ML103550030

Summary of Meeting with Florida Power & Light Company, Regarding Turkey Point, Units 3 & 4, Spent Fuel Criticality Analysis License Amendment Request

ML103550030
Person / Time
Site:	Turkey Point
Issue date:	01/19/2011
From:	Jason Paige Plant Licensing Branch II
To:	Florida Power & Light Co
Paige, Jason C, NRR/DORL,301-415-5888
References
TAC ME4470, TAC ME4471
Download: ML103550030 (27)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 19, 2011 LICENSEE: Florida Power & Light Company FACILITY: Turkey Point, Units 3 and 4

SUMMARY

OF NOVEMBER 23, 2010, MEETING WITH FLORIDA POWER &

LIGHT COMPANY, ON TURKEY POINT, UNITS 3 AND 4 SPENT FUEL CRITICALITY ANALYSIS LICENSE AMENDMENT REQUEST (TAC NOS.

ME4470 AND ME4471)

On November 23, 2010, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Florida Power & Light Company (FPL, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the Turkey Point, Units 3 and 4 Spent Fuel Criticality Analysis license amendment request (LAR) 207 currently under NRC review. A list of attendees is provided as Enclosure 1.

The licensee presented information (See Enclosure 2) and provided more specifics on its plan to resubmit LAR 207 to address items, in the draft interim staff guidance (ISG) on completing criticality analyses, that were not addressed in the Spent Fuel Criticality Analysis LAR currently under review. The licensee submitted LAR 207 on August 5, 2010, and FPL received the draft ISG after the LAR was submitted. To account for any deviations between LAR 207 and the draft ISG, FPL presented to the NRC staff work being performed to address the draft ISG and requested feedback from the NRC staff on its approach.

The licensee stated that they plan on using the bounding assembly exit temperature and soluble boron concentration for the depletion analysis. Also, the licensee is targeting keff less than 0.990, which provides more margin of safety from the previous target keff of less than 0.995.

FPL plans on modifying the spent fuel pool configurations by deleting configurations with one or no metamic inserts but configuring region 2 of the pool with two metamic inserts, three metamic inserts, or one metamic insert and a water hole. The licensee closed by stating that the resubmitted LAR will be changed to match the format of the draft ISG and FPL plans to resubmit by the end of January 2011.

-2 The NRC staff stated that the licensee's plan forward addresses the draft ISG and will delay issuing any requests for additional information until after the LAR is resubmitted.

Members of the public were in attendance. Public Meeting Feedback forms were not received.

Please direct any inquiries to Jason Paige at 301-415-5888, or Jason. Paige@nrc.gov.

Jason Paige, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251

Enclosures:

1. List of Attendees

2. Licensee Handout cc w/encl: Distribution via Listserv

LIST OF ATTENDEES NOVEMBER 23,2010, MEETING WITH FLORIDA POWER & LIGHT SPENT FUEL CRITICALITY ANALYSIS LICENSE AMENDMENT REQUEST U.S. Nuclear Regulatory Commission D. Cunanan K. Wood Florida Power & Light T. Abbatiello L. Abbott L. Nicholson C. Villard S. Franzone E. Fuentes Westinghouse T. Bishop V. Kucukboyaci E. Mercier D. Smith Enclosure 1

• F=PL.

Turkey Point Spent Fuel Criticality Analysis for LAR 207 NRC Public Meeting/Conference Call November 23, 2010 Enclosure 2

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Introduction

• FPL received draft Interim Staff Guidance (DSS-ISG 2010-01) (ISG) after LAR 207 was submitted

• NRC Staff, FPL and Westinghouse met in September 2010 to discuss LAR 207 approach

• The objectives today:

- Share with Staff additional work being performed

- Explain how this additional work addresses the draft ISG

- Obtain feedback on this approach 3

• F=PL.

FPL Participants

• Liz Abbott (FPL) - Director EPU Licensing

• Larry Nicholson (FPL) - Director Fleet Licensing

• Claude Villard (FPL) - Nuclear Fuels Director

• Steve Franzone (FPL) - EPU LAR Manager

• Tom Abbatiello (FPL) - EPU Engineer

• Emilio Fuentes (FPL) - Nuclear Fuels Supervisor

• Ed Mercier (W) - Manager, U.S. BWR & Criticality

• Darrin Smith (W) - Eng Project Mgr

• Tracy Bishop (W) - Criticality Analyst

• Vefa Kucukboyaci (W) - Criticality Analyst 4

• r=PL.

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Turkey Point Analysis Almroach

• LAR 207 includes new spent fuel criticality analysis for entire pool

- Staff accepted for review

• LAR 207 analysis was performed addressing known Staff concerns

• Due to ISG and self-assessment, additional work is being performed that augments previously submitted analysis 6

• FPL.

