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Category:Slides and Viewgraphs
MONTHYEARML23087A2972023-04-17017 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 ML14211A2132014-07-31031 July 2014 Duke Energy Presentation for 2014-07-31 Meeting ML14211A2162014-07-31031 July 2014 NRC Meeting Slides 7-31-14 Reg Conference ML14147A3652014-05-27027 May 2014 Annual Assessment Public Meeting Summary Memo ML14058A0512014-02-0404 February 2014 Slides on Oconee Nuclear Station - Standby Shutdown Facility (Ssf) Flood Barrier Breach Violation SDP Assessment ML14058A0352014-02-0404 February 2014 Meeting Slides on Oconee Flood Protection and the 10 CFR 50.54(f) Response ML14055A4102014-02-0404 February 2014 Meeting Slides on Standby Shutdown Facility Flood Barrier Breach Violation Informal Reassessment ML14058A0742014-02-0404 February 2014 Slides on Oconee Ssf Flood Barrier Breach SDP - Lessons Learned ML14058A0772014-02-0404 February 2014 Slides on Oconee Ssf Flood Barrier Breach SDP Lessons Learned 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 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 2023-04-17
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22130A0092022-04-28028 April 2022 Duke Presentation for April 28, 2022 Public Meeting - Bolting Integrity ML22130A0102022-04-28028 April 2022 Duke Presentation for April 28, 2022 Public Meeting - Containment Liner 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 ML14211A2132014-07-31031 July 2014 Duke Energy Presentation for 2014-07-31 Meeting ML14211A2162014-07-31031 July 2014 NRC Meeting Slides 7-31-14 Reg Conference 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. ML13056A1022013-02-0606 February 2013 Meeting Slides on Oconee Flood Issue Jocassee Dam Failure Frequency ML13056A0992013-02-0606 February 2013 Meeting Slides on Oconee Ssf Flood Barrier Breach Sdsp - Lessons Learned ML13052A7822013-02-0606 February 2013 Slides on Oconee Ssf Flood Barrier Breach SDP - Lessons Learned ML13035A2442013-01-30030 January 2013 Projects Meeting - NRC Slides ML13035A2332013-01-30030 January 2013 Projects Meeting - Licensee'S Public Meeting Slides 2022-09-14
[Table view] |
Text
Presented by Oconee Nuclear Station October 11, 2011
Introduction Purpose of revised strategy is to credit the minimum number of SSCs required to place and maintain the affected unit(s) at approximately 250 deg F.
Utilizing only these SSCs minimizes the post tornado recovery actions that must be accomplished within the first 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the event.
Proposed strategy is modeled using ONS NFPA 805 compliance strategy for the Auxiliary Building Fire Area.
Procedural actions denoted by an asterisk (*) have not yet been developed.
2
Compliance Strategy Affected unit(s) maintained safe and stable in mode 3
[hot standby] with RC temperature 525 deg F from SSF for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (unless the initiating event causes the unit(s) to be driven to a lower temperature).
Recovery actions restore SSCs required to transition affected unit(s) from mode 3 to an RC temperature of approximately 250 deg F.
A natural circulation cool down is performed and affected unit(s) are maintained safe and stable long term at approximately 250 deg F in natural circulation.
3
Method of Accomplishment for Maintaining Unit @ Hot Standby Reactivity Control Function o Shutdown margin initially established by the insertion of the control rods prior to SSF activation.
o Shutdown margin maintained by RCS makeup with borated water from the Spent Fuel Pool (SFP) using SSF RC Makeup pump with letdown back to the SFP.
Reactor Coolant Inventory Control Function o SSF control of RCP seal injection using the SSF Reactor Coolant Makeup Pump supplied from the SFP with Letdown back to the SFP.
4
Method of Accomplishment for Maintaining Unit @ Hot Standby Reactor Coolant Pressure Control Function o SSF control of RCS Pressure via Group B & C Pressurizer Heaters and Pressurizer Safety Relief Valves.
o Pressure control is partially satisfied by those systems associated with RC Inventory Control and Decay Heat Removal Control.
