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| {{#Wiki_filter:2006 Regulatory Information Conference Session TH5DDigital Instrumentation and Control Oconee Nuclear Station's Diver sity and Defense in Depth Analysis for the Digital RPS / ES Upgrade T. Preston Gillespie, Jr. | | {{#Wiki_filter:006 Regulatory Information Conference Session TH5D Digital Instrumentation and Control conee Nuclear Stations Diversity and Defense in Depth Analysis for the Digital RPS / ES Upgrade T. Preston Gillespie, Jr. |
| Reactor and Electrical Syst ems Engineering Manager Duke Power Company March 9, 2006 Diversity and Defense in Depth Analysis Historical Perspective*In 2001, ONS elected to replace its originally installed analog RPS/ES System with a digital based system*Framtome's Teleperm XS operating system was chosen as the platform for the new system.*This platform is also utilized for the site's emergency power supply's governor system. | | Reactor and Electrical Systems Engineering Manager Duke Power Company March 9, 2006 |
| 2 Diversity and Defense in Depth Analysis BTP-19 Requirements*Analyze UFSAR Transients & Accidents and Demonstrate Acceptability of a SWCMF in RPS&ES*Recognizes SWCMF is Beyond Design Basis | | |
| *Realistic Demonstration of Unit Capability to Accommodate SWCMF with No Unacceptable Consequences 3
| | iversity and Defense in Depth Analysis istorical Perspective In 2001, ONS elected to replace its originally installed analog RPS/ES System with a digital based system Framtomes Teleperm XS operating system was chosen as the platform for the new system. |
| Diversity and Defense in Depth Analysis BTP-19 Requirements*SWCMF is not considered single failure based on NRC endorsed guidelines for licensing digital upgrades.*NRC RIS 2002-22 endorsed EPRI TR-102348 Rev.1D 3 analysis is considered a beyond design basis concernRecognizes the likelihood of a co mmon case software failure in a high quality digital system is significantly below that of a single active hardware failure 4
| | This platform is also utilized for the sites emergency power supplys governor system. |
| Diversity and Defense in Depth Analysis D 3 Assumptions *Typical conservative initial conditions*No loss of offsite power*No single failures*Integrated Control System (ICS) in automatic
| | 2 |
| *Realistic core power distribution (SBLOCA only)
| | |
| *Realistic core flood tank initial conditions (SBLOCA only)*Realistic operator actions and times*Credit for AMSAC (trip turbine and start EFW on loss of main feedwater)
| | TP-19 Requirements Analyze UFSAR Transients & Accidents and Demonstrate Acceptability of a SWCMF in RPS&ES Recognizes SWCMF is Beyond Design Basis Realistic Demonstration of Unit Capability to Accommodate SWCMF with No Unacceptable Consequences 3 |
| *Credit for existing Diverse Scram System (DSS) at 2450 psig RCS pressure
| | |
| *Credit for Automatic Feedwater Isolation System (AFIS) on low SGpressure*Pre-existing SG tube leakage at administrative limit 5
| | TP-19 Requirements SWCMF is not considered single failure based on NRC endorsed guidelines for licensing digital upgrades. |
| Diversity and Defense in Depth Analysis Analyzed UFSAR Transients & Accidents*Bank Withdrawal @ Zero Power*Bank Withdrawal @ Full Power*Boron Dilution @ Full Power*Loss of Coolant Flow*Locked Rotor*Dropped Rod*Turbine Trip
| | NRC RIS 2002-22 endorsed EPRI TR-102348 Rev.1 3/4 D3 analysis is considered a beyond design basis concern 3/4 Recognizes the likelihood of a common case software failure in a high quality digital system is significantly below that of a single active hardware failure 4 |
| *FDW Line Break*Steam Generator Tube Rupture*Rod Ejection*Large Steam Line Break*SBLOCA (limiting case)*Small Steam Line Break*Loss of MFW*LOOP 6 Diversity and Defense in Depth Analysis Acceptance Criteria*Offsite dose limits based on R. G. 1.183Large steam line break 25 remTEDE (EAB & LPZ)Loss of flow 2.5 remTEDE (EAB & LPZ)Control Room 5 remTEDE*RCS overpressure limit is 3250 psia (ASME Service Level C), same as ATWS acceptance criterion for B&W plants*Reactor Building overpressure limit is 125 psi based on 98% of ultimate strength (design pressure is 59 psig) 7 Diversity and Defense in Depth Analysis Results Categories1.RPS and ESPS not actuated / no adverse impact2.Event terminated by DSS actuation / no adverse impact 3.Event bounded by another event4.Analysis required and results show acceptance limits are met5.Acceptance limits not met / fail diversity and defense-in-depth 8 Diversity and Defense in Depth Analysis Analysis ResultsCategory 1 -RPS and ESPS Not Actuated / No Adverse Impact*Dropped control rod*Steam generator tube rupture
