ML18264A149
| ML18264A149 | |
| Person / Time | |
|---|---|
| Site: | HI-STORE |
| Issue date: | 08/29/2018 |
| From: | NRC/OCIO |
| To: | |
| Shared Package | |
| ML18264A182 | List: |
| References | |
| FOIA, NRC-2018-000487 | |
| Download: ML18264A149 (684) | |
Text
ATIACHMENT 11 TO HOLTEC LETTER 5025012 AOL I EC PROPRIETARY llffORMATIGr~
Holtec Center, One Holtec Drive, Marlton, NJ 08053 Telephone (856) 797- 0900 HOLTEC INTERNATIO N AL Fax (856) 797 - 0909 STRUCTURAL CALCULATION PACKAGE FOR HI-STORE C/S FACILITY FOR HOLTEC Holtec Report No: Hl-2177585 Holtec Project No: 5025 Sponsoring Holtec Division: NPD Report Class : SAFETY RELATED COMPANY PRIVATE Page 1 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOB<l-EO'INtllff~NAL DOCUMENT NUMBER: HI-2177585 PROJECT NUMBER: 5025 DOCUMENT ISSUANCE AND REVISION STATUS DOCUMENT NAME: STRUCTURAL CALCULATION PACKAGE FOR I DOCUMENT CATEGORY: D GENERIC ~ PROJECT SPECIFIC HI-STORE CIS FACILITY REVISION No. Q REVISION No. - - REVISION No. - -
Document No.
Portiontt Author's Date Author' s Date Author's Date VIR # VIR # VIR #
Initials Approved Initials Approved Initials Approved
- l. MAIN AB 3/27/17 629350 SUPP 1 AK 3/27/17 454490 2.
SUPP 2 AK 3/27/ 17 15104 3.
SUPP 3 YC 3/27/ 17 580355 4.
3/27/17 8 18144
- 5. SUPP4 YC SUPP 5 DS 3/27/17 1397 17 6.
SUPP6 AB 3/27/17 119331 7.
SUPP 7 AR 3/27/17 32693 1 8.
SUPP 8 AR 3/27/ 17 807464 9.
SUPP9 PN 3/27/ 17 356967 10.
SUPP 10 PN 3/27/ 17 678835 11.
SUPP 11 RJ 3/27/1 7 748625 12.
SUPP 12 SP 3/27/17 544527 13.
SUPP 13 VM 3/27/17 563548 14.
SUPP 14 JZ 3/27/ 17 55113 15.
tt Chapter or secuon number.
Document #: HI-2177585 Project # : 5025 Form Last Revised 7/22/ 11 Holtec Form QA-18
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOM~PINl!lff~NAL DOCUMENT NUMBER* Hl-2177585 PROJECT NUMBER* 5025 DOCUMENT CATEGORIZATION In accordance with the Holtec Quality Assurance Manual and associated Holtec Quality Procedures (HQPs), this document is categorized as a:
Calculation Package3 (Per HQP 3.2) D 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 w ith the instructions of HQP 3 .2 or 3.4 except as noted below:
0vv ---*- - *- ,_L_,_., Privile"ed Intellectual Property contain extremely valuable intellectual/commercial * , ~::~..w mcernational. They cannot be released to external organizations or entities without explicit approva1 vi'" ~ . rne recipient ofHoltec's proprietary or Top Secret document bears full and undivided responsibility to safe1>11arci it-:-* ~-- v, uupucatton.
Notes:
- 1. 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 (VIR) 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 hjm.
- 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" .
Document#: HI-2177585 Project #: 5025 Form Last Revised 7/22/11 Holtec Form QA-18
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMATION Project 5025 HOLTEC PR-OPRIETARY Report HI-2 177585 HOLTEC SAFETY SIGNIFICANT DOCUMENTS In order to gain acceptance as a safety significant document in the company's qua lity assurance system, this document is required to undergo a prescribed review and concurrence process that requires the preparer and reviewer(s) of the document to answer a long list of questions crafted to ensure that the document has been purged of all errors of any material significance. A record of the review and verification activities is maintained in electronic fonn within the company's network to enable future retrieval and recapitulation of the programmatic acceptance process leading to the acceptance and release of this document under the company's QA system. Among the numerous requirements that this document must fu lfill, as applicable, to muster approval within the company's QA program are:
- The preparer(s) and reviewer(s) are technically qualified to perform their activities per the applicable Holtec Quality Procedure (HQP).
- T he input infonnation utilized in the work effort is drawn from referencable sources. Any assumed input data is so identified.
