ANP-2948NP, Rev. 0

49 Pages·2010·1.56 MB·English

BSEP 10-0126
Enclosure 3
AREVA Report ANP-2948NP, Revision 0,
MechanicalD esign Reportf or Brunswick ATRIUM 1 OXM Fuel Assemblies,
dated October 2010
Controlled Document
ANP-2948NP
Revision 0
Mechanical Design Report for
Brunswick ATRIUM 1OXM Fuel Assemblies
October 2010
AR EVA
AREVA NP Incý.
Controlled Document
AREVA NP
ANP-2948NP
Revision 0
Mechanical Design Report for
Brunswick ATRIUM 1OXM Fuel Assemblies
Controlled Document
AREVA NP
AREVA NP Inc.
ANP-2948NP
Revision 0
Copyright © 2010
AREVA NP Inc.
All Rights Reserved
Controlled Document
AREVA NP
ANP-2948NP
Mechanical Design Report for Revision 0
Brunswick ATRIUM 1OXM Fuel Assemblies Paae i
Nature of Changes
Revision Section(s)
Item Number or Page(s) Description and Justification
1. 0 All This is the initial release.
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Contents
1 .0 In tro d u ctio n ..................................................................................................................... 1
2.0 Design Description .................................................................................................... 2
2.1 Overview ......................................................................................................... 2
2.2 Fuel Assem bly ................................................................................................ 2
2.2.1 Spacer Grid ..................................................................................... .3
2.2.2 Wa ter Channel .................................................................................. 3
2.2.3 Lower Tie Plate .................................................................................. 4
2.2.4 Upper Tie Plate and Connecting Hardware ................... 4
2.2.5 Fuel Rods ......................................................................................... 5
2.3 Fuel Channel and Com ponents ...................................................................... 6
3.0 Fuel Design Evaluation .............................................................................................. 9
3.1 Objectives ....................................................................................................... 9
3.2 Fuel Rod Evaluation ...................................................................................... 9
3.3 Fuel System Evaluation .................................................................................. 9
3.3.1 Stress, Strain, or Loading Limits on Assembly Components ............ 10
3.3.2 Fatigue ............................................................................................ 10
3.3.3 Fretting W ear .................................................................................. 11
3.3.4 Oxidation, Hydriding, and Crud Buildup ........................................... 11
3.3.5 Rod Bow ......................................................................................... 11
3.3.6 Axial Irradiation Growth ..................................................................... 12
3.3.7 Rod Internal Pressure ..................................................................... 12
3.3.8 Assem bly Lift-off .............................................................................. 12
3.3.9 Fuel Assem bly Handling .................................................................. 13
3.3.10 Miscellaneous Com ponent Criteria ................................................. 14
3.3.10.1 Compression Spring Forces ............................................ 14
3.3.10.2 LTP Seal Spring ............................................................. 14
3.4 Fuel Coolability .............................................................................................. 14
3.4.1 Cladding Em brittlement ................................................................... 14
3.4.2 Violent Expulsion of Fuel ................................................................. 15
3.4.3 Fuel Ballooning ................................................................................ 15
3.4.4 Structural Deform ations .................................................................. 15
3.4.4.1 Fuel Storage Seismic Qualification .................................. 16
3.5 Fuel Channel and Fastener ........................................................................... 16
3.5.1 Design Criteria for Normal Operation ............................................... 16
3.5.2 Design Criteria for Accident Conditions ........................................... 17
4.0 Mechanical Testing .................................................................................................. 24
4.1 Fuel Assem bly Axial Load Test ..................................................................... 24
4.2 Spacer Grid Lateral Im pact Strength Test .................................................... 24
4.3 Tie Plate Strength Tests ................................................................................ 25