| | |
| *Small steam line break (for RCS pressure response and offsite doses)Note: The UFSAR analysis does not credit automatic RPS or ESPS actuation 9
| | iversity and Defense in Depth Analysis 3 Assumptions Typical conservative initial conditions No loss of offsite power No single failures Integrated Control System (ICS) in automatic Realistic core power distribution (SBLOCA only) |
| Diversity and Defense in Depth Analysis Analysis Results (cont.)Category 2 -Event Terminated by DSS Actuation / No Adverse Impact*Control rod bank withdrawal at zero power*Turbine trip*Loss of main feedwater
| | Realistic core flood tank initial conditions (SBLOCA only) |
| *Loss of offsite power
| | Realistic operator actions and times Credit for AMSAC (trip turbine and start EFW on loss of main feedwater) |
| *Main feedwater line break Note: The DSS mitigates the event w hen RCS pressure reaches 2450 psig 10 Diversity and Defense in Depth Analysis Analysis ResultsCategory 3 -Event Bounded by Another Event / No Adverse Impact*Boron dilution at full power (bounde d by control rod bank withdrawal)*Control rod ejection containm ent response and dose results (bounded by LOCA)Manual actuation of HPI at 5 minutes creditedManual actuation of RBCS and RBS at 8 minutes credited*SBLOCA containment response and doses (bounded by LOCA)Manual actuation of RBCS and RBS at 8 minutes credited 11 Diversity and Defense in Depth Analysis Analysis Results Category 4:
| | Credit for existing Diverse Scram System (DSS) at 2450 psig RCS pressure Credit for Automatic Feedwater Isolation System (AFIS) on low SG pressure Pre-existing SG tube leakage at administrative limit 5 |
| Analysis Required and Acceptance Criteria Met*Control rod bank withdrawal at full powerNo cladding failures, so offsite doses are not significantRCS and Reactor Building pressure limits not challenged*Loss of coolant flow (four-pump coastdown)26.0% cladding failure and 2.14% fuel meltRadiological doses bounded by two-pump coastdownRCS and Reactor Building pressure limits not challenged 12 Diversity and Defense in Depth Analysis Analysis Results Category 4:
| | |
| Analysis Required and Acceptance Criteria Met*Loss of coolant flow (two-pump coastdown)26.6% cladding failure and 2.46% fuel meltRCS and Reactor Building pre ssure limits not challengedRadiological doses*EAB boundary = 2.0 remTEDE (2.5 remis limit)*LPZ boundary = 0.4 remTEDE (2.5 remis limit)
| | nalyzed UFSAR Transients & Accidents Bank Withdrawal @ Zero Power |
| *Control Room = 1.2 remTEDE (5 remis limit) 13 Diversity and Defense in Depth Analysis Analysis Results Category 4: | | * Steam Generator Tube Bank Withdrawal @ Full Power Rupture Boron Dilution @ Full Power |
| Analysis Required and Acceptance Criteria Met*Large steam line break34.0% cladding failure and 4.75% fuel meltRCS pressure limit is not challengedPeak containment pressure is 44 psigRadiological doses*EAB boundary = 4.4 remTEDE (25 remis limit)*LPZ boundary = 0.9 remTEDE (25 remis limit)
| | * Rod Ejection Loss of Coolant Flow |
| *Control Room = 3.4 remTEDE (5 remis limit) 14 Diversity and Defense in Depth Analysis Analysis Results Category 4: | | * Large Steam Line Break Locked Rotor |
| Analysis Required and Acceptance Criteria Met*Locked rotorNo cladding failures, so offsite doses are not significantRCS and Reactor Building pressure limits not challenged*Small steam line breakPeak containment pressure is 45 psigManual actuation of RBCS and RBS credited at 8 minutes 15 Diversity and Defense in Depth Analysis Analysis Results Category 4:
| | * SBLOCA (limiting case) |
