ML20108E922
| ML20108E922 | |
| Person / Time | |
|---|---|
| Issue date: | 04/15/2020 |
| From: | NRC/OCIO |
| To: | |
| Shared Package | |
| ML20108E919 | List: |
| References | |
| FOIA, NRC-2020-000169 | |
| Download: ML20108E922 (153) | |
Text
AOL I EC PROPRIE I ARV INFORMATION FINAL SAFETY ANALYSIS REPORT ON THE HI-STORM FW MPC STORAGE SYSTEM By Holtec International Holtec Technology Campus One Holtec Boulevard Camden, NJ 081 04 (holtecinternational.com)
Holtec Project 5018 Holtec Report No. HI-2114830 Safety Category: Safety Significant Copyright Notice and Notice of Proprietary Information This document is a
- hted intellectual property of Holtec Inter
- a . All rights reserved.
In addition, proprietary infor is either noted oprietary or highlighted in gray.
Excerpting any part of this document, exce u lie domain citations included herein, by any person or entity except for the , a Holtec Use (HUG) member company, or a fore ign regu latory au
- with j urisdiction over a HUG mem clear faci lity w ithout o Holtec International is unlawful.
HOL~ iliNFtillRNtA6HO<NAL DOCUMENT NUMBER: HI-21 14830 PROJECT NUMBER: 5018 DOCUMENT ISSUANCE AND REVISION STATUS DOCUMENT NAME: FINAL SAFETY ANALYSIS REPORT ON THEJ HI-STORM FW MPC STORAGE SYSTEM DOCUMENT CATEGORY: ~ GENERIC 0 PROJECT SPECIFIC REVISION No. -0 REVISION No. -1 REVISION No. -2 Document No.
Portiont t Author's Date Author's Date Author's Date VIR # VIR # VIR #
Initials Approved Initials Approved Initials Approved
- l. CHAPl TSM 8/1912011 164667 VG 11/16112 354887 VG 6124113 491575
- 2. CHAP2 TSM 8/1 912011 149401 VG 11/16/12 506615 VG 6124113 198422
- 5. CHAPS HF 811912011 776910 HF 11/16112 275409 BK 6124/13 874187
- 13. CHAP13 TSM 8/1 91201 1 207404 VG 11/16112 191264 VG 6124113 787578
- 15. -
tt Chapter or section number.
DOCUMENT NUMBER: HI-2114830 PROJECT NUMBER: 5018 Form U:i~~~ ~iWl'flfSAR Page 1 of3 Holtec Form QA-18 Revision 5, June 20, 2017
HOL~ iliNFtillRNtA6HO<NAL DOCUMENT NUMBER: HI-21 14830 PROJECT NUMBER: 5018 DOCUMENT ISSUANCE AND REVISION STATUS DOCUMENT NAME: FINAL SAFETY ANALYSIS REPORT ON THEJ HI-STORM FW MPC STORAGE SYSTEM DOCUMENT CATEGORY: ~ GENERIC 0 PROJECT SPECIFIC REVISION No. -3 REVISION No. -4 REVISION No. -5 Document No.
Portiont t Author's Date Author's Date Author's Date VIR # VIR # VIR #
Initials Approved Initials Approved Initials Approved
- l. CHAPl RRN 512012014 590614 SJG 612412015 17525 SFT 6/20/2017 345861
- 2. CHAP2 RRN 512012014 408664 SJG 6124/2015 454373 SIT 6/20/2017 940353
- 3. CHAP3 CWB 512012014 37773 CWB 6/2412015 501669 CWB 6/20/2017 972964
- 6. CHAP6 VM 512012014 457513 VM 6/24/20 15 614209 VM 6/20/2017 623189
- 8. CHAPS LZ 512012014 838601 SJG 6/2412015 47 11 92 SFT 6/20/2017 532201
- 9. CHAP9 JG 512012014 81 026 SJG 6/24/20 15 617765 SFT 6/20/2017 6432 15
- 10. CHAPlO AF 512012014 680192 SJG 612412015 142858 SFT 6/20/20 17 387786
- 12. CHAP12 RRN 512012014 19906 SJG 6/2412015 298959 SFT 6/20/2017 729850
- 15. -
tt Chapter or section number.
DOCUMENT NUMBER: HI-2114830 PROJECT NUMBER: 5018 Form U:i~~~ ~iWl'flfSAR Page 2 of3 Holtec Form QA-18 Revision 5, June 20, 2017
HOL~ iliNFtillRNtA6HO<NAL DOCUMENT CATEGORIZATION In accordance with the Holtec Quality Assurance Manual and associated Holtec Quality Procedures (HQPs), this document is categorized as a:
D Calculation Package3 (Per HQP 3.2) ~ Technical Report (Per HQP 3.2)(Such as a Licensing Report)
D Design Criterion Document (Per HQP 3.4) D Design Specification (Per HQP 3.4)
D Other (Specify):
DOCUMENT FORMATTING The formatting of the contents of this document is in accordance with the instructions of HQP 3.2 or 3.4 except as noted below:
This is the standard format for a final safety analysis report per NUREG-1536 DECLARATION OF PROPRIETARY STATUS D Nonproprietary Q Holtec Proprietary D Privileged Intellectual Property (PIP)
Documents labeled Privileged Intellectual Property contain extremely valuable intellectual/commercial property ofHoltec International. T hey cannot be released to external organizations or entities without explicit approval of a company corporate officer. The recipient ofHoltec's proprietary or Top Secret document bears fu ll and undivided responsibility to safeguard it against loss or duplication.
Notes:
I. This document has been subjected to review, verification and approval process set forth in the Holtec Quality Assurance Procedures Manual. Password controlled signatures of Holtec personnel who participated in the preparation, review, and QA validation of this document are saved in the N-drive of the company's network. The Validation Identifier Record (VlR) number is a random number that is generated by the computer after the specific revision of this document has undergone the required review and approval process, and the appropriate Holtec personnel have recorded their password-controlled electronic concurrence to the document.
- 2. A revision to this document will be ordered by the Project Manager and carried out if any of its contents is materially affected during evolution of this project. The determination as to the need for revision will be made by the Project Manager with input from others, as deemed necessary by him.
- 3. Revisions to this document may be made by adding supplements to the document and replacing the "Table of Contents", this page and the "Revision Log".
Form U:i~~~ ~iWl'flfSAR Page 3 of3 Holtec Form QA-18 Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION Certificate of Compliance (1032) and Final Safety Analysis Report Matrix HI-STORM FW Final Safety Analysis Report (FSAR) NRC Certificate of Compliance (Coe) 1032 Revision Amendment No.
0 0 1 See Note 1 Below Note 2 2 0 3 1 4 1 Rev 1 5 2 Notes:
- 1) Revision 1 of the HI-STORM FW FSAR contains the safety analyses of MPC-37 and MPC-89 in support of the FW system's original certification as well as LAR# 1 and RAl#l. This Revision 1 is part of UMAX submittal under docket# 72-1040 for configuration control.
- 2) Revision 2 of the HI-STORM FW FSAR contains all EC0/72.48 changes. Revision O of the FW FSAR was the basis for creating Revision 2. If the chapter in R2 doesn't contain any EC0/72.48, then the revision is kept at RO since LAR# 1 and RAI# :1 changes are not included in Revision 2.
- 3) Revision 3 of the HI-STORM FW FSAR contains the changes related to Amendment 1. Revision 3 uses Revision 2 as the basis with all changes from Revision 2 marked with revision bars.
Using this strategy, changes already submitted in Revision 1, with docket 72-1040 may be marked as changes in this Revision 3, since they are changes from Revision 2. This ensures configuration control for docket 72-1032.
- 4) Revision 4 of the HI-STORM FW FSAR contains changes related to Amendment 1 Revision 1 and EC0/72.48 changes. Revision 4 uses Revision 3 as the basis with all changes from Revision 3 marked with revision bars.
- 5) Revision 5 of the HI-STORM FW FSAR contains changes related to Amendment 2 and EC0/72.48 changes. Revision 5 uses Revision 4 as the basis with all changes from Revision 4 marked with revision bars.
HOLTEC INTERNATIONAL COPYRrGHTED MATERIAL REPORT HI-2114830 Rev.5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HObTEC PROPRIETARY INFORMA'fteN-FSAR SECTION REVISION STATUS, LIST OF AFFECTED SECTIONS AND REVISION
SUMMARY
FSAR Report No.: HI-2114830 FSAR Revision Number: 5 FSAR
Title:
Final Safety Analysis Report on the HI-STORM FW System This FSAR is submitted to the USNRC in support of Holtec International 's application to secure a CoC under 10CFR Part 72.
FSAR review and verification are controlled at the chapter level and changes are annotated at the chapter level.
A section in a chapter is identified by two numerals separated by a decimal. Each section begins on a fresh page. Unless indicated as a "complete revision" in the summary description of change below, if any change in the content is made, then the change is indicated by a "bar" in the right page marg in and the revision number of the entire chapter including applicable figures (annotated in the footer) is changed.
A summary description of change is provided below for each FSAR chapter. Minor editorial changes to this FSAR may not be summarized in the description of change.
Chapter l (including Glossary and Notation)
Affected Current Section or Revision Summary Description of Change Table No. No.
Glossary The section has been revised per ECO 5018-66.
Table The table has been revised per ECO 50 18-40.
1.0.1 Section l.O The section has been revised per ECO 50 18-75.
Section 1.1 The section has been revised per ECO 5018-40 and 5018-54.
Paragraph The section has been revised per ECO 5018-40, 5018-54, and 5018-75.
1.2.1.2 5
Paragraph The section has been revised per ECO 5018-3 7 and 5018-73.
1.2.1.3 Paragraph The section has been revised per ECO 50 18-3 7 and 5018-73.
1.2.1.5 Paragraph The section has been revised per ECO 5018-58, 5018-75, and 5018-40.
1.2.2.l Page Sl of S8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
Paragraph The St:U l u11 11as oeen rev1M'd're1 EL.IJ '.':>01 8-37.
1.2.2.2 Table 1.2.10 The table has been revised per ECO 5018-37, 50 18-73, and 50 18-75.
Section 1.3 The section has been revised per ECO 5018-37.
Section 1.5 The section has been revised per ECO 501 8-37, 5018-40, a nd 501 8-73.
Chapter 2 Current Section or Revision Summary Description of Change Table No.
No.
Section 2.0.2 The section has been revised per ECO 501 8-45 and 50 18-73 .
Section 2.0.3 The section has been revised per ECO 501 8-3 7.
Table The table has been revised per ECO 50 18-62 and 5018-64.
2.0.1 Table The table has been revised per ECO 5018-54.
2.0.5 Table The table has been revised per ECO 501 8-37 and 73.
2.0.8 Table The table has been revised per ECO 50 18-73 .
2.0.9 Section 2.1.3 The section has been revised per ECO 501 8-6 1.
Table 2.1.2 The table has been revised per Amendment 2.
Table 2. 1.6 The table has been revised per Amendment 2.
5 Paragraph The section has been revised per ECO 501 8-37.
2.2.1.b Section 2.2.2 This section has been revised per ECO 501 8-47, 501 8-59, and Amendment 2.
Subsection The section has been revised per ECO 501 8-45 and 50 18-75.
2.2.3 Subsection The section has been revised per ECO 501 8-59.
2.2.5 Table 2.2.1 The table has been revised per ECO 5018-59.
Table 2.2.3 The table has been revised per ECO 5018-45, 5018-47, and 501 8-59.
Table 2.2.6 The table has been revised per ECO 5018-73 .
Table 2.2.7 The table has been revised per ECO 5018-59.
Page S2 ofS8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
Table 2.2.9 The L;~,t: 11as ut:t:111t:v1st:u I--'"' r;cu *,trl 8-50.
Table 2.2. J0 The table has been revised per ECO 5018-59.
Chapter 3 Current Section or Revision Summary Description of Change Table No.
No.
Paragraph The section has been revised per ECO 50 18-37 and 5018-75.
3.1.2.2 Paragraph The section has been revised per ECO 5018-40 and 50 18-54.
3.1.3.1 Paragraph The section has been revised per ECO 5018-59.
- 3. 1.3.2 Paragraph The section has been revised per ECO 50 18-3 7.
3.1.3.3 Table 3. 1. l The table has been revised per ECO 5018-37, 5018-59, and 50 18-73.
Tables 3.1.7, The tables have been revised per ECO 5018-59.
3.1.10, and 3.1.14 Tables 3.1.9 The tables have been revised per ECO 5018-40 and 5018-54.
and 3.2.I Table 3.1.12 The table has been revised per ECO 5018-40.
Section 3.2 5 The section has been revised per ECO 5018-40.
Table 3.2.4 The table has been revised per ECO 5018-3 7 and 5018-68.
Tables 3.2.5 The tables have been revised per ECO 5018-40 and 5018-54.
and 3.2.8 Tables 3.2.6 The tables have been revised per ECO 5018-37.
and 3.2.7 Paragraph The section has been revised per ECO 50 18-37, 5018-54, 5018-59, and 3.4.3.1 5018-75.
Paragraph The section has been revised per ECO 5018-3 7, 5018-40, 5018-51 , 50 18-3.4.3.2 54, and 50 18-59.
Subsection The section has been revised per ECO 50 18-45.
3.4.4 Subparagraph The section has been revised per ECO 50 18-52 and 5018-54.
3.4.4.1.2 Subparagraph The section has been revised per ECO 50 18-40, 5018-50, and 5018-54.
3.4.4.1.4 Page S3 ofS8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
Subparagraphs The s~ttt6h's' IH1.'ife B~~1 *1--ev'gett*p~r* 1::x.:u 5018-59.
3.4.4. 1.5 and 3.4.4. l .6 Subparagraph The section has been revised per ECO 5018-40 and 5018-54.
3.4.4.1.10 Subsection The section has been revised per ECO 5018-47.
3.4.12 Tables 3.4. 1, The tables have been revised per ECO 5018-59.
3.4.7, and 3.4.8 Table 3.4.2 The table has been revised per ECO 5018-37, 5018-47, and 5018-68.
Table 3.4.3 The table has been revised per ECO 5018-54.
Table 3.4.4 The table has been revised per ECO 5018-40 and 5018-54.
Tables 3.4.6, The tables have been revised per ECO 5018-40, 5018-45, and 5018-54.
and 3.4. 10 Table 3.4.9 The table has been revised per ECO 5018-47.
Table 3.4 . .16 The table has been revised per ECO 5018-40.
Table 3.4. 17 The table has been revised per ECO 5018-37.
Table 3.4.18 The table has been revised per ECO 5018-37 and 5018-68.
Figures 3.4.2, The figures have been revised per ECO 5018-59.
3.4.23, 3.4.24, 3.4.27, 3.4.29, 3.4.30, 3.4.32, 3.4.33 Figures 3.4.5, The figures have been revised per ECO 5018-40 and 5018-54.
3.4.6, 3.4.2 1, 3.4.22, and 3.4.25 Figures The figures have been revised per ECO 5018-50.
3.4.16, 3.4.17, and 3.4. 18 Section 3.8 The section has been revised per ECO 5018-40 and 5018-54.
Chapter 4 Current Section or Revision Summary Description of Change Table No.
No.
Subsection The section has been revised per ECO 5018-40 and 5018-54.
4.4.1 5 Page S4 ofS8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
Paragraphs The sections have been revised per ECO 5018-40.
4.4.1. 10 and 4.4.4. l Table 4.4.15 The table has been revised per ECO 5018-40.
Subsectio n The section has been revised per ECO 50 18-75.
4.5.l Subsectio n The section has been revised per ECO 50 18-48.
4.5.3 Table 4.5.1 The table has been revised per Amendment 2.
Section 4.6 The section has been revised per ECO 5018-45.
Paragraphs The sections have been updated per Amendment 2.
4.6.1.3 and 4.6.2.4 Tables 4.6. 1, The tables have been revised per ECO 5018-45.
4.6.2, 4.6.4.
and 4.6.5 Chapter 5 Current Section or Revision Summary Description of Change Table No.
No.
Subsection The section has been revised per ECO 5018-40 and 5018-54.
5.3.1 5
Paragraph The section has been revised per Amendment 2.
5.3.1.1 Chapter 6 Current Section or Revision Summary Description of Change Table No.
No.
Sections 6. 1, The sections have been revised per Amendment 2.
6.2, and 6.4 Tables 6.I. I, The tables have been revised per Amendment 2.
- 6. 1.4, 6.2.3, 5
6.2.5, and 6.2. 10 Subsection The section has been revised per Amendment 2.
6.B.4 Page S5 ofS8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
ll - V nm, Chapter 7 Changes Current Section or Revision Summary Description of Change Table No.
No.
4 No change.
Chapter 8 Changes Current Section or Revision Summary Description of Change Table No.
No.
Subsection T he section has been added per ECO 501 8-37.
8.4.3 Paragraph T he section has been added per ECO 5018-75.
8.4.4.1 5
Section 8.7 T he section has been added per ECO 501 8-69.
Subsection T he section has been added per ECO 501 8-69.
8.7.4 Chapter 9 Changes Current Section or Revision Summary Description of Change Table No.
No.
Subsection The section has been added per ECO 50 18-37.
9.2. 1 Paragraph The section has been added per ECO 501 8-44.
9.2.2.6 Subsection The section has been added per ECO 501 8-48.
9.2.4 Subsection T he section has been added per ECO 501 8-40, 501 8-44, and 5018-67.
9.2.6 Table 9.2.1 5 T he table has been added per ECO 5018-49.
Table 9.2.3 T he table has been added per ECO 501 8-40 and 5018-44.
Table 9.2.4 T he table has been added per ECO 50 18-44.
Table 9.2.5 T he table has been added per ECO 5018-37 and 5018-44.
Subsection The section has been added per ECO 50 18-37.
9.4. 1 Paragraph T he section has been added per ECO 501 8-44.
9.4.2.11 Page S6 of S8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
,..., .. ,_ n m, Chapter 10 Changes Current Section or Revision Sum mary Description of Change Table No.
No.
Paragraphs T he section has been added per ECO 5018-69.
10.1.1.1 and 10.1.1.5 Paragraph T he section has been added per ECO 5018-37 and 5018-73.
10.1.2. 1 Paragraph T he section has been added per ECO 5018-53.
10.1.6.2 5
Table I 0.1.3 The table has been added per ECO 50 18-37 and 5018-73.
Table I0. 1.6 T he table has been added per ECO 50 18-53.
Table 10.1.9 The table has been added per ECO 5018-69.
Subsection The section has been added per ECO 5018-44.
10.2. 1 Table 10.2.1 The table has been added per ECO 5018-37 and 5018-65.
Chapter 11 Changes Current Section or Revision Summary Description of Change Table No.
No.
Subsection The section has been added per ECO 5018-37.
11.1.2 Table I 1.2.1 5 The table has been added per ECO 5018-37.
Subsection T he section has been added per ECO 5018-45.
11.4.3 Chapter 12 Changes Current Section or Revision Summary Description of Change Table No.
No.
Section 12.1 T he section has been added per ECO Amendment 2.
Subsections The sections have been added pe r ECO Amendment 2.
- 12. l.4and 12.2. 13 5
Subsection The section has been added per ECO 5018-7 5.
12.2.1 Subsection T he section has been added per ECO 5018-45.
12.2.4 Page S7 of S8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
, __ -- . . . . ,.~ u. .. - -.
Chapter 13 Changes Current Section or Revision Summary Description of Change Table No.
No.
3 No change.
Chapter 14 Changes Current Section or Revision Summary Description of Change Table No.
No.
