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MONTHYEARML15194A0612015-07-0202 July 2015 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Project stage: Request ML16011A5172016-01-11011 January 2016 NRR E-mail Capture - Millstone Power Station, Unit 3, Reactor Vessel Surveillance Capsule Withdrawal Schedule - Request for Additional Information Project stage: RAI ML16034A2152016-01-28028 January 2016 Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Project stage: Request ML16067A2342016-03-15015 March 2016 Revision to the Reactor Vessel Surveillance Capsule Withdrawal Schedule Project stage: Other ML16122A0022016-04-27027 April 2016 2016/04/27 E-mail from W.Craft to R.Guzman Updated Information - Reactor Vessel Surveillance Capsule Withdrawal Schedule Revision Project stage: Other ML16124B1622016-05-0303 May 2016 2016/05/03 E-mail from R.Guzman to W.Craft NRC Staff Approval of MPS3 Rv Surveillance Capsule Withdrawal Schedule - Capsule Y Reinstallation Location Project stage: Other 2016-01-28
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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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1Guzman, RichardFrom:Guzman, RichardSent:Tuesday, May 03, 2016 4:28 PMTo:Wanda D Craft (Generation - 6)Subject:Re: MPS3 RV Surveillance Capsule Withdrawal Schedule revisionWanda,InresponsetoyourrequestforNRCapprovaloftherevisedcapsulewithdrawalscheduledescribedinyourApril27,2016,email,theNRCstaffhascompleteditsreviewandhasconcludedthatthereactorvesselmaterialsurveillancecapsulewithdrawalscheduleforMIllstonePowerStation,Unit3continuestosatisfytherequirementsofAppendixHto10CFRPart50andtherecommendationsoftheGALLReportastheyrelatetotheperiodofextendedoperation.Therefore,theproposedchangeinlocationforthereinstallationofCapsuleYfromthe241°locationtothe61°locationisacceptable.Asummaryofthestaff'stechnicalevaluationisprovidedbelow.ThisemailofficiallytransmitsNRCstaffapprovalofthelicensee'sApril27,2016,request.ItwillbeaddedtoADAMSasanofficialagencyrecord.
Pleasecontactmeifyouhaveanyquestions.
RichGuzmanSr.ProjectManagerNRR/DORLUSNRC3014151030
SummaryofNRCstaffevaluationIn the NRC letter with enclosed safety evaluation (SE) dated March 15, 2016, the NRC staff approved a revised reactor vessel material surveillance capsule withdrawal schedule for the Millstone Power Station, Unit 3 (MPS3). Capsule Y was withdrawn after 13.8 effective full power years (EFPY) and placed into storage in the spent fuel pool after accruing a neutron fluence of 2.98 x 1019 n/cm2. The withdrawal schedule was changed to allow the reinstallation of standby Capsule Y into the reactor vessel at the 241° location during the Spring 2016 refueling outage. During the MPS3 spring 2016 outage, Dominion Nuclear Connecticut, Inc. (the licensee) notified the NRC staff that the 241° location was obstructed, and therefore, the licensee proposed reinstallation of Capsule Y instead at the 61° location. The 61° and 241° locations have the same lead factor of 3.98. No other changes were proposed to the withdrawal schedule previously approved in the March 15, 2016, NRC SE. Appendix H to 10 CFR Part 50 includes the requirement of dosimetry monitoring as part of the reactor vessel material surveillance program. In addition, for the period of extended operation for license renewal, NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," Aging Management Program, XI.M31 Reactor Vessel Surveillance, states that programs without in-vessel capsules use alternative dosimetry to monitor neutron fluence during the period of extended operation, as part of the aging management program for reactor vessel 2neutron embrittlement. The July 2, 2015, submittal stated, "Concurrent reinsertion of Capsule Y will maintain continuous reactor vessel fluence monitoring as required by 10 CFR 50 Appendix H." Since the lead factors are identical in the 61° and 241° locations, the