| Analysis Required and Acceptance Criteria Met*Small-break LOCAReactor manually tripped by the operator at 2 minutesReactor coolant pumps manually tripped by the operator at 2 minutesHPI and LPI manually started by the operator at 5 minutesPeak cladding temperature is limited to around 1000ºFRCS pressure limit not challenged 16 Diversity and Defense in Depth Analysis Analysis ResultsCategory 5 -Acceptance Limits Not Met*Large-break LOCACrediting manual start of HPI and LPI at 5 minutes is not early enough to maintain a coolable geometryLBLOCA does not meet the divers ity and defense-in-depth requirementsA diverse actuation of LPI is required since LOCA is within the scope of the D 3 study 17 Diversity and Defense in Depth Analysis Conclusions*Diversity and defense-in-depth demonstrated for all events except large-break LOCA*Existing diverse plant systems credited for automatic mitigationDiverse Scram System (DSS)AMSACAutomatic Feedwater Isolation SystemIntegrated Control System 18 Diversity and Defense in Depth Analysis Conclusions*New manual operator action times creditedManual reactor trip at 2 minutes (SBLOCA)Manual start of HPI and LPI at 5 minutes (SBLOCA, REA)Manual start of RBCS and RBS at 8 minutes (SBLOCA, REA)*Acceptance criteria met (except for LBLOCA)Diverse actuation of LPI required for LBLOCA with failure of RPS/ES 19}}
| | Dropped Rod |
| | * Small Steam Line Break Turbine Trip |
| | * Loss of MFW FDW Line Break |
| | * LOOP 6 |
| | |
| | iversity and Defense in Depth Analysis cceptance Criteria Offsite dose limits based on R. G. 1.183 3/4 Large steam line break 25 rem TEDE (EAB & LPZ) 3/4 Loss of flow 2.5 rem TEDE (EAB & LPZ) 3/4 Control Room 5 rem TEDE RCS overpressure limit is 3250 psia (ASME Service Level C), same as ATWS acceptance criterion for B&W plants Reactor Building overpressure limit is 125 psi based on 98% of ultimate strength (design pressure is 59 psig) 7 |
| | |
| | iversity and Defense in Depth Analysis esults Categories |
| | . RPS and ESPS not actuated / no adverse impact |
| | . Event terminated by DSS actuation / no adverse impact |
| | . Event bounded by another event |
| | . Analysis required and results show acceptance limits are met |
| | . Acceptance limits not met / fail diversity and defense-in-depth 8 |
| | |
| | iversity and Defense in Depth Analysis nalysis Results ategory 1 - RPS and ESPS Not Actuated / No Adverse Impact Dropped control rod Steam generator tube rupture Small steam line break (for RCS pressure response and offsite doses) |
| | Note: |
| | The UFSAR analysis does not credit automatic RPS or ESPS actuation 9 |
| | |
| | iversity and Defense in Depth Analysis nalysis Results (cont.) |
| | ategory 2 - Event Terminated by DSS Actuation / No Adverse Impact Control rod bank withdrawal at zero power Turbine trip Loss of main feedwater Loss of offsite power Main feedwater line break Note: |
| | The DSS mitigates the event when RCS pressure reaches 2450 psig 10 |
| | |
| | iversity and Defense in Depth Analysis nalysis Results ategory 3 - Event Bounded by Another Event / No Adverse Impact Boron dilution at full power (bounded by control rod bank withdrawal) |
| | Control rod ejection containment response and dose results (bounded by LOCA) 3/4 Manual actuation of HPI at 5 minutes credited 3/4 Manual actuation of RBCS and RBS at 8 minutes credited SBLOCA containment response and doses (bounded by LOCA) 3/4 Manual actuation of RBCS and RBS at 8 minutes credited 11 |
| | |
| | iversity and Defense in Depth Analysis nalysis Results ategory 4: |
| | nalysis Required and Acceptance Criteria Met Control rod bank withdrawal at full power 3/4 No cladding failures, so offsite doses are not significant 3/4 RCS and Reactor Building pressure limits not challenged Loss of coolant flow (four-pump coastdown) 3/4 26.0% cladding failure and 2.14% fuel melt 3/4 Radiological doses bounded by two-pump coastdown 3/4 RCS and Reactor Building pressure limits not challenged 12 |
| | |
| | iversity and Defense in Depth Analysis nalysis Results ategory 4: |
| | nalysis Required and Acceptance Criteria Met Loss of coolant flow (two-pump coastdown) 3/4 26.6% cladding failure and 2.46% fuel melt 3/4 RCS and Reactor Building pressure limits not challenged 3/4 Radiological doses |
| | * EAB boundary = 2.0 rem TEDE (2.5 rem is limit) |
| | * LPZ boundary = 0.4 rem TEDE (2.5 rem is limit) |
