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| | number = ML12026A459 | | | number = ML12026A459 |
| | issue date = 01/26/2012 | | | issue date = 01/26/2012 |
| | title = Seabrook EDG Ifr | | | title = EDG Ifr |
| | author name = Wolfgang R J | | | author name = Wolfgang R |
| | author affiliation = NRC/NRR/DE/EPTB | | | author affiliation = NRC/NRR/DE/EPTB |
| | addressee name = | | | addressee name = |
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| | docket = 05000443, 05000444 | | | docket = 05000443, 05000444 |
| | license number = | | | license number = |
| | contact person = Wolfgang R J, NRR/DE/EPTB, 415-1624 | | | contact person = Wolfgang R, NRR/DE/EPTB, 415-1624 |
| | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs |
| | page count = 14 | | | page count = 14 |
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| =Text= | | =Text= |
| {{#Wiki_filter:EDG ActivitiesBobWolfgang Bob WolfgangDivision of EngineeringComponent Performance and Testing Branch NOT NRC POLICY OR POSITION | | {{#Wiki_filter:EDG Activities Bob Wolfgang Division of Engineering Component Performance and Testing Branch NOT NRC POLICY OR POSITION |
| *Reg.GuidebeingrevisedbyOfficeof Regulatory Guide 1.137, "Fuel Oil Systems for Emergency Power Supplies"Reg. Guide being revised by Office of New Reactors*Adding gas turbine generators
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| *Adding information on ULSD
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| *Adding information on biodiesel
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| *Updating referenced standards Preliminary OpE Insights for 2011*Increase in EDG issues related to inadequate bolt torquing 3
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| *The Standard Technical Specifications contain Surveillance Requirements that
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| verif y diesel generator volta g e and Voltage and Frequency yg gfrequency. Specifically, SR 3.8.1.7 has the following:-Frequency is allowed to vary +
| | Regulatory Guide 1.137, Fuel Oil Systems for Emergency Power Supplies |
| 2% *58.8 Hz -61.2 Hz-Voltage is allowed to vary up to +10% (rounded to the nearest 10 volts)*3740 V -4580 V (for a 4160 V system)
| | * Reg. Guide being revised by Office of New Reactors |
| *Account for the capability of the control systems, i.e., governor and voltage | | * Adding gas turbine generators |
| | * Adding information on ULSD |
| | * Adding information on biodiesel |
| | * Updating referenced standards |
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| regulator to control around those nominal PWROG Proposal values.*Treat the tolerance as an uncertainty, similar to an instrument setpoint, and
| | Preliminary OpE Insights for 2011 |
| | * Increase in EDG issues related to inadequate bolt torquing 3 |
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| perform an uncertainty calculation which
| | Voltage and Frequency |
| | * The Standard Technical Specifications contain Surveillance Requirements that verifyy diesel generator g voltageg and frequency. Specifically, SR 3.8.1.7 has the following: |
| | - Frequency is allowed to vary + 2% |
| | * 58.8 Hz - 61.2 Hz |
| | - Voltage is allowed to vary up to + 10% (rounded to the nearest 10 volts) |
| | * 3740 V - 4580 V (for a 4160 V system) |
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| considers the specified tolerance, measurement and test instrument uncertainties, and setting tolerances. | | PWROG Proposal |
| PWROG ProposalChanges to IST Requirements to Address DG Voltage/Frequency VariationsOriginal MaximumAllowable Pump HeadAdjusted MaximumAllowable Pump HeadPump FlowPump HeadOriginal Minimum Allowable Pump HeadAdjusted MinimumAllowable Pump Head
| | * Account for the capability of the control systems, i.e., governor and voltage regulator to control around those nominal values. |
| *Establish basis for minimum and maximum acceptable voltage*Ensure valve stroke time and torque are Issues acceptable*Ensure pumps can start, run and have adequate capability (Safety Analyses)*Loads that are not di sconnected continue to operate after voltage drop during large motor
