File - Summary of January 22, 2019, Meeting with Dominion to Discuss Proposed Alternative IR-3-39 Fillet Welds | | | title = Memo E-mail to File - Summary of January 22, 2019, Meeting with Dominion to Discuss Proposed Alternative IR-3-39 Fillet Welds |
| | author name = Guzman R V | | | author name = Guzman R |
| | author affiliation = NRC/NRR/DORL/LPLI | | | author affiliation = NRC/NRR/DORL/LPLI |
| | addressee name = Danna J G | | | addressee name = Danna J |
| | addressee affiliation = NRC/NRR/DORL/LPLI | | | addressee affiliation = NRC/NRR/DORL/LPLI |
| | docket = 05000423 | | | docket = 05000423 |
| | license number = NPF-049 | | | license number = NPF-049 |
| | contact person = Guzman R V | | | contact person = Guzman R |
| | case reference number = EPID L-2019-LRM-0004 | | | case reference number = EPID L-2019-LRM-0004 |
| | document type = E-Mail, Meeting Summary | | | document type = E-Mail, Meeting Summary |
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| =Text= | | =Text= |
| {{#Wiki_filter:From: Guzman, Richard To: Danna, James Bcc: Guzman, Richard | | {{#Wiki_filter:From: Guzman, Richard To: Danna, James Bcc: Guzman, Richard |
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| ==Subject:== | | ==Subject:== |
| Memo E-mail to File - Summary of January 22, 2019, Meeting with Dominion to Discuss Proposed Alternative Request, IR-3-39, Fillet Weld Alternative to ASME Code, Section XI Date: Friday, February 15, 2019 11:08:00 AM Jim, For your information, shown below is a summary of the January 22, 2019, Category 1 public meeting with Dominion Energy Nuclear Connecticut, Inc. to discuss the licensee's subject proposed alternative relief request for Millstone Power Station, Unit No. 3. This e-mail will be added to ADAMS as an official agency record and Listserv'd. | | Memo E-mail to File - Summary of January 22, 2019, Meeting with Dominion to Discuss Proposed Alternative Request, IR-3-39, Fillet Weld Alternative to ASME Code, Section XI Date: Friday, February 15, 2019 11:08:00 AM |
| Please contact me if you have any questions regarding this meeting. Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: | | : Jim, For your information, shown below is a summary of the January 22, 2019, Category 1 public meeting with Dominion Energy Nuclear Connecticut, Inc. to discuss the licensees subject proposed alternative relief request for Millstone Power Station, Unit No. 3. This e-mail will be added to ADAMS as an official agency record and Listservd. Please contact me if you have any questions regarding this meeting. |
| (301) 415-1030 Richard.Guzman@nrc.gov CATEGORY 1 PUBLIC MEETING WITH DOMINION ENERGY NUCLEAR CONNECTICUT, INC. (DENC), TO DISCUSS PROPOSED ALTERNATIVE REQUEST TO ASME CODE SECTION XI, IWA-4221 MILLSTONE POWER STATION, UNIT NO. 3 PRE-APPLICATION MEETING MEETING | | Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov CATEGORY 1 PUBLIC MEETING WITH DOMINION ENERGY NUCLEAR CONNECTICUT, INC. (DENC), |
| | TO DISCUSS PROPOSED ALTERNATIVE REQUEST TO ASME CODE SECTION XI, IWA-4221 MILLSTONE POWER STATION, UNIT NO. 3 PRE-APPLICATION MEETING MEETING |
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| ==SUMMARY== | | ==SUMMARY== |
| JANUARY 22, 2019 DOCKET NO. 50-423 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Dominion Energy Nuclear Connecticut, Inc. (DENC, the licensee) held a public meeting on January 22, 2019, to discuss the licensee's planned IR-3-39 Relief Request submittal regarding a fillet weld alternative from the requirements of the American Society of Mechanical Engineers (ASME) Code, Section XI, Paragraph IWA-4221 for Millstone Unit 3 (MPS3). The licensee's meeting slides are available in Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19022A243. The licensee's presentation is summarized as follows: Background and Request The licensee provided an overview of their proposed alternative relief request. Specifically, the licensee requests relief from the ASME Section XI, IWA-4221(c) requirements two fillet welds fabricated during the 'B' Reactor Plant Component Cooling Water (CCP) heat exchanger replacement project in Refueling Outage 17 for MPS3. The request would permit the two fillet welds, which were made without a 200 degree preheat as required by the code of construction, to remain in-service. | | |