| | * Control Room = 1.2 rem TEDE (5 rem is limit) 13 |
| | |
| | iversity and Defense in Depth Analysis nalysis Results ategory 4: |
| | nalysis Required and Acceptance Criteria Met Large steam line break 3/4 34.0% cladding failure and 4.75% fuel melt 3/4 RCS pressure limit is not challenged 3/4 Peak containment pressure is 44 psig 3/4 Radiological doses |
| | * EAB boundary = 4.4 rem TEDE (25 rem is limit) |
| | * LPZ boundary = 0.9 rem TEDE (25 rem is limit) |
| | * Control Room = 3.4 rem TEDE (5 rem is limit) 14 |
| | |
| | iversity and Defense in Depth Analysis nalysis Results ategory 4: |
| | nalysis Required and Acceptance Criteria Met Locked rotor 3/4 No cladding failures, so offsite doses are not significant 3/4 RCS and Reactor Building pressure limits not challenged Small steam line break 3/4 Peak containment pressure is 45 psig 3/4 Manual actuation of RBCS and RBS credited at 8 minutes 15 |
| | |
| | iversity and Defense in Depth Analysis nalysis Results ategory 4: |
| | nalysis Required and Acceptance Criteria Met Small-break LOCA 3/4 Reactor manually tripped by the operator at 2 minutes 3/4 Reactor coolant pumps manually tripped by the operator at 2 minutes 3/4 HPI and LPI manually started by the operator at 5 minutes 3/4 Peak cladding temperature is limited to around 1000ºF 3/4 RCS pressure limit not challenged 16 |
| | |
| | iversity and Defense in Depth Analysis Analysis Results ategory 5 - Acceptance Limits Not Met Large-break LOCA 3/4 Crediting manual start of HPI and LPI at 5 minutes is not early enough to maintain a coolable geometry 3/4 LBLOCA does not meet the diversity and defense-in-depth requirements 3/4 A diverse actuation of LPI is required since LOCA is within the scope of the D3 study 17 |
| | |
| | iversity and Defense in Depth Analysis onclusions Diversity and defense-in-depth demonstrated for all events except large-break LOCA Existing diverse plant systems credited for automatic mitigation 3/4 Diverse Scram System (DSS) 3/4 AMSAC 3/4 Automatic Feedwater Isolation System 3/4 Integrated Control System 18 |
| | |
| | iversity and Defense in Depth Analysis Conclusions New manual operator action times credited 3/4 Manual reactor trip at 2 minutes (SBLOCA) 3/4 Manual start of HPI and LPI at 5 minutes (SBLOCA, REA) 3/4 Manual start of RBCS and RBS at 8 minutes (SBLOCA, REA) |
| | Acceptance criteria met (except for LBLOCA) 3/4 Diverse actuation of LPI required for LBLOCA with failure of RPS/ES 19}} |
|
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22130A0102022-04-28028 April 2022 Duke Presentation for April 28, 2022 Public Meeting - Containment Liner ML22130A0092022-04-28028 April 2022 Duke Presentation for April 28, 2022 Public Meeting - Bolting Integrity ML22067A1992022-03-0303 March 2022 Annual Assessment Meeting Presentation ML22063A1142022-01-17017 January 2022 Duke Presentation for Public Meeting on February 17, 2022 ML21235A0452021-08-25025 August 2021 August 25, 2021, Oconee Nuclear Station, Units 1, 2, and 3 Subsequent License Renewal Application Public Environmental Scoping Meeting Presentation ML21102A0632021-04-14014 April 2021 ONS Slides for Pre-Application Meeting to Discuss Proposed Relief Request Related to Code Case N-853 ML21089A1732021-03-30030 March 2021 EOC Slides Final ML21081A1242021-03-22022 March 2021 EOC Slides Final ML20300A0902020-10-27027 October 2020 Subsequent License Renewal Environmental Pre-Application Meeting - NRC Presentation ML20300A0872020-10-27027 October 2020 Subsequent License Renewal Application NRC Environmental Pre-Application Meeting - Duke Energy Presentation ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19302E0512019-11-0606 November 2019 High Energy Line Break License Amendment Public Meeting ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML19207A0172019-07-30030 July 2019 Summary of Meeting with Duke Energy Carolinas, LLC to Discuss Proposed License Amendment Request for Oconee Nuclear Station, Units 1, 2, and 3 Regarding High Energy Line Break Licensing Basis ML18227B3212018-09-0505 September 2018 Tornado License Amendment Pre-Application Meeting Slides ML18134A2292018-05-14014 May 2018 Summary of April 26, 2018, Public Teleconference with Duke Energy Carolinas, LLC to Discuss