ML061210060

Duke Power Meeting Slides, Part 50 License Amendment Request for Dry Storage Loadings at Oconee

ML061210060
Person / Time
Site:	Oconee
Issue date:	03/22/2006
From:	Duke Power Co
To:	Office of Nuclear Reactor Regulation
References
TAC MD0238, TAC MD0239, TAC MD0240
Download: ML061210060 (17)

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)

• Discussion

• Obtain any NRC feedback and address initial questions

• Determine how Duke might support the review process March 22, 2006 2

Duke

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uJuU rIpresefnlaxives

• Oconee Nuclear Site e Reene' Gambrell - Regulatory Compliance

• Carl Fago - Supervisor, Reactor Team

• Nuclear General Office

• Steve Nesbit - Mgr. Spent Fuel Management

• Joe Coletta - SFM (criticality analyst)

• William Murphy - SFM (criticality analyst)

• Gary Walden - SFM (lead for ONS ISFSI)

March 22, 2006 3

, uke Overview N fIAF9%V

• Background (Nesbit)

• LAR Overview (Gambrell)

• Criticality Analysis (Coletta)

• Closing (Gambrell)

• Discussion (ALL)

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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5Pwr e General e Submitted March 1, 2006 e Requests Issuance of Amendment by June 1, 2006

• Criticality Analysis

• Oconee Compliance with 10 CFR 50.68(b)

• 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

• Commitments

• Oconee UFSAR to be updated prior to June 30, 2007 March 22, 2006 7

Duke

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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

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• NUHOMS)m24P and NUHOMS.,24PHB Systems Have Common Basket Design (End 3, Sec 2) 92ELD Par

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-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

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• Roadmap to Fuel Burnup Requirements (Encl 3,Secs 6.3 and 6.4)

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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)

• SCALE 4.4/ KENO V.a

>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

• SIMULATE-3

>3-D axial burnup bias determination kAxial bias applied to 95/95 k-eff calculations where positive March 22, 2006 11

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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

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• CASMO-3 Computational Canister Model (Encl 3, Secs 3 and 6.2)

• 2-D infinite lattice

)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

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• Analysis Results

[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

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• 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

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' MMkaw Clo~sing

• Pre-Submittal Meeting 1111105 41

• LAR Submitted 311106

• 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