0 No change.
Page S8 of S8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
--t IOLTEC PROPRIETARY INFORMATION TABLE OF CONTENTS GLOSSARY OF TERMS ........................................................................................................... xii CHAPTER 1: GENERAL DESCRIPTION ............................................................................ 1-l 1.0 GENERAL INFORMATION .......................................................................................... 1- l 1.0. l Engineering Change Orders ................................................................................... 1-4
1.1 INTRODUCTION
TO THE HI-STORM FW SYSTEM .............................................. 1-24 1.2 GENERAL DESCRIPTION OF HI-STORM FW SYSTEM ........................................ 1-36 1.2.1 System Characteristics ........................................................................................ 1-36 1.2.2 Operational Characteristics ................................................................................. 1-57 1.2. 3 Cask Contents ....................................................................................................... 1-60 1.3 IDENTIFICATION OF AGENTS AND CONTRACTORS ......................................... 1-78 1.4 GENERIC CASK ARRAYS ......................................................................................... 1-82 1.5 DRAWINGS ............ ...................................................................................................... 1-90
1.6 REFERENCES
.............................................................................................................. 1-91 APPENDIX 1.A: ALLOY X DESCRIPTION CHAPTER 2: PRINCIPAL DESIGN CRITERIA ................................................................. 2-1
2.0 INTRODUCTION
........................................................................................................... 2-1 2.0.1 MPC Design Criteria .............................................................................................. 2-1 2.0.2 HI-STORM FW Overpack Design Criteria ........................................................... 2-5 2.0.3 HI-TRAC VW Transfer Cask Design Criteria ....................................................... 2-8 2.0.4 Principal Design Criteria for the ISFSJ Pad ......................................................... 2-10 2.1 SPENT FUEL TO BE STORED ................................................................................... 2-23 2.1.1 Determination of the Design Basis Fuel ............................................................... 2-23
- 2. 1.2 Undamaged SNF Specifications .......................................................................... 2-23 2.1.3 Damaged SNF and Fuel Debris Specifications .................................................... 2-23 2.1.4 Structural Parameters for Design Basis SNF ...................................................... 2-24
- 2. 1.5 Thermal Parameters for Design Basis SNF ......................................................... 2-24
- 2. 1.6 Radiological Parameters for Design Basis SNF .................................................. 2-24 2.1. 7 Criticality Parameters for Design Basis SNF ....................................................... 2-25 2.1.8 Summary of Authorized Contents ....................................................................... 2-25 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR
1 IOLTEC PROPRte:r.ARY INFORMATION 2.2 HI-STORM FW DESIGN LOADINGS ........................................................................ 2-47 2.2. l Loadings Applicable to No1ma l Conditions of Storage ....................................... 2-48 2.2.2 Loadings App licable to Off-Nonna! Conditions ................................................ 2-5 1 2.2.3 Environmental Phenomena and Accident Condition Design Criteria ................. 2-53 2.2.4 Applicability of Governing Documents .............................................................. 2-60 2.2.5 Service Limits ..................................................................................................... 2-60 2.2.6 Loads ............. ...................................................................................................... 2-61 2.2.7 Design Basis Loads .............................................................................................. 2-61 2.2.8 Allowable Limits ................................................................................................ 2-61 2.3 SAFETY PROTECTION SYSTEMS ............................................................................ 2-82 2.3.1 General ................................................................................................................ 2-82 2.3.2 Protection by Multiple Confinement Barriers and Systems ............................... 2-82 2.3.3 Protection by Equipment and Instrumentation Selection .................................... 2-83 2.3.4 Nuclear Criticality Safety ................................................................................... 2-84 2.3.5 Radiological Protection ....................................................................................... 2-85 2.3.6 Fire and Explosion Protection............................................................................. 2-86 2.4 DECOMMISSIONING CONSIDERATIONS .............................................................. 2-89 2.5 REGULATORY COMPLIANCE ................................................................................. 2-93
2.6 REFERENCES
.............................................................................................................. 2-94 CHAPTER 3: STRUCTURAL EVALUATION ..................................................................... 3-1 3.0 OVERVIEW .................................................................................................................... 3- 1 3.1 STRUCTURAL DESIGN ................................................................................................ 3-3 3 .1. 1 Discussion .............................................................................................................. 3-3 3.1.2 Design Criteria and Applicable Loads ................................................................... 3-6 3.1.3 Stress Analysis Models ........................................................................................ 3-20 3.2 WEIGHTS AND CENTERS OF GRAVITY ................................................................ 3-41 3.3 MECHANICAL PROPERTIES OF MATERIALS ...................................................... 3-54 3.3.1 Structural Materials .............................................................................................. 3-54 3.3.2 Nonstructural Materials ....................................................................................... 3-56 3.4 GENERAL STANDARDS FOR CASKS .................................................................... 3-66 3.4.1 Chemical and Galvanic Reactions ...................................................................... 3-66 3.4.2 Positive C losure .................................................................................................. 3-66 3.4.3 Lifting Devices .................................................................................................... 3-66 3.4.4 Heat ..................................................................................................................... 3-77 HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 11 HI-STORM FW SYSTEM FSAR
HOLTEC PROPRIETARY INFORMATION 3.4.5 Cold ..................................................................................................................... 3-98 3 .4 .6 Miscellaneous Evaluations................................................................................... 3-99 3.4.7 Service Life of HI-STORM FW and HI-TRAC VW ........................................ 3-100 3.4.8 MPC Service Life ............................................................................................. 3-102 3.4.9 Design and Servi.c e Life .................................................................................... 3-104 3.5 FUEL RODS ................................................................................................................ 3-174 3.6 SUPPLEMENTAL DATA .......................................................................................... 3-175 3.6.1 Calculation Packages ....................................................................................... 3-175 3.6.2 Co1nputer Progra1ns .......................................................................................... 3-175 3.7 COMPLIANCE WITH STRUCTURAL REQUIREMENTS IN PART 72 ................ 3-1 78
3.8 REFERENCES
............................................................................................................ 3-181 APPENDIX 3.A: Response of HI-STORM FW and HI-TRAC VW to Tornado Wind Load and Large Missile Impacts APPENDIX 3.B: Missile Penetration Analysis for HI-STORM FW and HI-TRAC VW APPENDIX 3.C: Code Case N-284-2 Stability Calculations for MPC Shell CHAPTER 4: THERMAL EVALUATION ............................................................................ 4- 1 4.0 OVERVIEW .................................................................................................................... 4-1 4.1 DISCUSSION .................................................................................................................. 4-4 4.2
SUMMARY
OF THERMAL PROPERTIES OF MATERIALS .................................... 4-9 4.3 SPECIFICATIONS FOR COMPONENTS ................................................................... 4-16 4.4 THERMAL EVALUATION FOR NORMAL CONDITIONS OF STORAGE ........... 4-1 8 4.4 .1 Overview of the Thermal Model.. ....................................................................... 4-18 4.4.2 Effect of Neighboring Casks ............................................................................... 4-32 4.4.3 Test Model .... ...................................................................................................... 4-34 4.4.4 Maximum and Minimum Temperatures ............................................................. 4-34 4.4.5 Maximum Internal Pressure ................................................................................ 4-37 4.4.6 Engineered Clearances to Eliminate Thermal Interferences ............................... 4-40 4.4. 7 Evaluation of System Performance fo r Normal Conditions of Storage .............. 4-4 1 4.5 THERMAL EVALUATION OF SHORT TERM OPERATIONS ............................... 4-61 4.5.l Therma lly Limiting Evolutions Dw-ing Short-Term Operations ........................ 4-61 4.5.2 HI-TRAC VW The1mal Model.. ......................................................................... 4-62 4 .5.3 Maximum Time Limit During Wet Transfer Operations ................................... 4-65 HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 lll HI-STORM FW SYSTEM FSAR
AOL I EC PROPRIE I ARV INFORMATION 4.5.4 Analysis of Limiting Thermal States During Short-Term Operations ................ 4-68 4.5.5 Cask Cooldown and Reflood Analysis During Fuel Unloading Operations ...... 4-74 4.5.6 Maximum Internal Pressure ................................................................................. 4-74 4.6 OFF-NORMAL AND ACCIDENT EVENTS .............................................................. 4-87 4.6. 1 Off-Normal Events .............................................................................................. 4-87 4.6.2 Accident Events .................................................................................................. 4-88
- 4. 7 REGULATORY COMPLIANCE ............................................................................... 4-102
- 4. 7.1 Normal Conditions of Storage .......................................................................... 4- 102
- 4. 7 .2 Short Term Operations ...................................................................................... 4-102 4.7.3 Off-Nom1al and Accident Conditions ................................................................ 4-103
4.8 REFERENCES
........ .................................................................................................... 4-104 CHAPTER 5: SHIELDING EVALUATION .......................................................................... 5-1
5.0 INTRODUCTION
........................................................................................................... 5-1 5.1 DISCUSSION AND RESULTS ...................................................................................... 5-5 5.1.1 Normal and Off-Normal Operations ..................................................................... 5-9 5.1.2 Accident Conditions ............................................................................................ 5-10 5.2 SOURCE SPECIFICATION ......................................................................................... 5-24 5 .2.1 Garntna Source .................................................................................................... 5-24 5 .2.2 Neutron Source ................................................................................................... 5-26 5.2.3 Non-fuel Hardware ............................................................................................. 5-26 5.2.4 Choice of Design Basis Assembly ....................................................................... 5-28 5.2.5 Decay Heat Load and Allowable Burnup and Cooling Times ........................... 5-28 5.2.6 Fuel Assembly Neutron Sources ......................................................................... 5-28 5.3 MODEL SPECIFICATIONS ......................................................................................... 5-41 5.3.1 Description of the Radial and Axial Shielding Configuration ............................ 5-41 5 .3 .2 Regional Densities .............................................................................................. 5-43 5.4 SHIELDING EVALUATION ....................................................................................... 5-62 5.4. l Streaming Through Radial Steel Fins ................................................................. 5-66 5.4.2 Damaged Fuel Post-Accident Shielding Evaluation ........................................... 5-66 5 .4. 3 Site Boundary Evaluation .................................................................................... 5-67 5 .4.4 Non-Fuel Hardware ............................................................................................ 5-68 5 .4. 5 Effect of Uncertainties ........................................................................................ 5-70 5.5 REGULATORY COMPLIANCE ................................................................................. 5-81 HOLTEC INTERNATIONAL COPYRIGHTED MATER JAL REPORT HI-2114830 Rev. 5 IV HI-STORM FW SYSTEM FSAR Kev1s1on o, June iU, ,:.v Ir
i IOLTEC PROPRte:r.ARY INFORMATION
5.6 REFERENCES
.............................................................................................................. 5-82 APPENDIX 5.A: SAMPLE INPUT FILES FOR SAS2H, ORIGEN-S, AND MCNP CHAPTER 6: CRITICAL)[TY EVALUATION ........................ ...... ......... ... .. .. ............ .. ......... 6-1
6.0 INTRODUCTION
........................................................................................................... 6- 1 6.1 DISCUSSION AND RESULTS ...................................................................................... 6-3 6.2 SPENT FUEL LOADING ............................................................................................. 6-13 6.2.1 Definition of Assembly Classes .......................................................................... 6-13 6.3 MODEL SPECIFICATION ........................................................................................... 6-26 6.3. l Description of Ca lculational Model.. .................................................................. 6-26 6.3.2 Cask Regional Densities ..................................................................................... 6-28 6.3.3 Eccentric Positioning of Assemblies in Fuel Storage Cells ................................ 6-29 6.4 CRITICALITY CALCULATIONS ............................................................................... 6-45 6.4. l Calculational Methodology ................................................................................. 6-45 6.4.2 Fuel Loading or Other Contents Loading Optimization .................................... 6-45 6.4.3 Criticality Results ................................................................................................ 6-48 6.4.4 Damaged Fuel and Fuel Debris ........................................................................... 6-49 6.4.5 Fuel Assemblies with Missing Rods ................................................................... 6-52 6.4.6 Sealed Rods Replacing BWR Water Rods ......................................................... 6-52 6.4.7 Non-Fuel Hardware in PWR Fuel Assemblies ................................................... 6-52 6.4.8 Neutron Sources in Fuel Assemblies .................................................................. 6-53 6.4.9 Low Enriched, Channeled BWR fuel .................................................................. 6-53 6.5 CRITICALITY BENCHMARK EXPERIMENTS ....................................................... 6-66 6.6 REGULATORY COMPLIANCE ................................................................................. 6-67
- 6. 7 REFERENCES .............................................................................................................. 6-68 APPENDIX 6.A BENCHMARK CALCULATIONS APPENDIX 6.B MISCELLANEOUS INFORMATION CHAPTER 7: CONFINEMENT ............................................................................................... 7- 1
7.0 INTRODUCTION
........................................................................................................... 7-1 7.1 CONFINEMENT BOUNDARY ..................................................................................... 7-2 7.1.l Confinement Vessel .............................................................................................. 7-2 HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 V
....l:IObTEC PROPRIETARY INFORMATION 7 .1.2 Confinement Penetrations ..................................................................................... 7-3 7.1.3 Seals and Welds ..................................................................................................... 7-3 7 .1.4 Closure .......... ........................................................................................................ 7-4 7.2 REQUIREMENTS FOR NORMAL AND OFF-NORMAL CONDITIONS OF STORAGE ......... ........................................................................................................ 7-7 7.3 CONFINEMENT REQUIREMENTS FOR HYPOTHETICAL ACCIDENT CONDITIONS ................................................................................................................. 7-8
7.4 REFERENCES
................................................................................................................ 7-9 CHAPTER 8: MATERIAL EVALUATION ............................................................... ........... 8-1
8.1 INTRODUCTION
........................................................................................................... 8- l 8.2 MATERIAL SELECTION .............................................................................................. 8-7 8.2. l Structural Materials ................................................................................................ 8-8 8.2.2 Nonstructural Materials ...................................................................................... 8-11 8.2.3 Critical Characteristics and Equivalent Materials ............................................... 8-12 8.3 APPLICABLE CODES AND STANDARDS ............................................................. 8-16 8.4 MATERIAL PROPERTIES .......................................................................................... 8-17 8.4.1 Mechanical Properties ......................................................................................... 8-17 8.4.2 Thermal Properties .............................................................................................. 8-17 8.4.3 Low Temperature Ductility offerritic Steels ..................................................... 8-18 8.4.4 Creep Properties of Materials .............................................................................. 8-19 8.5 WELDING MATERIAL AND WELDING SPECIFICATION ................................... 8-21 8.6 BOLTS AND FASTENERS .......................................................................................... 8-24 8.7 COATINGS AND CORROSION MITIGATION ......................................................... 8-25 8.7.l Environmental Conditions Applicable to Coating Selection and Evaluation Criteria ................................................................................................................ 8-25 8.7 .2 Acceptable Coatings ........................................................................................... 8-26
- 8. 7.3 Coating Application ............................................................................................ 8-2 7 8.7.4 Optional MPC Surface Treatment (Peen ing) ...................................................... 8-27 8.8 GAMMA AND NEUTRON SHIELDING MATERIALS ............................................ 8-28 8.8. l Concrete .............................................................................................................. 8-28 8.8.2 Steel ..................................................................................................................... 8-29 8.8.3 Lead ..................................................................................................................... 8-29 HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 Vl HI-STORM FW SYSTEM FSAR
HOL.TEC PROPRIETARY INFORMATION-8.8.4 Water ................................................................................................................... 8-29 8.9 NEUTRON ABSORBING MATERIALS ..................................................................... 8-30 8.9. l Qualification and Properties of Metamic-HT ..................................................... 8-30 8.9.2 Consideration of Boron Depletion ...................................................................... 8-3 1
- 8. 10 CONCRETE AND REINFORCING STEEL. ............................................................... 8-32 8.11 SEALS ........................................................................................................................... 8-33
- 8. 12 CHEMICAL AND GALVANIC REACTIONS ............................................................ 8-34
- 8. 12. l Operating Environments ................................................................................... 8-34 8.12.2 Compatibility of MPC Materials ...................................................................... 8-35
- 8. 12.3 Compatibility of HI-STORM FW Overpack Materials .................................... 8-39 8.12.4 Compatibility of HI-TRAC VW Transfer Cask Materials ............................... 8-40 8.12.5 Potential Combustible Gas Generation ............................................................. 8-41 8.12.6 Oxidation of Fuel During Loading/Unload!ing Operations ............................... 8-41 8.12.7 Conclusion ......................................................................................................... 8-42 8.13 FUEL CLADDING INTEGRITY ................................................................................. 8-43 8.13.1 Regulatory Guidance ........................................................................................ 8-43 8.13.2 Measures to Meet Regu latory Gu idance ........................................................... 8-43 8.14 EXAMINATION AND TESTING ................................................................................ 8-45 8.14.1 Helium Leak Testing of Canister & Welds ....................................................... 8-45
- 8. 14.2 Periodic Inspections .......................................................................................... 8-45 8.15 CONCLUSION ............................................................................................................... 8-46 8.16 REFERENCES .............................................................................................................. 8-4 7 APPENDIX 8.A: DATASHEETS FOR COATINGS AND PAINT CHAPTER 9: OPERATING PROCEDURES ........................................................................ 9- 1
9.0 INTRODUCTION
........................................................................................................... 9-1 9.1 TECHNICAL AND SAFETY BASIS FOR LOADING AND UNLOADING PROCEDURES ................................................................................................................. 9-3 9.2 PROCEDURE FOR LOADING THE HI-STORM FW SYSTEM IN THE SPENT FUEL POOL ......................................................................................... 9-7 9 .2.1 Overv iew of Loading Operations ........................................................................... 9-7 9.2.2 Preparation of H I-TRAC VW and MPC .............................................................. 9-10 HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 vu HI-STORM FW SYSTEM FSAR
lelOb:rEG PROPRIETARY INFORMATIOl<l 9.2.3 MPC Fuel Loading ............................................................................................... 9-11 9.2.4 MPC C losure ......................................................................................................... 9-12 9.2.5 Preparation for Storage ......................................................................................... 9-17 9.2.6 Placement of H I-STORM FW Into Storage......................................................... 9-1 8 9.3 ISFSI OPERATIONS .................................................................................................... 9-41 9.4 PROCEDURE FOR UNLOADING THE HI-STORM FW FUEL IN THE SPENT FUEL POOL ..................................................................................................... 9-42 9.4.1 Overview of HI-STORM FW System Unloading Operations ............................ 9-42 9.4.2 HI-STORM Recovery from Storage ................................................................... 9-43 9.4.3 Preparation for Unloading................................................................................... 9-44 9.4.4 MPC Unloading .................................................................................................. 9-47 9.4.5 Post-Unloading Operations ................................................................................. 9-47
9.5 REFERENCES
.............................................................................................................. 9-49 CHAPTER 10: ACCEPTANCE CRITERIA AND MAINTENANCE PROGRAM ....... 10-1
10.0 INTRODUCTION
......................................................................................................... 10-1 I 0.1 ACCEPTANCE CRITERIA ......................................................................................... I 0-2 10.1.1 Fabrication and Nondestructive Examination (NOE) ......................................... 10-2 10.1.2 Structural and Pressure Tests .............................................................................. 10-7 10.1.3 Materials Testing .............................................................................................. 10-10 10.1.4 Leakage Testing ............................................................................................... 10-1 l 10.1.5 Component Tests .............................................................................................. 10- 11 10.1.6 Shielding Integrity ............................................................................................. 10-12 10.1.7 Thermal Acceptance Tests ................................................................................ 10-16 10.1.8 Cask Identification ............................................................................................ 10-17 10.2 MAINTENANCE PROGRAM ................................................................................... 10-32 10.2.1 Structural and Pressure Parts ............................................................................ 10-32 10.2.2 Leakage Tests .................................................................................................... 10-32 10.2.3 Subsystem Maintenance .................................................................................... 10-33 10.2.4 Pressure Relief Devices .................................................................................... 10-33 10.2.5 Shielding ........................................................................................................... 10-33 10.2.6 Thennal ............................................................................................................. 10-34 10.3 REGULATORY COMPLIANCE ............................................................................... 10-36
10.4 REFERENCES
............................................................................................................ 10-37 HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 Vlll HI-STORM FW SYSTEM FSAR
I IOLTEC PROPRIETARY INFORMATION CHAPTER 11: RADIATION PROTECTION ..................................................................... 11-1
11.0 INTRODUCTION
... ...................................................................................................... 11 - l 11.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS-LOW-AS-REASONABLY EXPECTED ................................................................................. 11 - l 11.1.l Policy Considerations ......................................................................................... 11- 1 11.1.2 Radiation Exposure Criteria ................................................................................. 11-2 11.1.3 Operational Considerations ................................................................................. 11-5 11.1.4 Auxiliary/Temporary Shielding .......................................................................... 11 -6 11.2 RADIATION PROTECTION FEATURES IN THE SYSTEM DESIGN .................... 11-7 11.3 ESTIMATED ON-SITE CUMULATIVE DOSE ASSESSMENT ............................. 11- 12 11.3.1 Estimated Exposures for Loading and Unloading Operations .......................... 11 -13 11.3.2 Estimated Exposures for Surveillance and Maintenance .................................. 11-13 11.4 ESTIMATED CONTROLLED AREA BOUNDARY DOSE ASSESSMENT ............................................................................................................ 11 - 19 11.4.1 Controlled Area Boundary Dose for Normal Operations ................................. 11-19 11.4.2 Controlled Area Boundary Dose for Off-Normal Conditions .......................... 11- 19 11.4.3 Controlled Area Boundary Dose for Accident Conditions ............................... 11 -20
11.5 REFERENCES
........................................................................................................... 11-22 CHAPTER 12: ACCIDENT ANALYSIS ............................................................................. 12- l 12.0 IN TRODUCTION .......................................................................................................... 12-1 12.1 OFF-NORMAL CONDITIONS .................................................................................... 12-2 12.1.1 Off-Normal Pressures ....................................................................................... 12-2 12.1.2 Off-Nonna! Environmental Temperatures ........................................................ 12-4 12.1.3 Leakage of One Seal ......................................................................................... 12-7 12.1.4 Partial Blockage of Air Inlets ........................................................................... 12-7 12.1.5 Malfunction of FHD System ............................................................................. 12-9 12.2 ACCIDENTS ............................................................................................................... 12-1 2 12.2.l HI-TRAC VW Transfer Cask Handling Accident.. ........................................ 12-12 12.2.2 HI-STORM FW Overpack Handling Accident .............................................. 12-12 12.2.3 HI-STORM FW Overpack Non-Mechanistic Tip-Over ................................. 12-13 12.2.4 Fire .................................................................................................................. 12-14 12.2.5 Partial Blockage of MPC Basket F low Holes ................................................. 12-17 12.2.6 Tornado ........................................................................................................... 12-1 7 12.2.7 Flood ............................................................................................................... 12-20 HOLTEC INTERNATION AL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 IX HI-STORM FW SYSTEM FSAR
HOLTEC F'RO~RIETARY lt~FORMATION 12.2.8 Earthquake ...................................................................................................... 12-22 12.2.9 100% Fuel Rod Rupture ................................................................................... 12-24 12.2. l O Confinement Boundary Leakage .................................................................. 12-26 12.2.11 Explosion ...................................................................................................... 12-26 12.2.12 Lightning ....................................................................................................... 12-28 12.2.1 3 100% Blockage of Air Inlets ......................................................................... 12-29 12.2.1 4 Burial UnderDebris ...................................................................................... 12-3 1 12.2.15 Extreme Environmental Temperature ............................................................ 12-33 12.3 OTHER EVENTS .... .................................................................................................... 12-38 12.3. l MPC Re-Flood ................................................................................................ 12-38
12.4 REFERENCES
............................................................................................................ 12-41 CHAPTER 13: OPERATING CONTROLS AND LIMITS ............................................... 13-l
13.0 INTRODUCTION
......................................................................................................... 13-l 13.1 PROPOSED OPERATING CONTROLS AND LIMITS ............................................. 13- l 13.1.1 NUREG-1536 (Standard Review Plan) Acceptance Criteria ........................... 13-1 13.2 DEVELOPMENT OF OPERATING CONTROLS AND LIMITS .............................. 13-4 13.2.1 Training Modules .............................................................................................. 13-4 13.2.2 Dry Run Training .............................................................................................. 13-5 13.2.3 Functional and Operating Limits, Monitoring Instruments, and Limiting Control Settings ................................................................................................ 13-6 13.2.4 Limiting Conditions for Operation ................................................................... 13-6 13.2.5 Equipment ......................................................................................................... 13-6 13 .2.6 Surveillance Requirements ............................................................................... 13-6 13 .2.7 Design Featu.res ................................................................................................. 13-6 13.2.8 MPC ............ ...................................................................................................... 13-7 13.2.9 HI-STORM FW Overpack ................................................................................ 13-7 13.2.1 0 HI-TRAC VW Transfer Cask ........................................................................... 13-7 13.2.11 Verifying Compliance with Fuel Assembly Decay Heat, Bumup, and Cooling Time Limits ................................................................................ 13-7 13.3 TECHNICAL SPECIFICATIONS .............................................................................. 13-11
13.4 REGULATORY EVALUATION
................................................................................ 13-11
13.5 REFERENCES
............................................................................................................ 13-11 APPENDIX 13.A TECHNICAL SPECIFICATION BASES FOR THE HOLTEC HI-STORM FW MPC STORAGE SYSTEM HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 X
I IOLTEC PROPRIETARY INFORMATION CHAPTER 14: QUALITY ASSURANCE PROGRAM ..................................................... 14- 1
14.0 INTRODUCTION
......................................................................................................... 14-1 14.0. 1 Overview ..... ...................................................................................................... 14- 1 14.0.2 Graded Approach to Quality Assurance ........................................................... 14-2
14.1 REFERENCES
.............................................................................................................. 14-3 HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 Xl HI-STORM FW SYSTEM FSAR
HOLTEO PROPRleT,A.RY INFORMATION GLOSSARY ALARA is an acronym for As Low As Reasonably Achievable Ancillary or Ancillary Equipment is the genetic name of a device used to carry out short term operations.
Bottom Lid means the removable lid that fastens to the bottom of the HI-TRAC VW transfer cask body to create a gasketed barrier against in-leakage of pool water in the space around the MPC.
BWR is an acronym for Boiling Water Reactor.
CG is an acronym for center of gravity.
Commercial Spent Fuel or CSF refers to nuclear fuel used to produce energy in a commercial nuclear power plant.
Confinement Boundary is the outline formed by the a ll-welded cylindrical enclosure of the MPC shell, MPC baseplate, MPC lid, MPC port cover plates, and the MPC closure ring which provides redundant sealing.
Confinement System means the Multi-Purpose Canister (MPC) which encloses and confines the spent nuclear fuel during storage.
Controlled Area means that area immediately surrounding an ISFSI for which the owner/user exercises authority over its use and within which operations are performed.
Cooling Time (or post-irradiation cooling time) for a spent fuel assembly is the time between reactor shutdown and the time the spent fuel assembly is loaded into the MPC.
Critical Characteristic means a feature of a component or assembly that is necessary for the proper safety function of the component or assembly. Critical characteristics of a material are those attributes that have been identified, in the associated material specification, as necessary to render the material's intended function.
DAS is the abbreviation for the Decontamination and Assembly .S.tation. It means the location where the Transfer Cask is decontaminated and the MPC is processed (i.e., where all operations culminating in lid and closure ring weld ing are comp leted).
DBE means Design Basis Earthquake.
DCSS is an acronym for Dry Cask Storage System.
HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 Xll HI-STORM FW SYSTEM FSAR
letObTEG PROPRIETARY INFORMATIOl<l Damaged Fuel Assembly is a fuel assembly with known or suspected cladding defects, as determined by review of records, greater than pinhole leaks or hairline cracks, empty fue l rod locations that are not replaced with dummy fuel rods, missing structural components such as grid spacers, whose structural integrity has been impaired such that geometric rearrangement of fuel or gross fa ilure of the cladding is expected based on engineering evaluations, or those that cannot be handled by normal mean s. Fuel assemblies that cannot be handled by normal means due to fuel cladding damage are considered fuel debris.
Damaged Fuel Container (or Canister) or DFC means a specially designed enclosure for damaged fuel or fuel debris which permits flow of gaseous and liquid media while m inimizing dispersal of gross particulates .
Design Basis Load (DBL) is a loading which bounds one or more events that are applicable to the storage system during its service life.