Proposed License Amendment and 3 Regarding Technical Specification 3.8.1 ML17258A0122017-09-26026 September 2017 Presentation Slide Regarding Committee to Review Generic Requirements Meeting on Oconee Nuclear Station Cable Separation TIA ML15348A2032015-12-14014 December 2015 Duke Energy Presentation in Support of December 15, 2015, Public Meeting with NRC Staff Cable Testing Discussion for Proposed 50.55a Alternative Request ML15343A1142015-12-0808 December 2015 NRC Questions to Duke Energy Regarding Cable Testing in Support of Public Meeting on 12/15/15 ML15321A1782015-11-17017 November 2015 Presentation Material in Support of November 18, 2015 Pre-Application Meeting Between NRC and Duke 50.55a(z) Alternative to Code and Standards Requirements ML15286A0762015-10-13013 October 2015 Duke Energy Presentation in Support of October 13, 2015, Public Meeting with NRC Staff Pre-Application Meeting for LAR to Support Khu Stator Replacement. (Revised) ML15282A0722015-10-0909 October 2015 Duke Energy Presentation in Support of October 13, 2015, Public Meeting with NRC Staff Pre-Application Meeting for LAR to Support Khu Stator Replacement ML15148A2632015-05-27027 May 2015 Meeting Slides from the May 27, 2015 Oconee Major Projects Between Duke Energy and NRC ML15113A6262015-04-23023 April 2015 April 14, 2015 Summary of Public Meeting on Oconee Nuclear Station, Units 1, 2 and 3 to Discuss the Annual Assessment ML14356A0062014-12-0303 December 2014 Presentation at December 3, 2014, Category 1 Public Meeting with Duke Energy Carolinas, LLC to Discuss NTTF Recommendation 2.1, Flooding Response ML14211A2162014-07-31031 July 2014 NRC Meeting Slides 7-31-14 Reg Conference ML14211A2132014-07-31031 July 2014 Duke Energy Presentation for 2014-07-31 Meeting ML14147A3652014-05-27027 May 2014 Annual Assessment Public Meeting Summary Memo ML14058A0772014-02-0404 February 2014 Slides on Oconee Ssf Flood Barrier Breach SDP Lessons Learned ML14058A0742014-02-0404 February 2014 Slides on Oconee Ssf Flood Barrier Breach SDP - Lessons Learned ML14058A0482014-02-0404 February 2014 NRR Briefing on Oconee Flood Protection (Nrr/Dra) ML13336A5452013-11-13013 November 2013 Presentation Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Keowee Hydro Unit Generator Field Pole Rewind Project - License Amendment Request ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13275A2692013-10-0303 October 2013 10/3/13 Presentation Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Protected Service Water Alternate Cooling ML13275A2252013-09-24024 September 2013 9/24/13 Meeting Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Jocassee Dam Seismic Analysis ML13239A3372013-08-27027 August 2013 NRC Meeting Slides, Oconee Major Project Meeting - August 28, 2013 ML13239A3402013-08-27027 August 2013 Presentation for NRC Projects ML13099A4472013-04-10010 April 2013 Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Milestones for Corrective Actions for an Apparent Violation of a License Condition on Fire Protection ML13095A2132013-04-0909 April 2013 Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, External Flood Reevaluation ML13123A2042013-03-25025 March 2013 Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Concerning the Flooding Hazard Reevaluation Report ML13064A1022013-03-0505 March 2013 Slides from Predecisional Enforcement Conference with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Apparent Violation of a License Condition on Fire Protection ML13056A1042013-02-0606 February 2013 Briefing Slides on the Fliod Scenario Rupture of Jocassee Dam ML13056A1032013-02-0606 February 2013 Briefing on Draft Information Notice - Potential Nonconservative Screening Value for Dam Failure Frequency in Probabilistic Risk Assessments. ML13052A7822013-02-0606 February 2013 Slides on Oconee Ssf Flood Barrier Breach SDP - Lessons Learned ML13056A0992013-02-0606 February 2013 Meeting Slides on Oconee Ssf Flood Barrier Breach Sdsp - Lessons Learned ML13056A1022013-02-0606 February 2013 Meeting Slides on Oconee Flood Issue Jocassee Dam Failure Frequency ML13035A2332013-01-30030 January 2013 Projects Meeting - Licensee'S Public Meeting Slides 2024-04-09
