|
|
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:1TMI-2 Transient -3/28/79 The Lessons Learned 2 ComparisonsTMI-1TMI-2Gilbert AssociatesBurns & RoeGE TurbineWestinghouse2568 MWt2772MWt870 Mwe (UP RATE)880 MweRunback at that time from full power for turbine trip, not a reactor trip.PORV setpoint 2255 vice 2355 psig. | | {{#Wiki_filter:TMI-2 Transient - 3/28/79 The Lessons Learned 1 |
| 3 SequenceTrouble with resin tr ansfer on condensate polisher.Pzr being cycled for boron equalization.
| |
| Spray valve in manual. Pzr heaters on.Condensate Pump 1A tripped.FW pumps 1A and 1B trip. (Low suction)Main Turbine Trip.
| |
| 4 8 secondsReactor trip on high RCS pressurePzr heaters returned to automatic control.Pressure decreases below 2205 PORV closure setpoint.Pzr level peaks at 256" and begins a rapid decrease.Letdown flow was stopped 5 13 secondsCondenser hotwell low level alarm receivedEFW pump discharge indicated.OTSG A water level indicated 74 " on startup range.PORV and pzr safety valve outlet high temp alrm comes in.
| |
| 6 30 seconds OTSG A water level decreased to 27.3"OTSG B water level decreased to 28.8"(41 sec) MUP-1A started (A & B running)Pzrlow level alarms at 200"(setpoint).Pzrlevel reaches a minimum of 158" 7>1 minutePzr safety valve outlet temperature alarmed high.Condenser hotwell high water level alarm received.Both OTSG's boiled dry(00:02:01) ESAS 1600# actuation.MU-P-1A ES starts / MUP-1B ES stops 8> 4 minutes RCDT relief valve lifts at 122 psig.RCDT high temperature alarm.Pressurizer high level alarm received.Operator stops MU-P-1C and throttles all high pressure injection valves.
| |
| 9> 5 MinutesIC-P-1A was started to prepare for max letdown flow.Letdown flow off scale highPressurizer level lowers to reached 377".Condensate pump 1A was started to try to restore secondary cooling.T hot reaches saturation at 1340# and 582F.
| |
| 10 Chronology05:51 Pressurizer level goes off scale high.08:18 EFW block valves 12A &B were opened.09:23 Letdown flow isolation valve re-opened10:15 Pressurizer level back on scale.10:48 Rx Building sump high level alarm was received.
| |
| 11 Chronology13:13 DHR pumps are secured (running dead headed).14:18 RCDT rupture disc blows.20:00 SR-NI departed from normal shutdown
| |
|
| |
|
| profile.01:13:29 RCP 2B stopped.01:13:42 RCP 1B stopped.01:40:37 RCP 2A stopped.01:40:45 RCP 1A stopped. | | Comparisons |
| 12 Chronology02:22:00 The PORV block valve (RC-V2) was closed.02:55:00 Site Emergency declared.
| | TMI-1 TMI-2 |
| 13 Estimated Final Condition of Core 14 Lessons Learned TMI-2 Accident Hardware changesESAS status panelThermal Hydraulic PanelPT plotWR NI'sRCIT'sAlarm System ReformatAdditional RMS 15 Lessons Learned TMI-2 AccidentOrganization Changes -Administrative processesShift Technical AdvisorEmergency PlanningLesson Learned-PRV behaviorINPO establishedSite Organizational Realignment. GPU established to run nuclear units.Radiation protection 16 Lessons Learned TMI-2 Accident Process changesSymptom Based ProceduresAdditional Training for Operators Simulators BWOGSPIP -improve safety system performance
| | Gilbert Associates Burns & Roe |
| *Control system power supply reliability | | GE Turbine Westinghouse |
| *Instrument air system upgrades}} | | 2568 MWt 2772 MWt |
| | 870 Mwe (UP RATE) 880 Mwe |
| | Runback at that time from full power for turbine trip, not a reactor trip. |
| | PORV setpoint 2255 vice 2355 psig. |
| | 2 |
| | |
| | Sequence |
| | Trouble with resin transfer on condensate polisher. |
| | Pzr being cycled for boron equalization. |
| | Spray valve in manual. Pzr heaters on. |
| | Condensate Pump 1A tripped. |
| | FW pumps 1A and 1B trip. (Low suction) |
| | Main Turbine Trip. |
| | 3 |
| | |
| | 8 seconds |
| | Reactor trip on high RCS pressure |
| | Pzr heaters returned to automatic control. |
| | Pressure decreases below 2205 PORV closure setpoint. |
| | Pzr level peaks at 256 and begins a rapid decrease. |
| | Letdown flow was stopped 4 |
| | |
| | 13 seconds |
| | Condenser hotwell low level alarm received |
| | EFW pump discharge indicated. |
| | OTSG A water level indicated 74 on startup range. |
| | PORV and pzr safety valve outlet high temp alrm comes in. |
| | 5 |
| | |
| | 30 seconds |
| | OTSG A water level decreased to 27.3 |
| | OTSG B water level decreased to 28.8 |
| | (41 sec) MUP-1A started (A & B running) |
| | Pzr low level alarms at 200(setpoint). |
| | Pzr level reaches a minimum of 158 6 |
| | |
| | >1 minute |
| | Pzr safety valve outlet temperature alarmed high. |
| | Condenser hotwell high water level alarm received. |
| | Both OTSGs boiled dry |
