ML042740022
| ML042740022 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/06/2003 |
| From: | AEP Industries |
| To: | Office of Nuclear Reactor Regulation |
| Shuaibi M, NRR/DLPM, 415-2859 | |
| References | |
| Download: ML042740022 (32) | |
Text
AEP/FANP/NRC Meeting November 6, 2003 Enclosure 2
Agenda
- Introduction
- Fuel Design Description
- Analyses and Methodology Changes
- Technical Specification Changes
- Schedule
- NRC Feedback
Introduction
- Fuel Vendor Transition D. C. Cook Unit 1
- Fuel Vendor Transition D. C. Cook Unit 2
- Discussion of Content and Schedule for Future Submittals
- Focus Today on D. C. Cook Unit 1
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
Introduction (continued)
- Experience
-10 Batches Framatome ANP (Exxon/ANF/Siemens) Fuel 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
15x15 HTP Fuel Assembly
- Six Zirc-4 HTP
- Top Nozzle Grids K Alloy 718 Leaf Springs
- Three Zirc-4 IFM K Removable Quick Grids Disconnect
- M5' Fuel Rod Cladding K M5' End Plugs
- Zirc-4 Guide Tubes
- FUELGUARD' Bottom Nozzle
- Lower Alloy 718 HMP Grid
HTP Grid S e ction A-A Line contact
- Line Contact Rod Support System
- Robust Construction
- Low Flow Resistance
- Curved Flow Channels for Flow Mixing
Intermediate Flow Mixer (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
- Line Contact Fuel Rod Support
- Alloy 718 for Increased Robustness
- Straight Flow Channels
FUELGUARD' Bottom Nozzle
- Curved Blade Design K No Direct Line of Sight K Precludes Debris, Even Straight Wires K Low Pressure Drop K Filtering Efficiency
>90%
K No Debris Failures in FUELGUARD' PWR Assemblies K Reduction of Inlet Turbulence
M5TM - An Advanced Zirconium Alloy for PWR Fuel Assemblies
- Alloy M5TM developed for high burnup applications
- M5' evolved from an extensive 15 year development program that evaluated 20 potential advanced alloys
- A Ternary Alloy
M5TM - An Advanced Zirconium Alloy for PWR Fuel Assemblies
- M5' 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 M5TM fuel rods in 17 reactors
- 36 all M5TM fuel assemblies in 9 reactors
- 71,000 MWd/tU burnup achieved
- M5' has been tested and proven in severe conditions in irradiated loops
- High lithium, temperature, heat flux, etc.
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)
Precedence for HTP Fuel Use
- 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
Operating Experience of HTP (08/2003)
Maximum Region Plant First In Operation Total Fuel Type FA Burnup Type Inserted Assemblies Fuel Rods Assemblies Fuel Rods (MWd/kgU)
KWU 15x15 2001 4 820 4 820 37 KWU 16x16 2001 7 1,652 8 1,888 24 KWU 16x16 2000 4 944 4 944 42 KWU 16x16 2003 32 7,552 32 7,552 6 KWU 16x16 1989 0 0 4 944 46 KWU 16x16 2000 24 5,664 24 5,664 45 KWU 18x18 1992 1 300 44 13,200 54 KWU 18x18 1992 14 4,200 28 8,400 53 European Market FANP 17x17 1994 0 0 40 10,560 48 FANP 17x17 1993 157 41,448 392 103,488 56 FANP 17x17 1994 157 41,448 392 103,488 57 FANP 17x17 1994 124 32,736 328 86,592 50 FANP 17x17 1993 132 34,848 368 97,152 49 FANP 17x17 1994 157 41,448 360 95,040 51 ACE 14x14 2002 8 1,432 8 1,432 7 ACE 14x14 1994 120 21,480 309 55,311 51 W 17x17 2000 36 9,504 36 9,504 40 PPP 17x17 2000 160 42,240 160 42,240 42 W 17x17 2003 44 11,616 44 11,616 1 FANP 17x17 2002 24 6,336 24 6,336 11 Totals 1,205 305,668 2,609 662,171 57 CE 14x14 1988 0 0 2 352 46 CE 14x14 2003 4 704 4 704 4 US & Far East Market CE 14x14 2001 93 16,368 93 16,368 24 W 14x14 1995 81 14,499 136 24,344 53 CE 14x14 2002 80 14,080 80 14,080 12 CE 15x15 1988 204 43,616 480 103,232 52 W 15x15 1991 157 32,028 477 97,308 57 W 17x17 1994 155 40,920 351 92,664 54 CE 14x14 2001 148 25,760 148 25,760 26 B&W 15x15 2003 85 17,680 85 17,680 0 MHI 17x17 2000 16 4,224 16 4,224 23 Totals 1,023 209,879 1,872 396,716 57 Global Totals 2,228 515,547 4,481 1,058,887 57
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
Analyses and Methodology Changes (continued)
- Technical Specification Changes Generally Limited to:
-References to NRC Approved Methods Used to Determine Thermal Limits in COLR
-Design Features
- COLR Thermal Limits are Determined for the Transition Core Based on Analyses Using NRC Approved Methods
Analyses and Methodology 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
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
Analyses to be Submitted for Review and Approval
- Add EMF-2103PA to List of Approved Methodology
- RLBLOCA Analysis
-Nodalization
-Input Parameters
-Results
Analyses to be Submitted for Review and Approval (cont.)
- Add EMF-2310PA to List of Approved Methodology
- Loss of Flow Analysis
- Nodalization
- Input Parameters
- Results
Approved Topical Reports for Application to D. C. Cook Unit 1
- XN-NF-82-06(P)(A) Revision 1 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
Approved Topical Reports for Application to D. C. Cook Unit 1
- 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
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 1 - Methodology Description, Volume 2 - Benchmarking Results, Siemens Power Corporation, January 1997
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
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
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
Topical Reports Under Review Needed for D. C. Cook Unit 1
- 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
Technical Specification Changes Anticipated
- Section 3.2.6 - Allowable Power Level (APL) -Change to Reflect Framatome ANP PDC-III Methodology
- Section 5.3.1 - Fuel Assembly Design- Add reference to M5 cladding
- 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
Schedule
- M5 Exemption Submittal - ? 2004
- LAR Submittal for All TS Changes - April 2004
- 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
NRC Feedback
- Presentation Addressed:
-Fuel Design Description
-Analyses and Methodology Changes
-Technical Specification Changes
-Schedule