Design Heat Load is the computed heat rejection capacity of the HI-STORM system with a ce1tified MPC loaded with CSF stored in uniform storage with the ambient at the nonnal temperature and the peak cladding temperature (PCT) limit at 400°C. The Design Heat Load is less than the thermal capacity of the system by a suitable margin that reflects the conservatism in the system thermal analysis.
Design Life is the minimum duration for whic h the component is engineered to perform its intended function set forth in this SAR, if operated and ma intained in accordance with this SAR.
Design Report is a document prepared, reviewed and QA validated in accordance with the provisions of 10CFR72 Subpa1t G. The Design Report shall demonstrate compliance with the requirements set forth in the Design Specification. A Design Report is mandatory for systems, structures, and components designated as Important to Safety. The SAR serves as the Design Report for the HI-STORM FW System.
Design Specification is a document prepared in accordance with the quality assurance requirements of 10CFR72 Subpart G to provide a complete set of design criteria and functional requirements for a system, structure, or component, designated as Important to Safety, intended to be used in the operation, implementation, or decommissioning of the HI-STORM FW System.
The SAR serves as the Des ign Specification for the HI-STORM FW System.
Enclosure Vessel (or MPC Enclosure Vessel) means the pressure vessel defined by the cylindrical shell, baseplate, port cover plates, lid, closure ring, and associated welds that provides confinement for the contents within the MPC. The Enclosure Vessel (EV) and the fue l basket together constitute the multi-purpose canister.
Equivalent (or Equal) Material is a material with critical characteristics (see defin ition above) that meet or exceed those specified for the designated materia l.
HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 Xlll HI-STORM FW SYSTEM FSAR
I IOLTEC PROPRIETARY INFORMATION Fracture Toughness is a property which is a measure of the ability of a material to limit crack propagation under a suddenly applied load.
FSAR is an acronym for Final Safety Analysis Report (10CFR72).
Fuel Basket means a honeycombed structural weldment with square openings which can accept a fuel assembly of the type for which it is designed.
Fuel Building is the generic term used to denote the building in which the fuel loading and where pa1t of "short-term operations" will occur. The Fuel Building is a Part 50 controlled structure.
Fuel Debris is ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting these loose fuel assembly parts, or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.
Fuel Spacer or Shim is a metallic part interposed in the space between the fuel and the MPC cavity at either the top or the bottom (or both) ends of the fuel to minimize the axial disp lacement of the SNF within the MPC due to longitudinal inertia forces.
High Burnup Fuel, or HBF is a commercial spent fuel assembly with an average burnup greater than 45,000 MWD/MTU.
HI-TRAC VW transfer cask or HI-TRAC VW means the transfer cask used to house the MPC during MPC fuel loading, unloading, drying, sealing, and on-site transfer operations to a HI-STORM storage overpack or HI-ST AR storage/transportation overpack. The HI-TRAC shields and protects the loaded MPC.
HI-STORM overpack or storage overpack means the cask that receives and contains the sealed multi-purpose canisters containing spent nuclear fuel for long term sotrage. It provides the gamma and neutron shielding, ventilation passages, missile protection, and protection against natural phenomena and accidents for the loaded MPC.
HI-STORM FW System consists of any loaded MPC model placed within the HI-STORM FW overpack.
Important to Safety (ITS) means a function or condition required to store spent nuclear fuel safely; to prevent damage to spent nuclear fuel during handling and storage, and to provide reasonable assurance that spent nuclear fuel can be received, hand led, packaged, stored, and retrieved without undue risk to the health and safety of the public.
HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 XlV HI-STORM FW SYSTEM FSAR
I IOLTEC PROPRIETARY INFORMATION Independent Spent Fuel Storage Installation (ISFSI) means a facility designed, constructed, and licensed for the interim storage of spent nuclear fue l and other radioactive materials associated with spent fuel storage in accordance with 10CFR72.
License Life means the duration for which the system is authorized by virtue of its certification by the U.S. NRC.
Long-term Storage means the time beginning after on-site handling is complete and the loaded overpack is at rest in its designated storage location on the ISFSI pad.
Lowest Service Temperature (LST) is the minimum metal temperature of a part for the specified service condition.
Maximum Reactivity means the highest possible k-effective including bias, uncertainties, and calculational statistics evaluated for the worst-case combination of fuel basket manufacturing tolerances.
MET AMIC is a trade name for an aluminum/boron carbide composite neutron absorber materia l qualified for use in the MPCs and in wet storage applications.
METAMIC-HT is the trade name for the metal matrix composite made by imbedding nano-partic les of a luminum oxide and fine boron carbide powder on the grain boundaries of aluminum resulting in improved structural strength properties at elevated temperatures.
METCON' is a trade name for the HI-STORM overpack strncture. The trademark is derived from the metal-concrete composition of the HI-STORM overpack.
MGDS is an acronym for Mined Geological Disposal System.
Minimum Enrichment is the minimum assembly average enrichment. Axial blankets are not considered in determining mfoimum enrichment.
Moderate Burnup Fuel, or MBF is a commercial spent fuel assembly with an average bumup less than or equal to 45,000 MWD/MTU.
Multi-Purpose Canister or MPC means the sealed canister consisting of a honeycombed fuel basket for spent nuclear fuel storage, contained in a cylindrical canister shell (the MPC Enclosure Vessel). There are different MPCs with different fuel basket geometries fo r storing PWR or BWR fue l, but all MPCs have identical exterior diameters. The MPC is the confinement boundary for storage conditions.
MPC Transfer means transfer of the MPC between the overpack and the transfer cask which begins when the MPC is lifted off the HI-TRAC bottom lid and ends when the MPC is supported from beneath by the overpack (or the reverse).
HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 xv HI-STORM FW SYSTEM FSAR
--t'10LTEC PROPRIETARY l~IFORMATION NDT is an acronym fo r Nil Ductility Transition Temperature, which is defined as the temperature at which the fracture stress in a material with a small flaw is equal to the yield stress in the same material if it had no flaws.
Neutron Absorber is a generic term to indicate any neutron absorber material qualified for use in the HI-STORM FW System.
Neutron Shielding means a material used to thermalize and capture neutrons emanating from the radioactive spent nuclear fuel.
Non-Fuel Hardware is defined as Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Devices (TPDs), Control Rod Assemblies (CRAs), Axial Power Shaping Rods (APSRs), Wet Annular Burnable Absorbers (W ABAs), Rod Cluster Control Assemblies (RCCAs), Control Element Assemblies (CEAs), Neutron Source Assemblies (NSAs), water displacement guide tube plugs, orifice rod assemblies, Instrument Tube Tie Rods (ITTRs), vibration suppressor inserts, and components of these devices such as individual rods.
Planar-Average Initial Enrichment is the average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.
Plain Concrete is concrete that is unreinforced.
Post-Core Decay Time (PCDT) is synonymous with cooling time.
PWR is an acronym for pressurized water reactor.
Reactivity is used synonymously with effective neutron multiplication factor or k-effective.
Regionalized Fuel Storage is a term used to describe an optimized fuel loading strategy wherein the storage locations are ascribed to distinct regions each with its own maximum allowable specific heat generation rate.
Removable Shielding Girdle is an ancillary designed to be installed to provide added shielding to the personne l working in the top region of the transfer cask.
SAR is an acronym for Safety Analysis Report.
Service Life means the duration for which the component is reasonably expected to perform its intended function, if operated and maintained in accordance with the provisions of this FSAR.
Service Life may be much longer than the Design Life because of the conservatism inherent in the codes, standards, and procedures used to design, fabricate, operate, and maintain the component.
HOLTEC INTERNATIONAL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 XVI HI-STORM FW SYSTEM FSAR
I IOLTEC PROPRIETARY INFORMATION Short-term Operations means those normal operational evolutions necessary to support fuel loading or fu el unloading operations. These include, but are not limited to MPC cavity drying, helium backfill, MPC transfer, and onsite handling of a loaded HI-TRAC VW transfer cask or HI-STORM FW overpack.
Single Failure Proof in order for a lifting device or special lifting device to be considered single failure proof, the design must follow the guidance in NUR EG-0612, which requires that a single failure proof device have twice the normal safety margin. This designation can be achieved by either providing redundant devices (load paths) or providing twice the design factor as required by the applicable code.
SNF is an acronym for spent nuclear fuel.
SSC is an acronym for Structures, Systems and Components.
STP is Standard Temperature and Pressure conditions.
TAL is an acronym for the I hreaded Anchor 1ocation. TALs are used in the HI-STORM FW and HI-TRAC VW casks as well as the MPCs.
Thermo-siphon is the term used to describe the buoyancy-driven natural convection circulation of he lium w ithin the MPC fue l basket.
Traveler means the set of sequential instructions used in a controlled manufacturing program to ensure that all required tests and examinations required upon the completion of each significant manufacturing activity are performed and documented for archival reference.
Undamaged Fuel Assembly is defined as a fuel assembly without known or suspected cladding defects greater than pinhole leaks and hairline cracks, and which can be handled by nonnal means. Fuel assemblies without fuel rods in fuel rod locations shall not be classified as Intact Fuel Assemblies unless dummy fuel rods are used to disp lace an amount of water greater than or equal to that displaced by the fuel rod(s).
Uniform Fuel Loading is a fuel loading strategy where any authorized fuel assembly may be stored in any fuel storage location, subject to other restrictions in the CoC, such as those applicable to non-fuel hardware, and damaged fuel containers.
ZPA is an acronym for zero period acceleration.
ZR means any zirconium-based fuel cladding material authorized for use in a commercial nuclear power plant reactor. Any reference to Zircaloy fuel cladding in this FSAR applies to any zirconium-based fuel cladding material.
HOLTEC INTERNATION AL COPYRIGHTED MATERJAL REPORT HI-2114830 Rev. 5 xvu HI-STORM FW SYSTEM FSAR
I IOLTEC PROPRIETARY INFORMATION CHAPTER 1: GENERAL DESCRIPTION 1.0 GENERAL INFORMATION This final safety analysis report (FSAR) describes the Holtec International HI-STORM FW System and contains the necessary information and analyses to support a United States Nuclear Regulatory Commi ssion (USNRC) licensing review as a spent nuclear fuel (SNF) dry storage cask under the provisions of 10 CFR 72 [1.0.1 ). Th is report, prepared pursuant to 10 CFR 72.230, describes the basis for NRC approval and issuance of a Certificate of Compliance (CoC) on the HI-STORM FW System under l OCFR 72, Subpart L to safely store spent nuclear fuel (SNF) at an Independent Spent Fuel Storage Installation (ISFSI) under the general license authorized by 10 CFR 72, Subpart K.
This report has been prepared in the format and content suggested in NRC Regulatory Guide 3.61
[ 1.0.2) and NUREG-1536 Standard Review Plan for Dry Cask Storage Systems [1.0.3). The only deviation in the format from the formatting instruction in Reg. Guide 3.61 is the insertion of a chapter (Chapter 8) on material compatibility pursuant to ISG- 15 and renumbering of all subsequent chapters. Rev 1A of NU REG 1536, available only as a draft document at the time of the initial composition of this report (Rev 0), has also been consulted to ensure conformance.
The p urpose of this chapter is to provide a general description of the design features and storage capabilities of the HI-STORM FW System, drawings of the structures, systems, and components (SSCs), designation of their safety c lassification, and the qualifications ofthe ce1tificate holder. This report is also suitable for incorporation into a site-specific Safety Analysis Report, which may be submitted by an applicant for a site-specific l OCFR 72 license to store SNF at an ISFSI or a facility that is similar in obj ective and scope.
Table 1.0.1 provides the principal components of the HI-STORM FW System. An MPC ( containing either PWR or BWR fuel) is placed inside the HI-STORM FW overpack for long term storage. The overpack provides shieldi ng, allows for convective cooling, and protects the MPC. The HI-TRAC VW transfer cask is used for MPC transfer and also provides shielding and protection while the MPC is being prepared for storage.
Table 1.0.2 provides a matrix of the topics in NUREG-1536 and Regulatory Guide 3 .61, the corresponding 10 CFR 72 requirements, and a reference to the applicable report section that addresses each topic.
The HI-STORM FW FSAR is in full compliance with the intent of all regulatory requirements listed in Section III of each chapter ofNUREG-1536. However, an exhaustive review of the provisions in NUREG-1536, particularly Section IV (Acceptance Criteria) and Section V (Review Procedures) has identified certain minor deviations in the method of compliance. Table 1.0.3 lists these deviations, along with a discussion of the approach for compliance, and justification. The justification may be in the form of supporting analysis, established industry practice, or other NRC guidance documents.
Each chapter in this FSAR provides a clear statement with respect to the extent of compliance to the NUREG-1536 provisions. (The extent of compliance with NUREG- 1536 in this docket mirrors that HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-1 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION in Docket No. 72-1014.)
The Glossary contains a listing of the terminology and notation used in this FSAR.
The safety evaluations in this FSAR are intended to bound the conditions that exist in the vast majority of domestic power reactor sites and potential away-from-reactor storage sites in the contiguous United States. This includes the potential fuel assemblies which will be loaded into the system and the environmental conditions in which the system will be deployed. This FSAR also provides the basis for component fabrication and acceptance, and the requirements for safe operation and maintenance of the components, consistent with the design bases and safety analyses documented herein. In accordance with 10CFR72, Subpart K, site-specific implementation of the generically certified HI-STORM FW System requires that the licensee perform a site-specific evaluation, as defined in 10CFR72.212. The HI-STORM FW System FSAR identifies a number of conditions that are site-specific and are to be addressed in t he licensee's IOCFR72.212 evaluation.
These include:
- Siting of the ISFSI and design of the storage pad and security system. Site-specific demonstration of compliance with regulatory dose limits. Implementation of a site-specific ALARA program.
- An evaluation of site-specific hazards and design conditions that may exist at the ISFSI site or the transfer route between the plant's cask receiving bay and the ISFSI. These include, but are not limited to, explosion and fire hazards, flooding conditions, land sl ides, and lightning protection.
- Detem1ination that the physical and nucleonic characteristics and the condition of the SNF assemblies to be stored meet the fuel acceptance requirements of the Certificate of Compliance.
- An evaluation of interface and design conditions that exist within the plant's Fuel Building in which canister fuel loading, canister closure, and canister transfer operations are to be conducted in accordance with the applicable 10CFR50 requirements and technical specifications for the plant.
- Detailed site-specific operating, maintenance, and inspection procedures prepared in accordance with the generic procedures and requirements provided in Chapters 9 and 10, and the Certificate of Compliance.
- Performance of pre-operational testing.
- Implementation of a safeguards and accountability program in accordance with 10CFR73.
Preparation of a physical security plan in accordance with l OCFR73.55.
- Review of the reactor emergency plan, quality assurance (QA) program, training program, and radiation protection program.
In presenting the bounding generic analyses of this safety report, selected conditions are drawn from authoritative sources such as Regulatory Guides and NUREGs, where available. For example, the wind and tornado characteristics are excerpted from Reg. Guide 1.76 [l.0.4].
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-2 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HO! IEC PROPRIETARY INFORMATION For analyses that do not have a prescribed acceptance limit or bounding condition, illustrative calculations are can-ied ou t w ith a fuel type most commonly used at reactor sites. The Reference SNF for PWR and BWR fuel types are listed in Table 1.0.4. These Reference SNF assemblies are used when fixed limits for compliance are not established by regulations, such as dose rates.
Where the analysis must demonstrate compliance with a fixed limit, s uch as the reactivity limit of 0.95 in criticality analysis, the most limiting fuel type is used in the analysis. The Design Basis Fuel (Table 2. 1.4) may differ depending on the analysis being performed (e.g., thermal, structural, etc ...).
Thus, broadly speaking, the analyses in this FSAR belong to two categories:
a . Those that are performed to satisfy a specific set o f hard limits in the regulations or the Standard Review Plan.
- b. Those that are rep resentati ve in nature and intended to demonstrate the acceptability of the analysis models and capabil ity of the system.
Within this report, all figures, tables and references cited are identified by the double decimal system m.n.i, where m is the chapter number, n is the section number, and i is the sequential number. Thus, for example, Figure 1.2.3 is the third figure in Section 1.2 of Chapter 1. Similarly, the following deci-numeric convention is used in the organization of chapters:
a . A chapter is identified by a who le numeral, say m (i.e., m=3 means Chapter 3).
- b. A section is identifi ed by one decimal separating two numerals. Thus, Section 3.1 is a section in Chapter 3.
- c. A subsection has three numerals separated by two decimals. Thus, Subsection 3.2. 1 is a subsection in Sectio n 3.2.
- d. A paragraph is denoted by four numerals separated by three decimals. Thus, Paragraph 3.2.1.1 is a paragraph in Subsection 3.2.1.
- e. A subparagraph has five numerals separated by four decimals. Thus, Subparagraph 3.2. 1.1.1 is a part of Paragraph 3.2. l. J.
Tables and figures associated with a section are placed after the text narrative. Complete sections are replaced if any material in the section is changed. The specific changes are appropriately annotated.
Drawing packages are controlled separately within the Ho ltec QA program and have individual revision numbers. If a drawing is revised in support of the current FSAR revision, that drawing is included in Section 1.5 at its latest revision level. Upon issuance of the CoC, drawings and text matter in this FSAR may be revised between formal updates under the 10CFR 72.48 process. All changes to the FSAR including the drawings are subject to a rigorous configuration control under the Company's QA program.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-3 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION 1.0.1 Engineering Change Orders The changes authorized by the Holtec ECOs (with corresponding 10CFR72.48 evaluations, if applicable) listed in the following table are reflected in thi s Revision of the FSAR.
LIST OF ECO'S AND APPLICABLE 10CFR72.48 EVALUATIONS Affected Item ECO Number 72.48 Evaluation or Screenin2 N umber MPC-89 Basket l Ol-6Rl 1021 MPC-37 Basket - -
MPC Enclosure Vessel 101 -19 1138 101-21 1164 101-22Rl NIA 102-1 9 1138 102-2 1 1164 102-23Rl 1212 102-24Rl NIA HI-STORM FW Overpack 100-1 5 1118 I00- 16Rl 1089 100-17Rl NIA 100-1 8Rl 1153 100-19 1159 100-20 1180 100-21 1193 100-23 1199 100-24 1203 I 00-25 1255 100-26Rl 1274 Hl-TRACVW 103-18 1246 General FSAR Changes 5018-37 1123 50l8-40Rl 111 8 5018-44 1120 5018-45 1124 5018-47Rl 1150 5018-48Rl 1136 5018-49 1137 5018-50 1148 501 8-5 1 1164 5018-52 1168 5018-53 1178 5018-54R3 1180 5018-58Rl 1204 501 8-59 1194 HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-4 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEG PROPRIET.ARY IMFORMAJIQN LIST OF ECO'S AND APPLICABLE 10CFR72.48 EVALUATIONS (Cont'd)
Affected Item ECO Number 72.48 Evaluation or Screenin2 Number General FSAR Changes (Cont'd) 5018-61 NIA 5018-62 1203 5018-63 1205 50 18-64 NIA 5018-65 1209 5018-66 NIA 5018-67 NIA 5018-68 1219 5018-69 1238 5018-73 NIA 5018-75 NIA HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOI IFC PROPRl6TA,RY INFORMATlmJ TABLE 1.0.1 HI-STORM FW SYSTEM COMPONENTS Item Desi2nation (Model Number)
Overpack HI-STORM FW (Includes Standard & Version XL)
PWR Multi-Purpose Canister MPC-37 BWR Multi-Purpose Canister MPC-89 Transfer Cask HI-TRACVW HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-6 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION TABLE 1.0.2 REGULA TORY COMPLIANCE CROSS REFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Requirement FSAR
- 1. General Description 1.1 introduction 1.lll. l General Description 10CFR72.24(b) I. I
& Operational Features 1.2 General Description I.HI.I General Description I OCFR72.24(b) 1.2
& Operational Features 1.2. 1 Cask Characteristics 1.111. l General Description 10CFR72.24(b) 1.2.l
& Operational Features 1.2.2 Operational Features l .lll. l General Description l OCFR72.24(b) 1.2.2
& Operational Features 1.2.3 Cask Contents l.lll.3 DCSS Contents 10CFR72.2(a)(l ) 1.2.3 10CFR72.236(a) 1.3 Identification of l .III.4 Qualification of the 10CFR72.24U) 1.3 Agents & Contractors Applicant I OCFR72.28(a) 1.4 Generic Cask Arrays I.IILI General Description IOCFR72.24(c)(3) 1.4
& Operational Features 1.5 Suoolemental Data I .TTJ.2 Drawings I OCFR72.24(c)(3) 1.5 NA l.lll.6 Consideration of IOCFR72.230(b) I.I Transport 10CFR72.236(m)
Requirements NA 1.lll.5 Quality Assurance I OCFR72.24(n) 1.3
- 2. Principal Desi2n Criteria 2.1 Spent Fuel To Be 2.HI.2.a Spent Fuel 10CFR72.2(a)(l) 2.1 Stored Specifications 10CFR72.236(a) 2.2 Design Criteria for 2. II I.2.b External Conditions, Environmental 2.m .3.b Structural, I OCFR72. I 22(b) 2.2 Conditions and 2.Ill.3.c Thennal 10CFR72.122(c) 2.2.3 Natural Phenomena 10CFR72. 122(b)(I) 2.2 10CFR72. l 22(b)(2) 2.2.3 I OCFR72.122(h)(I) 2.0 2.2. 1 Tornado and Wind 2.111.2.b External Conditions 10CFR72.122(b) (2) 2.2.3 Loading HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-7 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HObTEC PROPRIETARY INFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS R EFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Requirement FSAR 2.2.2 Water Level (Flood) 2.Til.2.b External Conditions 10CFR72.122(b)(2) 2.2.3 2.III.3.b Structural 2.2.3 Seismic 2.lH.3.b Structural I OCFR 72. 102(t) 2.2.3 10CFR72.122(b)(2) 2.2.4 Snow and lee 2.111.2.b External Conditions 10CFR72.122(b) 2.2. l 2.IIl.3.b Structural 2.2.5 Combined Load 2.TTT.3.b Structural 10CFR72.24(d) 2.2.7 10CFR72.1 22(b)(2)(ii)
NA 2.111. l Structures, Systems, 10CFR72.122(a) 1.5 and Components l OCFR72.24(c)(3)
Important to Safety NA 2.Jll.2 Design Criteria for l OCFR72.236(g) 2.0, 2.2 Safety Protection 10CFR72.24(c)( I)
Systems l OCFR72.24(c)(2) 10CFR72.24(c)(4) 10CFR72. I 20(a) 10CFR72.236(b)
NA 2.lll.3.c Thermal 10CFR72.128(a) (4) 2.3.2.2, 4.0 NA 2.TTT.3.f Operating Procedures 10CFR72.24(t) t 1.0, 9.0 IOCFR72.128(a)(5) 10CFR72.236(h) 9.0 10CFR72.24( I)(2) 1.2.1, l.2.2 I OCFR72.236(1) 2.3.2.1 10CFR72.24(e) u.o, 9.0 IOCFR72.104(b) 2.lll.3.g Acceptance Tests & 10CFR72.122(1) 10.0 Maintenance 10CFR72.236(g) 10CFR72.122(f) 10CFR72. 128(a)(1) 2.3 Safety Protection -- -- 2.3 Systems 2.3. 1 General -- -- 2.3 2.3.2 Protection by 2.IlI.3.b Structural 10CFR72.236(1) 2.3.2 Multiple Confinement Barriers and Systems 2.UI.3.c Thermal 10CFR72.236(t) 2.3.2.