- A ll significant assumptions are stated.
- The analysis methodology is consistent with the physics of the problem.
- Any computer code and its specific versions used m the work have been fonnally admitted for use within the company's QA system.
- The fmmat and content of the document is in accordance with the applicable Holtec quality procedure.
- The material content of the report is understandable to a reader with the requisite academic training and experience in the underlying technical disciplines.
ATTACHMENT 11 TO HO LTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATIOf~
Project 5025 IIOLTEC PROPRIETARY Report HI-2177585 Once a safety significant document, such as th is report, completes its review and certification cycle, it should be free of any materially significant error and should not require a revision unless its scope of treatment needs to be altered. Except for regulatory interface documents (i.e., those that are submitted to the NRC in support of a license amendment and request), editorial revisions to Holtec safety significant documents are not made unless such editorial changes are deemed necessary by the Holtec Project Manager to prevent erroneous conclusions from being inferred by the reader. In other words, the focus in the preparation of this document is to ensure correctness of the technical content rather than the cosmetics of presentation.
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 5025 I IOLTEC PROPRIETARY Report HI-2 177585 HOLTEC SAFETY SIGNIFICANT DOCUMENTS ................................................................ I REVISION LOG ........................................................................................................................... 5 PREFACE...................................................................................................................................... 6
1.0 INTRODUCTION
AND SCOPE........................................................................................... 7 2.0 METHODOLOGY ................................................................................................................. 8 3.0 ACCEPTANCE CRITERIA .................................................................................................. 9 4.0 ASSUMPTIONS .................................................................................................................... 10 5.0 INPUT DATA ........................................................................................................................ 11 6.0 COMPUTER CODES .......................................................................................................... 12 7.0 ANALYSES ........................................................................................................................... 13 8.0 COMPUTER FILES ............................................................................................................. 14 9.0 RESULTS OF ANALYSES ................................................................................................. 15 10.0
SUMMARY
AND CONCLUSIONS ................................................................................. 16
11.0 REFERENCES
.................................................................................................................... 17 I l .I G ENERIC R EFERENCES ............................................ ............ .... .................... ............ .................................. 17 11.2 SPECIF JC REFERENCES ........................................................ ............................................ .......................... 18 12.0 LIST O:F SUPPLEMENTS ................................................................................................ 19 Supplement No. I - HI-TRAC CS Lifting Analysis ( 14 pages including cover page)
Supplement No. 2 - HI-TRAC CS Tornado Wind and Missile Analyses (28 pages inc luding cover page)
Supplement No. 3 - HT-STAR 190 Lift Yoke Stress Analysis (21 pages inc luding cover page)
Supplement No. 4 - HI-TRAC CS Lift Yoke Stress Analysis (21 pages inc luding cover page)
Supplement No. 5 - HI-TRAC CS Stack-up Analyses at CTF and UMAX (47 pages including cover page)
Supplement No. 6 - VCT, HT-TRAC CS and HI-STAR 190 Seismic Stability Evaluations (27 pages including cover page)
Supplement No. 7 - MPC Lift Attachment Stress Analysis ( 14 pages including cover page)
Supplement No. 8 - MPC Lift Attachment Connector Stress Ana lysis (16 pages including cover page)
Supplement No. 9 - HI-STAR 190 Horizontal Lift Beam Stress Analysis (35 pages including cover page)
ATTACHMENT 11 TO HO LTEC LETTER 5025012 HOLTEC PR.OPR.IETAR.V IIIJFOR.MATIOIIJ Project 5025 IIOLTEC PROPRIET~Y Report HI-2177585 Supplement No. 10 - Fatigue Evaluation of HI-TRAC CS and Lifting Ancillaries (17 pages including cover page)
Supplement No. 11 - CTB Slab and CTF Foundation Slab Structural Evaluations (27 pages including cover page)
Supplement No. 12 - HI-TRAC CS Lift Links Stress Analysis (9 pages including cover page)
Supplement No. 13 - HI-ST AR 190 Tilt Frame and Saddle Stress Analyses (56 pages including cover page)
Supplement o. 14 - Evaluation of CTB Collapse on HI-TRAC CS and HI-STAR 190 (17 pages including cover page)
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY INFORMATIOf~
Project 5025 IIOLTEC PROPRIETARY Report HI-2177585 REVISION LOG Revision O- Original Issue
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 5025 HOLTEC PROPRIETARY Report HI-2 177585 PREFACE This Calculation Package lhas been prepared pursuant to the prov1s10ns of Holtec Qua lity Procedures (HQPs) 3.0, 3.2 and 3.3, which require that all ana lyses utilized in support of the design of a safety-related or important-to-safety structure, component, or system be fu lly documented such that the analyses can be reproduced at any time in the future by a specialist trained in the discipline(s) involved. HQPs 3.2 and 3.3 set down a rigid format structure for the content and organization of Calculation Packages that are intended to create a document that is complete in terms of the exhaustiveness of content. The Calculation Packages, however, lack the narration smoothness of a Technical Report, and are not intended to serve as a Technical Report.
