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MONTHYEARML0606600022006-03-0909 March 2006 Notice of Meeting with Duke Energy Corp. Oconee, Units 1, 2 and 3 to Discuss March 1, 2006, License Amendment Request Concerning Criticality Requirements for Loading and Unloading Dry Spent Fuel Storage Canisters in the Spent Fuel Pool Project stage: Meeting ML0612100602006-03-22022 March 2006 Duke Power Meeting Slides, Part 50 License Amendment Request for Dry Storage Loadings at Oconee Project stage: Meeting ML0608705332006-04-25025 April 2006 Duke Energy Corporation, Oconee, Units 1, 2, and 3 Meeting Summary, Dry Spent Fuel Storage Canisters Project stage: Meeting ML0612301862006-05-17017 May 2006 Transnuclear, Inc., Request for Withholding Information from Public Disclosure for Oconee Nuclear Station, Units 1, 2, and 3 (TAC Nos. MD0238, MD0239, and MD0240) Project stage: Withholding Request Acceptance ML0612300852006-05-17017 May 2006 Areva Np, Request for Withholding Information from Public Disclosure for Oconee Nuclear Station, Units 1, 2, and 3 Project stage: Withholding Request Acceptance ML0617103042006-06-15015 June 2006 Tech Spec Pages for Amendments 351, 353 and 352 Regarding Criticality Requirements for Loading and Unloading Dry Spent Fuel Storage Canisters in the Spent Fuel Pool Project stage: Other ML0613805292006-06-15015 June 2006 Biweekly Notice Memo, Notice of Issuance, Amendments Revised the Technical Specifications to Reconcile the Criticality Requirements of Title 10 of the Code of Federal Regulations Project stage: Other 2006-04-25
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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
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Text
UW Power Part 50 License Amendment. Request (LAR) for Dry Storage Loadings at Oconee Presentation to the United States Nuclear Regulatory Commission (NRC)
Rockville, MD March 22, 2006 Enclosure 2
Duke rul pube Pur ~Power.
- Provide Information to the NRC Concerning:
- Duke's recent LAR for dry cask loading at Oconee in response to Regulatory Issue Summary (RIS) 2005-05
- Duke's requested schedule for NRC approval of the LAR a Duke's schedule to resume Oconee dry storage loadings (currently suspended until the LAR is approved)
- Obtain any NRC feedback and address initial questions
- Determine how Duke might support the review process March 22, 2006 2
Duke
.a A d- -EPower.
uJuU rIpresefnlaxives
- Oconee Nuclear Site e Reene' Gambrell - Regulatory Compliance
- Carl Fago - Supervisor, Reactor Team
- Steve Nesbit - Mgr. Spent Fuel Management
- Joe Coletta - SFM (criticality analyst)
- William Murphy - SFM (criticality analyst)
March 22, 2006 3
, uke Overview N fIAF9%V
- Criticality Analysis (Coletta)
March 22, 2006 4
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- Pre-Submittal Meeting (November 1, 2005) v Informed NRC of Duke's Response to RIS 2005-05 pOconee dry storage systems had not been shown to meet requirement of 10 CFR 50.68(b) for subcriticality in unborated water
>Planned dry storage loadings suspended
- Informed NRC of Plan to Submit LAR LAR scope: all dry storage systems used at Oconee pTechnical approach: credit for fuel assembly burnup; partial soluble boron credit for SFP WPlanned submittal date: March 1, 2006 pRequested approval date: June 1, 2006
- NRC provided feedback on LAR, technical approach, and schedule March 22, 2006 5s
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ukAR vver-view AM~ -rPower. --.---
5Pwr e General e Submitted March 1, 2006 e Requests Issuance of Amendment by June 1, 2006
- NRC Recommendation from Pre-submittal Meeting
- Technical Specifications (TS)
- New 3.7.18 and Associated Bases (Dry Spent Fuel Storage Cask Loading and Unloading)
Specifies minimum burnup and cooling time for fuel assemblies in dry spent fuel storage cask while in SFP
>Covers all fuel types eligible for Oconee dry storage systems
> Format similar to 3.7.13 for Fuel Assembly Storage (for spent fuel storage racks)
March 22, 2006 6
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- Technical Specifications (Cont'd)
- New 4.4 (Dry Spent Fuel Storage Cask Loading and Unloading)
>Specifies design features associated with criticality
)>Similar to 4.3 for Fuel Storage NUHOMS-24P and NUHOMS-24PHB specified rather than center-to-center pitch
- Revised 3.7.12 and Associated Bases (Spent Fuel Pool Boron Concentration)
> Current limits maintained WApplicability revised to include when fuel assemblies are in a dry spent fuel storage cask located in the SFP
> Revised B3.7.12 provides revised basis for TS
- Oconee UFSAR to be updated prior to June 30, 2007 March 22, 2006 7
Duke
'Power.