2.Ill.3.d Shielding/ 10CFR72.126(a) 2.3.5 Confinement/ 10CFR72.128(a)(2)
Rad iation Protection 10CFR72. 128(a) (3) 2.3.2 HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS REFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Req uirement FSAR 10CFR72.236(d) 2.3.2, 2.3.5 I0CFR72.236(e) 2.3.2 2.3.3 Protection by 2.HI.3 .d Shield ing/ 10CFR72.122(h) (4) 2.3.5 Equipment & Confinement/ 10CFR72.122(i)
Instrument Selection Radiation Protection 10CFR72.128(a)(l) 2.3.4 Nuclear Criticality 2.111.3.e Critical ity 10CFR72.124(a) 2 .3.4, 6.0 Safety I0CFR72.236(c) 10CFR72. l24(b) 2.3.5 Radiological 2.Ill.3.d Shielding/ I OCFR72.24(d) 11.4.1 Protection Confinement/ I OCFR72.104(a)
Radiation Protection I OCFR72.236(d) 10CFR72.24(d) 11.4.2 10CFR72.106(b) 10CFR72.236(d) 10CFR72.24(m) 2.3 .2.1 2.3.6 Fire and Explosion 2.TTI.3.b Structural 10CFR72.122(c) 2.3.6, 2.2.3 Protection 2.4 Decommissioning 2.Ill.3.h Decommissioning 10CFR72.24(f) 2.4 Considerations 10CFR72.130 I OCFR 72.236(h)
- 14. IIL l Design I OCFR72. 130 2.4 14.III.2 Cask I OCFR72.236(i) 2.4 Decontamination (I)
- 14. Hl .3 Financial Assurance 10CFR72.30
& Record Keeping (I) 14.111.4 License Tennination 10CFR72.54
- 3. Structural Evaluation
- 3. 1 Structural Design 3.III.l SSC Important to 10CFR72.24(c)(3) 3.1 Safety 10CFR72.24( c)(4) 3.TTT.6 Concrete Structures 10CFR72.24(c) 3.1 3.2 Weights and Centers 3.V. I .b.2 Structural Design -- 3.2 of Gravity Features 3.3 Mechanical 3.V.l.c Structural Materials 10CFR72.24(c)(3) 3.3 Properties of 3.V.2.c Structural Materials Materials HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-9 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC PROPRIETARY INFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS R EFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Requirement FSAR NA 3.Til.2 Radiation, Shielding, 10CFR72.24(d) 3.4.4 Confinement, and 10CFR72.124(a) 3.4.7 Subcriticality I OCFR72.236(c) 3.4.10 10CFR72.236(d) 10CFR72.236(1)
NA 3.IIl.3 Ready Retrieval 10CFR72.122(f) 3.4.4 10CFR72.122(h) 10CFR72.122(1)
NA 3.lll.4 Design-Basis I0CFR72.24(c) 3.4.7 Ea1t hquake 10CFR72.102(f)
NA 3.HI.5 20 Year Minimum 10CFR72.24(c) 3.4. l J DesiITTJ Length 10CFR72.236(12:) 3.4.12 3.4 General Standards for -- -- 3.4 Casks 3.4. 1 Chemical and 3.V. l .b.2 Structural Design -- 3.4. 1 Galvanic Reactions Features 3.4.2 Positive Closure -- -- 3.4.2 3.4.3 Lifting Devices 3. V. l .ii(4)(a) Tmnnions -- 3.4.3 3.4.4 Heat 3. V. l.d Structural Analysis 10CFR72.24(d) 3.4.4 10CFR72.122(b) 3.4.5 Cold 3.V. l .d Structural Analysis 10CFR72.24(d) 3.4.5 10CFR72.122(b) 3.5 Fuel Rods -- 10CFR72.122(h)(l) 3.5
- 4. Thermal Evaluation 4.1 Discussion 4.llJ Regulatory I OCFR72.24(c)(3) 4.1 Requirements 10CFR72.128(a)(4) 10CFR72.236(f) 10CFR72.236(h) 4.2 Summary of Thermal 4.V.4.b Material Properties -- 4.2 Properties of Materials 4.3 Specifications for 4.1V Acceptance Criteria 10CFR72.122(h)( l ) 4.3 Components ISG-11 , Revision 3 4.4 Thermal Evaluation 4.TV Acceptance Criteria 10CFR72.24(d) 4.4, 4.5 for Normal lSG-11 , Revision 3 IOCFR72.236(g)
Conditions of Storage HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-10 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMA I ION TABLE 1.0.2 REGULATORY C OMPLIANCE CROSS R EFERENCE M ATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Req uirement FSAR NA 4.IV Acceptance Criteria 10CFR72.24(d) 4.6 for off-nonnal and 10CFR72.122(c) accident conditions 4.5 Supplemental Data 4.Y.6 Supplemental Info. -- --
- 5. Shieldine: Evaluation 5.1 Discussion and -- 10CFR72.104(a) 5.1 Results 10CFR72. 106(b) 5.2 Source Specification 5.Y.2 Radiation Source -- 5.2 Definition 5.2. 1 Gamma Source 5.Y.2.a Gamma Source -- 5.2. l 5.2.2 Neutron Source 5.Y.2.b Neutron Source -- 5.2.2 5.3 Model Specification 5.Y.3 Shielding Model -- 5.3 Specification 5.3. 1 Description of the 5.V.3.a Configuration of the IOCFR72.24(c)(3) 5.3. 1 Radial and Axial Shielding and Source Shielding Configurations 5.3.2 Shield Regional 5. V .3.b Material Properties 10CFR72.24(c)(3) 5.3.2 Densities 5.4 Shielding Evaluation 5.Y.4 Shielding Analysis 10CFR72.24(d) 5.4 10CFR72.104(a)
I OCFR72. l 06(b) 10CFR72. l 28(a)(2)
I OCFR72.236(d) 5.5 Supplemental Data 5.Y.5 Supplemental Info. -- Appendix 5.A
- 6. Criticality Evaluatiion
- 6. 1 Discussion and -- -- 6.1 Results 6.2 Spent Fuel Loading 6.V.2 Fuel Specification -- 6.1, 6.2 6.3 Model Specifications 6.V.3 Model Specification -- 6.3 6.3. 1 Description of 6. V .3 .a Configuration 10CFR72. l24(b) 6.3. I Calculational Model 10CFR72.24(c)(3) 6.3 .2 Cask Regional 6.V.3.b Material Properties 10CFR72.24(c)(3) 6.3.2 Densities 10CFR72.124(b) 10CFR72.236(g) 6.4 Criticality 6.Y.4 Criticality Analysis I OCFR72.124 6.4 Calculations H O LTEC INTERNATIONAL C OPYRIGHTED MA TERTAL REPORT HI-2114830 R ev. 5 1-11 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS REFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Requirement FSAR 6.4. 1 Calculational or 6.V.4.a Computer Programs 10CFR72.1 24 6.4. 1 Experimental Method 6.V.4.b Multiplication Factor 6.4.2 Fuel Loading or Other 6. V.3.a Confi guration -- 6.4.2, 6.3.3, Contents Loading 6.4.4 to Optimization 6.4.9 6.4.3 Criticality Results 6.lV Acceptance Criteria I OCFR72.24(d) 6.1 IOCFR72.124 IOCFR72.236(c) 6.5 Critical Benchmark 6.V.4.c Benchmark -- 6.5, Experiments Comparisons Appendix 6.A, 6.4.3 6.6 Supplemental Data 6.V.5 Supplemental Info. -- Appendix 6.B
- 7. Confinement 7.1 Confinement 7.Ill. I Description of JOCFR72.24(c)(3) 7.0, 7.1 Boundary Structures, Systems 10CFR72.24( I) and Components Important to Safety ISG-18
- 7. l.1 Confinement Vessel 7.III.2 Protection of Spent I OCFR72. l 22(h)(I) 7.1 , 7.l.1 Fuel Cladding 7.1.2 Confinement -- -- 7.1.2 Penetrations 7.1.3 Seals and Welds -- -- 7.1.3 7.1.4 Closure 7.lll.3 Redundant Sealing 10CFR72.236(e) 7. 1.1, 7.1.4 7.2 Requirements for 7.III.7 Evaluation of 10CFR72.24(d) 7.1 Normal Conditions of Confinement System 10CFR72.236(l )
Storage ISG-18 7.2. 1 Release of 7.Hr.6 Release of Nuclides I OCFR72.24( I)( I) 7. I Radioactive to the Environment Material 7.1U.4 Monitoring of I OCFR72.122(h)(4) 7.l.4 Confinement System 10CFR72.128(a)(l) 7.ITT.5 Instrumentation 10CFR72.24(1) 7.1 .4 l OCFR72.122(i) 7.lll.8 Annual Dose JSG-18 10CFR72.104(a) 7.1 7 .2.2 Pressurization of -- -- 7. 1 Confinement Vessel HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-12 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS REFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Requirement FSAR 7.3 Confinement 7.Til.7 Evaluation of 10CFR72.24(d) 7. 1 Requirements for Confinement System 10CFR72. l 22(b)
Hypothetical Accident lSG-18 I OCFR72.236(1)
Conditions 7.3.1 Fission Gas Products -- -- 7.1 7.3.2 Release of Contents ISG-18 -- 7.1 NA -- 10CFR72.106(b) 7.1 7.4 Supplemental Data 7.Y Supplemental Info. -- --
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-13 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HO! IEC PROPRIET,t\RY INFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS R EFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Req uirement FSAR
- 8. Material Evaluation NA X.5. 1 General Considerations 10CFR72.24(c)(3)
(ISG- 15) I OCFR 72.236(m) 10CFR72.122(a)
IOCFR72.104(a) 8.1 10CFR72.106(b) 10CFR72.124 10CFR72. l 28(a)(2)
X.5.2 Materials Selection 10CFR72.236(m)
(ISG-15) 10CFR72. I 22(a)
IOCFR72.104(a) 10CFR72.106(b)
I OCFR72. l24 8.2, 8.3, 8.4, 10CFR72.128(a)(2) 8.5, 8.6, 8.7, 10CFR72.122(a) 8.9, 8.10, I OCFR72. I22(b) 8.11 I OCFR72. I 22(c) 10CFR72.236(g) 10CFR72.236(1) 10CFR72.236(h)
X.5.3 Chemical and Galvanic 10CFR72.236(m)
Reactions (ISG-15) 10CFR72.122(a) 10CFR72.122(b) 10CFR72.122(c) 8.1 2 10CFR72.236(h) 10CFR72. l 22(h)(l) 10CFR72.236(m)
X.5.4 Cladding Integrity IOCFR72.236(rn)
(ISG- 15) 10CFR72.122(a)
(lSG-1 J) l OCFR72. J22(b) 10CFR72.122(c) 8.13 I OCFR72.24(c)(3) 10CFR72.236(g)
IOCFR72.236(h)
- 9. Operating Procedures 8.1 Procedures for 8.lll.J Develop Operating 10CFR72.40(a)(5) 9.0 et. seq.
Loading the Cask Procedures 8.lll.2 Operational 10CFR72.24(e) 9.2 Restrictions for 10CFR72.104(b)
ALARA HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1- 14 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS R EFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Requirement FSAR 8.Til.3 Radioactive Effluent 10CFR72.24( I)(2) 9.2 Control 8.lH.4 Written Procedures 10CFR 72.2 l 2(b)(9) 9.2 8.HI.5 Establish Written 10CFR72.234(f) 9.2 Procedures and Tests 8.IIl.6 Wet or Dry Loading l OCFR72.236(h) 9.2 and Unloading Compatibility 8.111. 7 Cask Design to 10CFR72.236(i) 9.2, 9.4 Facilitate Decon 8.2 Procedures for 8.ITI.1 Develop Operating I OCFR72.40(a)(5) 9.4 Unloading the Cask Procedures 8.TIT.2 Operational I OCFR72.24(e) 9.4 Restrictions for l OCFR72. l 04(b)
ALARA 8.Jll.3 Radioactive Effluent 10CFR72.24( I)(2) 9.4 Control 8.lll.4 Written Procedures 10CFR72.2 12(b) (9) 9.0 8.TTT.5 Establish Written I OCFR72.234(f) 9.0 Procedures and Tests 8.111.6 Wet or Dry Loading l OCFR72.236(h) 9.0 and Unloading Compatibility 8.lll.8 Ready Retrieval 10CFR72. 122(1 ) 9.4 8.3 Preparation of the -- -- 9.3.2 Cask 8.4 Supplemental Data -- -- Tables 9. 1.1 NA 8.HI.9 Design to Minimize l OCFR72.24(f) 9.2, 9.4 Radwaste I OCFR72. I 28(a)(5) 8.IIl. l O SSCs Permit 10CFR72.122(f) Table 9.1.6 lnspection, Maintenance, and Testing
- 10. Acceptance Criteria and Maintenance Program 9.1 Acceptance Criteria 9.JlJ.1.a Preoperational 10CFR72.24(p) 9. 1, 10.1 Testing & Initial Operations 9.lll. l.c SSCs Tested and l OCFR72.24(c) 10.l Maintained to IOCFR72. I22(a)
Appropriate Quality Standards HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-15 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS R EFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Requirement FSAR 9.Til. l .d Test Program 10CFR72.162 I0.1 9.lll. l .e Appropriate Tests 10CFR72.236(1) l 0.1 9.lH. l.flnspection for Cracks, I OCFR72.236U) JO.I Pinholes, Voids and Defects 9.III. I .g Provisions that I OCFR72.232(b) IO. I (2>
Permit Commission Tests 9.2 Maintenance Program 9.111.1 .b Maintenance IOCFR72.236(g) 10.2 9.JTI. I .c SSCs Tested and 10CFR72.122(f) 10.2 Maintained to I OCFR72.128{a){l)
Appropriate Quality Standards 9.111. 1.h Records of 10CFR72.2 l 2(b)(8) 10.2 Maintenance (J)
NA 9.Jll.2 Resolution of Issues 10CFR72.24(i)
Concerning Adequacy of Reliability
\'I/
9.lll. l .d Submit Pre-Op Test 10CFR72.82(e)
Results to NRC 9.JII. I .i Casks Conspicuously I OCFR72.236(k) 10. 1.7, and Durably Marked I 0.1. l.(12) 9.Ul.3 Cask Identification
- 11. Radiation Protection
Exposures are as Low IOCFR72.104(b) as Reasonably 10CFR72.126(a)
Achievable (ALARA) 10.2 Radiation Protection 1O.V.1.b Design Features 10CFR72.126(a)(6) 11.2 Design Features 10.3 Estimated Onsite 10.111.2 Occupational 10CFR20.1201 11.3 Collective Dose Exposures 10CFR20. 1207 Assessment I OCFR20.1208 10CFR20.1 30 I N/A 1O.ITI.3 Public Exposure 10CFR72. 104 11.4 10CFR72.106 I O. IIl. 1 Effluents and Direct 10CFR72. 104 Radiation
- 12. Accident Analyses HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-16 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS R EFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Requirement FSAR 1 I. I Off-Normal Operations 1 I .TU.2 Meet Dose Limits for 10CFR72.24(d) 12. l Anticipated Events 10CFR72.104(a)
I OCFR72.236(d) 1 I .Ill.4 Maintain Subcritical I0CFR72. l 24(a) 12. 1 Condition 10CFR72.236(c) 11.III.7 Instrumentation and 10CFR72.122(i) 12.l Control for Off-Normal Condition 11.2 Accidents 11.111.1 SSCs Important to 10CFR72.24(d)(2) 12.2 Safety Designed for 10CFR72.122b(2)
Accidents I OCFR72.122b(3) 10CFR72.122(d)
I OCFR72.122(g) 11 .111.5 Maintain 10CFR72.236(1) 12.2 Confi nement for Accident 11 .111.4 Maintain Subcritical 10CFR72.1 24(a) n.2,6.0 Condition 10CFR72.236(c) 11 .JTT.3 Meet Dose Limits I OCFR72.24(d)(2) 12.2, 5. 1.2, for Accidents 10CFR72.24(m) 7.3 10CFR72.106(b) 11.III.6 Retrieval 10CFR72.122(1) 9.4 (5) 11.TTT.7 Tnstmmentation and I OCFR72.122(i)
Control for Accident Conditions NA 11 .III.8 Confinement 10CFR72.122h(4) 7.1.4 Monitoring
- 13. Operating Controls and Limits
- 12. I Proposed Operating -- IOCFR72.44(c) 13.0 Controls and Limits 12.III. I .e Administrative I OCFR72.44(c)(5) 13.0 Controls 12.2 Development of 12.IIl. l General Requirement 10CFR72.24(g) 13.0 Operating Controls for Technical IOCFR72.26 and Limits Specifi cations 10CFR72.44(c) 10CFR72 Subpart E I OCFR72 Subpart F HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1- 17 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMA I ION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS R EFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Req uirement FSAR 12.2. 1 Functional and 12.TII. l .a Functional/ 10CFR72.44(c)( I) Appendix Operating Limits, Operating Units, 13.A Monitoring Monitoring Instruments, and Instruments and Limiting Control Limiting Controls Settings 12.2.2 Limiting Conditions 12.ITT. 1.b Limiting Controls I OCFR72.44( c)(2) Appendix for Operation 13.A 12.Ill.2.a Type of Spent Fuel 10CFR72.236(a) Appendix 13.A 12.III.2.b Enrichment
- 12. llI .2.c Burnup 12.TH.2.d Minimum Acceptance Cooling Time
- 12. IIl.2.f Max imum Spent Fuel Loading Limit 12.Ill.2g Weights and Dimensions
- 12. III.2.h Condition of Spent Fuel 12.IIJ.2e Maximum Heat 10CFR72.236(a) Appendix Dissipation 13.A 12.lII.2.i lnerting Atmosphere IOCFR72.236(a) Appendix Requirements 13.A 12.2.3 Surveillance 12.ITI. I .c Surveillance I OCFR72.44(c)(3) Chapter 13 Specifications Requirements 12.2.4 Design Features 12.Ill. l.d Design Features I0CFR72.44(c)(4) Chapter 13 12.2.4 Suggested Format -- -- Appendix for Operating 13.A Controls and Limits NA 12.IIJ.2 SSC Design Bases I OCFR72.236(b) 2.0 and Criteria NA 12. lll.2 Criticality Control IOCFR72.236(c) 2 .3.4, 6.0 NA 12.ITT.2 Shielding and 10CFR20 2 .3.5, 7.0, Confinement 10CFR72.236(d) 5.0, 10.0 NA 12. Ill.2 Redundant Sealing I OCFR72.236(e) 7 . .1 , 2.3.2 NA 12. III.2 Passive Heat 10CFR72.236(t) 2.3.2.2, 4.0 Removal H O LTEC INTERNATIONAL COPYRIG HTED MA TERTAL REPORT HI-2114830 R ev. 5 1-18 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HO! IEC PROPRIETARY l~IFORMATION TABLE 1.0.2 REGULATORY COMPLIANCE CROSS REFERENCE MATRIX Applicable HI-Regulatory Guide 3.61 Associated NUREG- 10CFR72 STORM Section and Content 1536 Review Criteria or 10CFR20 FW Requirement FSAR NA 12.TII.2 20 Year Storage and 10CFR72.236(g) 1.2.1.5, 9.0, Maintenance 3.4.10, 3.4. 11 NA 12. Ill .2 Decontamination 10CFR72.236(i) 9.0, 11.1 NA 12. Ul.2 Wet or Dry Loading 10CFR72.236(h) 9.0 NA 12.Ill.2 Confinement 10CFR72.236U) 9.0 Effectiveness NA 12. m.2 Evaluation for 10CFR72.236(1) 7.1 , 7.2, Confinement 10.0
- 14. Quality Assurance 13.J Quality Assurance 13.IIJ Regulatory 10CFR72.24(n) 14.0 Requirements I OCFR72.140(d) 13.IV Acceptance Criteria 10CFR72, Subpart G HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-19 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION Notes:
-( l l - The stated requirement is the responsibility of the licensee (i.e., utility) as part of the ISFSI pad and is therefore not addressed in this appl ication.
(2)
[tis assumed that approval of the FSAR by the NRC is the basis for the Commission' s acceptance of the tests defined in Chapter I 0.
(3)
Not applicable to HI-STORM FW System. The functional adequacy of all important to safety components is demonstrated by analyses.
(4)
The stated requirement is the responsibility of licensee (i.e., utility) as part of the lSFSI and is therefore not addressed in this application.
(5)
The stated requirement is not applicable to the HI-STORM FW System. No monitoring is required for accident conditions.
" " There is no correspond ing NUREG-1536 criteria, no applicable I OCFR72 or I OCFR20 regulatory requirement, or the item is not addressed in the FSAR.
"NA" There is no Regulatory Guide 3.61 section that corresponds to the NUREG-1536, 10CFR72, or 10CFR20 requirement being addressed.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-20 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HO! r ec PROPRleT,t\RY INFORMATION TABLE 1.0.3 ALTERNATNES TO NUREG-1536 A lternate Method to NUREG-1536 Guidance Meet NUREG-1536 Justification Intent 2.V.2.(b)(3)(f) " 10CFR Part 72 A site-specific safety In accordance with NUREG-1536, identifies several other natural analysis of the effects of 2.V.(b)(3)(f), ifseiche, tsunami, and phenomena events (including seiche, tsunami, and hurricane are not addressed in the seiche, tsunami, and hurricane) hurricane on the HI- FSAR and they prove to be that should be addressed for STORM FW system must applicable to the site, a safety spent fuel storage." be performed prior to use analysis is required p rior to approval if these events are for use of the DCSS under either a applicable to the site. site-specific, or general license.
3.V.1.d.i.(2)(a), page 3-11, The HI-STORM system All lifting and handling devices are "Drops with the axis generally components are lifted and also required to meet the ANSI or vertical should be analyzed for handled by lifting applicable code provisions to render both the conditions of a flus h equipment that meet the the potential of a drop event in the impact and an initial impact at a applicable provisions in part 72 jurisdiction non-credible.
comer of the cask. .. " NUREG-0612 and ANSI N14.6, as required, to preclude an uncontrolled lowering of the load.
3.V.2.b.i.(l), Page 3-19, Para. l , HI-STORM FW, like HI- Concrete is provided in the HI-
"All concrete used in storage STORM 100, uses plain STORM overpack primarily for the cask system lSFSls, and subject concrete. The structural purpose of radiation shielding, the to N RC review, should be function is rendered by a reinforcement in the concrete will reinforced ... " double wall shell of only serve to create locations of carbon steel. The primary micro-voids that will increase the steel shell structure is emitted dose from the cask.
designed to meet ASME Appendix l.D of the HI-STORM Section III, Subsection NF l 00 FSAR which provides technical stress limits for all normal and placement requirements on plain service conditions. concrete is also invoked for Hf-STORM FW concrete.
- 4. V.5.c, Page 4-10, Para. 3 "free All free volume Calculati ng the volume occupied by volume calculations should calculations use nominal the fuel assemblies using maximum account for thermal expansion of Confinement Boundary weights and minimum densities the cask internal components and dimensions, but the conservatively over predicts the the fuel when subjected to volume occupied by the volume occupied by the fuel and accident temperatures. fuel assemblies is correspondingly under predicts the calculated using maximum remaining free volume.
weights and minimum densities.
H O LTEC INT ERNATIONAL COPYRIG HTED M A TERTA L REP OR T H I-2 114830 Rev. 5 1-21 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION TABLE 1.0.3 ALTERNATIVES TO NUREG-1536 Alternate Method to NUREG-1536 Guidance Meet NUREG-1 536 Justification Intent
- 7. V.4 "Confinement Analysis. No confinement leakage The MPC uses redundan t c losures to Review the applicant's analysis is performed and assure that there is no release of confinement analysis and the no effluent dose at the radioactive materials under all resulting annual dose at the controlled area boundary credible conditions. Analyses controlled area boundary." is calculated. presented in Chapters 3 and 1 1 demonstrate that the Confinement Boundary does not degrade under all normal, off-normal, and accident conditions. Multiple inspection methods arc used to verify the integrity of the Confinement Boundary (e.g., non-destructive examinations and pressure testing).
Helium leakage testing of the MPC base metals (shell, baseplate, and MPC lid) and MPC she ll to baseplate and shell to shell welds is performed on the unloaded MPC.
Pursuant to !SG-18, the Holtec MPC is constructed in a manner that precludes leakage from the Confinement Boundary. Therefore, no analysis of leakage from confinement is required.
13 .lll, " the application must Chapter 14 incorporates The NRC has approved the Holtec include, at a minimum, a the NRC-approved Holtec Quality Assurance Program Manual description that satisfies the International Quality under 10 CFR 71 (NRC QA requirements of IO CFR Part 72, Assurance Program Program Approval for Radioactive Subpart G, 'Qual ity Manual by reference. Material Packages No. 0784, Rev.