| | * Treat the tolerance as an uncertainty, similar to an instrument setpoint, and perform an uncertainty calculation which considers the specified tolerance, measurement and test instrument uncertainties, and setting tolerances. |
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| start
| | PWROG Proposal Changes to IST Requirements to Address DG Voltage/Frequency Variations Original Maximum Allowable Pump Head Adjusted Maximum Allowable Pump Head Pump Head Original Minimum Allowable Pump Head Adjusted Minimum Allowable Pump Head Pump Flow |
| *Relocatestoredfueloil andlubeoilTechnical Specification Task Force TSTF 501 Relocate stored fuel oil and lube oil volume values to licensee control*Minor changes in volume requirements (e.g. ULSD) without
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| NRC approval
| | Issues |
| *The NRC SBO rule (10 CFR 50.63) requires that each nuclear power plant must be abl e to cool the reactor core and maintain containment integrity for a specified duration of SBO*RG1155"StationBlackout "describesanacceptable SBO Background | | * Establish basis for minimum and maximum acceptable voltage |
| *RG 1.155 , Station Blackout , describes an acceptable means to comply with 10 CFR 50.63*The method described in RG 1.155 results in a minimum acceptable SBO duration capability ranging from 2 to 16 hours*The result for all operating pl ants was a coping duration of 4 hours max. ( Refer NUMARC 87-00)*EDG Reliability was a factor to attain 4 hour coping duration
| | * Ensure valve stroke time and torque are acceptable |
| *Recommendation 4*The Task Force recommends that CSO Fukushima Actions the NR C strengthen S B O mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events | | * Ensure pumps can start, run and have adequate capability (Safety Analyses) |
| *Initiate rulemaking to revise 10 CFR 50.63 to require each operating and new reactor licensee to: | | * Loads that are not disconnected continue to operate after voltage drop during large motor start |
| (1) establish a minimum co p in g time of 8 hours for a Task Force Recommendations
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| ()pgloss of all ac powe r-may entail small AC source (2) establish the equipment, procedures, and training necessary to implement an "extended loss of all AC" coping time of 72 hours for core and spent fuel pool cooling and for reactor coolant system and primary containment integrity as needed (3) preplan and pre-stage offsite resources to support uninterrupted core and spent fuel pool cooling
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| *LCO 3.8.1 requires: -b. Two diesel generators capable of supplyingtheonsiteClass1Epower License Amendment RequestsFor Allowed Outage Time supplying the onsite Class 1E power distribution subsystem(s)-ACTION: Restore DG to OPERABLE status within 72 hours *Staff extending the LCO to maximum 14 days with compensatory actions and AAC power source*Need PRA and deterministic submittal Temporary Instruction 2515/176, "Emergency Diesel Generator Technical Specification | |
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| Surveillance Requirements Regarding EnduranceandMarginTesting "EDG Testing Survey Endurance and Margin Testing (ML080420064)*Staff Evaluating: | | Technical Specification Task Force TSTF 501 |
| | * Relocate stored fuel oil and lube oil volume values to licensee control |
| | * Minor changes in volume requirements (e.g. ULSD) without NRC approval |
| | |
| | SBO Background |
| | * The NRC SBO rule (10 CFR 50.63) requires that each nuclear power plant must be able to cool the reactor core and maintain containment integrity for a specified duration of SBO |
| | * RG 1.155, 1 155 Station Station Blackout Blackout, describes an acceptable means to comply with 10 CFR 50.63 |
| | * The method described in RG 1.155 results in a minimum acceptable SBO duration capability ranging from 2 to 16 hours |
| | * The result for all operating plants was a coping duration of 4 hours max. ( Refer NUMARC 87-00) |
| | * EDG Reliability was a factor to attain 4 hour coping duration |
| | |
| | Fukushima Actions |
| | * Recommendation 4 |