This Calculation Package acts as a compendium of all calculations supporting HI-STORE Consolidated Interim Storage (CIS) Faci lity that require supporting documentation that is not part of a stand-alone report. These calculations may support statements or summaries made in the Licensing Report on the HI-STORE CIS Facility (HI-2167374, Chapters 4 or 5 or 15). A di scussion of the technical work included may later be incorporated in the SAR as applicable.
Each calculation is self-contained and has a cover sheet that briefly identifies the purpose of the calculation and ties it to any associated electronic change order (ECO). Assumptions, references to fi nite e lement work, etc. are within the ind ividual calculation. Therefore, this report contains no " list of fi les" and its storage location is per the footer on this page. The HQP requirements for calculation packages are fo llowed to the extent practical within each calcu lation.
It is intended that updates to the report, in the form of supplements containing one or more individual calculations, will occur at reasonable intervals to maintain the document current. No new calculation may be referenced until it is officially made part of a supplement in this report and the report revision is updated.
Revisions shall be made, as necessary, to maintain the report as a living document.
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMAT IOt>l Project 5025 HOLTEC PROPRIETAR¥ Report HI-2 177585
1.0 INTRODUCTION
AND SCOPE This Calculation Package is compiled to provide archival infonnation to supplement the material presented in the HI-STORE CIS Facility SAR [11.2. l]. In particular, this Calculation Package contains structural and seismic calculations related to HI-TRAC CS transfer cask, HI-STAR 190 transport cask, Vertical Cask Transporter (VCT), Cask Transfer Building (CTB) slab and related ancillary equipment. The material presented in this Calculation Package is not needed to comprehend the material presented in the above-mentioned Technical Report (which is a self-contained document in full compliance with the USNRC regulations), unless the reader wishes to examine the computational detai ls. Herein, only specific "singular" calculations that support a specific SAR result are documented. Where a large body of calcu lations is necessary to support a SAR conclusion, this ca lculation package may be supplemented by other specialized reports that deal exclusively with the single topic requiring a substantial calcu lation effort. The resu lts from these specialized calculation packages are simply summarized in the SAR.
Because of its function as a repository of analyses performed on the subject of its scope, this document will be revised only if an error is discovered in the computations or the equipment design is modified. Additional analyses in the future, supporting either a new SAR ( or FSAR) amendment or a change supported by a 72.48 evaluation, will be added as numbered supplements to this Package. (Each time a supplement is added or the existing material is revised, the revision status of this Package is advanced to the next number and the Table of Contents is amended.)
In order to fully understand the format and layout of this Calculation Package, it is necessary to understand its two key attributes. First, unlike most calculation packages, this package contains a multitude of discrete analyses, all of which share a common body of input data, but are otherwise entirely distinct in their methods, models, and computer simu lations. Th is ca lculation package is in fact a compendium of an array of di stinct calculations.
All new SAR and FSAR submittals requiring structural calculations are supported by the work herein and by other specialized calculation packages.
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMATIOt>l Project 5025 HOLTEC PROPRIETARY Report HI-2177585 2.0 METHODOLOGY Calculation specific supplements are attached to this report. In general, the problem descriptions are provided in the introductory section of each calculation in the HI-STORE CIS Facility Licensing Report [ 11.2.1]. The problem descriptions, unique to each calculation, include the description of the component to be analyzed, the nature a nd source of the applied loading on the component, and the acceptance criteria. Where the calculation performed does not yet appear in summary form in the Technical Report, the calculation itself is complete insofar as having a full description of the problem, methodology, etc.
A ll structural and seismic calculations are either based on classical strength of materials solutions, or are based on finite element numerical analysis. Each calculation contains detailed explanation of the analysis methods. As noted earlier, th is Calcu lation Package contains supporting calculations for results that may only be summarized in the H I-STORE SAR [ 11.2.1].
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOL I EC PF\OF'F\IETA~'!' lt<Jt='ORMATIOM Project 5025 I IOLTEC PROPRIETARY Report HI-2177585 3.0 ACCEPTANCE CRITERIA This calculation package contains one or more supplements that deal with specific calculation items. If acceptance criteria are different for the individual calculations, then the appropriate acceptance criteria associated with each individual calculation are stated within the specific supplement.
