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Category:Report
MONTHYEARML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22193A1432022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Technical Requirements Manual Current Through Change No. 207 ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20352A3342020-12-17017 December 2020 Proposed Alternative Requests RR-05-04 and IR-4-02, Use of Alternative Pressure/Flow Testing Requirements for Service Water System Supply Piping ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML19352B8982019-12-17017 December 2019 Proposed Alternative Request RR-05-05, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML19246A1162019-10-0707 October 2019 Supplement to Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood Causing Mechanism Reevaluation(Epid Nos. 000495\05000336\L- 2015-JLD-0011 and 000495\05000423\L-2015-JLD-0012 - (2019Aug21) ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML19070A2172019-04-0303 April 2019 Supplement to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood - Causing Mechanism Reevaluation ML19064A5902019-02-28028 February 2019 Proposed Alternative Request IR-3-39, Alternative to ASME Code, Section XI, IWA-4221(C), to Permit Two Fillet Welds Not in Compliance with the Construction Code to Remain in Service ML19011A1742019-01-0404 January 2019 Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents ML19011A1722019-01-0404 January 2019 Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) ML19011A1732019-01-0404 January 2019 Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents ML18256A2002018-10-0303 October 2018 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (EPID L00495\05000336 L-2015-JLD-0011 and 00495\05000423\L-2015-JLD-0012) ML18247A2752018-06-18018 June 2018 Technical Requirements Manual ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15253A2062015-09-0101 September 2015 ANP-3315NP, Revision 0, Millstone Unit 2 M5 Upgrade, Small Break LOCA Analysis Licensing Report. ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML15078A2052015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 1 Through 2-57 ML15078A2082015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-172 Through the End ML15078A2072015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-126 Through 2-171 ML15078A2062015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-58 Through 2-125 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML13338A4332014-01-31031 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13357A3982014-01-24024 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Milestone Power Station, Unit 2, TAC No.: MF0858 ML14006A1592014-01-0808 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Millstone Power Station, Unit 3, TAC No.: MF0859 ML14087A0992013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13303B9072013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 2023-07-26
[Table view] Category:Miscellaneous
MONTHYEARML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13303B9072013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML12362A3922012-11-30030 November 2012 Spent Fuel Pool Criticality Analysis with No Credit for Boraflex. ML12353A2422012-11-27027 November 2012 Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3 ML12187A1752012-06-25025 June 2012 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2010 and 2011, and Commitment Change Report for 2010 and 2011 ML12151A3592012-06-0707 June 2012 End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review ML12046A8362012-01-31031 January 2012 Inservice Inspection Program - Owner'S Activity Report ML12031A1472012-01-25025 January 2012 Day Report for Emergency Core Cooling System Model Changes of 10 CFR 50.46 ML1116002202011-06-13013 June 2011 Exhibit D (Part 3): Millstone 2001 Safstor Cost Analysis (Normal Dollars) ML1028504382010-09-30030 September 2010 Attachments 2, 3, 5, 7, 8 & 9, to 10-579A, Westinghouse Electric Co. LLC, WCAP-17071-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Revision 2, Dated Sep ML1019403352010-06-30030 June 2010 Units, 1, 2, 3, & ISFSI, 10 CFR 50.59, 10 CFR 72.48 Change Report for 2008 and 2009, and the Commitment Change Report for 2009 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1009702062010-03-29029 March 2010 Chemistry Procedure, Liquid Waste Sample Sink, Rev. 003-00 ML0931701762009-11-12012 November 2009 Part 3 of 4--Weld Overlay Examination Report 2R19 ML0931701732009-11-12012 November 2009 Part 2 of 4--Weld Overlay Examination Report 2R19 ML0931701662009-11-12012 November 2009 Part 1 of 4--Weld Overlay Examination Report 2R19 ML0931701852009-09-23023 September 2009 Part 4 of 4--Weld Overlay Examination Report 2R19 ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0913204602009-04-28028 April 2009 2008 Occupational Radiation Exposure Information ML0901303822008-12-26026 December 2008 Revision 002 to CP 3804L Procedure Action Request, Pass Containment Air Sample, Dated 12/26/2008 ML0830903962008-10-24024 October 2008 End of Cycle 18 Steam Generator Tube Inspection Report ML0827701132008-09-30030 September 2008 Response to Request for Additional Information Regarding Spent Fuel Pool Storage License Amendment Request ML0819800752008-07-0707 July 2008 Revision to Control Room and OSC Assembly Area Building 475 1st Floor, and SAP Locker ML0818406072008-07-0101 July 2008 Final Evaluation of Weld Overlay Examinations in Refueling Outage 18 ML0727504022007-09-27027 September 2007 Alternative Request RR-89-64 for Use of a Limited One-Sided Ultrasonic Examination Technique LBDCR 07-MP2-034 ML0720003902007-07-13013 July 2007 Attachment 1, Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate, Descriptions, Technical Analysis and Regulatory Analysis for the Proposed Operating License and Technical Specifications Changes ML0715203992007-05-30030 May 2007 Fy 2007 Final Fee Rule Workpapers ML0713501882007-05-17017 May 2007 Review of Steam Generator Tube Inservice Inspection Report for the 2005 Refueling Outage at Millstone Power Station, Unit No. 2 ML0713502492007-05-0808 May 2007 Steam Generator Tube Plugging Report ML0708805652007-03-28028 March 2007 Response to Request for Additional Information Regarding an Alternative for the Weld Overlay of Pressurizer Nozzle Welds ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report 2023-07-26