| | * The Task Force recommends that the NRCC strengthen S SBOO mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events |
| | |
| | Task Force Recommendations |
| | * Initiate rulemaking to revise 10 CFR 50.63 to require each operating and new reactor licensee to: |
| | ( ) establish a minimum coping (1) p g time of 8 hours for a loss of all ac power- may entail small AC source (2) establish the equipment, procedures, and training necessary to implement an extended loss of all AC coping time of 72 hours for core and spent fuel pool cooling and for reactor coolant system and primary containment integrity as needed (3) preplan and pre-stage offsite resources to support uninterrupted core and spent fuel pool cooling |
| | |
| | License Amendment Requests For Allowed Outage Time |
| | * LCO 3.8.1 requires: |
| | - b. Two diesel generators capable of supplying the onsite Class 1E power distribution subsystem(s) |
| | - ACTION: Restore DG to OPERABLE status within 72 hours |
| | * Staff extending the LCO to maximum 14 days with compensatory actions and AAC power source |
| | * Need PRA and deterministic submittal |
| | |
| | EDG Testing Survey Temporary Instruction 2515/176, Emergency Diesel Generator Technical Specification Surveillance Requirements Regarding Endurance and Margin Testing Testing (ML080420064) |
| | * Staff Evaluating: |
| : 1) Consistency in testing requirements | | : 1) Consistency in testing requirements |
| : 2) Test Load to envelope postulated accident load 3) R.G. 1.9 allows 90% of continuous rating Qti Q ues ti ons 14}} | | : 2) Test Load to envelope postulated accident load |
| | : 3) R.G. 1.9 allows 90% of continuous rating |
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| | Q Questions ti 14}} |
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24145A0012024-05-24024 May 2024 5/29/2024, Annual Assessment Meeting for Seabrook Station - NRC Presentation Slides ML24121A1512024-04-30030 April 2024 Pre-Submittal Meeting to Discuss Upcoming NextEra Energy License Amendment Request for a One-Time Extension to TS 3.8.1.1.a Completion Time ML24073A3372024-03-13013 March 2024 NextEra - NRC Slides for the Public Meeting on March 19, 2024 Regarding Emergency Plan Licensing Amendment ML23177A1142023-06-26026 June 2023 Annual Assessment Meeting Reactor Oversight Process 2023 ML23066A2472023-03-0707 March 2023 Presubmittal Meeting Slides for March 7, 2023, Public Meeting ML22146A3472022-02-23023 February 2022 Slides - Pre-Submittal Meeting for February 23 with Nextera Energy Seabrook, LLC Regarding Planned Submittal of License Amendment Request to Update Pressure-Temperature Limits Curves Period of Applicability ML20161A0812020-06-0303 June 2020 Annual Assessment Meeting June 3, 2020 Slides ML19050A4602019-02-13013 February 2019 Handouts from the Public at the February 13, 2019, Seabrook ASR Public Meeting ML18136A4822018-05-0202 May 2018 Annual Assessment Meeting 05-02-2018 Presentation ML17341A0622017-11-17017 November 2017 NextEra Energy Seabrook Presentation Slides - Seabrook Station ASR Methodology LAR: Structural Deformation - LAR 16-03, Methodology and Responses to Rais D2-D8 - for November 17, 2017, Public Meeting ML17278A7482017-10-13013 October 2017 Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17283A0402017-10-10010 October 2017 Enclosure 2 - Nrc'S Presentation Slides-Seabrook Station, License Amendment Request, Stage 3 Methodology ML17283A0412017-08-24024 August 2017 Enclosure 3 - Licensee'S Presentation-Seabrook Station, License Amendment Request 16-03 ASR Structural Evaluation Methodology ML17164A2712017-06-0707 June 2017 Presentation Slides for Annual Assessment Meeting 2017 ML17129A3942017-05-0909 May 2017 Status of Safety Review of Seabrook License Renewal for May 9, 2017, Public Meeting on ASR in Seabrook LRA ML17129A3842017-05-0909 May 2017 NextEra Presentation at May 9, 2017, Public Meeting Re ASR in License Renewal ML16176A0542016-06-21021 June 2016 6/21/2016 - Seabrook Station Annual Assessment Meeting - NRC Presentation Slides (Assessment and ASR Update) ML16146A2002016-04-28028 April 2016 License Renewal Application, April 28, 2016, Public Meeting NextEra Presentation