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML23087A2972023-04-17017 April 2023 Annual Assessment Meeting Presentation ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22130A0102022-04-28028 April 2022 Duke Presentation for April 28, 2022 Public Meeting - Containment Liner ML22130A0092022-04-28028 April 2022 Duke Presentation for April 28, 2022 Public Meeting - Bolting Integrity ML22109A2122022-04-20020 April 2022 Duke Energy Pre-Submittal Public April 20, 2022, Meeting Presentation ML22075A2012022-03-0707 March 2022 Duke 03/07/2022 Presentation - Bolting Integrity ML22067A1992022-03-0303 March 2022 Annual Assessment Meeting Presentation ML22301A1672022-02-0505 February 2022 Presentation 5 - Oconee Trip and Notification of Unusual Event on February 5, 2022 ML22063A1142022-01-17017 January 2022 Duke Presentation for Public Meeting on February 17, 2022 ML21322A3262021-11-29029 November 2021 Duke Energy November 29, 2021 Pre-Submittal Public Meeting Slides for EOF Relocation Licensing Amendment Request ML21235A0452021-08-25025 August 2021 August 25, 2021, Oconee Nuclear Station, Units 1, 2, and 3 Subsequent License Renewal Application Public Environmental Scoping Meeting Presentation ML21102A0632021-04-14014 April 2021 ONS Slides for Pre-Application Meeting to Discuss Proposed Relief Request Related to Code Case N-853 ML21089A1732021-03-30030 March 2021 EOC Slides Final ML21081A1242021-03-22022 March 2021 EOC Slides Final ML21034A5552021-01-26026 January 2021 SLRA - NRC Presubmittal Meeting Slides ML21034A5562021-01-26026 January 2021 SLRA - Duke Presubmittal Meeting Slides ML20300A0872020-10-27027 October 2020 Subsequent License Renewal Application NRC Environmental Pre-Application Meeting - Duke Energy Presentation ML20300A0902020-10-27027 October 2020 Subsequent License Renewal Environmental Pre-Application Meeting - NRC Presentation ML20134J0052020-05-13013 May 2020 EOC Slides (2) ML20125A2312020-05-0404 May 2020 EOC Slides ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19302E0512019-11-0606 November 2019 High Energy Line Break License Amendment Public Meeting ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML18086A7742018-02-21021 February 2018 LOR Program Biennial Inspection 71111.11B Exam Overlap Issues ML17296A1462017-10-24024 October 2017 Duke Energy Presentation to CRGR - Oconee Nuclear Station ML17258A0122017-09-26026 September 2017 Presentation Slide Regarding Committee to Review Generic Requirements Meeting on Oconee Nuclear Station Cable Separation TIA ML15348A2032015-12-14014 December 2015 Duke Energy Presentation in Support of December 15, 2015, Public Meeting with NRC Staff Cable Testing Discussion for Proposed 50.55a Alternative Request ML15282A0722015-10-0909 October 2015 Duke Energy Presentation in Support of October 13, 2015, Public Meeting with NRC Staff Pre-Application Meeting for LAR to Support Khu Stator Replacement ML15148A2632015-05-27027 May 2015 Meeting Slides from the May 27, 2015 Oconee Major Projects Between Duke Energy and NRC ML15113A6262015-04-23023 April 2015 April 14, 2015 Summary of Public Meeting on Oconee Nuclear Station, Units 1, 2 and 3 to Discuss the Annual Assessment ML14356A0062014-12-0303 December 2014 Presentation at December 3, 2014, Category 1 Public Meeting with Duke Energy Carolinas, LLC to Discuss NTTF Recommendation 2.1, Flooding Response ML14211A2162014-07-31031 July 2014 NRC Meeting Slides 7-31-14 Reg Conference ML14211A2132014-07-31031 July 2014 Duke Energy Presentation for 2014-07-31 Meeting ML14147A3652014-05-27027 May 2014 Annual Assessment Public Meeting Summary Memo ML14058A0772014-02-0404 February 2014 Slides on Oconee Ssf Flood Barrier Breach SDP Lessons Learned ML14058A0742014-02-0404 February 2014 Slides on Oconee Ssf Flood Barrier Breach SDP - Lessons Learned ML14055A4102014-02-0404 February 2014 Meeting Slides on Standby Shutdown Facility Flood Barrier Breach Violation Informal Reassessment ML14058A0352014-02-0404 February 2014 Meeting Slides on Oconee Flood Protection and the 10 CFR 50.54(f) Response ML14058A0512014-02-0404 February 2014 Slides on Oconee Nuclear Station - Standby Shutdown Facility (Ssf) Flood Barrier Breach Violation SDP Assessment ML13336A5452013-11-13013 November 2013 