Assurance' ... 3). Pursuant to IOCFR 72. 140(d),
Holtec will apply this QA p rogram to all important-to-safety dry storage cask activities.
HOLTEC INTERNATIONAL COPYRIGHTED MA TERTAL REPORT HI-2 114830 Rev. 5 1-22 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I-IOLTl::C PROPRIETARY INFORMATION TABLE 1.0.4 REFERENCE SNF DESIGNATIONS Fuel Type Fuel ID PWR W 17xl 7 BWR GE lOxlO HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-23 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC PROPRIETARY INFORMATIOl<l
1.1 INTRODUCTION
TO THE HI-STORM FW SYSTEM This section and the next sect ion (Section 1.2) provide the necessary information on the HI-STORM FW System pursuant to 10CFR72 paragraphs 72.2(a)(l),(b); 72.122(a),(h)(l); 72.140(c)(2);
72.230(a),(b); and 72.236(a),(c),(h),(m).
HI-STORM (acronym for Holtec International Storage Module) FW System is a spent nuclear fuel storage system designed to be in full compliance with the requirements of 10CFR72. The model designation "FW" denotes this as a system which has been specifically engineered to withstand sustained flood and Wind.
The HI-STORM FW System consists of a sealed metallic multi-purpose canister (MPC) contained within an overpack constructed from a combination of steel and concrete. The design features of the HI-STORM FW components are intended to simplify and reduce the on-site SNF loading and handling work effort, to minimize the bW'den of in-use monitoring, to provide utmost radiation protection to the plant personnel, and to minimize the site bounda1y dose.
The HI-STORM FW System can safely store either PWR or BWR fuel assemblies, in the MPC-37 or MPC-89, respectively. The MPC is identified by the maximum number of fuel assemblies it can contain in the fuel basket. The MPC external diameters are identical to allow the use of a single overpack design, however the height of the MPC, as well as the overpack and transfer cask, are variable based on the SNF to be loaded.
Figure 1.1.1 shows the HI-STORM FW System with two of its major constituents, the MPC and the storage overpack, in a cut-away view. The MPC, shown partially withdrawn from the storage overpack, is an integrally welded pressure vessel designed to meet the stress limits of the ASME Boiler and Pressure Vessel Code,Section III, Subsection NB [1.1.l]. The MPC defines the Confinement Boundary for the stored spent nuclear fuel assemblies. The HI-STORM FW storage overpack provides structw*al protection, cooling, and radiological shielding for the MPC.
The HT-STORM FW overpack is equipped with thru-wall penetrations at the bottom ofthe overpack.
The exit air passageway is located in the body of the standard lid. The "Version XL" (extra-large) lid and "Domed" lid are variants of the standard lid design with the exit air passageway located at the bottom of the lid near the cask body interface to pennit effic ient, natural circulation of air to cool the MPC and the contained SNF. The HI-STORM FW System is autonomous inasmuch as it provides SNF and radioactive material confinement, radiation shielding, criticality control and passive heat removal independent of any other facil ity, structures, or components at the site. The surve illance and maintenance required by the plant's staff is minimized by the HI-STORM FW System since it is completely passive and is composed of proven materials. The HI-STORM FW System can be used either singly or as an array at an ISFSI. The site for an ISFSI can be located either at a nuclear reactor faci lity or an away-from-a-reactor (AFR) location.
The information presented in this report is intended to demonstrate the acceptability of the HI-STORM FW System for use under the general license provisions of Subpart K by meeting the criteria set forth in 10CFR72.236.
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-24 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION The HI-STORM FW overpack is designed to possess certain key elements of flexibility to achieve ALARA. For example:
- The HI-STORM FW overpack is stored at the ISFSI pad in a vertical orientation, which helps minimize the size of the ISFSI and leads to an effective natural convection cooling flow around the exterior and also in the interior of the MPC.
- The HI-STORM FW overpack handling operations do not require the cask to be downended at any time which eliminates the associated handling risks and fac ilitates compliance with radiation protection objectives.
- The HI-STORM FW overpack can be loaded with the MPC containing SNF using the HI-TRAC VW transfer cask and prepared for storage while inside the 10CFR50 [ 1.1.2] facility. From the 10CFR50 facility the loaded overpack is then moved to the ISFSI and stored in a vertical configuration. The overpack can also be directly loaded using the HI-TRAC VW transfer cask adjacent to the ISFSI storage pad. Some examples of MPC transfer between the FW overpack and the HI-TRAC VW transfer cask are illustrated in Figures 1.1.2 (transfer at the cask transfer facility) and 1.1.3 (transfer in the plant's egress (truck/rail) bay).
The HI-STORM FW overpack features an inlet and outlet duct configuration engineered to mitigate the sensitivity of wind direct ion on the thermal performance of the system. More specifically, the standard HI-STORM FW overpack features a radially symmetric outlet vent (located in its lid) pursuant to Holtec' s Patent Number 7,330,526B2 and inlet ducts arranged at 45-degree intervals in the circumferential direction to approximate an axisymmetric opening configuration, to the extent possible. The HI-STORM FWVersion XL lid is similar in design to the standard overpack lid, but it provides greater outlet flow area and enhanced shielding against sky shine. The Domed lid features the same outlet design as Version XL but has a thicker section of steel and concrete directly above the canister, enhancing its shielding performance against sky shine compared to the XL lid.
A number of design measures are taken in the HI-STORM FW System to limit the fuel cladding temperature rise under a most adverse flood event (i.e., one that is just high enough to block the inlet duct):
- a. The overpack's inlet duct is narrow and does not allow a direct pathway through the overpack, therefore the MPC stands directly on the overpack's baseplate. This allows floodwater to come in immediate contact with the bottom of the MPC and assist the ventilation air flow in cooling the MPC.
- b. The overpack's inlet duct is tall and the MPC stands directly on the overpack's baseplate, which is welded to the overpack's inner and outer shells. Thus, if the flood water rises high enough to block air flow through the inlet ducts, substantial surface area of the lower region of the MPC will be submerged in the water. Although heat transfer from the exterior of the MPC through air circu lation is limited in such a scenario, the reduction is offset by convective cooling through the floodwater itself.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-25 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION
- c. The MPCs are equipped with internal thermosiphon capability, which brings the heat emitted by the fuel back to the bottom region of the MPC as the circulating helium flows along the downcomer space around the fuel basket. This thermos.iphon action places the heated helium in c lose thermal communication with the floodwater, further enhancing convective cooling via the floodwater.
The above design features of the HI-STORM FW System are subject to intellectual property protection rights (patent rig hts) under United States Patent and Trademark Office (USPTO) regulations.
Regardless of the storage cell count, the constrnction of the MPC is fundamentally the same; the basket is a honeycomb structure comprised of cellular elements. This is positioned within a circumscribing cylindrical canister shell. The egg-crate construction and cell-to-canister shell interface employed in the MPC basket impart the structural stiffness necessary to satisfy the limiting load conditions discussed in Chapter 2. Figures 1.1.4 and 1.1.5 provide cross-sectional views of the PWR and BWR fuel baskets, respectively. Figures 1.1.6 and 1.1.7 provide isometric perspective views of the PWR and BWR fuel baskets, respectively.
The HI-TRAC VW transfer cask is required for shielding and protection of the SNF during loading and closure of the MPC and during movement of the loaded MPC from the cask loading area of a nuclear plant spent fuel pool to the storage overpack. Figure 1.1.8 shows a cut away view of the transfer cask. The MPC is placed inside the HI-TRAC VW transfer cask and moved into the cask loading area of nuclear plant spent fuel pools for fuel loading (or unloading). The HI-TRAC VW /MPC assembly is designed to prevent (contaminated) pool water from entering the nan*ow annular space between the HI-TRAC VW and the MPC while the assembly is submerged. The HI-TRAC VW transfer cask also allows dry loading (or unloading) of SNF into the MPC in a hot eel I.
To summarize, the HI-STORM FW System has been engineered to:
- maximize shielding and physical protection for the MPC;
- maximize resistance to flood and wind;
- minimize the extent of handling of the SNF;
- minimize dose to operators during loading and handling;
- require minimal ongoing surveillance and maintenance by plant staff;
- permit rapid and unencumbered decommissioning of the ISFSI; HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-26 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HO! IEC PROPRIETARY INFORMATION Finally, design criteria for a forced helium dehydration (FHD) system, as described in Appendix 2.B of the HI-STORM 100 FSAR [1.1.3] is compatible with HI-STORM-FW. Thus, the references to a FHD system in this FSAR imply that its design criteria must comply with the provisions in the latest revision of the HI-STORM l 00 FSAR (Docket No. 72-10 14).
All HI-STORM FW System components ( overpack, transfer cask, and MPC) are designated ITS and their sub-components are categorized in accordance with NUREG/CR-6407 [1.1.4].
The principal ancillaries used in the site implementation of the HI-STORM FW System are summarized in Section 1.2 and referenced in Chapter 9 in the context ofloading operations. A listing of common ancillaries needed by the host site is provided in Table 9.2.1. The detailed desi.gn of these ancillaries is not specified in this FSAR. In some cases, there are multiple distinct ancillary designs available for a particular application (such as a forced helium dehydrator or a vacuum drying system for drying the MPC) and as such, not every anci llary will be needed by every site. Ancillary designs are typically specific to a site to meet ALARA and personnel safety objectives.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-27 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HQJ rec PROPRIET,A,RY INFORMATION TOP LID WITH AXISYMMETRIC AIR PASSAGE MPC LID MPC CLOSURE RING MPC FUEL BASKET INLET AIR VENT FIGURE 1.1.1: HI-STORM FW VVM AND MPC-37 IN CUTAWAY VIEW HOLTEC ]NTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 Rt:v. 5 1-28 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION FIGURE 1.1 .2: MPC TRANSFER AT THE CANISTER TRANSFER FACILITY (PIT)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 R~v. 5 1-29 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEO PROPRIETARY INFORMATION FIGURE 1.1.3: MPC TRANSFER IN THE PILANT'S EGRESS BAY HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 Rt!v. 5 1-30 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
MObTEC PROPRIETARY l~IFORMATION THERMOSIPHON FLOW SLOTS BASKET SHIM (TYPICAL)
FIGURE 1.1 .4: MPC-37 IN CROSS SECTION HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 R~v. 5 1-3 1 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRleT.ARY INFORMAIION THERMOSIPHON FLOW SLOTS BASKET SHIM
{TYPICAL)
FIGURE 1.1.5: MPC-89 IN CROSS SECTION HOLTEC ]NTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 R~v. 5 1-32 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEO PROPRIETARY INFORMATION FIGURE 1.1.6: PWR FUEL BASKET (37 STORAGE CELLS) IN PERSPECTIVE VIEW HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 Rev. 5 1-33 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRleT.ARY INFORMATION FIGURE 1.1.7: BWR FUEL BASKET (89 STORAGE CELLS) IN PERSPECTIVE VIEW HOLTEC ]NTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 Rt!V. 5 1-34 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HO! IEC PROPRIETARY INEORMAIION TOP FLANGE \ INNER SHELL THREADED ANCHOR
\ (C.S.J LOCATIONS (TYPICAL)
RECESSED COUPLING RECESSED FOR COUPLING RUPTURE FOR DISC RELIEF VALVE LEAD SHIELDING OUTER SHELL (C.S .)
INTERMEDIATE SHELL (C.S.)
(WATER JACKET)
BOTIOM LID BOTTOM LID BOLT (TYPICAL)
FIGURE 1.1 .8: CUTAWAY VIEW OF HI-TRAC VW HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 Rev. 5 1-35 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEG PROPRle:r.ARY lf)IFORMAJIQN 1.2 GENERAL DESCRIPTION OF HI-STORM FW SYSTEM 1.2.1 System Characteristics The HI-STORM FW System consists of interchangeable MPCs, which maintain the configuration of the fuel and is the confinement boundary between the stored spent nuclear fuel and the environment; and a storage overpack that provides structural protection and radiation shielding during long-tenn storage of the MPC. In addition, a transfer cask that provides the structural and radiation protection of an MPC during its loading, unloading, and transfer to the storage overpack is also subject to certification by the USNRC. Figure 1.1. l provides a cross sectional view of the HI-STORM FW System with an MPC inserted into HI-STORM FW. Both casks (storage overpack and transfer cask) and the MPC are described below. The description includes information on the design details significant to their functional performance, fabrication techniques and safety features. All structures, systems, and components of the HI-STORM FW System, which are identified as Impo1tant-to-Safety (ITS), are specified on the licensing drawings provided in Section 1.5.
There are three types of components subject to certification in the HI-STORM FW docket (see Table 1.0.1 ).
- 1. The multi-purpose canister (MPC)
- 11. The storage overpack (HI-STORM) 111. The transfer cask (HI-TRAC)
A listing of the common ancillaries not subject to ce1tification but which may be needed by the host site to implement this system is provided in Table 9.2.1.
To ensure compatibility with the HI-STORM FW overpack, MPCs have identical external diameters.
Due to the differing storage contents of each MPC, the loaded weight differs among MPCs (see Table 3.2.4 for loaded MPC weight data). Tables 1.2.1 and 1.2.2 contain the key system data and parameters for the MPCs.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-36 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION The HI-STORM FW System shares certain common attributes with the HI-STORM 100 System, Docket No. 72- 1014, namely:
- 1. the honeycomb des ign of the MPC fuel basket~
- 11. the effective distribution of neutron and gamma shielding materials within the system; u1. the high heat dissipation capability; iv. the engineered features to promote convective heat transfer by passive means;
- v. a structurally robust steel-concrete-steel overpack construction.
The honeycomb design of the MPC fue l baskets renders the basket into a multi-flange egg-crate strncture where all strnctural elements (i.e. , cell walls) are arrayed in two orthogonal sets of plates.
Consequently, the walls of the cells are either completely co-planar (i.e., no offset) or orthogonal with each other. There is complete edge-to-edge continuity between the contiguous cells to promote conduction of heat.
The composite shell construction in the overpack, steel-concrete-steel, allows ease of fabrication and eliminates the need for the sole reliance on the strength of concrete.
A description of each of the components is provided in this section, along with fabrication and safety feature information.
1.2.1.1 Multi-Purpose Canisters The MPC enclosure vessels are cylindrical weldments with identical and fixed outside diameters.
Each MPC is an assembly consisting of a honeycomb fuel basket (Figures 1.1.6 and 1.1. 7), a baseplate, a canister shell, a lid, and a closure ring. The number of SNF storage locations in an MPC depends on the type of fuel assembly (PWR or BWR) to be stored in it.
Subsection 1.2.3 and Table 1.2.1 summarize the allowable contents for each MPC model listed in Table 1.0. 1. Subsection 2.1.8 provides the detailed specifications for the contents authorized for storage in the HI-STORM F W System. Drawings for the MPCs are provided in Section 1.5.
The MPC enclosure vessel is a fu lly welded enclosure, which provides the confinement for the stored fuel and radioactive material. The MPC baseplate and shell are made of stainless steel (A lloy X, see Appendix l .A). The lid is a two piece construction, with the top structural portion made ofAlloy X .
The confinement boundary is defined by the MPC baseplate, shell, lid, port covers, and closure ring.
The HI-STORM FW System MPCs shares external and internal features with the HI-STORM 100 MPCs certified in the §72-1014 docket, as summarized be low.
- 1. MPC-37 and MPC-89 have an identical enclosure vessel which mimics the enclosure vessel design detai ls used in the HI-STORM l 00 counterparts including the shell thickness, the vent and drain port sizes, construction details of the top lid and closure ring, and closme weld details. The baseplate is made slightly th icker to ensure its bending rigid ity is comparable to its counterpart in the HI-STORM 100 system. The material of construction of the pressure HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-37 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HObTEC PROPRIETARY INFORMATION retaining components is also identical (options of austenitic stainless steels, denoted as Alloy X, is explained in Appendix l .A herein as derived from the HI-STORM 100 FSAR with appropriate ASME Code edition updates). There are no gasketed joints in the MPCs.
- 11. The top lid of the MPCs contains the same attachment provisions for lifting and handling the loaded canister as the HI-STORM 100 counterparts.
iii. The drain pipe and sump in the bottom baseplate of the MPCs (from wh ich the drain pipe extracts the water during the dewatering operation) are also similar to those in the HI-STORM l 00 counterparts.
1v. The fuel basket is assembled from a rectilinear gridwork of plates so that there are no bends or radii at the cell corners. This structural feature eliminates the source of severe bending stresses in the basket structure by eliminating the offset between the cell walls which transfer the inertia load of the stored SNF to the basket/MPC interface during the various postulated accident events (such as non-mechanistic tipover). This structural feature is shared with the HI-STORM 100 counterparts. Figures 1.1.6 and 1.1.7 show the PWR and BWR fuel baskets, respectively, in perspective view.
- v. Precision extruded and/or machined blocks of aluminum alloy with axial holes (basket shims) are installed in the peripheral space between the fuel basket and the enclosure vessel to provide conformal contact surfaces between the basket shims and the fuel basket and between the basket shims and the enclosure vessel shell. The axial holes in the basket shims serve as the passageway for the downward flow of the helium gas under the thermosiphon action. This thermosiphon action is common to all MPCs including those of the HI-STORM I00. Various options are available to install these extruded shims in the basket periphe1y as summarized in Table 1.2.9.
v1. To facilitate an effective convective circulation inside the MPC, the operating pressure is set the same as that in the HI-STORM I00 counterparts.
vii. Like the high capacity baskets in the HI-STORM l 00 MPCs, the fuel baskets do not contain flux traps.
Because of the above commonalities, the HI-STORM FW System is loaded in the same manner as the HI-STORM 100 system, and will use similar anci llary equipment, (e.g. , lift attachments, lift yokes, lid welding machine, weld removal machine, cask transporter, mating device, low profile transporter or zero profi le transpo1ter, drying system, the hydrostatic pressure test system).
Lifting lugs, attached to the inside surface of the MPC shell, are used to p lace the empty MPC into the HI-TRAC VW transfer cask. The lifting lugs also serve to axially locate the MPC ]id prior to welding. These internal lifting lugs cannot be used to handle a loaded MPC. The MPC lid is installed prior to any handling of a loaded MPC and there is no access to the internal lifting lugs once the MPC lid is insta lled.
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lelObTi;C PROPRIETARY INFORMATION The MPC incorporates a redundant closure system. The MPC lid is edge-welded (welds are depicted in the licensing drawing in Section 1.5) to the MPC outer shell. The lid is equipped with vent and drain ports that are utilized to remove moisture from the MPC and backfill the MPC with a specified amount of inert gas (helium). The vent and drain ports are closed tight and covered with a port cover (plate) that is seal welded before the closure ring is installed. The closure ring is a circular ring edge-welded to the MPC shell and lid; it covers the MPC lid-to shell weld and the vent and drain port cover plates. The MPC lid provides sufficient rigidity to allow the entire MPC loaded with SNF to be lifted by the s uitably sized threaded anchor locations (TALs) in the MPC lid.
As discussed later in this section, the height of the MPC cavity plays a direct role in setting the amount of shielding availab]e in the transfer cask. To maximize shielding and ach ieve ALARA within the constraints of a nuclear plant (such as crane capacity), it is necessary to minimize the cavity height of the MPC to the length of the fuel to be stored in it. Accordingly, the he ight of the MPC cavity is custom ized for each fuel type listed in Section 2.1. Table 3.2.1 provides the data to set the MPC cavity length as a small adder to the nominal fuel length (with any applicable NFH) to account for manufacturing tolerance, irradiation growth and thermal expansion effects.
For fuel assemblies that are shorter than the MPC cavity length (such as those without a control element in PWR SNF) a fuel shim may be utilized (as appropriate) to reduce the axial gap between the fuel assembly and the MPC cavity to approximately 1.5-2.5 inches. A small axial clearance is provided to account for manufacturing tolerances and the irradiation and thermal growth of the fuel assemblies. The actual length of fuel shims ( if required) will be determined on a site-specific and fuel assembly-specific basis.
A ll components of the MPC assembly that may come into contact w ith spent fuel pool water or the ambient environment are made from stainless steel alloy o r aluminum/aluminum alloy materials.
Prominent among the aluminum based materials used in the MPC is the Metamic-HT neutron absorber lattice that comprises the fuel basket. As discussed in Chapter 8, concerns regarding interaction of coated carbon steel materials and various MPC operating environments [1.2.1] are not applicable to the HI-STORM FW MPCs. All structural components in an MPC enc losure vessel shall be made of Alloy X, a designation whose origin, as explained in the HI-STORM 100 FSAR
[1.1.3], lies in the U.S. DOE's repository program.
As explained in Appendix l .A, Alloy X (as defined in this FSAR) may be one of the following materials.
- Type 316
- Type 316LN
- Type 304
- Type 304LN Any stainless steel part in an MPC may be fabricated from any of the acceptable Alloy X materials listed above.
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AOL I EC PROP~IETARY lrffORMATION The Alloy X group approach is accomplished by qualifying the MPC for all mechanical, structural, radiological, and thermal conditions using material thermo-physical prope1ties that are the least favorable for the entire group for the analysis in question. For example, when calculating the rate of heat rejection to the outside environment, the va lue of thenna l conductivity used is the lowest for the candidate material group. Similarly, the stress analysis calculations use the lowest value of the ASME Code allowable stress intensity for the entire group. Stated differently, a material has been defined that is referred to as Alloy X, whose thermo-physical properties, from the MPC design perspective, are the least favorable of the above fou r candidate materials.
The evaluation of the candidate Alloy X materials to determine the least favorable properties is provided in Appendix LA. The AlloyX approach is conservative because no matter which material is ultimately utilized in the MPC construction, it guarantees that the performance of the MPC will exceed the analytical predictions contained in this document.
The principal materials used in the manufacturing of the MPC are listed in the licensing drawings (Section 1.5) and the acceptance criteria are provided in Chapter 10. A listing of the fabrication specifications utilized in the manufacturing of HI-STORM FW System components is provided in Table 1.2.7. The specifications, procedures for sizing, form ing machining, welding, inspecting, cleaning, and packaging of the completed equipment implemented by the manufacturer on the shop floor are required to conform to the fabrication specification in the above referenced tables.
1.2.1.2 HI-STORM FW Overpack HI-STORM FW is a vertical ventilated module engineered to be fu lly compatible with the HI-TRAC VW transfer cask and the MPCs listed in Table 1.0.1. The HI-STORM FW overpack consists of two major parts:
- a. A dual wall cylindrical container with a set of inlet ducts near its bottom extremity and an integrally welded basep1ate.
- b. A removable top lid equipped with a radially symmet ric ex it vent system.
The HI-STORM FW overpack is a rugged, heavy-walled cylindrical vessel. Figure 1.1. l provides a pictorial view of the standard HI-STORM FW overpack w ith the MPC-37 partially inserted. The main structural function ofthe storage overpack is provided by carbon steel, and the main shielding function is provided by plain concrete. The overpack plain concrete is enclosed by a steel weldment of cylindrical shells, a thick baseplate, and a top annu lar plate. A set of four equally spaced radial connectors join the inner and outer shells and define a fixed width annular space for placement of concrete. The overpack lid also has concrete to provide neutron and gamma shielding.
The storage overpack provides an internal cylindrical cavity of sufficient height and diameter for housing an MPC (Figure 1.1.1) with an annular space between the MPC enclosure vessel and the overpack for ventilation air flow. The upward flowing air in the annular space (drawn from the ambient by a purely passive action), extracts heat from the MPC surface by convective heat transfer.
The rate of air flow is governed by the amount of heat in the MPC (i.e., the greater the heat load, the greater the air flow rate).
