ML20077E781
| ML20077E781 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/06/1991 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC |
| Shared Package | |
| ML20077E625 | List: |
| References | |
| NUDOCS 9106110224 | |
| Download: ML20077E781 (9) | |
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e METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 201, Supplement 1 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1.
As a part of this request, proposed replacement pages for Appendix A are also included.
GPU NUCLEAR CORPORATION BY:
b hi k Vice Preside $ and Director, TM1-1 Sworn and subscribed to before me this 6th day of June 1991.
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Notary Public NotwWrag T
%mmmnhDecA4 21,19 m bue. PwverMana h d m 9106110224 910606 PDR ADOCK 05000289 p
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-2B9 LICENSE NO. DPR-50 GPU NUCLEAR This is to cortify that a copy of Technical Specification Change Request No. 201, Supplement I to Appendix A of the Operating License DPR-50 for Three Mile Island Nuclear Station Unit 1, has, on the date below, been filed with the U.S. Nuclear Regulatory Cnmmission and served to the chief executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:
Mr. Jay H. Kopp, Chairman Ms. Sally Klein, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County i
R. D. #1, Geyers Church Road Dauphin County Court House Middletown, PA 17057 Harrisburg, PA 17120 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection PA Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORFORATION i
i BY:
b Vice President khd Director, TMl-1 DATE:
June 6, 1991 l
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f14 CLOSURE TO C311-91-2043 Revision 7 Replacement Pages - Licensing Report for Pool A Reracking, TM1-1, Holtec Report H1-89407 f
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SUMMARY
_QE_ REVISIONS Holtoc Report liI-89407 EeYin19A_1 The following pages are revisodi i, 11, vi, viii, 1-2, 1-7, 2-7, 2-12, 2-19, 2-20, 2-21, 3-3, 3-5, 4-1, 4-2, 4-3, 4-4, 4-5, 4-6, 4-7, 4-8, 4-9, 4-10, 4-11, 4-12, 4-13, 4-14, 4-15, 4-16, 4-17, 4-18, 4-19, 4-20, 4-21, 4-22, 4-23, 4-24, 4-25, 4-26, 4-27, 2-28, 4-29, 4-30, 4-31, 4-32, 4-33, 4-34, 4-35, 5-25, 7-3, 10-3 0
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p HOLTEC
!NTERNATIONAL REVIEW AND CERTIFICATION LOG Li sing Report for Spent Fuel Pool DOCUMENT NAME:
Modification of Pool A: three Mile Isla51 Unit I HI-89407 HOLTEC DOCUMENT I.D. NO.
HOLTEC PROJECT NUMBER 90310 CUSTOMER / CLIENT GPU Nuclear, Inc.
REVISION BLOCK ISSUE QUALITi PROJECT C~i NO.
AUTHOR REVIEWER ASSURANCE MANAGER
& DATE
& DATE
& DATE
& DATE
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- E Y ar + })e)O REV. 7 91 t< 7&r W"fi e-,o-81
!./6 bi REV. 8 REV. 9 REV. 10 Must be Project Manager or his Designee.
NOTE:
Signatures and printed names are requirad in the review l
block.
I This document conforms to the requirements of the design l
specification and the applicable sections of the governing codes.
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TABLE OF CONTENTS
1.0 INTRODUCTION
1-1 2.0 MODULE DATA 2-1 2.1 Synopsis of New Modules 2-1 2.2 Multi-Region Storage 2-2 2.3 Material Considerations 2-4 2.3.1 Introduction 2-4 2.3.2 Structural Materials 2-4 2.3.3 Poison Material 2-4 2.3.4 Compatibility with Coolant 2-7 2.4 Existing Rack Modules and Proposed Reracking 2-7 Operation 3.0 RACK FABRICATION aND APPLICABLE CODES 3-1 3.1 Fatrication Objective 3-1 3.2 Rack Module f ar Region I 3-2 3.3 Rack Module for Region 'II 3-4 3.4 Codes, Standards and Practices 3-6 for the TMI-I Spent Fuel Pool Racks 3.5 Materials of Construction 3-8 O
4.0 CRITICALITY SAFETY ANALYSES 4-1 4.1 Design Bases 4-1 4.2 Summary of Criticality Analyses 4-4 4.2.1 Normal Operating conditions 4-4 4.2.2 Abnormal and Accident Conditions 4-5 4.3 Reference Fuel Storage Calls 4-7 4.3.1 Reference Fuel Assembly 4-7 4.3.2 Region 1 Fuel Storage Cells 4-7 4.3.3 Region 2 Fuel Storage Calls 4-7 4.4 Analytical Methodology 4-8 4.4.1 Reference Design Calculations 4-8 4.4.2 Fuel Burnup Calculations and 4-9 Uncertainties 4.4.3 Effect of Axial Burnup 4-11 l