| | (00:02:01) ESAS 1600# actuation. |
| | MU-P-1A ES starts / MUP-1B ES stops 7 |
| | |
| | > 4 minutes |
| | RCDT relief valve lifts at 122 psig. |
| | RCDT high temperature alarm. |
| | Pressurizer high level alarm received. |
| | Operator stops MU-P-1C and throttles all high pressure injection valves. |
| | 8 |
| | |
| | > 5 Minutes |
| | IC-P-1A was started to prepare for max letdown flow. |
| | Letdown flow off scale high |
| | Pressurizer level lowers to reached 377. |
| | Condensate pump 1A was started to try to restore secondary cooling. |
| | T hot reaches saturation at 1340# and 582F. |
| | 9 |
| | |
| | Chronology |
| | 05:51 Pressurizer level goes off scale high. |
| | 08:18 EFW block valves 12A &B were opened. |
| | 09:23 Letdown flow isolation valve re-opened |
| | 10:15 Pressurizer level back on scale. |
| | 10:48 Rx Building sump high level alarm was received. |
| | 10 |
| | |
| | Chronology |
| | 13:13 DHR pumps are secured (running dead headed). |
| | 14:18 RCDT rupture disc blows. |
| | 20:00 SR-NI departed from normal shutdown profile. |
| | 01:13:29 RCP 2B stopped. |
| | 01:13:42 RCP 1B stopped. |
| | 01:40:37 RCP 2A stopped. |
| | 01:40:45 RCP 1A stopped. |
| | 11 |
| | |
| | Chronology |
| | 02:22:00 The PORV block valve (RC-V2) was closed. |
| | 02:55:00 Site Emergency declared. |
| | 12 |
| | |
| | Estimated Final Condition of Core 13 |
| | |
| | Lessons Learned TMI-2 Accident Hardware changes |
| | ESAS status panel |
| | Thermal Hydraulic Panel |
| | PT plot |
| | WR NIs |
| | RCITs |
| | Alarm System Reformat |
| | Additional RMS 14 |
| | |
| | Lessons Learned TMI-2 Accident Organization Changes - Administrative processes |
| | Shift Technical Advisor |
| | Emergency Planning |
| | Lesson Learned-PRV behavior |
| | INPO established |
| | Site Organizational Realignment. GPU established to run nuclear units. |
| | Radiation protection 15 |
| | |
| | Lessons Learned TMI-2 Accident Process changes |
| | Symptom Based Procedures |
| | Additional Training for Operators |
| | Simulators BWOG |
| | SPIP -improve safety system performance |
| | * Control system power supply reliability |
| | * Instrument air system upgrades 16}} |
|
---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24040A0722024-02-13013 February 2024 – Energy Solution Feb 13 Pubic Meeting Slides on TMI-2 Decommissioning 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 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) 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 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants 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 ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15327A0812015-11-0909 November 2015 Fall 2015 Outage Call Regarding the Steam Generator Tube Inservice Inspections - Slides ML15238B6272015-08-26026 August 2015 Case Study Overview 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 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) ML1115901302011-06-0808 June 2011 NRC Slides - TMI Public Meeting, June 7, 2011 ML11090A0872011-04-0505 April 2011 Fire (a)(4) Tabletop Pilot Method and Results ML1007802632010-01-25025 January 2010 Presentation - Health Physics Society Mid-Year Meeting ML1007805052009-12-23023 December 2009 Executive Team Daily Brief ML1007805442009-12-0202 December 2009 Executive Team Daily Brief ML1007805412009-11-27027 November 2009 Executive Team Daily Brief ML1007805402009-11-25025 November 2009 Executive Team Daily Brief ML1007805062009-11-24024 November 2009 Executive Team Daily Brief ML0929406112009-11-0202 November 2009 Summary of Category 1 Public Meeting with Exelon to Discuss Proposed Control Rod Drive Control System License Amendment Request ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes 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 ML0906302662009-02-24024 February 2009 02/24/2009 Three Mile Island Nuclear Station, Unit 1, Dseis Meeting Presentation Slides Preliminary Results of the Three Mile Island Nuclear Station, Unit 1 License Renewal Environmental Review. ML0906302652009-02-24024 February 2009 Dseis Meeting Handouts 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 ML0735507162007-12-21021 December 2007 TMI Refueling Outage Performance Summary 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 2024-02-13
[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
TMI-2 Transient - 3/28/79 The Lessons Learned 1
Comparisons
TMI-1 TMI-2
Gilbert Associates Burns & Roe
GE Turbine Westinghouse
2568 MWt 2772 MWt
870 Mwe (UP RATE) 880 Mwe
Runback at that time from full power for turbine trip, not a reactor trip.