| Precedent Request The proposed alternative request is similar to one submitted by Entergy on August 19, 2013, for River Bend Station, Unit No. 1 (ADAMS Accession No. ML13239A074). | | JANUARY 22, 2019 DOCKET NO. 50-423 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Dominion Energy Nuclear Connecticut, Inc. (DENC, the licensee) held a public meeting on January 22, 2019, to discuss the licensees planned IR-3-39 Relief Request submittal regarding a fillet weld alternative from the requirements of the American Society of Mechanical Engineers (ASME) Code, Section XI, Paragraph IWA-4221 for Millstone Unit 3 (MPS3). The licensees meeting slides are available in Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19022A243. The licensees presentation is summarized as follows: |
| This request was approved by the NRC on January 28, 2014 (ADAMS Accession No.ML13353A608). | | Background and Request The licensee provided an overview of their proposed alternative relief request. Specifically, the licensee requests relief from the ASME Section XI, IWA-4221(c) requirements two fillet welds fabricated during the B Reactor Plant Component Cooling Water (CCP) heat exchanger replacement project in Refueling Outage 17 for MPS3. The request would |
| Unlike the River Bend request, the Millstone request does not state that there is hardship associated with meeting the code requirement. | | |
| River Bend's condition involved ten valves in both trains of service water. Repair or replacement was quantitatively shown to have a measurable increase on risk due to unavailability of associated safety related systems over multiple refueling outages. No such quantitative assessment is currently planned as part of the proposed Millstone alternative request, IR-3-39. Instead, the request will conclude that based on studies and tests, the multi-pass gas tungsten arc-welded fillet welds made without the 200 degree preheat, produce comparable microstructures and hardness (of the weld and heat affected zone) as compared to equivalent code compliant single pass fillet welds with 200 degree preheat. Evaluation of Production Welds An evaluation of the production welds FW-12 and FW-30 was performed. | | permit the two fillet welds, which were made without a 200 degree preheat as required by the code of construction, to remain in-service. |
| The licensee determined that the outer diameter fillet welds are capable of accommodating all design loads and maintaining structural integrity even without the inner diameter weld in place. Visual and magnetic particle examinations on the production welds were also completed with no recordable indications. | | Precedent Request The proposed alternative request is similar to one submitted by Entergy on August 19, 2013, for River Bend Station, Unit No. 1 (ADAMS Accession No. ML13239A074). This request was approved by the NRC on January 28, 2014 (ADAMS Accession No. ML13353A608). Unlike the River Bend request, the Millstone request does not state that there is hardship associated with meeting the code requirement. River Bends condition involved ten valves in both trains of service water. Repair or replacement was quantitatively shown to have a measurable increase on risk due to unavailability of associated safety related systems over multiple refueling outages. No such quantitative assessment is currently planned as part of the proposed Millstone alternative request, IR 39. Instead, the request will conclude that based on studies and tests, the multi-pass gas tungsten arc-welded fillet welds made without the 200 degree preheat, produce comparable microstructures and hardness (of the weld and heat affected zone) as compared to equivalent code compliant single pass fillet welds with 200 degree preheat. |