Distribution 4.4.4 Long-term Changes in Reactivity 4-12 i
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TABLE OF CONTENTS (continued) 4.5 Region I Criticality Analyses and Tolerances 4-B 4.5.1 Nominal Design 4-D 4.5.2 Uncertainties Due to Tolerances 4 - 13 4.5.2.1 Boron Loading Tolerances 4-D 4.5.2.2 Boral Width Tolerance 4 - 14 4.5.2.3 Tolerances in Cell Lattico 4-M Spacing 4.5.2.4 Stainless Steel Thickness 4-M Tolerances 4.5.2.5 Fuel Enrichment and 4 - 15 Density Tolerances 4.5.3 Eccentric Fuel Positioning 4-b 4.5.4 Reactivity Effects of Boral 4-M Length 4.6 Region 2 Criticality Analyses 4 - 37 4.6.1 Nominal Design Case 4 - 17 O
4.6.2 Uncertainties Due to Tolerances 4 -16 4.6.2.1 Poron Loading Tolerances 4-18 4.6.2.2 Boral Width Tolerance 4-18 4.6.2.3 Tolerance in Cell Lattice 4-19 Spacing 4.6.2.4 Stainless Steel 4 19 Thickness Tolerance 4.6.2.5 Fuel, Enrichment 4-19 and Density Tolerances 4.6.3 Eccentric Fuel Positioning 4 - 19 4.6.4 Reactivity Effect of Boral length 4-20 4.7 Abnormal and Accident Conditions 4 21 4.7.1 Temperature and Water Density 4 21 Effects 4.7.2 Dropped Fuel Assembly 4 -'21 4.7.3 Lateral Rack Movement 4-27 1
4.7.4 Abnormal Location of a Fuel Assembly 4 22 4 22 l
l 4.8 References for Section
- 4-24 l O Appendix A - Benchmark Calculations A-1 11
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LIST OF TABLES IAHLE NQiREE TITLE EAGE 1.1 Discharge Schedule 1-5 1.2 Available Storage Capacity 1-6 2.1 Module Data (Region 1) 2-10 2.2 Module Data (Region 2) 2-10 2.3 Module Data for Future Region 2-11 2 Racks 2.4 Common Module Data 2-12 2.5 Module Data 2-13 2.6 Boral Experience List 2-14 (Domestic and Foreign) 2.7 1100 Alloy Aluminum Physical 2-16 Properties 2.8 Chemical Composition - Aluminum 2-17 (1100 Alloy) 2.9 Boron Carbide Chemical Composition 2-18 l
Weight, %
i Boron Carbide Physical Properties 4.1 Summary of Criticality Safety Analyses 4 -26 4.2 Reactivity Ef fects of Abnormal and Accident Conditions 4 -27 4.3 Design Basis Fuel Assembly Specifications 4-28 4.4 Allowance for Uncertainties in Reactivity Due to Depletion Calculations 4 -29 4.5 Long-Term Changes in Reactivity in l
Storage Rack Calculated by CASMO-2E 4 - 30 4.6 Puel Burnup Values for Required 4-31 Reactivities (km) with Fuel of Various Initial Enrichments 4.7 Effect of Temperature and Void on 4 -32 Calculated Reactivity of Storage Rack 5.4.1 Fuel Specific Power and Pool Capacity Data 5-19 5.4.2 Data for Scenarios 1 through 5 5-20 l
S.4.3 Data for Scenarios 1 through 5 5-21
. 5.1 Bulk Pool Temperature Resillts When 5-22 Considering Heat Losses to the Ambient Assuming 90 Tubes Plugged in Each Cooler O
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O LIST OF FIGURES FIGURE NUMBEB TITLE PAGE 1.1 Module Layout - TMI Unit I (Pool A) 1-7 2.1 Planview of THI-I Pool System 2-19 2.2 Module Layout - Pool A 2-20 2.3 Module Layout - Pool A 2-21 (Present.Reracking Campaign) 3.1 Setm Welding Precision Formed Channels 3-9 3.2 Lead-In for Region 1 Modules 3-10 3.3 Composite Box Assembly 3-11 3.4 Assembling of Region 1 Boxes 3-12 3.5 Adjustable Support Leg 3-13 3.6 Elevation View of a Region 1 Rack 3-14
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showing Two Storage Cells 3.7 Elevation View of Region 2 Rack Module 3-15 3.8 Array of Region 2 Cells (Non-Flux Trap construction) 3-16 4.1 Relationship between Initial Enrichment 4-33 and Acceptable Fuel Burnup 4.2 Cross-section of Region i Storage Cell 4-34 4.3 Cross-Section of Region 2 Storage Cell 4-35 5.5.1 Pool Bulk Temperature Model for 5-27 Normal Discharge Scenario 5.5.2 Cooler Temperature Effsetiveness p vs.
5-28 Number of Tubes Plugged 5.5.3 Bulk Pool Temperature for Case 1 5-29 5.5.4 Bulk Pool Temperature for Case 2 5-30 5.5.5 Bulk Pool Temperature for Case 3 5-31 5.5.6 Bulk Pool Temperature for Case 4 5-32 5.5.7 Bulk Pool Temperature for Case 5 5-33 5.5.8 Maximum Bulk Pool Temperature of 5-34 Case i vs. Number of Tubes Plugged in the Cooler (One Cooler in Operation) 5.5.9 Pool Water Inventory During the Loss 5-35 of Cooling Event for Case 1 O
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