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.',veni Notification Report for April 26, 2005 Page1 of 2 U.S. Nuclear Regulatory Commission Operation Center Power Reactor Event Number: 41607 Facility: MILLSTONE Notification Date: 04/17/2005 Region: 1 State: CT Notification Time: 09:23 [EST]
Unit: [3] Event Date: 04/17/2005 RX Type: [1] GE-3,[2] CE,[3] W-4-LP Event Time: 08:42 [EDT]
NRC Notified By: MICHAEL GOBELI Last Update Date: 04/17/2005 HO OPS Officer: JOHN KNOKE Emergency Class:ALERT Person (Organization):
10 CFR Section: SAM COLLINS (RA) 50.72(a) (1) (i) - EMERGENCY DECLARED TIM MCGINTY (IRD) 50.72(b)(2)(iv)(A) - ECCS INJECTION JIM DYER (ET) 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL R1 BLAST DIAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION E. BRENNER (PAO)
THOMAS (NRC) l SCAM l l Initial l l Current Unit Code IRXCRIT PWR initial RX Mode I PWR Current RX Mode 3 AIAR -1~ 100 Power Operation 0 Hot Standby Event Text ALERT DECLARED DUE TO UNIT 3 MAIN STEAM RELIEF VALVES NOT RESEATING AFTER ACTUATION At 09:23 the licensee indicated that several Main Steam Relief Valves lifted and stayed open. A high pressure flow signal from the secondary Steam Generator caused initiation of Unit 3 Safety Injection, which In turn caused the Reactor to trip. All rods fully inserted as required.
Activation of the Safety Injection subsequently caused the Pressurizer level to go solid. About 30 minutes into the event the primary Reactor Coolant and Main Steam Systems stabilized, including the Pressurizer level and pressure. During the initial briefing, about 09:35, the licensee reported that all secondary Safety Relief Valves have reseated. Decay heat is being directed to the Atmospheric Dumps due to the Main Condenser not being available. The licensee is attempting to establish ERDS.
Initial assessment of this incident is believed not to be security related, however, follow-up is being conducted to verify same. At 09:48, NRC management made a decision to enter into Monitoring Mode. At about 11:15 the licensee indicated that a valve in the Charging System indicated some leakage, therefore it was isolated. Licensee stated that no radiological releases and no S/G tube leakage was indicated.
Licensee notified State and local emergency response agencies. They will notify the NRC Resident Inspector.
Notified DHS (Doyle), FEMA (Biscue), DOE (Smith), USDA (Magners), and HHS (Hogan).
- UPDATE FROM D. DODSON TO W. GOTT 1328 EDT 04/17/05 ^ * ^
- At approximately 0830 on April 17, 2005 Millstone Unit 3 experienced an automatic reactor trip from full power. The Reactor is in a stable shutdown condition and is proceeding to Mode 5 cold shutdown. No release of radioactivity other than those minor releases associated with normal plant operation has occurred. There were no personnel injuries associated with the event.
'In addition to the Reactor Trip, half-train Safety Injection (SI) and half-train Main Steam Isolation (MSI) actuations occurred. Control room personnel were successful at manually initiating full SI and MSI. SI has since been terminated and RCS pressure control has been restored.
Multiple steam line safety valves (MSSV) lifted with at least one MSSV indicating a failure to reclose. As a result, an ALERT was declared at approximately 0853 due to the failure of at least one MSSV failing to reclose. All MSSVs are currently closed. Auxiliary Feedwater (AFW) actuated automatically as expected, however, the turbine driven auxiliary feedwater pump (TDAFWP) tripped on start-up and was subsequently reset locally. Both motor driven auxiliary feedwater pumps (MDAFWPs) operated as expected to maintain steam generator water levels. Due to the additional inventory injected to the Reactor Coolant System (RCS) as a result of the SI actuation, the pressurizer filled and a primary system safety valve (PSSV) actuated at a lower than expected pressure. All PSSVs are currently closed, however, there is indication of leakage past either a PSSV or Pilot Operated Relief Valve (PORV). Upon alignment of the Charging system to Refueling Water Storage Tank recirculation flow path, 2 valves had indication of packing leakage. Those packing leaks have been terminated.
'The cause of the event is under investigation.'
The licensee has issued a press release. The licensee will notify the NRC Resident Inspector.
03Z
Evens Notification Report for April 26, 2005 Page 2 of 2 U.S. Nuclear Regulatory Commission Operation Center Notified R1 DO (J.White) and IRD Manager (T. McGinty)
- UPDATE FROM D. DODSON TOW. GOTT AT 1915 ON 04/17/05 *
'The previously reported time of the Alert declaration should be corrected to read 08:42. Millstone Unit 3 entered Mode 4 [Hot Shutdown] at approximately 19:03 on April 17, 2005. The event at Millstone Unit 3 was terminated at 19:05. The cause of the event is under investigation.
A recovery plan is being formulated."
Internal NRC notifications, DHS (Frost), NRC/EPA (Threatt), FEMA (Erwin), DOE (Morone), USDA (Smeltzer), HHS (Desi)
The licensee will notify the NRC Resident Inspector.
At 23:45 the Agency exited Monitoring Mode and entered Into Normal Mode.