5
Method of Accomplishment for Maintaining Unit @ Hot Standby Decay Heat Removal Control Function o Following loss of RCPs, DHR established by SSF control of natural circ between the core and SG A & B.
o SSF ASW pump feeds SG A & B for reactor coolant heat removal.
o MS pressure is regulated using MS isolation and steam release through the SRVs.
o The SSF Submersible pump provides water to the CCW system for supplying the SSF ASW pump.
6
Method of Accomplishment for Maintaining Unit @ Hot Standby Process Monitoring Function o The following system process variables are monitored from the SSF:
- Pressurizer pressure and level,
- RCS pressure and temperature,
- SSF RC Makeup flow and suction/discharge pressure,
7
Method of Accomplishment for Maintaining Unit @ Hot Standby Vital Auxiliaries o SSF electrical distribution system is separated from normal plant power to SSF power systems. SSF Diesel Generator provides power for AC and DC power systems.
o SSF cooling credited for SSF control room, battery rooms, computer room, and response room. SSF ventilation equipment credited for SSF diesel generator, HVAC, SWGR, and pump rooms.
8
Method of Accomplishment for Transition to Mode 4 Reactivity Control Function o Shutdown margin maintained by adequate concentration of borated water from the BWST via local operation of HPI Pump A or B and RC letdown through local operation of the RV head vent valves.
Reactor Coolant Inventory Control Function o RC makeup via local operation of HPI Pump A or B for makeup via RCP seal injection and A RC makeup header with suction aligned from the BWST and RC letdown through local operation of the RV head vent valves.
9
Method of Accomplishment for Transition to Mode 4 Reactor Coolant Pressure Control Function o Local operation of PZR PORV and operation of Pressurizer Heaters from SSF CR credited for controlling system pressure during natural circulation cooldown.
Decay Heat Removal Function o DHR provided by natural circulation between core and SGs using the SSF Auxiliary Service Water Pump taking suction from CCW intake piping.
o RCS cooldown control provided by local operation of the Main Steam atmospheric dump valves.
10
Method of Accomplishment for Transition to Mode 4 Process Monitoring Function o Following system process variables are monitored from the SSF CR: Pressurizer pressure and level, RCS pressure and temperature, SSF ASW flow, and SG level.
o Following system process variables are monitored locally following repair: RCP seal injection flow and BWST level.
11
Method of Accomplishment for Transition to Mode 4 Vital Auxiliaries o Credited electrical power path for HPI Pump A or B is PSW 4KV SWGR supplied from either Keowee Hydro Generator through underground power path or 100KV transmission line.
o Credited electrical power path for SSF ASW Pump is PSW 4KV power aligned to SSF 4KV SWGR and supplied from either Keowee Hydro Generator through underground power path or 100KV transmission line.
12
Event Sequence Tornado Watch is declared.
o Operating crews enter AP/06, Natural Disaster.
Tornado Warning is declared.
o One licensed operator (either RO or SRO) proceeds to SSF and establishes communications with control rooms.
o All operations shift personnel report to assigned unit CR.
13
Event Sequence continued Tornado strikes site resulting in:
o Three unit blackout.
o Tornado related damage disables TD emergency feedwater pump on each unit.
This is assumed worst case scenario.
14
Event Sequence continued All three units trip.
o CR SRO on each unit enters EP/01, EOP.
o Reactor operators perform immediate manual actions and symptoms check of EOP and determine that a loss of RCP seal cooling and SG DHR function has occurred.
o Licensed operator at SSF directed to establish RCP seal cooling via reactor coolant makeup system on one unit (existing 20 minute TCA), aligns SSF ASW for all affected units and establishes SG DHR via SSF ASW system (existing 14 minute TCA) on one unit.*
15
Event Sequence continued Two additional licensed operators (LO) proceed to SSF and establish SG DHR and RCP seal cooling.*
o LOs proceed via current credited travel path.
o If travel path blocked LOs proceed via alternate egress points from auxiliary building.
o LOs enter SSF via north or south entrance.