| Additionally, mock-up testing was performed by the licensee to further support that the existing configuration has an acceptable level of quality. The licensee concluded that the production welds which were made without the 200 degree preheat on the MPS3 'B' CCP heat exchanger have acceptable properties for continued use without repair or replacement. | | Evaluation of Production Welds An evaluation of the production welds FW-12 and FW-30 was performed. The licensee determined that the outer diameter fillet welds are capable of accommodating all design loads and maintaining structural integrity even without the inner diameter weld in place. |
| Schedule The licensee stated their planned submittal is on track and projected for submission by the end of February 2019. No decisions were made regarding the acceptability of the licensee's proposed submittal. | | Visual and magnetic particle examinations on the production welds were also completed with no recordable indications. Additionally, mock-up testing was performed by the licensee to further support that the existing configuration has an acceptable level of quality. |
| There were no members of the public in attendance by teleconference. | | The licensee concluded that the production welds which were made without the 200 degree preheat on the MPS3 B CCP heat exchanger have acceptable properties for continued use without repair or replacement. |
| To date, no public meeting feedback forms have been submitted through the NRC public meeting feedback system. LIST OF ATTENDEES JANUARY 22, 2019, CATEGORY 1 PUBLIC MEETING WITH DOMINION ENERGY NUCLEAR CONNECTICUT, INC. (DENC), TO DISCUSS PROPOSED ALTERNATIVE REQUEST TO ASME CODE SECTION XI, IWA-4221 MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 ATTENDEE ORGANIZATION Robert Davis U.S. Nuclear Regulatory Commission (NRC)Richard Guzman NRC Justin Fuller NRC Joseph Rigatti DENC David Dodson DENC Marc Hall DENC Michael Lalikos DENC Lori Kelly DENC Jeff Langan DENC Craig Sly DENC Eric Stanistreet DENC Philip Brant DENC Shayan Sinha DENC}} | | Schedule The licensee stated their planned submittal is on track and projected for submission by the end of February 2019. |
| | No decisions were made regarding the acceptability of the licensees proposed submittal. |
| | There were no members of the public in attendance by teleconference. To date, no public meeting feedback forms have been submitted through the NRC public meeting feedback system. |
| | LIST OF ATTENDEES JANUARY 22, 2019, CATEGORY 1 PUBLIC MEETING WITH DOMINION ENERGY NUCLEAR CONNECTICUT, INC. (DENC), |
| | TO DISCUSS PROPOSED ALTERNATIVE REQUEST TO ASME CODE SECTION XI, IWA-4221 MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 |
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| | ATTENDEE ORGANIZATION Robert Davis U.S. Nuclear Regulatory Commission (NRC) |
| | Richard Guzman NRC Justin Fuller NRC Joseph Rigatti DENC David Dodson DENC Marc Hall DENC Michael Lalikos DENC Lori Kelly DENC Jeff Langan DENC Craig Sly DENC Eric Stanistreet DENC Philip Brant DENC Shayan Sinha DENC}} |
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EPID:L-2019-LRM-0004, Presentation Material for 1/22/19 Pre-Submittal Meeting Fillet Weld Preheat Alternative Request (Open) |
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MONTHYEARML19022A2432019-01-22022 January 2019 Presentation Material for 1/22/19 Pre-Submittal Meeting Fillet Weld Preheat Alternative Request Project stage: Request ML19046A1502019-02-15015 February 2019 Memo E-mail to File - Summary of January 22, 2019, Meeting with Dominion to Discuss Proposed Alternative IR-3-39 Fillet Welds Project stage: Meeting 2019-01-22
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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
[Table view] Category:Meeting Summary