NRC staff determined that the neutron fluence exposures would be essentially identical at both locations. Based on the information in the References listed below and the staff assessment that Capsule Y will experience sufficiently similar neutron fluence conditions at the 61° and 241° locations, the NRC staff concludes that the reactor vessel material surveillance capsule withdrawal schedule for MPS3 continues to satisfy the requirements of Appendix H to 10 CFR Part 50 and the recommendations of the GALL Report as they relate to the period of extended operation. Therefore, the proposed change in location for the reinstallation of Capsule Y from the 241° location to the 61° location is acceptable.References:1.LetterdatedJuly2,2015(ADAMSAccessionNo.ML15194A061),supplementedbyletterdatedJanuary28,2016(ADAMSAccessionNo.ML16034A215)fromDominionNuclearConnecticut,Inc.2.SafetyEvaluationdatedMarch15,2016(ADAMSAccessionNo.ML16067A2343.EmailfromW.CrafttoR.GuzmandatedApril27,2016From:"WandaDCraft(Generation6)"<wanda.d.craft@dom.com>Subject:[External_Sender]MPS3RVSurveillanceCapsuleWithdrawalSchedulerevisionDate:27April201616:08To:"Guzman,Richard"<Richard.Guzman@nrc.gov>Rich,InlettersdatedJuly2,2015andJanuary28,2016,DNCrequestedNRCreviewandapprovalofarevisiontothesurveillancecapsulewithdrawalscheduleforMPS3.TheNRCapprovedtherevisedwithdrawalscheduleinaletterdatedMarch15,2016.DNCplannedtoreinstallstandbyCapsuleYintothereactorvesselfromthespentfuelpoolduringthespring2016refuelingoutage.CapsuleYwasscheduledforreinsertionatthe241°locationbutcouldnotbereinsertedthereduetotheobstructioncausedbytheliftrigfortheupperinternals.Thisobstructionlimitedtraveloftherefuelbridgeandtherefore,restrictedaccesstothe241°specimenguides.DNCproposestorevisethecapsulewithdrawalscheduleforreinsertionofCapsuleYatthe61°location,whichhasthesameleadfactorasthe241°location.NootherchangesareproposedtothewithdrawalschedulepreviouslyapprovedintheMarch15,2016NRCsafetyevaluation.
3Theproposedrevisiontothereactorvesselsurveillancecapsulewithdrawalscheduleisshownbelow.Proposedrevisionstothecapsulewithdrawalscheduleareshownwithadditionsinbold,italicizedtextanddeletionsareshownwithstrikethrough. Proposed Millstone Unit 3 Reactor Vessel Surveillance Capsule Withdrawal Schedule CAPSULELOCATIONLEAD FACTOR(a)REMOVAL / INSTALLATION TIME (EFPY)(b)FLUENCE (n/cm2,E>1.0MeV)(a)U58.5°4.061.34.00 x 1018(c)X238.5°4.358.01.98 x 1019(c)W121.5°4.2213.83.16 x 1019(c, d)Y(e)(f)241°3.9813.8Footnote (i)Y(f)61°3.98 Footnote (i)V(e)61°3.98Storage Z(g)301.5°4.2223.45.37x 1019(h)a. Updated in Capsule W dosimetry analysis. b. Effective Full Power Years (EFPY) from plant startup. c. Plant specific evaluation. d. This fluence is not less than once or greater than twice the peak end of license fluence, and isapproximately equal to the peak vessel fluence at 63 EFPY. e. Capsules Y and V were withdrawn after 13.8 EFPY (EOC 10) and placed into storage after accruing 2.98 x 1019 n/cm2 fluence. f. Capsule Y was reinserted into its original location (24161°) at EOC 17 (approximately 23.4 EFPY).g. Capsule Z was withdrawn at 23.4 EFPY (EOC 17) after accruing approximately 5.37 x 1019 n/cm2fluence. Dosimetry analysis was performed and the test specimens placed into vendor storage forfuture testing. h. This projected fluence is greater than once and less than twice the projected 72 EFPY and 90 EFPYpeak vessel fluence. i. Capsule Y is installed for fluence monitoring during the operating license in accordance with ASTME 185-82.
4Thanksforyourreviewandwearelookingforwardtodiscussingthiswithyouinacalltomorrow.WewillneedNRCapprovaloftherevisedcapsulewithdrawalschedulepriortoenteringMode2,whichiscurrentlyexpectedtooccuronMay9th.Ifyouhaveanyquestions,pleaseletmeknow.Thanks. Wanda D. CraftNuclear Licensing and Operations SupportDominion Resources Services, Inc(804) 273-4687tie-line 730-4687CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.