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I IOLTEC PRO~RIETARY INPORMATIOl<l To maximize the cooling action of the ventilation air stream, the ventilation flow path is optimized to minimize hydraulic resistance. The HI-STORM FW features eight inlet ducts. Each duct is na1Tow and tall and ofan interna lly refractive contour which minimizes radiation stream ing while optimizing the hydraulic resistance of airflow passages. The inlet air duct design, referred to as the " Radiation Absorbent Duct," is subject to an ongoing action on a provisional Holtec International patent application by the USPTO (ca. March 2009) and is depicted in the licensing drawing in Section 1.5.
The Radiation Absorbent Duct also permits the MPC to be placed directly on the baseplate of the overpack instead of on a pedestal that would raise it above the duct.
A n array of radial tube-type gussets (MPC guides) welded to the inner shell and the baseplate are shaped to guide the MPC during MPC transfer and ensure it is centered within the overpack. The MPC guides have an insignificant effect on the overall hydraulic resistance of the ventilation air stream. Furthermore, the top array of MPC guides are longitudinally oriented members, sized and aligned to serve as impact attenuators which will crush against the solid MPC lid during an impactive collision, such as a non-mechanistic tip-over scenario.
The height of the storage cavity in the HI-STORM FW overpack is set equal to the he ight of the MPC plus a fixed amount to allow for thennal growth effects and to provide for adequate ventilation space (low hydraulic resistance) above the MPC (See Table 3 .2. 1).
The overpack lid, like the body, is also a steel weldment filled with plain concrete. The lid is equipped with a steel weldment to center the lid on the overpack body. The centering weldment projects into the overpack she ll space which ensures that the lid will not slide across the top surface of the overpack body during a non-mechanistic tip-over or missile impact event. As shown in the Licensing Drawing Package in Section 1.5, the HI-STORM lid is available in three versions, namely:
(i) The standard lid wherein the outer diameter of the lid is truncated and the air flow passage is internal to the lid body.
h1 the standard lid design, the outlet duct is located in the standard overpack lid (Figure 1.1. l) pursuant to Holtec Patent No. 6,064,7 10. The outlet duct opening is narrow in height which reduces the radiation streaming path from the contents, however, aside from the minor interference from the support plates, the duct extends circumferentia lly 360° which significantly increases the flow area and in-turn minimizes hydraulic resistance.
(ii) Version XL (extra large) lid wherein the outer diameter ofilie lid is enlarged and the exit air passageway is located in the interstitial space between the top ofthe overpack body and the underside of the lid.
The objective of the Version XL lid is to introduce a more effective closure lid for the HI-STORM FW to further reduce sky shine and vent outlet dose. The Version XL lid can on ly be used with the Version XL HI-STORMFW overpack, which is slightly taller than the standard overpack to ensure the overpack cavity height and the gap HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-41 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC PROPRIETARY INEORMAIION between the MPC and HI-STORM is maintained in accordance with Table 3.2.1. The Version XL lid differs from the Standard lid in the following key aspects:
I. The outer diameter of the XL lid is enlarged to provide a greater level of radiation blockage against the skyward (obliquely) emanating radiation from theMPC.
- 2. The internal ex it a ir flow path within the lid is removed and replaced with a radially symmetric air flow path between the XL lid and the top surface ofthe XL overpack body. This has the beneficial effect of rendering the lid into a solid concrete fi lled disc without any streaming paths.
Because Version XL provides a greater level of radiation blockage (i.e. a reduced site boundary dose), it sho uld be used unless other considerations hinders its use.
(i ii) The "Domed" lid is an alternative to the XL lid (which is flat) for use in the HI-STORM FW system and is the counterpart of the Closure Lid previously certified for HI-STORM 1OOU in Docket # 72-1014 in terms of its structural attributes. Like, the Version XL lid, the domed lid can only be used with the Version XL HI-STORM FW overpack to ensure the overpack cavity height and the gap between the MPC and HI-STORM is maintained in accordance with Table 3.2.1.
The "Domed" lid configuration is employed at those ISFSis where extremely large impulsive or impactive loads are specified as Design Basis Loads (DBLs) for the storage system. A crashing commercial airliner or a militaty aircraft is an example of severe DBLs that are increasing ly adopted by ISFSI owners to fortify their d1y storage systems against extenuating threats that were unthinkable in the previous century. An o utlier earthquake, with inertial g-loads in excess of 2g's postulated at ce1tain earthquake vulnerable sites, is another example of a mechanical loading that may demand the resort to the domed lid. T he chief design attributes of the domed lid are:
- 1. The top of the lid emulates a tori spherical surface of revolution. The principal structural strength of the lid derives from its domed construction defined by an array of radially disposed thick plate girders welded to a thick bottom plate below to form an extremely rigid skeletal structure within which the shielding concrete is placed.
- 2. The concrete in the lid can be plain or re bar reinforced to add to the structural capacity of the lid, if desired. Ca lculations show, however, that such reinforcement is not necessary to deal with aircraft impact loadings defined by the US and European nuclear plant owners in the wake of 9/ 11.
- 3. The sloped top profile of the lid fac ilitates drainage of ra inwater in outdoor ISFSI installations.
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AOL I EC PROPRIE I ARV INFORMA I ION
- 4. Because the flow passage for the ventilation air in the system is una ltered, the domed lid is thermally equivalent to the XL lid; in other words, both lid types provide equal heat rejection capacity.
- 5. Because of a thicker section of steel and concrete in the domed lid directly above the canister, its shielding performance against sky shine is substantially better than that achievable from the XL lid.
- 6. The lifting and handling of the domed lid is carried out by a set of four lift lugs designed to meet Regulatory Guide 3.61 and NUREG-0,6 12 stress margin requirements.
In summary, the domed lid is a strncturally enhanced version of the XL (flat) lid, whose other safety functions (viz., thermal, shielding) are comparable to its XL counterpart.
The reference design of the domed lid provided herein must be customized, as necessary, to meet the site mechanical and structural loadings applicable to the host site. The site boundary dose requirements of the specific site as well as those of 10CFR 72. l 06 must be demonstrated to be satisfied using the methodology documented in the system FSAR.
Within the air outlet ducts, an array of duct photon attenuators (DPAs) may be installed (Holtec Patent No.6,5 19,307B 1) to fu11her decrease the amount ofradiation scattered to the environment.
These Duct Photo Attenuators (DPAs) are designed to scatter any radiation stream ing through the ducts. Scattering the rad iation in the ducts reduces the streaming through the overpack penetration resulting in a significant decrease in the local dose rates. The configuration of the DPAs is such that the increase in the resistance to flow in the air inlets and o utlets is minimized. The DP As are not credited in the safety analyses perfo1med in this FSAR, nor are they depicted in the licensing drawings. DPAs can be used at a site if needed to lower site boundary dose rates with an appropriate site-specific engineering evaluation.
Each duct opening is equipped with a heavy duty insect banier (screen). Routine inspection of the screens or temperature monitoring of the air exiting the o utlet ducts is required to ensure that a blockage of the screens is detected and removed in a timely manner. The evaluation of the effects of partial and complete blockage of the air d ucts is considered in Chapter 12 of this FSAR.
Four threaded anchor blocks at the top of the overpack are provided for lifting. The anchor blocks are integrally welded to the radial plates which join the overpack inner and outer steel shells. The four anchor blocks are located at 90° angular spacing around the circumference of the top ofthe overpack body.
HOLTEC INTERNATIONAL COPYRIGHTED MA TERTAL REPORT HI-2114830 Rev. 5 1-43 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION The internal surfaces of the HI-STORM FW overpack facing the MPC may be optionally equipped with a heat shield made of a thin steel sheet stock to limit the radiant heat delivered to the overpacks's body.
The plain concrete between the overpack inner and outer steel shells and the lid is specified to provide the necessary shielding properties (dry density) and compressive strength. The shielding concrete shall be in accordance with the requirements specified in Appendix l .D of the HI-STORM l 00 FSAR [1.1.3] and Table 1.2.5 herein. Commitment to follow the specification of plain concrete in the HI-STORM 100 FSAR in this docket ensures that a common set of concrete placement procedures will be used in both overpack types which will be important for configuration control at sites where both systems may be deployed.
The principal function of the concrete is to provide shielding against gamma and neutron radiation.
However, the massive bulk of concrete impa1ts a large thermal inertia to the HI-STORM FW overpack, allowing it to moderate the rise in temperature of the system under hypothetical conditions when all ventilation passages are assumed to be blocked. During the postulated fire accident the high thermal inertia characteristics of the HI-STORM FW concrete control the temperature of the MPC.
Although the annu lar concrete mass in the overpack shell is not a structural member, it does act as an elastic/plastic filler of the inter-shell space buttressing the steel shells.
Density and compressive strength are the key parameters that bear upon the performance ofconcrete in the HI-STORM FW System. For eva luating the physical properties of concrete for completing the analytical models, conservative formulations of Reference [1.2.2] are used.
Thermal analyses, presented in Chapter 4, show that the temperatures dming normal storage conditions do not threaten the physical integrity of the HI-STORM FW overpack concrete.
The principal materials used in the manufacturing ofthe overpack are listed in the licensing drawings and the acceptance criteria are provided in Chapter 10. Tables 1.2.6 and 1.2.7 provide applicable code paragraphs for manufacturing the HI-STORM FW overpack.
1.2.1.3 HI-TRAC VW Transfer Cask The HI-TRAC VW transfer cask (Figure 1.1.8) is engineered to be used to pe1form all short-term loading operations on the MPC beginning with fuel loading and ending with the emplacement of the MPC in the storage overpack. The HI-TRAC VW is also used for short term unloading operations beginning with the removal of the MPC from the storage overpack and ending with fuel unloading.
The HI-TRAC VW is available in the standard version as well as the "Version P", which is only designed for use with the MPC-89. The Version P licensing drawing (see Section 1.5) provides a stand-alone reference basis for safety analyses for the HI-TRAC VW Version P. Unless otherwise stated, the discussion below applies to both versions of the HI-TRAC VW.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-44 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION HI-TRAC VW is designed to meet the following specific perfom1ance objectives that are centered on ALARA and physical safety of the plant's operations staff.
- a. Provide maximum shielding to the plant personnel engaged in conducting short-term operations.
- b. Provide protection of the MPC against extreme environmental phenomena loads, such as tornado-borne missiles, during short-term operations.
- c. Serve as the container equipped with the appropriate lifting appurtenances in accordance with ANSI Nl 4.6 [ 1.2.3] to lift, move, and handle the MPC, as required, to perform the short-term operations.
- d. Provide the means to restrain the MPC from sliding and protruding beyond the shielding envelope of the transfer cask under a (postulated) handling accident. An MPC restraining device may be used as an ancillary for the HI-TRAC VW if deemed necessary to restrain the MPC during horizontal on-site transfer or a credible accident event. The MPC restraining device is designated as a site specific ancillary that must remain attached to the cask under any credible accident applicable to the site.
- e. Facilitate the transfer of a loaded MPC to or from the HI-STORM FW overpack (or another physically compatible storage or transfer cask) by ve1tical movement of the MPC without any risk of damage to the canister by friction.
The above performance demands on the HI-TRAC VW are met by its design configuration as summarized below and presented in the licensing drawings in Section 1.5.
As discussed in Chapter 3, the licensed basis of HI-TRAC VW design is ALARA focused with the thickness of lead specified as a variable that can be optimized to maximize the cask's shielding effectiveness within the constraint of the plant's crane capacity. Therefore, it is necessa1y to perfonn the safety analysis of the HI-TRAC VW design customized for a specific site to ensure that the occupational dose is ALARA. Because the transfer cask serves no criticality or confinement function, the safety analyses pertain to structural, thermal-hydraulic and shielding compliance. Table 1.2.10 contains a list of all safety evaluations that must be performed on a HI-TRAC VW cask embodiment to qualify it for use at a plant site. As can be seen from Table 1.2. l 0, the required evaluations must be performed for the specific site conditions with the provision that the analysis methodology does not violate that documented in this FSAR.
HI-TRAC VW is principally made of carbon steel and lead. The cask consists of two major parts, namely (a) a multi-shell cylindrical cask body, and (b) a quick connect/disconnect bottom lid. The cylindrical cask body is made of three concentric shells joined to a solid annular top flange and a solid annular bottom flange by circumferential welds. The innermost and the middle shell are fixed in place by longitudinal ribs which serve as radial connectors between the two shells. The radial connectors provide a continuous path for radial heat transfer and render the dual shell configuration into a stiff beam under flexura l loadings. The space between these two shells is occupied by lead, which provides the bulk of the transfer cask's gamma radiation shielding capability and accounts for a major po1tion of its weight.
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HOLfEC PROPRIETARY INFORMATION Between the middle shell and the outermost shell is the weldment that is referred to as the "water jacket." The water jacket is filled with water and may contain ethylene glycol fortified water, if wa1Tanted by the environmental conditions at the time ofuse. The water jacket provides most of the neutron shielding capability to the cask. The water jacket is outfitted with pressure relief devices to prevent over-pressurization in the case of an off-normal or accident event that causes the water mass inside of it to boil.
The water in the water jacket serves as the neutron shie ld when required. When the cask is being removed from the pool and the MPC is full of water, the water jacket can be empty. This will minimize weight, if for example, crane capacities are limited, since the water within the MPC cavity is providing the neutron shielding during this time. However, the water jacket must be filled before the MPC is emptied of water. This keeps the load on the crane (i.e., weight of the loaded transfer cask) nearly constant between the lifts before and after MPC processing. Fmthem1ore, the amount of shielding provided by the transfer cask is maximized at all times within crane capacity consn*aints.
The water jacket concept is disclosed in a Holtec Patent [6,587,536 Bl).
As the description of loading operations in Chapter 9 of this FSAR indicates, most of the human activities occur near the top of the transfer cask. Therefore, the geometry of the transfer cask is configured to minimize the use of penetrations and discontinuities and maximize shielding in areas where penetrations and discontinuities are necessary. The standard version HI-TRAC VW is lifted using a pair of lift blocks that are anchored into the top forging of the transfer cask using a set ofhigh strength bolts. An optional device which prevents the MPC from sliding out of the n*ansfer cask is attached to the lift blocks. The HI-TRAC VW Version P is lifted using a pair of radial trunnions embedded in an enlarged top forging, as shown in the Licensing drawing package (Section 1.5).
The bottom of the transfer cask is equipped with a thick lid. It is provided with a gasket sea l against the machined face of the bottom flange creating a watertight (open top) container. A set of bolts that tap into the machined holes in the bottom lid provide the required physical strength to meet the snuctural imperatives ofANSI N 14.6 and as well as bolt pull to maintain joint integrity. The bottom lid can be fastened and released from the cask body by accessing its bolts from above the transfer cask bottom flange, which is an essential design feature to pennit MPC transfer operations described in Chapter 9.
To optimize the shielding in the body of HI-TRAC VW, two design strategies have been employed;
- 1. The height of the HI-TRAC's cavity is set to its optimal value (slightly greater than the MPC height as specified in Table 3.2.1), therefore allowing more shielding to be placed in the rad ial direction of the transfer cask.
- 2. The thickness of the lead in the transfer cask shall be customized for the host site. The thickness of the lead cylinder can be varied within the limits given in Table 3.2.2. The nominal radial thickness of the water jacket is fixed and therefore the outside diameter of the HI-TRAC will vary accordingly.
The above design approach permits the quantity of shie ldi ng around the body of the transfer cask to be maximized for a given length and weight of fuel in keeping with the practices of ALARA. At HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-46 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HObTEC PROPRIETARY INFORMATION some host sites, a lead thickness greater than allowed by Table 3.2.2 may be desirable and may be feasible but will require a site-specific safety evaluation.
The use of the suffix VW in the HI-TRAC's designation is intended to convey this Variable W eight feature incorporated by changing the HI-TRAC height and lead thickness to best accord with the MPC height and plant's architecture. Table 3.2.6 provides the operating weight data for a HI-TRAC VW when handling the Reference PWR and BWR fuel in Table 1.0.4.
The principal materials used in the manufacturing of the transfer cask are listed in the licensing drawings and the acceptance criteria are provided in Chapter 10. Tables 1.2.6 and 1.2.7 provide applicable code paragraphs for manufacturing the HI-TRAC VW.
1.2.1.4 Shielding Materials Steel and concrete are the principal shielding materials in the HI-STORM FW overpack. The steel and concrete shielding materials in t he lid provide additiona l gamma attenuation to reduce both direct and skyshine radiation. The combination of these shielding materials ensures that the radiation and exposure objectives of 10CFR72.104 and 10CFR72.106 are met.
Steel, lead, and water are the principal shielding materia ls in the HI-TRAC transfer cask. The combination of these three shielding materials ensures that the radiation and exposure objectives of 10CFR72.106 and ALARA are met. The extent and location of shielding in the transfercaskplays an important role in minimizing the personnel doses during loading, handling, and transfer.
The MPC fuel basket strncture provides the initial attenuation of gamma and neutron radiation em itted by the radioactive contents. The MPC shell, baseplate, and thick lid provide add itional gamma attenuation to reduce direct radiation.
1.2.1.4.1 Neutron Absorber - Metamic HT Metamic-HT is the designated neutron absorber in the HI-STORM FW MPC baskets. It is also the structural material of the basket. The properties ofMetamic-HT and key characteristics, necessary for ensuring nuclear reactivity control, thermal, and structural perfonnance of the basket, are presented be low.
(b)(4)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2 114830 Rev. 5 1-47 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
-HObTeC PROPRIETARY l~IF9RMA'l't0N-(b)(4)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2 114830 Rev. 5 1-48 HI-STORM FW SYSTEM FSAR Revision 5. June 20, 2017
I IOLTEC PROl3RIETARY INFORMATIO~
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HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-49 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I fOLTEC PROPRle:TARY INFORMAIIQN (b)(4)
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-50 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC PROPRIE'flo;R't1NPORIVIA I ION
{b)(4)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-51 Hi-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
1IOLTEC PROPRle+ARY IJl,IFORMAIION .
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HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2 114830 Rev. 5 1-52 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION (b)(4) 1.2.1.4.2 Neutron S hie lding Neutron shield ing in the HI-STORM FW overpack is provided by the thick walls of concrete contained inside the steel vessel and the top lid. Concrete is a shielding material with a long proven hi story in the nuclear industry. The concrete composition has been specified to ensure its continued integrity under long term temperatures required for SNF storage.
The specification of the HI-STORM FW overpack neutron shielding material is predicated on functional performance criteria. These criteria are:
- Attenuation of neutron radiation to appropriate levels;
- Durability of the shie lding material under normal conditions (i.e. under norma l condition thermal, chemical, mechanical, and radiation environments);
- Stability of the homogeneous nature of the shielding material matrix; HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-53 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HO! IEC PROPRIETARY INFORMATION
- Stability of the shie lding materia l in mechanical or thermal accident conditions to the desired performance levels; and
- Predictability of the manufacturing process under adequate procedural control to yield an in-place neutron shield of desired function and uniformity.
Other aspects of a shielding material, such as ease of handling and prior nuclear industry use, are also considered. Final specificatio n of a shield materia l is a result of optim izing the materia l properties with respect to the above ciiteria, along with the design of the shield system, to achieve the desired shielding results.
The HI-TRAC VW transfer cask is equipped with a water jacket providing radial neutron shie lding.
The water in the water jacket may be fortified with ethylene glycol to prevent freezing under low temperature operations [ 1.2.4].
During ce1tain evolutions in the short term hand ling operations, the MPC may contain water which will supplement neutron shie lding.
1.2. 1.4.3 Gamma Shielding Material Gamma shielding in the HI-STORM FW storage overpack is primarily provided by massive concrete sections conta ined in the robust steel vessel. The carbon steel in the overpack supplements the concrete gamma shielding. To reduce the radiation streaming through the overpack penetrations, duct photon attenuators may be installed (as discussed previously in section 1.2.1.2) to further decrease radiation streaming from the ducts.
1n the HI-TRAC VW transfer cask, the primary gamma shielding is provided by lead. As in the storage overpack, carbon steel supplements the lead gamma shielding of the HI-TRAC VW transfer cask.
1n the MPC, the gamma shielding is provided by its stainless steel enclosure vessel (including a thick lid); and its aluminum based fuel basket and aluminum alloy basket shims.
1.2.1.5 Lifting Devices 1.2. 1.5. 1 HI-STORM FW Lifting Devices Lifting and handling of the loaded HI-STORM FW overpack is carried out in the ve1tical upright configuration using the threaded anchor blocks a1rnnged circumferentially at 90° spacing around the overpack. These anchor blocks are used for overpack lifting as well as securing the overpack lid to the overpack body. The storage overpack may be lifted with a li fting device that engages the anchor blocks with threaded studs and connects to a crane or similar equipment. The overpack anchor blocks are integral to the overpack and designed in accordance with Regulatory Guide 3.61. All lifting appurtenances used w ith the HI-STORM FW overpack are designed in accordance with NUREG-061 2 and ANSI N 14.6, as appl icable.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-54 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC F'RO~RIETARY lt~FORMATION 1.2.1.5.2 HI-TRAC VW Lifting Devices (Standard Version)
Like the storage overpack, the loaded standard version HI-TRAC VW is also lifted using a special ly engineered appurtenance denoted as the lift block in Table 9.2.1 and Figure 9.2.1. The top flange of the standard version HI-TRAC VW is equipped with threaded holes that allow lifting of the loaded HI-TRAC VW in the ve1tical upright configuration. These threaded lifting holes are integral to the transfer cask and are designed in accordance with NUREG-0612. Al11 ifting appurtenances used with the HI-TRAC VW are designed in accordance with NUREG-0612 and ANSIN14.6, as applicable.
1.2.1.5.3 HI-TRAC VW Lifting Devices (Version P)
Several L WR pools are characterized by cask loading areas that are not sufficiently spacious to allow a standard HI-TRAC VW to be staged with adequate clearance to the fixed proximate structures located in the pool. In other cases, the TAL (acronym for threaded anchor locations) lifting appurtenance built into the top flange in the classical "VW" design is not amenable to convenient handling. To address such limitations that may exist at certain Plant sites, a variation of tl1e standard "VW" model called Version P has been devised which fu lfills a ll of the design and safety predicates of the standard HI-TRAC VW. The main aspects in which Version P differs from the classic "VW" model are:
- 1. The threaded lifting holes in the lift block arrangement are substituted witl1 two radial trunnions that are embedded in the Version P's top flange and are designed to eliminate intrusion of water when the cask is in an aqueous environment. The trunnions are designed to meet the structural criteria in Table 1.2.10.
- 2. To maximize the structural margin, the top flange is enlarged in length such that the trunnions are entirely contained wiiliin the flange.
- 3. The top trunnions and the top flange are designed such that the trunnion extremities do not project beyond the cylindrical outline of the transfer cask. Because the trunnions do not project beyond the cask, the risk of the trunnions becoming a hard impact point in the (hypothetical) event of a cask tip-over accident is minimized.
The chief distinguishing feature of Version P, namely the trunnion set, illustrated in the Licensing drawing, has been demonstrated to meet the structural acceptance criteria in this FSAR for the specified lifted load on the drawing. As stated in Table 1.2. l 0, an increase in the payload or any other geometric change that can materially affect the lifting capacity of the cask structure will require a site specific qualification of the trunnion and the affected cask components.
1.2.1.5.4 MPC Lifting Devices The top of the MPC lid is equipped with eight threaded holes that allow lifting of the loaded MPC.
These holes allow the loaded MPC to be ra ised and/or lowered through the HI-TRAC VW transfer cask using lifting attachments (functional equivalent ofthe lift blocks used with HI-TRAC VW). The HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-55 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC PROPRIETARY INFORMATIOl<l threaded holes in the MPC lid are integral to the MPC and designed in accordance with NUREG 0612. All lifting appurtenances used with the MPC are designed in accordance with NUREG-0612 and ANSI N 14.6, as applicable.