MONTHYEARML24222A6992024-08-16016 August 2024 August 6, 2024, Summary of Regarding Potential License Amendment Request Change to Surveillance Requirements for Moderator Temperature Coefficient for Millstone, Unit No. 3, North Anna, Unit Nos. 1 and 2, and Summer, Unit No. 1 - ML24150A1542024-05-29029 May 2024 5/16/2024, Annual Assessment Meeting for Millstone Power Station - Meeting Summary 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 ML23080A1902023-03-21021 March 2023 Annual Assessment Meeting for Millstone Power Station - Meeting Summary 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) ML22130A1702022-05-20020 May 2022 Summary of April 21, 2022, Public Meeting to Discuss Potential Emergency Preparedness License Amendment Request ML22131A0702022-05-12012 May 2022 Summary of Conference Call Regarding the Spring 2022 Steam Generator Tube Inspections ML22102A1642022-04-12012 April 2022 Annual Assessment Meeting for Millstone Power Station - Meeting Summary ML21091A0522021-04-0101 April 2021 3/18/21 - Annual Assessment Meeting for Millstone Power Station - Meeting Summary ML21027A0232021-01-28028 January 2021 Summary of January 26, 2021 Closed Meeting with Dominion Energy Regarding Performance of Force on Force Exercises in a Pandemic Environment ML20272A3112020-09-28028 September 2020 Memo E-mail to File - Summary of August 19, 2020, Meeting with Dominion to Discuss Proposed Exemption Request Biennial Emergency Preparedness Exercise Date Change ML20210M4232020-08-0505 August 2020 Summary of June 29, 2020, Pre-Submittal Teleconference with Dominion Energy Nuclear Connecticut, Inc. Proposed License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML20176A5992020-06-29029 June 2020 Summary of May 26, 2020, Pre-Submittal Teleconference with Dominion Energy Nuclear Connecticut, Inc. Proposed Alternative Request for Steam Generator Weld Examinations ML20121A1082020-04-30030 April 2020 Annual Assessment Meeting for Millstone Power Station - Meeting Summary ML19194A0012019-07-12012 July 2019 Memo E-mail to File - Summary of June 3, 2019, Meeting with Dominion to Discuss Proposed License Amendment Request to Extend Integrated Leak Rate Test Interval ML19159A0012019-06-0707 June 2019 Memo E-mail to File - Summary of May 9, 2019, Meeting with Dominion to Discuss Proposed License Amendment Request Revised TS Limits for Coolant Activity ML19144A1292019-05-30030 May 2019 Summary of November 20, 2018, Pre Application Meeting with Dominion Energy Regarding the Planned License Amendment Request to Revise Emergency Action Levels ML19046A1502019-02-15015 February 2019 Memo E-mail to File - Summary of January 22, 2019, Meeting with Dominion to Discuss Proposed Alternative IR-3-39 Fillet Welds ML18341A0982018-12-0707 December 2018 Memo E-mail to File - Summary of November 8, 2018, Meeting with Dominion to Discuss Proposed LAR - 10 CFR 50.69 Risk-Informed Approach ML18113A2672018-04-25025 April 2018 Summary of Meeting with Dominion Energy Nuclear Connecticut, Inc. on Planned Relief Request Submittal Concerning the In-Service Testing of the C Charging Pump ML18101A0422018-04-10010 April 2018 Summary of Annual Assessment Meeting for Millstone Power Station Held on 4/4/18 ML17274A0002017-09-29029 September 2017 Memo E-mail to File - Summary of August 31, 2017, Meeting with Dominion to Discuss Proposed License Amendment, Revised Spent Fuel Pool Criticality Safety Analysis ML17227A0052017-08-15015 August 2017 Memo E-mail to File - Summary of July 18, 2017, Meeting with Dominion to Discuss Proposed License Amendment Request, TS 3.8.1.1, AC Sources Operating ML17096A4512017-04-0505 April 2017 3/22/2017 - Summary of Annual Assessment Meeting for Millstone Power Station ML16160A0282016-06-0808 June 2016 Teleconference Memo to File - Millstone Power Station, Unit 2, Summary of May 3, 2016 Pre-submittal Teleconference with Dominion Nuclear Connecticut ML16102A0732016-04-0808 April 2016 3/29/2016 Summary of Public Annual Assessment Meeting for Millstone Power Station ML16035A4802016-02-12012 February 2016 Jsc Meeting Summary Attachment ML16004A4732016-01-0404 January 2016 Teleconference Memo to File: Summary of December 17, 2015 - Pre-submittal Call with the NRC Related to Confirmatory Item IV.5 ML16004A4722016-01-0404 January 