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EPID:L-2022-LRM-0020, Notice of Pre-submittal Meeting with Energy Harbor Nuclear Corp. for Beaver Valley Power Station, Units 1 and 2 (Open) |
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Category:Slides and Viewgraphs
MONTHYEARML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML22187A0652022-06-0808 June 2022 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - NRC Presentation Slides ML22061A1392022-03-0202 March 2022 Pre-submittal Meeting Slides for Planned License Amendment Request to Consolidate Fuel Decay Time Requirements ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML20143A0422020-05-22022 May 2020 Presentation Slides - Technical Justification for the Ghent Version 2 Probe Qualification and Probability of Detection - May 26, 2020 (Non-Proprietary Version) ML20143A0352020-05-22022 May 2020 Presentation Slides - Ghent Version 2 Probe License Amendment Request - Pre-submittal Phone Call - May 26,2020 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides ML17335A0372017-12-0505 December 2017 Presentation Slides - Beaver Valley Power Station, Unit 2 - Steam Generator Alloy 800 Sleeve License Amendment Request - Pre-Submittal Meeting on 12/05/2017 ML16089A0622016-03-30030 March 2016 Meeting to Discuss BVPS Draft PRA RAI - Slides ML16098A1642016-03-30030 March 2016 Fpra Dependency Analysis ML15230A2882015-08-13013 August 2015 Slides: NRC Fundamental of Emergency Preparedness Beaver Valley Power Station, August 13, 2015 ML12319A1322012-11-15015 November 2012 FENOC - NRC Pre-Application Meeting License Amendment Request November 15, 2012 ML12269A0612012-09-26026 September 2012 FENOC Presentation for 2012-09-26 Public Meeting ML12215A4152012-08-0101 August 2012 Presentation from Firstenergy Nuclear Operating Company Beaver Valley NFPA 805 Transition ML1117303602011-06-21021 June 2011 FENOC Licensee Slides for 6-21-11 All FENOC Meeting ML1112503982011-05-0505 May 2011 Aam - NRC Slides ML1027903512010-10-18018 October 2010 Summary of Meeting with Firstenergy Nuclear Operating Company, on the Request for Additional Resposnses Regarding the Spent Fuel Rerack for Beaver Valley Power Station, Unit No. 2 ML1014706172010-05-27027 May 2010 Region I and Region III Fire Protection Organization Meeting Slides ML1014101372010-05-21021 May 2010 Bv NRC Strategic Plans Slides for Aam, May 4, 2010 ML1013700202010-05-17017 May 2010 Bv Slides for Annual Assessment Meeting, May 4, 2010 ML1009102662010-03-31031 March 2010 Slides FENOC and NRC Senior Management Briefing, 3-31-10 ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides ML0835303832008-12-11011 December 2008 Meeting Presentation with FENOC - Beaver Valley Power Station, Unit No. 2 Spent Fuel Pool Rerack Project Pre-submittal Meeting ML0832400512008-11-17017 November 2008 Preliminary Results of Environmental Review ML0834504752008-11-0202 November 2008 11/12/2008 Meeting Slides, Beaver Valley License Renewal Public Exit Meeting. 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[Table view] |
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Energy Harbor Nuclear Corp. Beaver Valley Power Station Pre-submittal Meeting
~ energy
~ harbor
License Amendment Request to Consolidate Fuel Decay Time Requirements in a New Decay Time Limiting Condition for Operation 2
Agenda
- Regulatory History of Decay Time Requirements
- Current Decay Time Requirements
Regulatory History of Decay Time Requirements
- Fuel handling accident (FHA) analyses assume a minimum fuel decay time has occurred after irradiation in order to bound the potential accident source term.
- The BVPS FHA analysis assumes the accident involves fuel that has decayed greater than or equal to 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
- Fuel decayed less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> is defined as recently irradiated.
- Fuel decayed greater than or equal to 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> is referred to as non-recently irradiated fuel.
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Regulatory History of Decay Time Requirements (contd)
- Prior to the Improved Technical Specification conversion, the Limiting Condition of Operation 3.9.3 required the reactor to be subcritical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> during movement of irradiated fuel assemblies in the reactor pressure vessel.
- This requirement was then moved to the Licensing Requirements Manual LR 3.9.3, Decay Time, for both units.
- However, Technical Specification (TS) requirements addressing the condition of moving recently irradiated fuel assemblies were retained.
The NRC staff determined that fuel handling limits should be retained in the TSs should the licensee develop future capability to move recently irradiated fuel.
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Current Decay Time Requirements The applicability statements for the following TS Limiting Conditions for Operations (LCOs) include referencing movement of recently irradiated fuel assemblies, and movement of fuel assemblies over recently irradiated fuel. Additionally, certain conditions and notes in the following TS LCOs reference recently irradiated fuel or non-recently irradiated fuel.
TS 3.3.6, Unit 2 Containment Purge and Exhaust Isolation Instrumentation; TS 3.3.7, Control Room Emergency Ventilation System (CREVS)
Actuation Instrumentation; TS 3.7.10, Control Room Emergency Ventilation System (CREVS);
TS 3.7.11, CR Emergency Air Cooling System; TS 3.7.12, Supplemental Leak Collection and Release System (SLCRS);
TS 3.8.2, AC Sources - Shutdown; TS 3.8.5, DC Sources - Shutdown; TS 3.8.8, Inverters - Shutdown; TS 3.8.10, Distribution Systems; TS 3.9.3, Containment Penetrations.
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Proposed Changes Add a new TS LCO 3.9.7, titled Decay Time:
LCO 3.9.7: The reactor shall be subcritical for greater than or equal to 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> APPLICABILITY:
- During movement of irradiated fuel assemblies within the containment,
- During movement of fuel assemblies over irradiated fuel assemblies within the containment.
Condition A: Reactor subcritical less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> requires immediate suspension of movement of irradiated fuel assemblies within containment.
SR 3.9.7.1: The reactor shall be determined to have been subcritical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by verification of the date and time of subcriticality prior to movement of irradiated fuel assemblies within containment.
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Proposed Changes (contd) 8
Proposed Changes (contd)
- Addition of LCO 3.9.7, Decay Time allows deletion of:
3.3.6 - Unit 2 Containment Purge and Exhaust Isolation Instrumentation 3.7.12 - Supplemental Leakage Collection and Release System (SLCRS) 3.9.3 - Containment Penetrations (Refueling)
TS 5.5.7 - SLCRS testing from the Ventilation Filter Testing Program (VFTP) 9
Proposed Changes (contd)
TS 3.3.7, CREVS Actuation Instrumentation - Applicability, Condition D, Table 3.3.7-1, and SRs.
TS 3.7.10, CREVS - Applicability, and Conditions D and E.
TS 3.7.11, CR Emergency Air Cooling System - Applicability, Conditions C and D, and SR 3.7.11.1 Note.
TS 3.8.2, AC Sources - Shutdown - Applicability, Conditions A and B.
TS 3.8.5, DC Sources - Shutdown - Applicability, Condition A.
TS 3.8.8, Inverters - Shutdown - Applicability, Condition A.
TS 3.8.10, Distribution Systems - Shutdown - Applicability, Condition A.
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Conclusions
- The current TS requirements are in place to establish an initial condition in the fuel handling accident safety analysis. The proposed change maintains that initial condition.
- The addition of one new LCO would allow the removal of three LCOs, as well as simplifying several others.
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Schedule
- Plan to submit by April 8, 2022.
- Request NRC approval by April 28, 2023.
- Request a 60-day implementation period after amendments become effective.
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Question or Comments Please?
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