Turkey Point Analysis Almroach

• Following slides and tables address issues in these categories:

- Fuel Assembly Selection

- Depletion Analysis

- Criticality Analysis

- Criticality Code Validation

• Major changes noted in the following slides 7

• FPL.

Turkey Point Fuel Assembly Selection Item FPL Approach Fuel Assembly Demonstrated limiting fuel assembly properly Selection selected Additional work performed to expand the demonstration of the limiting fuel assembly selection 8

• FPL.

Fuel Assemblv Selection

• Depletion and criticality calculations performed for each assembly design

- Burnup and enrichment range

- Borated and un-borated cases

- With and without spacer grids

• Criticality calculations performed for various configurations

- 4 / 4 assemblies with no inserts

- 4 / 4 assemblies with 2 inserts

- 3 / 4 assemblies with no inserts

• Spacer grids explicitly modeled to evaluate their reactivity worth 9

• ~PL.

Turkey Point Depletion Analysis Item FPL Approach Depletion 5% applied for both borated and unborated cases Uncertainty Moderator Bounding assembly exit temperature Temperature Soluble Boron Used maximum cycle average concentration, Concentration established from past and expected future operation

- updated Fuel Temperature Calculated based on other parameters Specific Power Used nominal value Burnable Absorbers Plant specific configurations evaluated to ensure

& Radial Zoning bounded by analysis Rodded Operation Other than typical operational maneuvers, plants operate unrodded 10

• FPL.

Depletion Analysis Moderator Temperature

• Moderator temperature used is higher than the core exit temperature

- Assuming minimum core flow from safety analysis

• Temperature used is based on the peak power assembly exit temperature 11

• F=PL.

Depletion Analysis Soluble Boron Concentration

• Included justification for maximum cycle average for both pre-EPU and EPU conditions

- Pre-EPU value compared to previous operation

- EPU value compared to fuel management models 12

• I=PL.

Turkey Point Criticality Analysis Item FPL Approach Axial Burnup Profiles Dischar~ed fuel assemblies axial burnup profiles as well as rom future projections evaluated to establish limiting shape Simplified Models Demonstrations included to address rack or fuel assembly geometrical simplifications - expanded Neutron Absorber Analysis uses nominal value, tolerance included and statistically added Interfaces Justification included - expanded Tolerance Justification included Calculations Normal Conditions All normal conditions included in analysis expanded Accident Conditions All accident conditions analyzed Target keff < 0.990 13

• F=PL.

Criticality Analysis Simplified Models

• Evaluated reactivity effects due to fuel geometry changes during depletion

- Pellet swelling, clad thinning, oxide thickness

• Evaluated impact of water displacement due to burnable absorbers, spacer grids 14

• FPL.

Criticality Analysis Interfaces

• Changed approach from using average bias and uncertainties to bounding bias and uncertainties across interfaces 15

• FPL.

Criticality Analysis Normal Conditions

• Performed self-assessment of all potential normal conditions

- Evaluated reactivity impact of each condition to ensure it remained within bounds of analysis performed 16

• F=PL.

Turkey Point Criticality Code Validation Item FPL Approach Area of Applicability Matrix included in analysis - updated Critical Experiments Multiple experiments evaluated, appropriate experiments included - updated Actinides HTC experiments included in benchmark set Fission Products Uncertainty (5% of fission product worth) calculated and statistically combined with other uncertainties Bias and Uncertainty Statistical analysis follows NUREG/CR-6698 guidance; uncertainty based on population variance Trend Analysis Included in analysis, trends identified addressed -

updated Normal Distribution Statistical analysis included - updated Lumped Fission Not applicable Products 17

• F=PL.

Criticality Code Validation Statistical Treatment

• Code Validation I Benchmarking re-performed to follow NUREG/CR-6698 guidelines

• Set of critical experiments updated 18 GF=PL.

Criticality Code Validation Fission Products

• Uncertainty calculated and statistically combined with other uncertainties

- 50/0 of fission product worth 19

• F=PL.

Turkey Point Other ChanA!!

• Due to changes presented, SFP configurations from LAR 207 have been modified

- Deleted configurations with one or no metamic inserts

- Deleted all but one of the checkerboard configurations

- Included configurations with three metamic inserts, and one empty location and one metamic insert

• Report format will be changed to match draft ISG 20

• I=PL.

Turkey Point Path Forward

• Feedback based on current LAR 207 review

• Timing of submitting additional work to NRC

• Plan to maintain open dialog going forward 21

• I=PL.

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Closing Summary

• FPL appreciates Staff participation and interface

• Review meeting objectives

• Review action items

• Summary of path forward 23 GFPL.

ML103550030 OFFICE DORULPL2-2 IPM DORULPL2-2/LA DORULPL2-21BC DORULPL2-21PM NAME JPaige BClayton DBroaddus (TOrt for) JPaige DATE 01/05/11 01/05/11 01/19/11 01/19/11