PORV setpoint 2255 vice 2355 psig.
2
Sequence
Trouble with resin transfer on condensate polisher.
Pzr being cycled for boron equalization.
Spray valve in manual. Pzr heaters on.
Condensate Pump 1A tripped.
FW pumps 1A and 1B trip. (Low suction)
Main Turbine Trip.
3
8 seconds
Reactor trip on high RCS pressure
Pzr heaters returned to automatic control.
Pressure decreases below 2205 PORV closure setpoint.
Pzr level peaks at 256 and begins a rapid decrease.
Letdown flow was stopped 4
13 seconds
Condenser hotwell low level alarm received
EFW pump discharge indicated.
OTSG A water level indicated 74 on startup range.
PORV and pzr safety valve outlet high temp alrm comes in.
5
30 seconds
OTSG A water level decreased to 27.3
OTSG B water level decreased to 28.8
(41 sec) MUP-1A started (A & B running)
Pzr low level alarms at 200(setpoint).
Pzr level reaches a minimum of 158 6
>1 minute
Pzr safety valve outlet temperature alarmed high.
Condenser hotwell high water level alarm received.
Both OTSGs boiled dry
(00:02:01) ESAS 1600# actuation.
MU-P-1A ES starts / MUP-1B ES stops 7
> 4 minutes
RCDT relief valve lifts at 122 psig.
RCDT high temperature alarm.
Pressurizer high level alarm received.
Operator stops MU-P-1C and throttles all high pressure injection valves.
8
> 5 Minutes
IC-P-1A was started to prepare for max letdown flow.
Letdown flow off scale high
Pressurizer level lowers to reached 377.
Condensate pump 1A was started to try to restore secondary cooling.
T hot reaches saturation at 1340# and 582F.
9
Chronology
05:51 Pressurizer level goes off scale high.
08:18 EFW block valves 12A &B were opened.
09:23 Letdown flow isolation valve re-opened
10:15 Pressurizer level back on scale.
10:48 Rx Building sump high level alarm was received.
10
Chronology
13:13 DHR pumps are secured (running dead headed).
14:18 RCDT rupture disc blows.
20:00 SR-NI departed from normal shutdown profile.
01:13:29 RCP 2B stopped.
01:13:42 RCP 1B stopped.
01:40:37 RCP 2A stopped.
01:40:45 RCP 1A stopped.
11
Chronology
02:22:00 The PORV block valve (RC-V2) was closed.
02:55:00 Site Emergency declared.
12
Estimated Final Condition of Core 13
Lessons Learned TMI-2 Accident Hardware changes
ESAS status panel
Thermal Hydraulic Panel
PT plot
WR NIs
RCITs
Alarm System Reformat
Additional RMS 14
Lessons Learned TMI-2 Accident Organization Changes - Administrative processes
Shift Technical Advisor
Emergency Planning
Lesson Learned-PRV behavior
INPO established
Site Organizational Realignment. GPU established to run nuclear units.
Radiation protection 15
Lessons Learned TMI-2 Accident Process changes
Symptom Based Procedures
Additional Training for Operators
Simulators BWOG
SPIP -improve safety system performance
- Control system power supply reliability
- Instrument air system upgrades 16