2016 Teleconference Memo to File: Summary of December 10, 2015 - Pre-submittal Call with the NRC Related to Confirmatory Item IV.2 ML15316A2522015-11-19019 November 2015 October 20, 2015, Millstone, Units 2 and 3, Surry, Units 1 and 2, North Anna, Units 1 and 2 - Summary of Pre-submittal Conference Call Regarding Emergency Action Level Scheme Changes ML15173A0002015-06-23023 June 2015 Summary of Conference Call Regarding the Fall 2014 Steam Generator Tube Inspections ML15162A8662015-06-16016 June 2015 Summary of May 21, 2015 Meeting with Dominion Nuclear Connecticut, Inc. to Discuss Pre-Submittal of License Amendment Request for Removal of Severe Line Outage Detection at Millstone Power Station ML15128A3872015-05-0808 May 2015 4/14/2015 Summary of Annual Assessment Meeting for Millstone Power Station ML14210A0212014-08-0808 August 2014 June 25, 2014, Summary of Category 1 Public Meeting with Dominion Nuclear to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1 ML14093A7182014-04-0303 April 2014 Summary of Annual Assessment Meeting for Millstone Power Station on 3/31/2014 ML14029A6532014-01-29029 January 2014 2013 Annual Summary of the Green Mountain Power Special Nuclear Committee ML13207A2592013-07-30030 July 2013 7/17/2013 - Summary of Meeting with Dominion Nuclear Connecticut, Inc. and Areva to Discuss Upgrade to Areva Standard CE14 Htp Fuel Assembly.7/17/2013 - Summary of Meeting with Dominion Nuclear Connecticut, Inc. and Areva to Discuss Upgrade ML13127A0832013-05-0707 May 2013 4/9/13 - Summary of Annual Assessment Meeting with Millstone Power Station ML12115A1072012-04-23023 April 2012 Summary of Public Meeting to Discuss Annual Assessment of Safety Performance at Milstone for 2011 ML12115A1162012-04-23023 April 2012 4/19/2012 - Millstone Power Station/Neac 2011 Annual Assessment Meeting Summary ML1205803622012-03-12012 March 2012 2/15/2012 - Summary of Pre-Application Meeting with Dominion Nuclear Connecticut, Inc., to Discuss a Proposed Millstone Power Station, Unit No. 2, License Amendment Request Concerning Spent Fuel Pool Criticality Re-Analysis ML11292A1612011-10-20020 October 2011 Summary of Meeting with Beyond Nuclear Regarding Their 10 CFR 2.206 Petition to Suspend Operating Licenses of General Electric Mark I Boiling Water Reactors ML1118806442011-07-0707 July 2011 Summary of the Millstone 2011 Annual Assessment Meeting with the Connecticut Nuclear Energy Advisory Council (Neac) ML1118805312011-07-0707 July 2011 Annual Assessment Meeting Summary ML11166A1342011-06-22022 June 2011 Meeting Summary with the Beyond Nuclear Petitioners Regarding Their 2.206 Petition to Suspend Operating Licenses (Ols) of General Electric (GE) Boiling Water Reactors (Bwrs) Mark I (Bwrs) ML1106907942011-05-10010 May 2011 Summary of Meeting with Dominion Nuclear Connecticut, Inc. Discussing Millstone Power Station, Units 2 and 3 Licensing Activities ML1034807622011-01-12012 January 2011 November 8, 2010 Summary of Teleconference W/ DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information ML1022201102010-09-14014 September 2010 July 28, 2010, Summary of Teleconference with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information ML1020102612010-07-29029 July 2010 Summary of July 13, 2010, Meeting with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information 2024-08-16
[Table view] |
Text
From: Guzman, Richard To: Danna, James Bcc: Guzman, Richard
Subject:
Memo E-mail to File - Summary of January 22, 2019, Meeting with Dominion to Discuss Proposed Alternative Request, IR-3-39, Fillet Weld Alternative to ASME Code,Section XI Date: Friday, February 15, 2019 11:08:00 AM
- Jim, For your information, shown below is a summary of the January 22, 2019, Category 1 public meeting with Dominion Energy Nuclear Connecticut, Inc. to discuss the licensees subject proposed alternative relief request for Millstone Power Station, Unit No. 3. This e-mail will be added to ADAMS as an official agency record and Listservd. Please contact me if you have any questions regarding this meeting.
Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov CATEGORY 1 PUBLIC MEETING WITH DOMINION ENERGY NUCLEAR CONNECTICUT, INC. (DENC),
TO DISCUSS PROPOSED ALTERNATIVE REQUEST TO ASME CODE SECTION XI, IWA-4221 MILLSTONE POWER STATION, UNIT NO. 3 PRE-APPLICATION MEETING MEETING
SUMMARY
JANUARY 22, 2019 DOCKET NO. 50-423 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Dominion Energy Nuclear Connecticut, Inc. (DENC, the licensee) held a public meeting on January 22, 2019, to discuss the licensees planned IR-3-39 Relief Request submittal regarding a fillet weld alternative from the requirements of the American Society of Mechanical Engineers (ASME) Code,Section XI, Paragraph IWA-4221 for Millstone Unit 3 (MPS3). The licensees meeting slides are available in Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19022A243. The licensees presentation is summarized as follows:
Background and Request The licensee provided an overview of their proposed alternative relief request. Specifically, the licensee requests relief from the ASME Section XI, IWA-4221(c) requirements two fillet welds fabricated during the B Reactor Plant Component Cooling Water (CCP) heat exchanger replacement project in Refueling Outage 17 for MPS3. The request would
permit the two fillet welds, which were made without a 200 degree preheat as required by the code of construction, to remain in-service.
Precedent Request The proposed alternative request is similar to one submitted by Entergy on August 19, 2013, for River Bend Station, Unit No. 1 (ADAMS Accession No. ML13239A074). This request was approved by the NRC on January 28, 2014 (ADAMS Accession No. ML13353A608). Unlike the River Bend request, the Millstone request does not state that there is hardship associated with meeting the code requirement. River Bends condition involved ten valves in both trains of service water. Repair or replacement was quantitatively shown to have a measurable increase on risk due to unavailability of associated safety related systems over multiple refueling outages. No such quantitative assessment is currently planned as part of the proposed Millstone alternative request, IR 39. Instead, the request will conclude that based on studies and tests, the multi-pass gas tungsten arc-welded fillet welds made without the 200 degree preheat, produce comparable microstructures and hardness (of the weld and heat affected zone) as compared to equivalent code compliant single pass fillet welds with 200 degree preheat.
Evaluation of Production Welds An evaluation of the production welds FW-12 and FW-30 was performed. The licensee determined that the outer diameter fillet welds are capable of accommodating all design loads and maintaining structural integrity even without the inner diameter weld in place.
Visual and magnetic particle examinations on the production welds were also completed with no recordable indications. Additionally, mock-up testing was performed by the licensee to further support that the existing configuration has an acceptable level of quality.
The licensee concluded that the production welds which were made without the 200 degree preheat on the MPS3 B CCP heat exchanger have acceptable properties for continued use without repair or replacement.
Schedule The licensee stated their planned submittal is on track and projected for submission by the end of February 2019.
No decisions were made regarding the acceptability of the licensees proposed submittal.
There were no members of the public in attendance by teleconference. To date, no public meeting feedback forms have been submitted through the NRC public meeting feedback system.
LIST OF ATTENDEES JANUARY 22, 2019, CATEGORY 1 PUBLIC MEETING WITH DOMINION ENERGY NUCLEAR CONNECTICUT, INC. (DENC),
TO DISCUSS PROPOSED ALTERNATIVE REQUEST TO ASME CODE SECTION XI, IWA-4221 MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423
ATTENDEE ORGANIZATION Robert Davis U.S. Nuclear Regulatory Commission (NRC)
Richard Guzman NRC Justin Fuller NRC Joseph Rigatti DENC David Dodson DENC Marc Hall DENC Michael Lalikos DENC Lori Kelly DENC Jeff Langan DENC Craig Sly DENC Eric Stanistreet DENC Philip Brant DENC Shayan Sinha DENC