Presentation Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Keowee Hydro Unit Generator Field Pole Rewind Project - License Amendment Request ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13275A2692013-10-0303 October 2013 10/3/13 Presentation Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Protected Service Water Alternate Cooling ML13275A2252013-09-24024 September 2013 9/24/13 Meeting Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Jocassee Dam Seismic Analysis ML13239A3402013-08-27027 August 2013 Presentation for NRC Projects ML13239A3372013-08-27027 August 2013 NRC Meeting Slides, Oconee Major Project Meeting - August 28, 2013 ML13226A2662013-05-0303 May 2013 E-mail from J. Boska, NRR to S. Hicks, Ois FW: Change in Public Availability of Slide Package ML13226A2592013-04-23023 April 2013 E-mail from D. Hubbard, Duke to J. Boska, NRR on Non-Security Sensitive Version of March 25th Presentation ML13226A2652013-04-23023 April 2013 E-mail from D. Hubbard, Duke to J. Boska, NRR on Security Sensitive Version 2024-04-09
[Table view] |
Text
006 Regulatory Information Conference Session TH5D Digital Instrumentation and Control conee Nuclear Stations Diversity and Defense in Depth Analysis for the Digital RPS / ES Upgrade T. Preston Gillespie, Jr.
Reactor and Electrical Systems Engineering Manager Duke Power Company March 9, 2006
iversity and Defense in Depth Analysis istorical Perspective In 2001, ONS elected to replace its originally installed analog RPS/ES System with a digital based system Framtomes Teleperm XS operating system was chosen as the platform for the new system.
This platform is also utilized for the sites emergency power supplys governor system.
2
TP-19 Requirements Analyze UFSAR Transients & Accidents and Demonstrate Acceptability of a SWCMF in RPS&ES Recognizes SWCMF is Beyond Design Basis Realistic Demonstration of Unit Capability to Accommodate SWCMF with No Unacceptable Consequences 3
TP-19 Requirements SWCMF is not considered single failure based on NRC endorsed guidelines for licensing digital upgrades.
NRC RIS 2002-22 endorsed EPRI TR-102348 Rev.1 3/4 D3 analysis is considered a beyond design basis concern 3/4 Recognizes the likelihood of a common case software failure in a high quality digital system is significantly below that of a single active hardware failure 4
iversity and Defense in Depth Analysis 3 Assumptions Typical conservative initial conditions No loss of offsite power No single failures Integrated Control System (ICS) in automatic Realistic core power distribution (SBLOCA only)
Realistic core flood tank initial conditions (SBLOCA only)
Realistic operator actions and times Credit for AMSAC (trip turbine and start EFW on loss of main feedwater)
Credit for existing Diverse Scram System (DSS) at 2450 psig RCS pressure Credit for Automatic Feedwater Isolation System (AFIS) on low SG pressure Pre-existing SG tube leakage at administrative limit 5
nalyzed UFSAR Transients & Accidents Bank Withdrawal @ Zero Power
- Rod Ejection Loss of Coolant Flow
- Large Steam Line Break Locked Rotor
Dropped Rod
- Loss of MFW FDW Line Break
iversity and Defense in Depth Analysis cceptance Criteria Offsite dose limits based on R. G. 1.183 3/4 Large steam line break 25 rem TEDE (EAB & LPZ) 3/4 Loss of flow 2.5 rem TEDE (EAB & LPZ) 3/4 Control Room 5 rem TEDE RCS overpressure limit is 3250 psia (ASME Service Level C), same as ATWS acceptance criterion for B&W plants Reactor Building overpressure limit is 125 psi based on 98% of ultimate strength (design pressure is 59 psig) 7
iversity and Defense in Depth Analysis esults Categories
. RPS and ESPS not actuated / no adverse impact
. Event terminated by DSS actuation / no adverse impact
. Event bounded by another event
. Analysis required and results show acceptance limits are met
. Acceptance limits not met / fail diversity and defense-in-depth 8
iversity and Defense in Depth Analysis nalysis Results ategory 1 - RPS and ESPS Not Actuated / No Adverse Impact Dropped control rod Steam generator tube rupture Small steam line break (for RCS pressure response and offsite doses)
Note:
The UFSAR analysis does not credit automatic RPS or ESPS actuation 9
iversity and Defense in Depth Analysis nalysis Results (cont.)