The design criteria are compiled in Chapter 4 of the HI-STORE SAR [11.2.1). The design criteria represent the basis for the acceptance criteria for the design of the systems, structures and components (SSCs) at HI-STORE CIS Facility. The applicable stress limits for the primary steel structures at the HI-STORE CIS Facility are listed in Chapter 4 of HI-STORE SAR [11.2.1]. The components of HI-TRAC CS are designed to meet the stress limits of ASME Code,Section III, Subsection NF [11.1.6] per Chapter 4 of [l 1.2. l ]. The material properties of all steel structures used in the evaluations in thi s calculation package are obtained from one of the fo llowing:
iii. ASME Code,Section II, Part A [11. 1.3] and/or Part D [11.1.4) iv. ASTM Standards, ASTM International (specific standard will be referred to in applicable supplements)
- v. Material manufacturers' catalog for special materials (referred to in applicable supplements)
ATTACHMENT 11 TO HO LTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMATIOf~
Project 5025 IIOLTEC PROPRIETARY Report HI-2177585 4.0 ASSUMPTIONS In general, each calculation in this package contains a unique set of conservative analysis assumptions. In most cases these assumptions are listed under a separate section in each of the calculations; for some calculations that supplement work already detailed in the SAR or in another calculation, references are made to the originating document section for the assumptions.
Page 10 of 19 eaae.J3-0f ~,:1-
ATTACHMENT 11 TO HO LTEC LETTER 5025012 I IOLTEC PROPRIETARY l~JFORMATIOtil Project 5025 IIOLTEC PROPRIETA&Y Report HI-2177585 5.0 INPUT DATA Input data is provided in the calculation supplements as needed for the specific analysis. Data input requirements for geometry, material properties, design and acceptance criteria, and applicable load combinations along with their references are provided in individual supplements.
The sources of the input data that are repetitively used are listed as references in Section 11.
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOL'fEC PROPRIETARY INFORMATION Project 5025 HOLTEC PROPRIETARY Report HI-2177585 6.0 COMPUTER CODES The main section of this report is written using Microsoft Word, while the calculation supplements are prepared using Mathcad and/or Microsoft Word, and contain manual calculations and/or finite element resu lts. The computer codes used are documented and referenced within each supplement.
All computer codes used for the analysis and design of SSCs at HI-STORE CIS Facility are approved under Holtec's QA program. A complete listing of Holtec Approved Computer Program List is provided in [ 11.1.1 OJ.
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMATIOf~
Project 5025 IIOLTEC PROPRIET~Y Report HI-2177585 7.0 ANALYSES Analyses to support the SAR are contained in the form of supplements. As new supporting calculations are added, the revision log and the table of contents will note the additions or modifications to this document.
ATTACHMENT 11 TO HO LTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMATIOf~
Project 5025 IIOLTEC PROPRIETARY Report HI-2177585 8.0 COMPUTER FILES All relevant computer files associated with this calculation package are archived on the Holtec Server at: (b)( 4) l(b)(4) 1.
A directory listing appropriate to the supplements is included within each supplement.
ATTACHMENT 11 TO HO LTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 5025 IIOLTEC PROPRIETARY Report HI-2177585 9.0 RESULTS OF ANALYSES All calculations are documented, as appropriate, in Chapter 5 of HI-STORE SAR [ 11.2.1] along with a brief description of the analysis . The analysis evaluation contains details of the analysis results and the comparison of the result to the applicable code allowables. The design adequacy is also conclusively demonstrated by the computation of the positive margins of safety. The specific calculations within each supplement also evaluate, if applicable, the margins of safety and the results where applicable.
Page 15 of 19 Pr-allet.W-Of ~,:\*
- ATTACHMENT 11 TO HO LTEC LETTER 5025012 I IOLTEC PROPRIETARY ll'llf-ORMATION Project 5025 HOLTECPROPR:IETARY Report HI-2177585 10.0
SUMMARY
AND CONCLUSIONS This Calculation Package supports the structural integrity evaluations of the SSCs for HI-STORE CIF Facility required by the 10CFR 72 Submittal. All analysis calculations and documentation meet Holtec's QA requirements and procedures.
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY lt<JF'ORMATIOM Project 5025 HOLTEC PROPRIETARY Report HI-2177585
11.0 REFERENCES
- 11. 1 Generic References A comprehens ive list of a ll references that may be applicable to some or all of the specific calculations performed with in this document are given be low. Not all references need to be cited within th is document to be contained in thi s comprehensive li sting.