SPOC is notified to deploy SSF submersible pump.
16
Event Sequence continued Affected unit(s) maintained in natural circulation hot standby conditions (typically 555 deg F/2155 psig) from SSF for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
TSC is activated. RP/1000/22, Procedure for Major Site Damage Assessment and Repair, is entered to coordinate site assessment and repair activities.*
OP/1102/24, Plant Assessment and Alignment Following Major Site Damage, is entered to assess availability of systems required for unit cool down and make necessary alignments once repairs are completed.*
17
Recovery Actions 13.8 KV line from PSW substation to PSW building is restored.*
A & B HPI discharge headers assessed for damage and repaired as necessary.*
RCP seal injection header assessed for damage and repaired as necessary.*
18
Recovery Actions continued (Existing) portable valve control panel installed.
o Panel is placed outside WPR in yard area.
o Panel is connected to PZR PORV, RV head vent valves and CFT isolation valves at reactor building penetration in WPR.
o Panel receives 600 vac, 120 vac and 125 vdc power from SSF.
TSC arranges for fire truck to replenish SFP inventory per RP/1000/22 (existing 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> TCA) via installed connection.
PSW power aligned to SSF and SSF D/G shutdown.*
19
Post Recovery Action Event Sequence OP/1102/25, Cooldown Following Major Site Damage, is entered and RCS cool down is performed with command and control from SSF CR.*
o PSW booster pump is locally started to supply HPI pump cooling.
o HPI pump A or B is locally started.
o RCP seal injection control valve is locally throttled to establish RCP seal injection.
o SSF RCMU System secured from SSF CR.
20
Post Recovery Action Event Sequence o PZR heaters de-energized from SSF CR.
o RV head vent valves opened by local operation from portable valve control panel.
o Cool down initiated by local operation of Main Steam atmospheric dump valves.
o RC letdown to SFP secured from SSF CR.
o RCS pressure reduction is initiated by local operation of PZR PORV from portable valve control panel.
o CFT isolation valves closed by local operation from portable valve control panel.
21
Post Recovery Action Event Sequence o Affected unit(s) stabilized in natural circulation hot shutdown conditions at approximately 250 deg F/300 psig.
o RV head vents are closed.
o HPI system is secured.
o Long term RC pressure provided by SSF powered PZR heaters.
o Long term DHR provided by SGs fed from SSF ASW.
o SSF submersible pump maintains SSF ASW pump suction inventory.
22
Acronyms AP - Abnormal (Operating) Procedure ASW - Auxiliary Service Water BWST - Borated Water Storage Tank CCW - Condenser Circulating Water CFT - Core Flood Tank CR - Control Room D/G - Diesel Generator DHR - Decay Heat Removal EOP - Emergency Operating procedure HPI - High Pressure Injection HSB - Hot Standby HVAC - Heating, Ventilation and Air Conditioning Mode 3 - reactor subcritical with RC temperature 250 deg. F.
MS - Main Steam NC - Natural Circulation OP - Operating Procedure PORV - Power (Pilot) Operated Relief Valve PSW - Protected Service Water PZR - Pressurizer 23
Acronyms continued RC - Reactor Coolant RCP - Reactor Coolant Pump RCS - Reactor Coolant System RO - Reactor Operator RP - (Emergency) Response Procedure RV - Reactor Vessel SFP - Spent Fuel Pool SG - Steam Generator SPOC - (Maintenance) Single Point of Contact SRO - Senior Reactor Operator SRV - Safety Relief Valves SSC - Structures, Systems and Components SSF - Standby Shutdown Facility SWGR - Switchgear TCA - Time Critical Action TD - Turbine Driven TORMIS - Tornado Missile Analysis Program TSC - Technical Support Center WPR - West Penetration Room 24