ML15176A5012015-06-18018 June 2015 Aam Attendance List for June 18, 2015 ML13357A0462013-12-23023 December 2013 Update on ASR ML13357A0432013-12-23023 December 2013 ASR at Seabrook Station Update on Testing Program ML13357A0412013-12-23023 December 2013 Public Meeting on Seabrook Station Testing Program ML14023A7212013-12-18018 December 2013 No More Fukushima Statement for NRC Public Meeting on Dec 18, 2013 ML13133A2492013-05-29029 May 2013 Slides from May 9, 2013, Meeting with NextEra Energy Seabrook, LLC on Pre-Submittal of a Fixed Incore Detector License Amendment Request ML13066A4882013-03-21021 March 2013 Summary of Meeting Held on February 21, 2013, Between the NRC and NextEra Energy Seabrook, LLS Regarding License Renewal Application, Seabrook Station ML12356A0432012-12-11011 December 2012 Safety Implications and Status of ASR Condition - Public Meeting on 12/11/2012 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML12131A4312012-05-10010 May 2012 Aam ROP-12 Slides-Safety Performance & Alkali-Silica Reaction - r9 Revised Format ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12026A4592012-01-26026 January 2012 EDG Ifr ML11343A4482011-12-0909 December 2011 NextEra Drop in Meeting Summary and Slides from 11-14-2011 Meeting with Region-I ML11259A0022011-09-15015 September 2011 Meeting Slides Preliminary Site-Specific Results of the License Renewal Environmental Review for Seabrook Station. ML1116500382011-06-0808 June 2011 Aam Slides, June 8, 2011 ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides ML1013901282010-05-17017 May 2010 License Renewal Overview Presentation for Seabrook Station ML0910604982009-04-30030 April 2009 NRC Slides for Annual Assement Meeting, 4/30/09 ML0809300252008-04-0202 April 2008 NRC Slides - Seabrook Aam 2008 ML0708001192007-03-21021 March 2007 Slides, End of the Presentation, from Seabrook Station Annual Assessment Meeting for EOC 2006-07 ML0608202482006-03-23023 March 2006 NRC Slides for Public Meeting with FPL Seabrook to Discuss Cy 2005 Performance ML0603805612006-02-0606 February 2006 Meeting with FLP, Meeting Handouts, Proposed Submittal to Adopt Quality Assurance Topical Report ML0727105482005-12-16016 December 2005 Measurement Uncertainty Recapture Fple/Caldon - NRC Meeting ML0512201092005-04-22022 April 2005 Slides & Handouts from Meeting with FPL Energy Seabrook, LLC, Regarding Implementation of Technical Specification 3/4.8.1.1 ML0507302062005-03-14014 March 2005 NRC Slides for Public Meeting of Seabrook Station Annual Assessment ML0414201102004-05-20020 May 2004 Public Meeting Handouts Re Power Uprate License Amendment Request for Seabrook Station Unit No. 1 ML0406304312004-03-0303 March 2004 Powerpoint Presentation Slides for Meeting with Florida Power & Light Company Regarding Planned Power Uprate Request for Seabrook Station, Unit No. 1 ML0317404312003-06-12012 June 2003 Sign in Sheet ML0232601592002-11-14014 November 2002 Meeting Handout, Seabrook Steam Generator Tube Assessment Project 2024-05-24
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24145A0012024-05-24024 May 2024 5/29/2024, Annual Assessment Meeting for Seabrook Station - NRC Presentation Slides ML24121A1512024-04-30030 April 2024 Pre-Submittal Meeting to Discuss Upcoming NextEra Energy License Amendment Request for a One-Time Extension to TS 3.8.1.1.a Completion Time ML24073A3372024-03-13013 March 2024 NextEra - NRC Slides for the Public Meeting on March 19, 2024 Regarding Emergency Plan Licensing Amendment ML23177A1142023-06-26026 June 2023 Annual Assessment Meeting Reactor Oversight Process 2023 ML23066A2472023-03-0707 March 2023 Presubmittal Meeting Slides for March 7, 2023, Public Meeting ML22130A1282022-05-10010 May 2022 Annual Assessment Meeting for Seabrook Station - NRC Presentation Slides ML22146A3472022-02-23023 February 2022 Slides - Pre-Submittal Meeting for February 23 with Nextera Energy Seabrook, LLC Regarding Planned Submittal of License Amendment Request to Update Pressure-Temperature Limits Curves Period of Applicability ML21168A1452021-06-22022 June 2021 Annual Assessment Meeting Slides ML20161A0812020-06-0303 June 2020 Annual Assessment Meeting June 3, 2020 Slides