Wa UILI UdII Analysis
. Addresses All Oconee Dry Fuel Storage Systems Site-Specific NUHOMS-24P yes 40 (loaded) 1990-1996 General NUHOMS(D-24P yes 44 (loaded) 1999-2005 General NUHOMS-24PHB yes 28 (to be loaded) 2005-2009 March 22, 2006 8
,Duke fw s4.o I:fnm o- -aIU ift:so 'Power
- NUHOMS)m24P and NUHOMS.,24PHB Systems Have Common Basket Design (End 3, Sec 2) 92ELD Par
,I KATIE MAE GMIE SLEEVE-\ r _f -CMIt rO%
UFgu ZrTnL Fl --- Cid 9HELL
-urTnH LW n RMom SUPPDwr MCKEr uELY 911EuD PUN MERN '*M OMuEE BW FUEL REPEE mmT PLAlE CATED Aurch A3E PLAW Source: NUHOMS FSAR, Rev. 8, June 2004 March 22, 2006 9
al l Duke Power.
aL- /A I
- Roadmap to Fuel Burnup Requirements (Encl 3,Secs 6.3 and 6.4)
- j I
I March 22, 2006 10
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d k Duke MEW DW1 ownN Criticality Analysis a Codes Used for Analysis (Encl 3,Secs 6.3 and 6.4)
>3-D full detail canister model with fresh fuel kUsed to demonstrate conservatism of CASMO-3 (and validate CASMO-3 2-D fresh-fuel cases)
- .CASMO-3 DBase 2-D model calculations kBurnup credit computations
- Reactor depletion D dry storage canister "rack" calculations with burned fuel
>3-D axial burnup bias determination kAxial bias applied to 95/95 k-eff calculations where positive March 22, 2006 11
Duke
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. Geometric Models (End 3, Sec 6.3) 1 representative spacing for infinite lattice (CASMO-3) 3 different fuel assembly spacings (KENO V.a)
March 22, 2006 12
h Duke fa:jL: ILL. A _ I- __ rPower.
%,1 o~l I tY Hl IdlV: bi
- CASMO-3 Computational Canister Model (Encl 3, Secs 3 and 6.2)
)No axial or radial canister leakage credited
- Single representative fuel assembly spacing pConservatism is demonstrated
- Full density moderator in dry storage canister
- Water temperature up to 150OF ("off-normal" up to 2120F)
- Fuel designs: Mark B2-B8; B9; B10; B10L
- Conservative reactor depletion parameters
- Credit for 5 years post-irradiation cooling time March 22, 2006 13
Duke vriuca~ieiy Analysis C -
- Criticality Analysis Results (End 3,Sec 6.5)
A Criticality calculations performed per 10 CFR 50.68 (b) and Kopp guidance PCredit for 430 ppm soluble boron (same as current Oconee SFP licensing basis)
- Max 95/95 keffS for normal conditions:
>No boron - 0.9980
>430 ppm boron credit - 0.9264
- Worst-case accident condition (per Kopp) is misload pSingle 5.0 wt % unirradiated fuel assembly "misloaded" in NUHOMS-24P/24PHB canister pRequires 630 ppm soluble boron (2220 ppm available)
March 22, 2006 14
,Duke A..I---!- Power.
kol 1L1L;k211LV M11d1Vb1b
[continued] (End 3,Sec 6.5) 50 45 a Curve specifies minimum c0 40 burnup based on maximum =
m 35 initial enrichment / minimum D D 30 5 years cooling time 0 a 25
( O 20
- Single "region" within dry *E 15 storage canister E 10 5
m Applies to all eligible fuel 0 2.0 2.5 3.0 3.5 4.0 4.5 5.0 types analyzed Initial Max. Design Enrichment (wt. % U-235) m Applicable to NUHOMS-24P and NUHOMS-24PHB March 22, 2006 15
ebDuke e"* w: : _a, I z.A ^.I [Paw __ r.
- Conservatisms in Analysis (End 3,Sec 6.2)
- Infinite lattice (radial and axial) canister model (- 0.04 Ak)
- Mechanical and burnup-related uncertainties (> 0.01 Ak)
- In-reactor depletion parameters
>Boron concentration (700 ppm)
> Moderator temperature (630 OF)
>Discrete BP presence (25 GWD/MTU exposure, max B4C poison loading)
>Fuel temperature (1054 OF)
- Axial burnup bias (linear function of assembly burnup)
- Most reactive eligible fuel assembly design March 22, 2006 16
,Duke eW
' MMkaw Clo~sing
- Pre-Submittal Meeting 1111105 41
- Requested NRC approval 611106
- Load 4 Dry Storage Canisters 6119 - 8118/06
- Outage Preparation Starts* 8121/06
- Unit 1, EOC 23 Refuel Outage Fall 2006
- Must load 2 canisters to avoid outage impacts March 22, 2006 17