1.2.1.5.5 Transporter The transporter used to handle the loaded transfer cask or overpack during transpo1t operations must be engineered to provide a high integrity handling of the load, defined as a lifting/handling operation wherein the risk of an uncontrolled lowering of the heavy load is non-credible. In handling equipment such as a transporter, high integrity handling is achieved through (a) a body and any vertical columns designed to comply with stress limits ofASME Section III, Subsection NF, Class 3, (b) an overhead beam that is single-failure-proof, and (c) redundant drop protection features. Single failure proof handling capability is achieved by ensuring that the applicable factor of safety is 200%
of that required by the reference design code or national consensus standard. It is acceptable to have certain load carrying members (such as the lifting towers in a vertical cask transporter) designed with redundant devices and others (such as the transverse beam) designed to the doubled factor of safety in order to meet the criteria set above. Heavy load handling device criteria are set down in TM-14 l
[Ref 1.2. l 5].
1.2.1.6 Design Life The design life of the HI-STORM FW System is 60 years. This is accomplished by using materials of construction with a long proven history in the nuclear industry and specifying materials known to withstand their operating environments with little to no degradation (see Chapter 8). A maintenance program, as specified in Chapter 10, is also implemented to ensure the service life of the HI-STORM FW System will exceed its des ign life of 60 years. The design considerations that assure the HI-STORM FW System performs as designed include the following:
HI-STORM FW Overpack and HI-TRAC VW Transfer Cask
- Exposure to Environmental Effects
- Material Degradation
- Maintenance and Inspection Provisions
- Corrosion
- Structural Fatigue Effects
- Maintenance of Helium Atmosphere
- Allowable Fuel Cladding Temperatures
- Neutron Absorber Boron Depletion The adequacy of the HI-STORM FW System materials for its design life is discussed in Chapter 8.
Transportability considerations pursuant to 10CFR72.236(m) are discussed in Section 2.4.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-56 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION 1.2.2 Operational Characteristics 1.2.2.1 Design Features The design features of the HI-STORM FW System, described in Subsection 1.2. l in the foregoing, are intended to meet the following principal performance characteristics under all credible modes of operation:
(a) Maintain subcriticality (b) Prevent unacceptable release of contained radioactive material (c) Minimize occupational and site boundary dose (d) Permit retrievability of contents (fuel must be retrievable from the MPC under normal and off-normal conditions in accordance with ISG-2 and the MPC must be recoverable after accident conditions in accordance with ISG-3)
Chapter 11 identifies the many design features built into the HI-STORM FW System to minimize dose and maximize personnel safety. Among the design features intrinsic to the system that facilitate meeting the above obj ectives are:
- 1. The loaded HI-STORM FW overpack and loaded HI-TRAC VW transfer cask are typically maintained in a vertical orientation during handling (except as described in Subsection 4.5.1).
- 11. The height of the HI-STORM FW overpack and HI-TRAC VW transfer cask is minimized consistent with the length of the SNF. This eliminates the need for major structural modifications at the plant and/or eliminates operational steps that impact ALARA.
111. The extent of shielding in the transfer cask is maximized at each plant within the crane and architectural limitations of the plant by minimizing the height in accordance with the length of the SNF to pe1mit additional shielding material in the walls of the transfer cask.
1v. The increased number of inlet ducts and the circumferential outlet vents in HI-STORM FW overpack are configured to make the thermal performance less susceptible to wind.
- v. Tall and narrow inlet ducts in the HI-STORM FW overpack in conjunction with the thermosiphon action in the MPC design, render the HI-STORM FW System more resistant to a thermally adverse flood condition (Section 2.2).
v1. The design of the HI-STORM FW affords the user the flexibility to utilize higher density concrete than the minimum prescribed value in Table 1.2.5 or concrete with Shielding Enhancer Additives such as, but not limited to, those in ASTM C638-14
[1.2.16] as described in Appendix l.D of the HJ-STORM 100 FSAR [l.1 .3] to HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-57 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC F'RO~RIETARY lt~FORMATION further reduce the site boundary dose.
The HI-STORM FW overpack utilizes the same cross-connected dual steel shell configuration used in other HI-STORM mode ls. The dual shell steel weldment w ith an integrally connected baseplate forms a well defined annulus wherein plain concrete of the desired density is installed. While both steel and concrete in the overpack body are effective in neutron and gamma shielding, the principal role of the radially conjoined steel shell is to provide the structural rigidity to support the mass of the shielding concrete. As ca lculations in Chapter 3 show, the dual steel shell structure can suppo1t the mass of concrete of any available density with ample margin of safety. Consequently, the mass of concrete utilized to shield against the stored fuel is only limited by the density of the available aggregate. Users of HI-STORM 100 systems have used concrete of density approaching 200 lb/ft' to realize large dose reductions at ISFSis to support site specific considerations.
The above comment also applies to the standard HI-STORM FW overpack lid, which is a massive steel weldment made of plate and shell segments filled with shielding concrete. The steel in the lid, while contributing principally to gamma shielding, provides the needed structural capacity. Concrete performs as a missile barrier and is critical to minimizing skyshine. High density concrete can also be used in the standard HI-STORM FW overpack lid if reducing skyshine is a design objective at a plant.
The site boundary dose from the HI-STORM FW System is minimized by using specially shaped ducts at the bottom of the overpack and in the lid region. The ducts and the annular space between the stored MPC and the HI-STORM FW cavity serve to promote ventilation of air to reject the MPC's decay heat to the environment.
The criticality control features of the HI-STORM FW are designed to maintain the neutron multiplication factor k-effective (including uncertainties and calculational bias) at less than 0.95 under all normal, off-normal, and accident conditions of storage as analyzed in Chapter 6.
1.2.2.2 Sequence of Operations A summary sequence of loading operations necessary to defuel a spent fuel pool using the HI-STORM FW System (shown with MPC Transfer in the plant's Egress Bay) is shown in a series of diagrams in Figure 1.2.3 (Figure 1.2.3 is strictly illustrative; it does not contend with exiguous details such as the trunnions used in Version P of HI-TRAC VW in lieu of the Lift Block). The loading sequence underscores the inherent simplicity of the loading evolutions and its compliance with ALARA. A more detailed sequence of steps for loading and handling operations is provided in Chapter 9, aided by illustrative figures, to serve as the guidance document for preparing site-specific implementation procedures.
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-58 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
1'10LTEC PROPRIETARY INFORMATION 1.2.2.3 Identification of Subjects for Safety and Reliability Analysis 1.2.2.3.l Criticality Prevention Criticality is controlled by geometry and neutron absorbing materials in the fuel basket. The entire basket is made ofMetamic-HT, a uniform dispersoid of boron carbide and nano-pa1ticles ofalumina in an aluminum matrix, serves as the neutron absorber. This accrues four major safety and reliability advantages:
(i) The larger B-10 areal density in the Metamic-HT allows higher enriched fuel (i.e., BWR fuel with planar average initial enrichments greater than 4.5 wt% U-235) without relying on gadolinium or burn-up credit.
(ii) The neutron absorber cannot be removed from the basket or displaced within it.
(iii) Axial movement of the fue l with respect to the basket has no reactivity consequence because the entire length of the basket contains the B-10 isotope.
(iv) The larger B-10 areal density in the Metamic-HT reduces the reliance on soluble boron credit during loading/unloading of PWR fuel.
1.2.2.3.2 Chemical Safety There are no chemical safety hazards associated with operations of the HI-STORM FW System. A detai led evaluation is provided in Section 3.4.
1.2.2.3.3 Operation Shutdown Modes The HI-STORM FW System is totally passive and consequently, operation shutdown modes are unnecessary.
1.2.2.3.4 Instrumentation As stated earlier, the HI-STORM FW MPC, which is seal welded, non-destructively examined, and pressure tested, confines the radioactive contents. The HI-STORM FW is a completely passive system with appropriate margins of safety; therefore, it is not necessary to deploy any instrumentation to monitor the cask in the storage mode. At the option of the user, temperature elements may be utilized to monitor the air temperature of the HI-STORM FW overpack exit vents in lieu of routinely inspecting the vents for blockage.
1.2.2.3.5 Maintenance Technique Because of its passive nature, the HI-STORM FW System requires minimal ma intenance over its lifetime. No special maintenance program is required. Chapter 10 describes the maintenance program set forth for the HI-STORM FW System.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-59 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelOb:rEG PROPRIETARY INFORMATIOl<l 1.2.3 Cask Contents This sub-section contains information on the cask contents pursuant to 10 CFR72, paragraphs 72.2(a)(l),(b) and 72.236(a),(c),(h),(m).
The HI-STORM FW System is designed to house both BWR and PWR spent nuclear fuel assemblies. Tables 1.2.1 and 1.2.2 provide key system data and parameters for the MPCs. A description of acceptable fuel assemblies for storage in the MPCs is provided in Section 2.1. This includes fue l assemblies classified as damaged fuel assemblies and fuel debris in accordance with the definitions of these terms in the Glossary. All fuel assemblies, non-fuel hardware, and neutron sources authorized for packag ing in the MPCs must meet the fuel specifications provided in Section 2.1. All fuel assemblies classified as damaged fuel or fuel debris must be stored in damaged fuel containers (DFC).
As shown in Figure 1.2. 1 (MPC-37) and Figure 1.2.2 (MPC-89), each storage location is assigned to one of three regions, denoted as Region 1, Region 2, and Region 3 with an associated cell identification number. For example, cell identified as 2-4 is Cell 4 in Region 2. A DFC can be stored in the outer peripheral locations of both MPC-37 and MPC-89 as shown in Figures 2. 1. l and 2.1.2, respectively. The pennissible heat loads for each cell, region, and the total canister are given in Tables 1.2.3 and 1.2.4 for MIPC-37 and MPC-89, respectively. The sub-design heat loads for each cell, region and total canister are in Table 4.4. 11 .
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-60 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC PROPRIETARY INFORMATION TABLE 1.2.l KEY SYSTEM DATA FOR HI-STORM FW SYSTEM lTEM QUANTITY NOTES 1 for PWR Types of MPCs 2 I for BWR MPC storage capacityf: MPC-37 Up to 37 undamaged ZR c lad PWR fuel assemblies with or without non-fuel hardware. Up to 12 damaged fuel containers containing PWR damaged fuel and/or fuel debris may be stored in the locations denoted in Figure 2 .1.1 with the remaining basket cells containing u ndamaged fuel assembl ies, up to a total of 37.
MPC storage capacity t: MPC-89 Up to 89 undamaged ZR clad BWR fue l assemblies. Up to 16 damaged fuel containers containing BWR damaged fuel and/or fuel debris may be stored in locations denoted in Figure
- 2. 1.2 with the remaining basket cells containing undamaged fuel assemblies, up to a total of 89.
t See Chapter 2 for a complete description of authorized cask contents and fuel specifications.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-61 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION TABLE 1.2.2 KEY PARAMETERS FOR HI-STORM FW MULTI-PURPOSE CANISTERS Parameter PWR BWR Pre-disposal service life (years) JOO 100 Design temperature, max./min. (F) 752t;_4o*tt 152t;_4ot 1*
Design internal pressure (psig)
Normal conditions 100 100 Off-normal conditions 120 120 Accident Conditions 200 200 Total heat load, max. (kW) See Table 1.2.3 See Table 1.2 .4 Maximum pennissible peak fuel cladding temperature:
Long Tem1 Nonna! (F) 752 752 Short Term Operations (F) 752 or 1058m 752 or I05gtt t Off-normal and Accident (F) 1058 1058 Maximum pennissible multiplication factor (k rr) 0
< 0.95 < 0.95 including all w1cc1iaintics and biases B4C content (by weight) (min.) in tbe Metamic-HT Neutron Absorber 10% .10%
(storaee cell walls)
(b)(4)
(b)(4)
End closure(s) Welded Welded Fuel handling Basket cell openings Basket cell openings compatible compatible witl1 standard with standard grapples grapples Heat dissipation Passive Passive t Maximum normal condition design temperatures for the MPC fuel basket. A complete listing of design temperatures for all components is provided in Table 2.2.3.
tt Temperature based on off-normal minimum environmental temperatures specified in Section 2.2.2 and no fue l decay heat load.
ttt See Section 4.5 for discussion of the applicabil ity of the 1058°F temperature limit during short-term operations, including MPC drying.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-62 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelOLTEG PROPRIETARY l~FORMA I ION TABLE 1.2.3 MPC-37 HEAT LOAD DATA (See Figure 1.2.1)
Number of Regions: 3 Number of Storage Cells: 37 Maximum Design Basis Heat Load (kW): 44.09 (Pattern A); 45.0 (Pattern B)
Region Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per No. kW per Region Region, kW Pattern A Pattern B Pattern A Pattern B 1 1.05 1.0 9 9.45 9.0 2 1.70 1.2 12 20.4 14.4 3 0.89 1.35 16 14.24 21 .6 Note: See Chapter 4 for decay heat limits per cell when vacuum drying high burnup fuel.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-63 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC F'ROF'RIETAR ( l~FORMATIOl<l TABLE 1.2.4 MPC-89 HEAT LOAD DATA (See Fiqure 1.2.2)
Number of Regions: 3 Number of Storage Cells: 89 Maximum Design Basis Heat Load: 46.36 kW Region No. Decay Heat Limit Number of Cells Decay Heat Limit per per Cell, kW per Reqion Reqion, kW 1 0.44 9 3.96 2 0.62 40 24.80 3 0.44 40 17.60 Note: See Chapter 4 for decay heat limits per cell when loading high burnup fue l and using vacuum drying of the MPC.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-64 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
1IOLTEC PROPRll:.TARY INFORMAi ION TABLE 1.2.5 CRITICALITY AND SHIELDING SIGNIFICANT SYSTEM DATA Item Property Value Metamic-HT Neutron Absorber Nominal Thickness (mm) 10 (MPC-89) 15 (MPC-37)
Minimum B4C Weight % 10 (MPC-89) 10 (MPC-37)
Concrete in HI-STORM FW Installed Nominal Density 150 (reference) overpack body and lid (lb/ft 3 ) 200 (maximum)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-65 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTEG PROPRIETARY INFORMATIOl<l TABLE 1.2.6 REF E RENCE ASME CODE P A RAGRAPHS FOR HJ-STORM F W OVERPACK and HJ-TRAC VW TRANSFER CASK , PRCMARY LOAD BEARING PARTS Item Code Notes, Explanation and Applicability Para2rapht
- l. Definition of primary and NF-1215 -
secondary members
- 2. Jurisdictional boundary NF-1 133 The " intervening elements" are termed interfacing SSCs in this FSAR.
- 3. Certification of material NF-2130 M aterials for lTS components shall be certified (b) and (c) to the applicable Section II of the ASME Code or equivalent ASTM Specification.
- 4. Heat treatment of materia l NF-2 170 -
and NF-2 180
- 5. Storage of welding material NF-2440, -
NF-4411
- 6. Welding procedw*c specification Section IX Acceptance Criteria per Subsection NF
- 7. Welding material Section 11 -
- 8. Definition of Loading conditions NF-3 11 1 -
- 9. Allowable stress values NF-3112.3 -
- 10. Rolling and sliding suooorts NF-3 124 -
- 11. Differential thermal expansion NF-3127 -
- 12. Stress analysis NF-3 143 Provisions for stress analysis for Class 3 linear NF-3380 structures is applicable for overpack top lid and NF-3522 the ovcrpack and transfer cask shells.
NF-3523
- 13. Cutting of plate stock NF-42 11 -
NF-4211.1
- 14. Forming NF-4212 -
- 15. Forming tolerance NF-4221 All cylindrical parts.
- 16. Fitting and Aligning Tack Welds NF-4231 -
NF-4231.1
- 17. Alignment NF-4232 -
- 19. Backing Strips, Peening NF-4421 Applies to structural and non-structural welds NF-4422
- 20. Pre-heating and Tnterpass NF-46 11 Applies to structural and non-structural welds Temperature NF-461 2 NF-461 3 2 1. Non-Destructive Examination NF-5360 InvokesSection V, Aoolies to Code welds only
- 22. NOE Personnel Certification NF-5522 Applies to Code welds only NF-5523 NF-5530 t All references to the ASME Code refer to applicable sections of the 2007 edition.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-66 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HObTEC PROPRIETARY INFORMATION TABLE 1.2.7
SUMMARY
REQUIREMENTS FOR MANUFACTURJNG OF HI-STORM FW SYSTEM COMPONENTS Item MPC Hl-STORMFW HI-TRAC VW Transfer Cask
- 1. Material Specification NB-2000 and ASME Section II ASME Section II ASME Section TI
- 2. Pre-welding operations (viz., NB-4000 Holtec Standard Holtec Standard cutting, fonning, and machining) Procedures (HSPs) Procedures (HSPs)
- 3. Weld wire NB-2000 and ASME Section II ASME Section II ASME Section TI
- 4. Welding Procedure ASME Section IX ASME Section IX ASME Section IX specifications and reference code and NB-4000 andASME for acceptance criteria Section III, Subsection NF
- 5. NDE Procedures and reference ASME Section V, ASME Section V, ASME Section V, code for acceptance criteria Subsection NB Subsection NF Subsection NF
- 6. Qualification Protocol for SNT-TC-I A SNT-TC-IA SNT-TC-IA Inspection Personnel
- 7. Cleaning ANSI N45.2. l ANSI N45.2. l ANSI N45.2.1 Section 2 Section 2 Section 2
- 8. Packaging & Shipping ANSI N45.2.2 ANSI N45.2.2 ANSI N45.2.2
- 10. Inspection and Acceptance Section 1.5 Section 1.5 Section 1.5 Drawings and Drawings and Drawings and Chapter 10 Chapter 10 Chapter 10
- 11. Quality Procedures Holtec Quality Holtec Quality Holtec Quality Assurance Assurance Assurance Procedures Procedures Procedures Manual Manual Manual HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-67 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
1'!0t:TEC PROPRIETARY INFORMATION I TABLE l.2.8a I (b)(4)
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-68 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
-MObTeC PROPRIETARY l~IFeRMA-fteN-TARI F' I J .8h I (b)(4)
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-69 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION TABLE 1.2.9 DESIGN OPTIONS FOR EXTRUDED BASKET SHIMS As-Built Maximum Average Emissivity of Average Cold Emissivity of Cold Radial Gap Option Extruded 2 Solid Shims3 Radial Gap Solid Sh ims After Solid Sh ims Basket Shims (inch) are Placed (inch)4 NOT Not 1 Note 1 ::: 0.281 Not Applicable REQUIRED Applicable 2 Note 1 > 0.281 REQUIRED Note 1 ::: 0.24 NOT Not 3 0.4 < 0.2 Not Applicable REQUIRED Applicable 4 0.4 > 0.2 REQUIRED Note 1 < 0.2 NOT Note 5 0.6 ::: 0.281 Not Applicable REQUIRED Applicable 6 0.6 >0.281 REQUIRED Note 1 < 0.24 Notes:
- 1. Emissivity must meet the requirements tabulated in Note 2 of Table 1.2.8.
- 2. This is the average total combined radial cold air gap between the basket and extruded shims, and the extruded shim and the inner surface of the MPC shell before the placement of solid shim plates.
- 3. Extruded shims are shaped to conform to the geometry of its intended annular space and sized to provide a loose fit in the basket periphery. If the as-built average total combined radial cold gap between the basket and extruded shims and the extruded shim and the inner surface of the MPC enclosure shell exceeds the gap tabulated herein, solid shim aluminum p lates shall be inserted in the space between the basket external wall and extruded shims.
- 4. The average total combined radial cold air gap between the basket and extruded shims and the extruded shim and the inner surface of the MPC shell must be below the value tabulated herein if solid shim plates are placed between the basket wall and extruded shim.
HOLTEC INTERNATIONAL COPYRIGHTED MA TERTAL REPORT HI-2114830 Rev. 5 1-70 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC F'RO~RIETARY lt~FORMATION TABLE 1.2.10 CRITERIA FOR SITE-SPECIFIC SAFETY QUALIFICATION OF HI-TRAC VW CASK VERSIONS (INCLUDING VERSION P)
- Consideration/Criterion Applicable Area Comment of Safety I The maximum loaded weight of Structural safety The mass of lead and water in the water the cask plus the hand ling j acket shall be optimized within the equipment during the in-plant constraint of the permitted dose rate in the handling evolutions must be less CoC to ensure that the crane's capacity is than the plant's crane capacity not violated.
2 The cask lifting features and the Structural safety The Version P trunnions and the cask's supporting cask structure must support structure shall meet the stress meet the safety margins of criteria of Table 2.2.6.
NUREG 0612 and Reg. Guide Tn chapter 3, the trunnions, cask support 3.6 l. structure, and bottom lid for Version P have been qualified for bounding weight with maximum length fue l listed in Table 3.2.8.
3 The top of the cask has provisions Structural safety For horizontal transfer cask operations, a against accidental ejection of the suitable anci llary that prevents an loaded MPC. (Horizontal transfer accidental ejection of the loaded MPC shall cask operations only) be designed within the architectural constraints of the site.
4 The available aggregate bolt pull Structural Safety These criteria seek to ensure that the cask in the bottom lid bolts will be water-tight when staged for draining corresponding to the Code and drying operations.
(Section III class 3) design stress In Chapter 3, the compliance with this of the bolt material does not criterion is demonstrated for the Version P exceed the apparent weight of the design shown in the Licensing drawing lifted load. carrying the max imum weight MPC per Table 3.2.8.
5 The Bottom flange gasket material Environmental -
is compatible with the pool's compatibility aqueous environment.
6 The coating used to protect the Material -
cask from c01Tosion is suitable for considerations its intended purpose.
7 The design includes a reliable Mechanical Required to prevent potential contamination (proven) annular seal design to Design of the external surface of the MPC protect against contamination of the MPC's external cylindrical surface.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-71 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATIOl<l TABLE 1.2.10 CRITERIA FOR SITE-SPECIFIC SAFETY QUALIFICATION OF HI-TRAC VW CASK VERSIONS (INCLUDING VERSION P)
- Consideration/Criterion Appl icable Area Comment of Safety 8 The primary bending stress in the Structural safety This analysis for HI-TRAC VW Version P bottom lid under the weight of the margm is documented in Chapter 3 of the FSAR.
loaded MPC must meet Level A improvement stress limit for NF class 3 structures. (The MPC's support surface on the bottom Lid may be preferably equipped w ith a suitable means to direct the MPC's weight towards the periphery of the Lid) 9 The top of the MPC properly Operational R ecommended to ensure a high q uality aligned with the top elevation of convenience weld outcome.
the transfer cask to permit ALARA edge welding and PT of the top lid welds.
10 The transfer cask's kinematic Structural safety A HERM IT (Holtec Patent No. 6 ,848,223 stability is established under all B2) may be used, if necessary, to ensure loading evolutions where the cask kinematic compliance (no tip-over or is freestanding. collision with a prox imate structure). Tn the case of an extremely severe earthquake, lateral restraints may be necessary. The k inematic response of the cask, because of its heavy wall and shtbby construction, may be simulated using rigid body dynamics.
11 The bolts j oining the Bottom Radiation A temporary shielding may be used to Flange to the bottom lid are protection reduce crew dose.
engineered for quick (A LARA) fastening and unfastening.
12 Careful consideration has been Operational Structural adequacy of the "stack" under given to ensuring that the safety the applicable earthquake must be interfacing ancillary (Mating demonstrated for the specific site.
Device) is compatible with the cask for safe MPC transfer.
13 The cask satisfies the CoC dose Mandatory Site specific demonstration necessary if not limit for the MPCs to be loaded. ALARA bounded by a previous analysis.
requirement 14 The cask protects the MPC from Mandatory for The analysis method used to demonstrate breach due to a missile impact site specific safety must have been approved !by the postulated in the plant's FSAR. safety evaluation. N RC in a Holtec docket.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-72 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTEG PROPRIETARY INFORMATIOl<l TABLE 1.2.10 CRITERIA FOR SITE-SPECIFIC SAFETY QUALIFICATION OF HI-TRAC VW CASK VERSIONS (INCLUDING VERSION P)
- Consideration/Criterion Appl icable Area Comment of Safety J5 The cask maintains the fuel The heat load in The horizontal configuration is thermally cladding temperature, T, within the loaded more limiting because the thennos-siphon ISG- 11 Rev 3 limits under the can ister must mode of heat rejection is partially disabled.
heat load of the MPCs to be meet the reduced loaded at the site under the capacity of the limiting condition (e.g. cask is transfer cask oriented in the horizontal when it is in the configuration) for the required non-vertical length of time. configuration 16 An active supplemental cooling - The operationa l reliability of the active device, if deployed to meet cooling system under normal and potential cladding temperature limit during accident conditions must be established Short Tenn Operations, has been consistent with the safety guideli nes in this qualified to be single failure FSAR by Holtec's corporate engineering.
proof.
