ML033140048

Handouts for Public Meeting Between NRC, DC Cook, and Framatome Fuel Transition

ML033140048
Person / Time
Site:	Cook
Issue date:	11/06/2003
From:	American Electric Power Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML033140048 (17)

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AEP/FANP/NRC Meeting November 6, 2003 Agenda

• Introduction

• Fuel Design Description

• Analyses and Methodology Changes

• Technical Specification Changes

• Schedule

• NRC Feedback 2

1

Introduction

• Fuel Vendor Transition D. C. Cook Units 1 & 2

• Focus Today on D. C. Cook Unit 1

• Discussion of Content and Schedule for Future Submittals 3

Introduction (continued)

• Objectives

-Describe Fuel and Methodology to be used for D. C. Cook Unit 1

-Reach an Understanding on NRC Submittals Required

-Provide Information on Submittal Schedule and Requested Review Dates 4

2

Fuel Design Description Experience

-10 Batches Exxon/ANF/Siemens Fuel (with B&W, now Framatome ANP) Previously Used in the Cook Units

-Framatome ANP has Supplied Other Ice Condensers: Catawba, McGuire, Sequoyah Fuel Design Description

• Assembly Description

• 15x15 HTP Assembly with M5TM

• Operating Experience 6

3

15x15 HTP Fuel Assembly

• Top Nozzle

• Alloy 718 Leaf Springs

• Removable Quick Disconnect

• M57 Fuel Rod Cladding

• M5Thm End Plugs

• Zirc-4 Guide Tubes

• FUELGUARDm Bottom Nozzle

• Six Zirc-4 HTP Grids

• Three Zirc-4 IFM Grids

• Lower Alloy 718 HMP Grid Hjigh Thermal Performance (HTP) Grid l'S..ji.

1

• 'Line Contact" Rod Support System

• Robust Construction

• Low Flow Resistance

• Curved Flow Channels forFlow Mixing 4

Intermediate Flow Mixer M

0 (IFM)

• Contact Features of HTP Grid

• Low Resistance for Compatibility with Non-IFM Cores

• Angled Flow Channels for Enhanced Mixing at Mid Spans High Mechanical Performance (HMP) Grid

• Design Based on HTP Grid

• uLine Contact" Fuel Rod Support

• Alloy 718 for Increased Robustness

• Straight Flow Channels 5

FUELGUARDTm Boftom Nozzle Curved Blade Design

. No Direct Line of Sight

• Precludes Debris, Even Straight Wires

• Low Pressure Drop

. Filtering Efficiency

>90%

• No Debris Failures in FUELGUARD Tx PWR Assemblies I4'

. Reduction of Inlet Turbulence D

M5TM-An Advanced Zirconium Alloy for PWR Fuel Assemblies 0

• Alloy M5TM developed for high burnup applications

• M5Tm evolved from an extensive 15 year development program that evaluated 20 potential advanced alloys

• A Ternary Alloy

• Niobium, Oxygen, Zirconium 12 6

M5TM-An Advanced Zirconium Alloy for PWR Fuel Assemblies

• M5Tm has been tested and proven in a wide range of PWR operating environments

- Over 349,000 fuel rods in 35 PWR reactors

- 30 reloads with M5r' fuel rods in 17 reactors

- 36 all M5T fuel assemblies in 9 reactors

- 71,000 MWd/tU bumup achieved

• M5Tm has been tested and proven in severe conditions in irradiated loops

- High lithium, temperature, heat flux, etc.

13 HTP Assembly with M5TM Cladding

• Lead HTP Assembly to Use M5 Cladding

-Calvert Cliffs

-14x14 CE Assembly

• Lead 15x15 HTP Assembly to Use M5 Cladding

-Crystal River (B&W Plant)

-D. C. Cook Unit 1 (Westinghouse Plant) 14 7

Precedents for HTP Fuel Use i

• Design Variants for 14x14, 15x15, 16x16, 17x17, and 18x18 Arrays in Framatome ANP, Siemens/ KWU, CE, and Westinghouse Plants

• Since 1989, Nearly 4,500 HTP Fuel Assemblies Delivered Worldwide

• Maximum Fuel Assembly Burnup of 57 GWd/MTU

• No Fretting Failures at HTP Spacer Positions

• No Manufacturing Defect in Fuel Made Since 1995 15 Operating Experience of HTP (08/2003)

Pr Ane.a t

Fuel Rdds.d AM,8tsh UFl Rotd-P-WMJ4L9 tWVU tS 2001 4

o20 4

820 N7

~Km1

=6162 ~2001r U

A2='~j8~

4 KU 16,18 2000 4

944 4

94.4 42 tZJ* st16816 8008 0

8 4

944 42

4W10

-16o161 702tX10 ~3C>=t4, ~24

.964';.

~5t4-45 tWtt t1X18 8982 1

200 44 16200 64 5 FANJP MIT1 1994 8

0 40 10.54 4

2JIF flh Bx1T$ Zm~o93 2ttt 103.49t-6

YAN- =I7XI?4 'Zn993

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"=

FANP 1717IT 9194 1IS 41."4 392 103.408 ST AW t7x17

_-1994:

0 =

04

=

l t

=

lFAP MIT 19-3

-132 2.648 268 87.152 40 ACE 14x14 20D2 8

1,432 8

1-42 7

-ACE-IZU14d4

-194-

-- 20=i 1AW0-I W

17it7 200 21 9,804 36 9_504 t0 C 7,t17 202 0

40 4 11616 44 1.616 1

W 14.14 1908 0

0 0

25 445 1404W 2003

.4

,704.2 4

T04 54 CIE 14x14 2001 93 12.36 8 93 162568 24

-CE 14514 2002 so 1t5080 so 14700

-0 1015

.180 204

.43.616

'400 1103.212 6:2 14*14 198 1

440

.3.

