|
---|
Category:Training Manual
MONTHYEARML11221A3262011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 18 Three Mile Island ML11221A3252011-07-0101 July 2011 521- R326C B&W Tech Cross Training - Chapter 18 Three Mile Island ML11216A2452008-12-0202 December 2008 0523 - R504P - Westinghouse Advanced Technology - 07.4 - Core Damaging Events ML11216A0992008-07-0101 July 2008 0523 - R504P - Westinghouse Advanced Technology - 07.4 - Core Damaging Events 2011-08-01
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24040A0722024-02-13013 February 2024 – Energy Solution Feb 13 Pubic Meeting Slides on TMI-2 Decommissioning ML22301A1402022-10-28028 October 2022 1993 TMI Event - Jure Kutlesa, Security Specialist ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20050H0232020-02-20020 February 2020 Presentation Slides for Meeting to Discuss Environmental Regulatory Approach to TMI-2 Decommissioning ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16070A1152016-03-11011 March 2016 Efforts to Improve Rulemaking Tracking and Reporting ML16006A2882016-01-0606 January 2016 Significant Operational Experience: 7 Major Industry Events with Regulatory Implications ML15327A0812015-11-0909 November 2015 Fall 2015 Outage Call Regarding the Steam Generator Tube Inservice Inspections - Slides ML14304A7832014-11-14014 November 2014 Public Meeting with the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate ML14300A5452014-10-30030 October 2014 10/30/2014, Meeting Slide with NRC Regarding GL 2004-02 Close Out for Three Mile Island, Unit 1 ML13262A1492013-09-19019 September 2013 Enclosure 3- NRC Presentation Handout ML13262A1172013-08-28028 August 2013 Enclosure 4 - Scott Portzline Presentation ML12262A3352012-09-13013 September 2012 9.13.2012 TMI Alert Presentation Nreg 0654 Public Mtg ML12116A0482012-04-25025 April 2012 Aam ROP-12 Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML12262A4762012-02-22022 February 2012 TMI Alert Portzline Presentation NUREG-0654 Public Mtg ML1202501052012-01-25025 January 2012 Licensee Slides for 1/26/12 Meeting Three Mile Island, Unit 1 - Summary of Tube to Tube Wear Identified During T1R19 (Fall 2011) ML11221A3262011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 18 Three Mile Island ML1115901302011-06-0808 June 2011 NRC Slides - TMI Public Meeting, June 7, 2011 ML13197A0522011-04-19019 April 2011 FOIA/PA-2011-0118, FOIA/PA-2011-0119, FOIA/PA-2011-0120 - Resp 111 - Partial, Group Letter Bt. Part 5 of 7 ML1007802632010-01-25025 January 2010 Presentation - Health Physics Society Mid-Year Meeting ML1007703672009-12-0707 December 2009 E-mail from J. White of USNRC to D. Screnci and J. Hawkins of USNRC, Regarding TMI NRC Slides.Ppt ML0929400522009-10-22022 October 2009 Meeting Power Uprate Meeting Slides ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides ML0910702242009-04-17017 April 2009 Riv Regional Administrator Presentation at Texas A&M University March 30, 2009, Three Mile Island - Impact on Safety Perspectives and Safety Belief ML0907508342009-03-16016 March 2009 Meeting Slides, Three Mile Island Annual Assessment Meeting 2008 Reactor Oversight Process ML11216A2452008-12-0202 December 2008 0523 - R504P - Westinghouse Advanced Technology - 07.4 - Core Damaging Events ML0828805412008-10-14014 October 2008 Herbaceous Wetlands ML0826712092008-09-23023 September 2008 TMI Pre-Application Meeting - Control Rod Drive Control System Upgrade and Elimination of Axial Power Shaping Rods ML0812007842008-06-0202 June 2008 Meeting Slides, Nrc/Exelon Licensing Counterparts Meeting. ML0813301852008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Handouts and Slides ML0813301832008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Written Comments ML0807906742008-03-19019 March 2008 Slides, NRC Annual Performance Assessment of Three Mile Island - 2007 Reactor Oversight Program. ML0806700982008-03-0404 March 2008 License Renewal Process Overview Three Mile Island Unit 1 Public Meeting Handout 03/04/2008 ML0802501172008-01-15015 January 