17 The cask maintains the fuel This requirement Restricted ventilation space around the cladding temperature, T, within must be satisfied transfer cask and extremely high in building the applicable ISG-1 1 Rev 3 limit for the ambient temperature are among the plant's during Short Tenn operations. architectural architectural characteristics that must be constraints of the considered in the thermal qualification.
applicable plant site.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-73 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HO! r ec PROPRIET,t\RY INFORMATION 3-1 3-2 3-3 3-4 2-1 2-2 2-3 3-5 3-6 2-4 1-1 1-2 1-3 2-5 3-7 3-8 2-6 1-4 1-5 1-6 2-7 3-9 3-10 2-8 1-7 1-8 1-9 2-9 3-11 3-12 2-10 2-11 2-12 3-13 3-14 3-15 3-16 Legend Region-Cell ID Figure 1.2. l : MPC-37 Basket, Region and Cell Identification HOLTEC INTERNATIONAL COPYRIGHTED MA TERTAL REPORT HI-2114830 Rev. 5 1-74 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC PROPRIE I ARV INFORMA I ION 3-1 3-2 3-3 3-4 3-5 3-6 2-1 3-7 3-8 3-9 3-10 3-11 2-2 2-3 2-4 2-5 2-6 3-12 3-13 3-14 2-7 2-8 2-9 2-10 2-11 2-12 2-13 3-15 3-16 3-17 2-14 2-15 1-1 1-2 1-3 2-16 2-1 7 3-18 3-19 3-20 2-18 2-19 2-20 1-4 1-5 1-6 2-21 2-22 2-23 3-21 3-22 3-23 2-24 2-25 1-7 1-8 1-9 2-26 2-27 3-24 3-25 3-26 2-28 2-29 2-30 2-31 2-32 2-33 2-34 3-27 3-28 3-29 2-35 2-36 2-37 2-38 2-39 3-30 3-31 3-32 3-33 3-34 2-40 3-35 3-36 3-37 3-38 3-39 3-40 Legend Region-Ccll 10 Figure 1.2.2: MPC-89 Basket, Region and Cell Identification HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2 114830 Rev. 5 1-75 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HQI rec PROPRIETARY INFORMATION
- 1. MPC Placed in HI-TRAC 2. HI-TRAC Placement in the spent fuel pool
- 3. Fuel Loading into the MPC 4. HI-TRAC/MPC Removal from the spent fuel pool FIGURE 1.2.3:
SUMMARY
OF TYPICAL LOADING OPERATIONS HOLTEC ]NTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-76 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HQI rec PROPRIET.A.RY INFORMATION
- 7. System Stackup and MPC Transfer 8. HI-STORM Movement to the ISFSI Operations FIGURE 1.2.3 (CONTINUED):
SUMMARY
OF TYPICAL LOADING OPERATIONS HOLTEC ]NTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-77 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION 1.3 IDENTIFICATION OF AGENTS AND CONTRACTORS This section contains the necessary information to fulfill the requirements pertaining to the qualifications of the applicant pursuant to 10 CFR72.2(a)( 1),(b) and 72.230(a). Holtec International, headquartered in Marlton, NJ, is the system designer and applicant for ce11ification of the HI-STORM FW system.
Holtec International is an engineering technology company with a principal focus on the power industry. Holtec International Nuclear Power Division (NPD) specializes in spent fuel storage technologies. NPD has carried out turnkey wet storage capacity expansions (engineering, licensing, fabrication, removal of existing racks, perfom1ance of underwater modifications, volume reduction of the old racks and hardware, installation of new racks, and conunissioning of the fuel pool for increased storage capacity) in numerous nuclear plants around the world. Over 80 plants in the U.S.,
Britain, Brazil, Korea, Mexico and Taiwan have utilized the Company's wet storage technology to extend their in-pool storage capacities.
NPD is also a turnkey provider of dry storage and transportation technologies to nuclear plants around the globe. The company is contracted by over 40 nuclear units in the U.S. to provide the company's vertical ventilated dry storage technology. Utilities in China, Korea, Spain, Ukraine, and Switzerland are also active users of Holtec International 's dry storage and transport systems.
Four U.S. commercial plants, namely, Dresden Unit 1, Trojan, Indian Point Unit 1, and Humboldt Bay have thus far been completely defueled using Holtec International' s technology. For many of its dry storage cl ients, Holtec International provides a ll phases of dry storage including: the required site-specific safety evaluations; ancillary designs; manufacturing of all capital equipment; preparation of site construction procedures; personnel training; dry runs; and fuel loading. The USNRC dockets in parts 71 and 72 CU1Tently maintained by the Company are listed in Table 1.3. l Holtec Intemational's corporate engineering consists of professional engineers and experts with extensive experience in every discipline germane to the fuel storage technologies, namely structural mechanics, heat transfer, computational fluid dynamics, and nuclear physics. Virtually all engineering analyses for Holtec's fuel storage projects (including HI-STORM FW) are carried out by the company's full-time staff. The Company is actively engaged in a continuous improvement program of the state-of-the-art in dry storage and transport of spent nuclear fuel. The active patents and patent applications in the areas of dry storage and transport of SNF held by the Company (ca.
January 2009) are listed in Table 1.3.2. Many of these listed patents have been utilized in the design of the HI-STORM FW System.
Holtec International's quality assurance (QA) program was originally developed to meet NRC requirements delineated in ] OCFR50, Appendix B, and was expanded to include provisions of 10CFR71, Subpart H, and 10CFR72, Subpart G, for structures, systems, and components designated as important to safety. The Holtec qua lity assurance program, which satisfies all 18 criteria in 10CFR72, Subpart G, that apply to the design, fabrication, construction, testing, operation, modification, and decommissioning of structmes, systems, and components important to safety is HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-78 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION incorporated by reference into this FSAR. Holtec Intemational's QA program has been certified by the USNRC (Certificate No. 7 1-0784).
The HI-STORM FW System will be fabricated by Holtec International Manufacturing Division (HMD) located in Pittsburgh, Pennsylvania. HMD is a long term N-Stamp holder and fa bricator of nuclear components. In particular, HMO has been manufacturing HI-STORM and HI-STAR system components since the inception ofHoltec lnternational's dry storage and transportation program in the l 990s. HMO routinely manufactures ASME code components for use in the US and overseas nuclear plants. Both Holtec International' s headquarters and the HMO subsidiary have been subject to triennial inspections by the USNRC. If another fabricator is to be used for the fabrication of any part of the HI-STORM FW System, the proposed fabricator wilJ be evaluated and audited in accordance with Holtec Internationa l's QA program.
The Metamic-HT is fabricated by Holtec affiliate, Orrvilon located in Orrville, Ohio. Orrvilon's QA program is controlled by Holtec International. If another fabricator is to be used for the fabrication of Metamic-HT, the proposed fabricator will be evaluated and audited in accordance with Holtec lntemational 's QA program.
Holtec International's Nuclear Power Division (NPD) also carries out site services for dry storage deployments at nuclear power plants. Several nuclear plants, such as Trojan (completed) and Wate1ford (ongoing, ca. 2009) have deployed dry storage at their sites using a turn key contract with Holtec International.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-79 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC F'RO~RIETARY lt~FORMATION TABLE 1.3.l USNRC DOCKETS ASSIGNED TO HOLTEC INTERNATIONAL Svstem Name Docket Number HI-STORM 100 (Storage) 72-1014 ID-STAR 100 (Storage) 72- 1008 HI-STORM Flood/Wind (Storage) 72-1032 HI-STORM UMAX (Storage) 72-1040 ID-STAR 100 (Transportation)71-926 1 HI-STAR 180 (Transportation) 71-9325 ID-STAR 180D (Transportation) 71-9367 HI-STAR 60 (Transportation) 7 1-9336 Holtec Quality Assurance Program 71-0784 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-80 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
--t'lOLTEC PROPRleT,ARY INFORMATION TABLE 1.3.2 DRY STORAGE AND TRANSPORT PATENTS ASSIGNED TO HOLTEC INTERNATIONAL Colloquial Name of the patent USPTO Patent Number Honeycomb Fuel Basket 5,898,747 HI-STORM lOOS Overpack 6,064,710 Duct Photon Attenuator 6,519,307Bl HI-TRAC Operation 6,587,536Bl Cask Mating Device 6,625,246Bl (Hermetica lly Sealable Transfer Cask)
Improved Ventilator Overpack 6,718,000B2 Below Grade Transfer Facility 6,793,450B2 HERMIT (Seismic Cask Stabilization Device) 6,848,223B2 Cask Mating Device ( operation) 6,853,697 Davit Crane 6,957,942B2 Duct-Fed Underground HJ-STORM 7,068,748B2 Forced Helium Dehydrator (design) 7,096,600B2 Below Grade Cask Transfer Facility 7, 139,358B2 Forced Gas Flow Canister Dehydration 7,210,247B2 (alternate embodiment)
HI-TRAC Operation (Maximizing Radiation 7,330,525 Shielding During Cask Transfer Procedures)
HI-STORM l OOU 7,330,526B2 HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-81 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC F'RO~RIETARY lt~FORMATION 1.4 GENERIC CASK ARRAYS The HI-STORM FW System is stored in a ve1tical configuration. The required center-to-center spacing between the modules (layout pitch) on the Independent Spent Fuel Storage Installation (ISFSI) pad is guided by operational considerations such as size, access ibility, security, dose, and functionality. Tables 1.4.1, 1.4.2, and 1.4.3 provide the typical layout pitch information for 2 x N (N can be any integer), 3 x N (N can be any integer), and rectangular arrays, respectively.
The following is a generic discussion on the HI-STORM FW ISFSI pad, its suggested arrangement, and supporting infrastructure. The final design of the ISFSI is the responsibility ofthe user ofthe HI-STORM FW System.
The HI-STORM FW ISFSI pad is typically 24" to 28" thick, reinforced concrete supported by engineered fill with depth and properties selected to satisfy a site-specific design. The casks are arrayed in the manner of a rectilinear grid such as that shown in Figures 1.4.1 , 1.4.2, and 1.4.3. The pitch values in Table 1.4.1 may be varied to suit the user's s.pecific needs. The spacing (X, Y, etc., in the figures) is chosen to satisfy two competing requirements. Typically, the ISFSI owner desires to minimize the spacing in order to produce self-shielding between the storage casks, however the spacing must also be sufficient to allow the transporter access to emplace and remove the overpacks.
The HI-STORM FW spacing (pitch) shown in Table 1.4.1 are typical values that meet both competing requirements.
A Canister Transfer Facility (CTF) may be needed in the future (when the Fuel Building is no longer available) to remove the multi-purpose canister from the HI-STORM FW overpack and place it into a HI-ST AR transpo1t cask, suitable for offsite shipment. The MPC transfer should be performed in a controlled area. Therefore, the ISFSI facility should preferably be sized to accommodate the CTF; however the construction of t he CTF can be performed during a later development phase.
The general area surrounding the HI-STORM FW ISFSI pad will be graded to be compatible with the current drainage features, with additional storm water catch basins and piping added and incorporated into the existing storm water collection system, as necessary. The general area surrounding the ISFSI pad is typically covered with crushed stone or gravel to provide a suitable smface for the transporter and to prevent weeds and other unsuitable fo liage from sprouting.
The ISFSI should have an area designated as a HI-STORM FW fabrication pad. This area is used to prepare HI-STORM FW casks for concrete placement, assembly, touch-up painting, storage, and maintenance between the time of initial on-site delive1y and actual MPC transfer. An adjacent garage and maintenance shop may also be required for housing the transfer cask and ancillaries, such as the transporter, lifting appurtenances, etc.
If the ISFSI pad is located outside the plant's protected area, a security post building to provide a weather enclosure for temporary security guard support staffmay be needed during casks movement and facility access. The building would also provide a common termination point for security equipment wiring and the HI-STORM FW temperature monitoring data acquisition equipment, if used. A backup power diesel generator and associated transformers may be skid mounted on a pad HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-82 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOL'fEC PROPRIETARY INFORMATION adjacent to the security post.
The discussion of the security and related systems below presumes that the ISFSI is located outside the plant's protected area. The security requirements are adjusted accordingly if the ISFSI is located inside the plant's protected area.
The requirements on the security system provided below are generic and illustrative of the state-of-the-art practice, i.e., they are not meant to be mandatory provisions. The ISFSI owner bears the ultimate responsibility to comply with all security related regulations and mandates.
1.4.2 Security System and Other Ancillary Requirements A security system for the ISFSI wi ll be designed to include intrusion detection and camera systems, security fencing, lighting, isolation zones, monitoring systems, and electrical supply. The design must be integrated with the existing plant security system and its components. The system must meet the requirements of 10CFR72 and 10CFR73, and shall be integrated into the existing Plant's Physical Security Plan. The design of the security system shall also take into consideration the guidelines provided by NUREG-1619, NUREG-1497, and NRC Regulato1y Guide 5.44.
Electrical design features must also be included for HI-STORM FW temperature monitoring, HI-STORM FW grounding, and the storage/maintenance building, as required. The HI-STORM FW temperature monitoring system (if used) will include thermal detectors mounted directly to the overpacks. These detectors will provide continuous monitoring and data acquisition equipment to collect, process, and transmit data to a central computer system to allow frequent review of data results and to indicate any temperature alerts. The storage building should have sufficient electrical power supply to support lights, outlets, and power equipment associated with maintenance of HI-STORM FW anci llary equipment, such as the transpo1ter. In the event of loss of power to the site, a backup power supply is required.
1.4.2.1 Security System The ISFSI security system design shall provide the layout for all components and associated power and signal wiring. The security interface building located adjacent to the ISFSI would provide a transition point to connect all of the wiring to the existing plant power and data acquisition systems.
The ISFSI security systems will consist of two separate systems supplementing each other: perimeter intrusion detection system (PIDS) and a closed circuit television (CCTV) system. The PIDS will provide an alarm signal to the existing security system whenever one ofthe perimeter zones has been accessed without authorization. The CCTV system will provide assessment of the alarming zone.
Both of these systems have to work with each other in order to provide proper assessment. All signals generated by the security systems will be transmitted to the Central Alarm Station (CAS) through a robust communication means. The ISFSI security system design will be compatible with the plant's existing design.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-83 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelOLTEC PROPRIETARY l~FORMA I ION The security systems design will include details for PIDS mounting, CCTV system mounting, zone arrangements, fiber optic hardware/cable connections for ala1m and tamper, camera and microwave unit locations, and upgrades to the existing security system to accommodate the new ISFSI systems.
1.4.2.2 Lighting System The design of the lighting system includes light fixtme selection, quantity, mounting, and airnngement throughout ISFSI perimeter and the assessment of illumination levels in foot-candles.
The illum ination levels required at the perimeter area and inside the plant's protected area w ill be maintained at the ISFSI in accordance with plant commitments and regulatory requirements. The design will also include infrared illuminators to be installed, as an option with the CCTV system cameras to provide minimum light level required for IR sensitive cameras.
1.4.2.3 Fence System The design for ISFSI perimeter fence includes a double fence configuration. The inner fence will be the protected area perimeter and the outer fence will be a nuisance fence to establ ish the appropriate isolation zone. The typical fence arrangements, including man-gates; vehicle gates; and grounding details; will be based on the existing plant fence specifications and design standards.
1.4.2.4 Electrical System The conceptual des ign for the electrical system would entail the following activities and use their results as inputs:
- design for security systems (PIDS and CCTV)
- design for perimeter lighting system (PLS)
- design for temperature mon itoring system (TMS) ( if used)
- design for storage/support building The total ISFSI site load will determine what type and size of power source will be used in this application. The existing power distribution faci lities must be reviewed to determine a capability of the potential power sources. To be able to add the new ISFSI load to an existing system an analysis will be completed including the evaluation of the existing loads on 4160VAC line, cable sizes, and the approximate cable length. The transformers (4160-480V and 480-208/ 120V) will be sized accordingly to accommodate a new distribution system. The conceptual design will also include all the aspects of sizing a backup power distribution system based on providing a dedicated diesel generator as a source.
1.4.2.5 Cask Grounding System The design of the grounding system should be based on NEC requirements and engineering and plant practices. The new grounding system, if required, will SUITOund the TSFSI perimeter and provide a ground path for all ISFSI related equipment and structures including storage casks, microwave HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2 114830 Rev. 5 1-84 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
MOLTEC PROPRIETARY INFORMATlmJ equipment and mounting poles, camera and towers, security lighting, perimeter fences , and the security building at the ISFSI site. The grounding system will be connected to the primary source transformer ground.
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-85 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
1IOLTEC PROPRIETARY INFORMATlmJ TABLE 1.4.1 TYPICAL (AND MINIMUM) LAYOUT PITCH AND SPACING DIMENSIONS FOR HI-STORM FW ARRAYS Item Layout in Layout in Layout in Fbrure 1.4.1 Fhrure 1.4.2 Fi2ure 1.4.3 Xl 16 ft (15 ft) 16 ft (15 ft) 16 ft (15 ft)
Yl 16ft(15ft) 16 ft (15 ft) 16 ft (15 ft)
Y2 12 ft 12 ft NIA Y3 12 ft 12 ft NIA HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-21 14830 Rev. 5 1-86 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HO! rec PROPRleT,t\RY INFORMATION
-x,-
1 888 lI 8888 y2
+-'------ -------------.
Y, j
88808 88808 88808 88888 FIGURE 1.4.1: 2xN HI-STORM FW ARRAYS HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-87 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY IMFORMATION
- x ,- -
Y, 888 8888 8888 t---- - -------1 Y,
1 - . - - - - -- - - - - -
88888 88888 88888 FIGURE 1.4.2: 3xN HI-STORM FW ARRAYS HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 Rev. 5 1-88 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
HOLTEC PROPRIETARY lt~FORMATION 8
88 888 FIGURE 1.4.3: RECTANGULAR HI-STORM FW ARRAY HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 Rev. 5 1-89 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PRO~RIETARY INPORMATIOl<l 1.5 DRAWINGS The following HI-STORM FW System drawings are provided on subsequent pages in this section to fulfill the requirements in IO CFR 72.2(a)(l ),(b) and 72.230(a):
Drawing No. Title Revision 6494 HI-STORM FW BODY 18 6508 HI-STORM FW STANDARD LID 8 ASSEMBLY 65 14 HI-TRAC VW - MPC-3 7 9 6799 HI-TRAC VW - MPC-89 9 I0115 HT-TRAC VW Version P - MPC-89 1 6505 MPC-37 ENCLOSURE VESSEL 17 6506 MPC-37 FUEL BASKET 12 65 12 MPC-89 ENCLOSURE VESSEL 18 6507 MPC-89 FUEL BASKET 11 9964 HI-STORM FW Version XL Lid Assembly 3 10455 HI-STORM FW Domed Closure Lid 3 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 1-90 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
I IOLTEC PROPRIETARY INFORMATION
1.6 REFERENCES
[ 1.0.1] 10 CFR Part 72, "Licensing Requirements for the Independent Storage of Spent Fuel, High-level Radioactive Waste, and Reactor-Related Greater than Class C Waste",
Title l O of the Code of Federa l Regulations- Energy, Office of the Federal Register, Washington, D.C.
[l.0.2] Regulatory Guide 3.61 (Task CE306-4) "Standard Format for a Topical Safety Analysis Report for a Spent Fuel Storage Cask", USNRC, February 1989.
[l.0.3] NUREG-1536, "Standard Review Plan for Dry Cask Storage Systems", U.S. Nuclear Regulatory Commission, January 1997.
[l.0.4] Regulatory Guide 1.76 "Design-Basis Tornado and Tornado Missiles for Nuclear Power Plant", U.S. Nuclear Regulatory Commission, March 2007.
[ 1.1.1] ASME Boiler & Pressure Vessel Code, Section ill, Subsection NB, American Society of Mechanical Engineers, New York, 2007.
[ 1.1.2] I OCFR Part 50, "Domestic Licensing of Production and Utilization Facilities", Title 10 of the Code of Federal Regulations, Office of the Federal Register, Washington, D.C.
[1.1.3] USNRC Docket 72-1014, "Final Safety Analysis Report for the HI-STORM 100 System", Holtec Repo1t No. HI-2002444, latest revision.
[ 1.1.4] NUREG/CR-6407, "Classification ofTranspo1tation Packaging and Dry Spent Fuel Storage System Components According to In1portance to Safety", U.S. Nuclear Regulatory Commission, February 1996.
[ 1.2.1] U.S. NRC Information Notice 96-34, "Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket".
[1.2.2] American Concrete Institute, "Building Code Requirements for Structural Plain Concrete (ACI 318.1-89) (Revised 1992) and Commentary - ACI 3 18. lR-89 (Revised 1992)".
[ 1.2.3] ANSI N 14.6-1993, "American National Standard for Radioactive Materials - Special Lifting Devices for Shipping Containers Weighing l 0,000 Pounds (4,500 Kg) or More", American National Standards Institute, Inc. , Washington D.C., June 1993.
[ 1.2.4] Companion Guide to the ASME Boiler & Pressure Vessel Code, K.R. Rao (editor),
Chapter 56," Management of Spent Nuclear Fuel", Third Edition, ASME (2009).
[ 1.2.5] HI-STAR 180 Transportation Package, USNRC Docket No. 71-9325.
HOLTEC INTERNATIONAL COPYRIGHTED MATERTAL REPORT HI-2114830 Rev. 5 1-91 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017
lelObTi;C PROPRIETARY INFORMATION
[ 1.2.6] "Metamic-HT Qualification Sourcebook", Holtec Report No. HI-2084122, Latest Revision (Holtec Proprietary).
[ 1.2.7] "Metamic-HT Manufacturing Manual", Nanotec Metals Division, Holtec International, Latest Revision (Holtec Proprietary).
[l.2.8] Metamic-HT Purchasing Specification", Holtec Document JD PS-11 , Latest Revision, (Holtec Proprietary).
[l.2.9] Sampling Procedures and Tables for Inspection by Attributes", Military Standard MIL-STD-I 05E, (10/5/ 1989).
[ 1.2.1 O] USNRC Docket No. 72-1004 SER on NUHOMS 61BT (2002).
[1.2.11] Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Holtec International Report Hl-2022871 Regarding Use of Metamic in Fuel Pool A pplications," Facility Operating License Nos. DPR-5 1 and NPF-6, Entergy Operations, Inc. , docket No. 50-313 and 50-368, USNRC, June 2003.
[ 1.2.12] Dynamic Mechanical Response and Microstructural Evolution of High Strength Aluminum-Scandium (Al-Sc) Alloy, by W.S. Lee and T.H. Chen, Materials Transactions, Vol. 47, No. 2(2006), pp 355-363, Japan Institute for metals.
[1.2. 13] Turner, S.E., "Reactivity Effects of Streaming Between Discrete Boron Carbide Pa1t icles in Neutron Absorber Panels for Storage or Transport of Spent Nuclear Fuel," Nuclear Science and Engineering, Vol. 151, Nov. 2005, pp. 344-347.
[1.2. 14] Natrella, M.G., "Experimental Statistics", National Bureau of Standards Handbook 9 1, National Bureau of Standards, Washington, DC, 1963.
[1.2. 15] Technical Memo TM-141R l, NRC's Guidance on Design of Lifting Systems and Special Liftin g Devices Used in Holtec's Used Fuel Management Program, dated 4/15/ 15.
[ 1.2.16] ASTM C638- 14, "Standard Descriptive Nomenclature ofConstituents of Aggregates for Radiation-Shielding Concrete," American Society for Testing and Materials, June 20 14.
HOLTEC INTERNATIONAL COPYRIGHTED MA TERTAL REPORT HI-2114830 Rev. 5 1-92 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017