ML19042A1102019-02-13013 February 2019 Presentation Slides - 2019 Seabrook Public Meeting ML18136A4822018-05-0202 May 2018 Annual Assessment Meeting 05-02-2018 Presentation ML18086A7742018-02-21021 February 2018 LOR Program Biennial Inspection 71111.11B Exam Overlap Issues ML17341A0622017-11-17017 November 2017 NextEra Energy Seabrook Presentation Slides - Seabrook Station ASR Methodology LAR: Structural Deformation - LAR 16-03, Methodology and Responses to Rais D2-D8 - for November 17, 2017, Public Meeting ML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 ML17278A7482017-10-13013 October 2017 Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17283A0402017-10-10010 October 2017 Enclosure 2 - Nrc'S Presentation Slides-Seabrook Station, License Amendment Request, Stage 3 Methodology ML17283A0412017-08-24024 August 2017 Enclosure 3 - Licensee'S Presentation-Seabrook Station, License Amendment Request 16-03 ASR Structural Evaluation Methodology ML17164A2712017-06-0707 June 2017 Presentation Slides for Annual Assessment Meeting 2017 ML16176A0542016-06-21021 June 2016 6/21/2016 - Seabrook Station Annual Assessment Meeting - NRC Presentation Slides (Assessment and ASR Update) ML16168A4122016-06-15015 June 2016 Slides for Public Meeting with NextEra Energy Regarding Seabrook Station ASR License Amendment ML16146A2002016-04-28028 April 2016 License Renewal Application, April 28, 2016, Public Meeting NextEra Presentation ML14190B0432014-07-0909 July 2014 Annual Assessment Meeting Performance Slides - June 24 2014 ML13357A0432013-12-23023 December 2013 ASR at Seabrook Station Update on Testing Program ML13357A0412013-12-23023 December 2013 Public Meeting on Seabrook Station Testing Program ML13357A0462013-12-23023 December 2013 Update on ASR ML13133A2492013-05-29029 May 2013 Slides from May 9, 2013, Meeting with NextEra Energy Seabrook, LLC on Pre-Submittal of a Fixed Incore Detector License Amendment Request ML13066A4882013-03-21021 March 2013 Summary of Meeting Held on February 21, 2013, Between the NRC and NextEra Energy Seabrook, LLS Regarding License Renewal Application, Seabrook Station ML12356A0432012-12-11011 December 2012 Safety Implications and Status of ASR Condition - Public Meeting on 12/11/2012 ML12236A3852012-08-23023 August 2012 Memo Summary of NextEra Energy Seabrook Drop in Visit and Slides, August 22, 2012 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML12131A4312012-05-10010 May 2012 Aam ROP-12 Slides-Safety Performance & Alkali-Silica Reaction - r9 Revised Format ML1211604142012-04-23023 April 2012 Structural Assessment of Seabrook Station - Role of Concrete Material Testing ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12026A4592012-01-26026 January 2012 EDG Ifr ML11343A4482011-12-0909 December 2011 NextEra Drop in Meeting Summary and Slides from 11-14-2011 Meeting with Region-I SBK-L-11190, Supplement to Request for Closed Meeting to Discuss Proprietary Test2011-09-19019 September 2011 Supplement to Request for Closed Meeting to Discuss Proprietary Test ML11259A0022011-09-15015 September 2011 Meeting Slides Preliminary Site-Specific Results of the License Renewal Environmental Review for Seabrook Station. ML1116500382011-06-0808 June 2011 Aam Slides, June 8, 2011 ML12054A6412011-05-24024 May 2011 Concrete Degradation - Alkali Silica Reaction, W/Handwritten Notes ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides ML1019703702010-07-19019 July 2010 License Renewal Process Overview ML1013901282010-05-17017 May 2010 License Renewal Overview Presentation for Seabrook Station ML1011004582010-04-20020 April 2010 NRC Slides for Seabrook Annual Assessment Meeting, April 14, 2010 ML0927403042009-09-22022 September 2009 NextEra Letter and Slide Presentation to NRC Seabrook Regulatory Conference, Dated 9/22/09 ML0910604982009-04-30030 April 2009 NRC Slides for Annual Assement Meeting, 4/30/09 ML0809300252008-04-0202 April 2008 NRC Slides - Seabrook Aam 2008 ML0710002082007-03-29029 March 2007 Aam Slides for EOC 2006-07 ML0708001192007-03-21021 March 2007 Slides, End of the Presentation, from Seabrook Station Annual Assessment Meeting for EOC 2006-07 ML0727105992006-06-0505 June 2006 Viewgraphs of Use of Ultrasonic Flow Measurement to Determine Reactor Power 2024-05-24