4.4 Debris Filter Efficiency Test ........................................................................... 25
4.5 Fuel Assem bly Fretting Test ......................................................................... 26
4.6 Fuel Assem bly Static Lateral Deflection Test ................................................ 26
4.7 Fuel Assem bly Lateral Vibration Tests ......................................................... 26
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4.8 Fuel Assembly Impact Tests ......................................................................... 27
5 .0 R efe re n ce s .................................................................................................................... 2 8
A ppendix A Illustrations .................................................................................................. 29
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Tables
Table 2-1 Fuel Assembly and Component Description ......................................................... 7
Table 2-2 Fuel Channel and Fastener Description ................................................................ 8
Table 3-1 Results for ATRIUM 1OXM Fuel Assembly ........................................................... 18
Table 3-2 Results for Advanced Fuel Channels .................................................................. 21
Table 3-3 Results for Channel Fasteners ........................................................................... 23
Figures
Figure A-1 ATRIUM 1OXM Fuel Assembly .......................................................................... 30
Figure A-2 UTP with Locking Hardware ............................................................................. 31
Figure A-3 Improved FUELGUARD LTP ............................................................................. 32
Figure A-4 ATRIUM 1OXM ULTRAFLOW Spacer Grid ......................................................... 33
Figure A-5 Full and Part-Length Fuel Rods ......................................................................... 34
Figure A-6 Advanced Fuel Channel .................................................................................... 35
Figure A-7 Fuel Channel Fastener Assembly ....................................................................... 36
This document contains a total of 44 pages.
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Nomenclature
Acronym Definition
AFC Advanced fuel channel
AOO Anticipated operational occurrences
ASME American Society of Mechanical Engineers
B&PV Boiler and pressure vessel
BWR Boiling water reactor
CHF Critical heat flux
EOL End of life
FPM Fuel preparation machine
HDSFSR High density spent fuel storage racks
LOCA Loss-of-coolant accident
LTP Lower tie plate
MWd/kgU Megawatt-days per kilogram of Uranium
NFS New fuel storage
NRC U. S. Nuclear Regulatory Commission
PLFR Part-length fuel rods
psi Pounds per square inch
RPV Reactor pressure vessel
Sn Design stress intensity
SRA Stress relief annealed
SRP Standard review plan
Su Ultimate stress
SY Yield stress
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1.0 Introduction
This report provides a design description, mechanical design criteria, fuel structural analysis results, and
test results for the ATRIUMTM* 10 XM fuel assembly and 100/75 Advanced Fuel Channel (AFC) designs
supplied by AREVA NP Inc. (AREVA) for use at Brunswick Nuclear Plant beginning with Unit 2 Cycle 20
and Unit 1 Cycle 19.
The scope of this report is limited to an evaluation of the structural design of the fuel assembly and
channel. The fuel assembly structural design evaluation is not cycle-specific so this report is intended to
be referenced for each cycle where the fuel design is in use. Minor changes to the fuel design and cycle-
specific input parameters will be dispositioned for future reloads. AREVA will confirm the continued
applicability of this report prior to delivery of each subsequent reload of ATRIUM 1 OXM fuel at Brunswick
Units I and 2.
The fuel assembly design was evaluated according to the AREVA boiling water reactor (BWR) generic
mechanical design criteria (Reference 1). The fuel channel design was evaluated to the criteria given in
fuel channel topical report (Reference 2). The generic design criteria have been approved by the U.S.
Nuclear Regulatory Commission (NRC) and the criteria are applicable to the subject fuel assembly and
channel design.
Mechanical analyses have been performed using NRC-approved design analysis methodology
(References 1, 2, 3, and 4). The methodology permits maximum licensed assembly and fuel channel
exposures of 54 MWd/kgU (Reference 3). Documentation of compliance with the generic design criteria
using approved methods demonstrates licensing approval of the fuel design.
The fuel assembly and channel meets all mechanical compatibility requirements for use in Brunswick
Units 1 and 2. This includes compatibility with both co-resident fuel and the reactor core internals.
ATRIUM is a trademark of AREVA NP Inc.
AREVA NP Inc.