2008 1/15/2008 Slides from Drop-in Visit Exelon/Amergen ML0726404902007-08-14014 August 2007 TMI Intro ML0726404922007-08-14014 August 2007 TMI Tritium Update 08/07 - Slide Presentation ML0713701672007-04-30030 April 2007 Enclosure 2 (Slides) - 04/30/2007 Summary of Meeting with Amergen Energy Co., LLC, Regarding License Amendment Request Relating to the Insertion of New Area High Thermal Performance Fuel in the TMI-1 Reactor ML0710901582007-04-19019 April 2007 Aam Final Slides for Reactor Oversight Program 2006-07 Public Meeting 04/11/07 ML0726404942007-03-28028 March 2007 Unit 2 Accident - Presentation Slides ML0708513862007-03-26026 March 2007 Annual Assessment Slides for ROP 2006-07 Public Meeting on 4-11-07 ML0716601022007-03-20020 March 2007 Slides to Counterparts Meeting with Exelon to Discuss Current and Planned Licensing Activities and Process - Correction ML0607508032006-03-22022 March 2006 NRC Slide Presentation for Public Meeting Ref: Three Mile Island, Unit 1 Annual Assessment Performance CY2005 2024-02-13
[Table view] |
Text
Core Damaging Events Objectives1.State how the following parameters respond to a stuck-open pilot-operated relief valve (PORV) following a reactor tripfrom100%power:
2 trip from 100% power:*PORV tail-pipe temperature*Reactor coolant system pressure
- Reactor vessel level Objectives2.State the significance of superheated conditions in the reactor coolant system.3.State the key operator errors that contributed to core damage during the Three Mile Island (TMI) accident.
3 ()4.Describe the event that initiated the core damage sequence at TMI.5.Discuss industry and regulatory changes that resulted from the accident at TMI.6.Describe the differences in technology that make U.S. commercial reactors not susceptible to an event similar to the
Chernobyl accident.
Core Damaging Events*Three Mile Island Accident 4*Chernobyl Accident BWSTOUTSIDESG"B"SG"A"CFTCFTRCPsPZRRCDT TOMAINSTEAMFROMFEEDWATERLETDOWNHEATEXCHANGERCCWRCPsREACTORHPIANDMAKEUPPUMPSMAKEUPTANKFILTERIONEXCHANGERSSCWDHRSCWREACTORBUILDINGAUXILIARYBUILDING Accident Contributors*Equipment failure *Poor design 6*Personnnel error Equipment Failure*PORV failed to close as required 7 Poor Design*PORV position indication *Poor human factors 8*No reactor vessel level indication Personnel Error*Failed to isolate the open PORVRddkfli 9*R e d uce d ma k eup fl ow i n response to PZR level Common Sense vs. Uncommon Sense*Pressurizer level*PORV tail pipe temperature 10 Plant Response to Open PORV 11 12 Industry and Regulatory Response to TMI accident*INPO*Operator training and examination
- NUREG-0737, "Clarification of TMI Action Plan Requirements" Chernobyl Accident 14 15 RBMK-1000*Graphite moderated*Boiling water reactor
- Positivevoidcoefficient(water 16*Positive void coefficient (water is a poison)*Total power coefficient usually negative Transient*Partial loss of flow (test) with positive power coefficient*Voiding causes prompt criticality Tk11000%d 17*Two power pea k s -11 , 000% an d 47,000% of RTP*Core becomes a large burning crater
- 30 individual fires where graphite was spewed Why this accident is not possible at U.S. reactors.*Graphite moderation (moderation continues when coolant leaves)*Positive void coefficientNtitbildi 18*N o con t a i nmen t b u ildi ng Objectives1.State how the following parameters respond to a stuck-open pilot-operated relief valve (PORV) following a reactor tripfrom100%power:
19 trip from 100% power:*PORV tail-pipe temperature*Reactor coolant system pressure
- Reactor vessel level Objectives2.State the significance of superheated conditions in the reactor coolant system.3.State the key operator errors that contributed to core damage during the Three Mile Island (TMI) accident.
20 ()4.Describe the event that initiated the core damage sequence at TMI.5.Discuss industry and regulatory changes that resulted from the accident at TMI.6.Describe the differences in technology that make U.S. commercial reactors not susceptible to an event similar to the
Chernobyl accident.