[Table view] |
Text
EDG Activities Bob Wolfgang Division of Engineering Component Performance and Testing Branch NOT NRC POLICY OR POSITION
Regulatory Guide 1.137, Fuel Oil Systems for Emergency Power Supplies
- Reg. Guide being revised by Office of New Reactors
- Adding gas turbine generators
- Adding information on ULSD
- Adding information on biodiesel
- Updating referenced standards
Preliminary OpE Insights for 2011
- Increase in EDG issues related to inadequate bolt torquing 3
Voltage and Frequency
- The Standard Technical Specifications contain Surveillance Requirements that verifyy diesel generator g voltageg and frequency. Specifically, SR 3.8.1.7 has the following:
- Frequency is allowed to vary + 2%
- Voltage is allowed to vary up to + 10% (rounded to the nearest 10 volts)
- 3740 V - 4580 V (for a 4160 V system)
PWROG Proposal
- Account for the capability of the control systems, i.e., governor and voltage regulator to control around those nominal values.
- Treat the tolerance as an uncertainty, similar to an instrument setpoint, and perform an uncertainty calculation which considers the specified tolerance, measurement and test instrument uncertainties, and setting tolerances.
PWROG Proposal Changes to IST Requirements to Address DG Voltage/Frequency Variations Original Maximum Allowable Pump Head Adjusted Maximum Allowable Pump Head Pump Head Original Minimum Allowable Pump Head Adjusted Minimum Allowable Pump Head Pump Flow
Issues
- Establish basis for minimum and maximum acceptable voltage
- Ensure pumps can start, run and have adequate capability (Safety Analyses)
- Loads that are not disconnected continue to operate after voltage drop during large motor start
Technical Specification Task Force TSTF 501
- Relocate stored fuel oil and lube oil volume values to licensee control
- Minor changes in volume requirements (e.g. ULSD) without NRC approval
SBO Background
- The NRC SBO rule (10 CFR 50.63) requires that each nuclear power plant must be able to cool the reactor core and maintain containment integrity for a specified duration of SBO
- RG 1.155, 1 155 Station Station Blackout Blackout, describes an acceptable means to comply with 10 CFR 50.63
- The method described in RG 1.155 results in a minimum acceptable SBO duration capability ranging from 2 to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />
- The result for all operating plants was a coping duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> max. ( Refer NUMARC 87-00)
- EDG Reliability was a factor to attain 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> coping duration
Fukushima Actions
- The Task Force recommends that the NRCC strengthen S SBOO mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events
Task Force Recommendations
- Initiate rulemaking to revise 10 CFR 50.63 to require each operating and new reactor licensee to:
( ) establish a minimum coping (1) p g time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for a loss of all ac power- may entail small AC source (2) establish the equipment, procedures, and training necessary to implement an extended loss of all AC coping time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for core and spent fuel pool cooling and for reactor coolant system and primary containment integrity as needed (3) preplan and pre-stage offsite resources to support uninterrupted core and spent fuel pool cooling
License Amendment Requests For Allowed Outage Time
- b. Two diesel generators capable of supplying the onsite Class 1E power distribution subsystem(s)
- ACTION: Restore DG to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
- Staff extending the LCO to maximum 14 days with compensatory actions and AAC power source
- Need PRA and deterministic submittal
EDG Testing Survey Temporary Instruction 2515/176, Emergency Diesel Generator Technical Specification Surveillance Requirements Regarding Endurance and Margin Testing Testing (ML080420064)
- 1) Consistency in testing requirements
- 2) Test Load to envelope postulated accident load
- 3) R.G. 1.9 allows 90% of continuous rating
Q Questions ti 14