ategory 2 - Event Terminated by DSS Actuation / No Adverse Impact Control rod bank withdrawal at zero power Turbine trip Loss of main feedwater Loss of offsite power Main feedwater line break Note:
The DSS mitigates the event when RCS pressure reaches 2450 psig 10
iversity and Defense in Depth Analysis nalysis Results ategory 3 - Event Bounded by Another Event / No Adverse Impact Boron dilution at full power (bounded by control rod bank withdrawal)
Control rod ejection containment response and dose results (bounded by LOCA) 3/4 Manual actuation of HPI at 5 minutes credited 3/4 Manual actuation of RBCS and RBS at 8 minutes credited SBLOCA containment response and doses (bounded by LOCA) 3/4 Manual actuation of RBCS and RBS at 8 minutes credited 11
iversity and Defense in Depth Analysis nalysis Results ategory 4:
nalysis Required and Acceptance Criteria Met Control rod bank withdrawal at full power 3/4 No cladding failures, so offsite doses are not significant 3/4 RCS and Reactor Building pressure limits not challenged Loss of coolant flow (four-pump coastdown) 3/4 26.0% cladding failure and 2.14% fuel melt 3/4 Radiological doses bounded by two-pump coastdown 3/4 RCS and Reactor Building pressure limits not challenged 12
iversity and Defense in Depth Analysis nalysis Results ategory 4:
nalysis Required and Acceptance Criteria Met Loss of coolant flow (two-pump coastdown) 3/4 26.6% cladding failure and 2.46% fuel melt 3/4 RCS and Reactor Building pressure limits not challenged 3/4 Radiological doses
iversity and Defense in Depth Analysis nalysis Results ategory 4:
nalysis Required and Acceptance Criteria Met Large steam line break 3/4 34.0% cladding failure and 4.75% fuel melt 3/4 RCS pressure limit is not challenged 3/4 Peak containment pressure is 44 psig 3/4 Radiological doses
iversity and Defense in Depth Analysis nalysis Results ategory 4:
nalysis Required and Acceptance Criteria Met Locked rotor 3/4 No cladding failures, so offsite doses are not significant 3/4 RCS and Reactor Building pressure limits not challenged Small steam line break 3/4 Peak containment pressure is 45 psig 3/4 Manual actuation of RBCS and RBS credited at 8 minutes 15
iversity and Defense in Depth Analysis nalysis Results ategory 4:
nalysis Required and Acceptance Criteria Met Small-break LOCA 3/4 Reactor manually tripped by the operator at 2 minutes 3/4 Reactor coolant pumps manually tripped by the operator at 2 minutes 3/4 HPI and LPI manually started by the operator at 5 minutes 3/4 Peak cladding temperature is limited to around 1000ºF 3/4 RCS pressure limit not challenged 16
iversity and Defense in Depth Analysis Analysis Results ategory 5 - Acceptance Limits Not Met Large-break LOCA 3/4 Crediting manual start of HPI and LPI at 5 minutes is not early enough to maintain a coolable geometry 3/4 LBLOCA does not meet the diversity and defense-in-depth requirements 3/4 A diverse actuation of LPI is required since LOCA is within the scope of the D3 study 17
iversity and Defense in Depth Analysis onclusions Diversity and defense-in-depth demonstrated for all events except large-break LOCA Existing diverse plant systems credited for automatic mitigation 3/4 Diverse Scram System (DSS) 3/4 AMSAC 3/4 Automatic Feedwater Isolation System 3/4 Integrated Control System 18
iversity and Defense in Depth Analysis Conclusions New manual operator action times credited 3/4 Manual reactor trip at 2 minutes (SBLOCA) 3/4 Manual start of HPI and LPI at 5 minutes (SBLOCA, REA) 3/4 Manual start of RBCS and RBS at 8 minutes (SBLOCA, REA)
Acceptance criteria met (except for LBLOCA) 3/4 Diverse actuation of LPI required for LBLOCA with failure of RPS/ES 19