0.4 Is.,01 801 157 32.828 477

.97.208 97

~ W 1717 19`4

'155

• 40 920!

.351

.92.644 "4

.. CE 14.14 2001 14 20.78 140 05.760 26 ISM

0*0 2003 SS

'17.680 Ss

.05

.. 600 a

MIHI 17-17 2000 16 4224 16 4 224 23

, Total*

1.023 209.87S 1.t72 396.71t 57 w-Glabsl!To tah~

o t

-L27J S15j47 -

4 4t r t05V U

7 01r5 8

Analyses and Methodology Changes - Transition Core

• Minimize Changes to Current Plant Licensing Bases

• Evaluate the Introduction of HTP Fuel Design per the Requirements of 10 CFR 50.59

- Similar to Approach Used for any Plant Change

-Similar to Approach Used for Each Reload Core Design (except scope)

• Identify Plant Safety Analyses Potentially Affected

• Assess Impact of Fuel Design Change on Plant Safety Analyses and Repeat Analyses as Required 17 Analyses and Methodology 4

Changes (continued)

• Review all Event Analyses Identified in FSAR (Disposition of Events)

• Analyses are Dispositioned as:

- Not Impacted by the Change in Fuel Design

- Bounded by the Consequences of Another Event

- Potentially Limiting - Analyze using Framatome ANP Methodology

• Potentially Limiting Events are Analyzed Using NRC Approved Methodology 18 9

Analyses and Methodology Changes (continued)

- Results from Disposition of Events Define the Required Transition Cycle Safety Analyses for each Area

-Thermal Hydraulic Analyses

-Anticipated Operation Occurrence (AOO) Transient Analyses

-Accident Analyses

-Special Analyses 19 Analyses to be Submitted for Review and Approval

• Add EMF-2103PA (Realistic LBLOCA) to List of Approved Methodology

• RLBLOCA Analysis

-Nodalization

-Input Parameters

-Results

-North Anna Lessons Learned 20 10

Analyses to be Submitted for Review and Approval (cont.)

• Add EMF-231 OPA (Non-LOCA) to List of Approved Methodology

• Loss of Flow Analysis

- Nodalization

- Input Parameters

- Results 21 Approved Topical Reports for Application to D.C. Cook Unit I

• XN-NF-82-06(P)(A) Revision I and Supplements 2, 4 and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, October 1986

• XN-75-32(A) Supplements 1, 2, 3, and 4, "Computational Procedure for Evaluating Rod Bow," Exxon Nuclear Company, October 1983 22 11

Approved Topical Reports for Application to D.C. Cook Unit I

• XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986

• ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991 23 Approved Topical Reports for Application to D.C. Cook Unit 1

• EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Design,' Siemens Power Corporation, February 1999

• EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs Volume I - Methodology Description, Volume 2 - Benchmarking Results," Siemens Power Corporation, January 1997 24

Approved Topical Reports for Application to D.C. Cook Unit 1

• EMF-92-081(P)(A) Revision 1, "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," Siemens Power Corporation, February 2000

• EMF-92-153(P)(A) and Supplement 1, 'HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, March 1994 25 Approved Topical Reports for Application to D.C. Cook Unit 1

• EMF-2328(P)(A) Revision 0, PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," Framatome ANP, March 2001

• EMF-2103(P)(A) Revision 0, Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Framatome ANP, April 2003

• ANF-88-054(P)(A), "PDC-3 Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2," Advanced Nuclear Fuels Corporation, October 1990 26 13

Topical Reports Under Review Needed for D. C. Cook Unit 1

• EMF-2310P Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors"

-Revise Boron Dilution Event Analysis Methodology

-Submitted on 8/12/2003

-NRC Approval Anticipated Early 2004 27 Topical Reports Under Review A

Needed for D. C. Cook Unit I

- BAW-10240P Revision 0, "Incorporation of M5TM Properties in Framatome ANP Approved Methods"

- Modify Previously Approved Methods to Reflect M5 Material

-Submitted on 10/1/2002

- NRC Approval Anticipated December 2003 28 14

I Technical Specification Changes Anticipated

• Section 3.2.6 - Allowable Power Level (APL) - Change to Reflect Framatome ANP PDC-3 Methodology

• Section 5.3.1 - Fuel Assembly Design - Add reference to M5 cladding and accompanying exemption

• Section 5.6.2 - Fuel Storage Criticality New Fuel - Change to Reflect Use of Framatome ANP Fuel

• Section 6.9.1.9.2 - Core Operating Limits Report - Change to Add Framatome ANP Topical Reports to COLR List

• No Changes to Limits Anticipated 29 Schedule MliN

• M5 Exemption Submittal

- ? 2004

• LAR Submittal for All TS Changes - April 2004

-Based on current approval schedule for Topicals

• Loss of Flow Analysis Report

- June 2004

• RLBLOCA Analysis Report

- August 2004

• LAR Approval

- January 2005

• Startup of D. C. Cook Unit 1

- April 25, 2005 30 15

Parallel Licensing Actions

• ITS Conversion

• License Renewal

• Fall 2004 Outage Related Changes

-SI Setpoint Change

-Containment Penetrations 31 Objectives

• Describe Fuel and Methodology to be used for D. C. Cook Unit 1

• Reach an Understanding on NRC Submittals Required

• Provide Information on Submittal Schedule and Requested Review Dates 32

.16

NRC Feedback

W

• Presentation Addressed:

-Fuel Design Description

-Analyses and Methodology Changes

-Technical Specification Changes

-Schedule 33