[11.1.1] NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants",
United States Nuclear Regulatory Commission, July 1980.
[11.1.2] ANSI N l4.6-1993, "American National Standard for Special Lifting Devices for Shipping Containers Weighing 10000 Pounds (4500 kg) or More for Nuclear Materials", American National Standards Institute, Inc.
[11. 1.3] ASME Boiler & Pressure Vessel Code, Section 11, Part A, 2010.
[11.1.4] ASME Boiler & Pressure Vessel Code,Section II, Part D, 2010.
[11.1.5] American Concrete Institute, "Building Code Requirements for Structural Concrete (ACI 3 18-05) and Commentary (ACI 3 l 8R-05)".
[11. 1.6] ASME Boiler & Pressure Vessel Code,Section III, Subsection NF, 2010.
[11.1.7] ASME Boiler & Pressure Vessel Code, Section ITT, Appendices, 2010.
[11.1.8] AISC, "Manual of Steel Construction", 9th Edition or later.
[11. 1.9] J. Shigley and C. Mischke, "Mechanical Engineering Design", 5th Ed ition or later, McGraw-Hill.
[11. 1. 10] Holtec Approved Computer Program List (ACPL), Revision 342.
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIET.A.RY lt>IFORM4!10N Project 5025 HOLTEC PROPIUETARY Report HI-2177585 11.2 Specific References In addition to the comprehensive reference list provided in Section 11. 1, additional specific references are cited below. Additional references, where applicable, are cited in the respective supplements.
[ 11.2.l] Licensing Report on the HI-STORE ClS Facility, H (-2 167374, Revision 0.
[ 11.2.2] Final Safety Analysis Report on the HI-STORM UMAX Canister Storage System, HI-2115090, Revision 3.
[ 11.2.3] Final Safety Analysis Report on the HI-STORM FW MPC Storage System, HI-2 11 4830, Revision 4.
[1 1.2.4] Holtec Drawings:
10868, HI-TRAC CS Licensing Drawing, Revision 0.
10875, HI-STO RM UMAX Vertical Ventilated Module, Version C, Revision 0.
10889, MPC Lifting Device Extension Licensing Drawing, Revision 1.
I 0891, MPC Lift Attachment Licensing Drawing, Revision I.
I 0894, Transport Cask Horizontal Lift Beam Licensing Drawing, Revision 0.
I 0895, Canister Transfer Facility (CTF) Licensing Drawing, Revision 0.
I 0899, T ilt Frame and Saddle L icensing Drawing, Revision 0.
I 0900, L ift Yoke for Hf-TRAC CS Licensing Drawing, Revision 1.
10901, HI-TRAC CS Lift Link Licensing Drawing, Revision 0.
I 0902, Lift Yoke for HI-STAR 190 Licensing Drawing, Revision I.
10912, Cask Transfer Building Floor Slab, Revision 0.
9841, HI-STAR 190 Cask Assembly Licensing Drawing, Revision 0.
Page 18 of 19 l?,,aae. 2T1 -Of,37,:1,
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY lt~FORMATION Project 5025 IIOLTEC PROPRIETARY Report HI-2177585 12.0 LIST OF SUPPLEMENTS Supplement No. Description In Support of Revision Specific Locations in SARt Subsection 5.4.2 1 HI-TRAC CS Lifting Analysis HI-STORE SAR 0 Table 5.4.2 Subsection 5.4.2 2 HT-TRAC CS Tornado Wind and Missile Analyses HT-STORE SAR 0 Table 5.4.3 Figure 5.4.2 Subsection 5.4.4 3 Hl-ST AR 190 Lift Yoke Stress Analysis HT-STORE SAR 0 Table 5.4.4 Subsection 5.4.6 4 HI-TRAC CS Lift Yoke Stress Analysis HI-STORE SAR 0 Table 5.4.6 Subsection 5.4.2 5 HI-TRAC CS Stack-up Analyses at CTF and UMAX HI-STORE SAR 0 Table 5.4.1 Figure 5.4. 1 VCT, HI-TRAC CS and HI-STAR 190 Seismic Stability Subsections 5.4.2 and 5.5.2 6 HI-STORE SAR 0 Evaluations Tables 5.4.7 and 5.5.2 Subsection 5.4.5 and Table 7 MPC Lift Attachment Stress Analysis HI-STORE SAR 0 5.4.5 Subsection 5.4.6 and Table 8 MPC Lift Attachment Connector Stress Analysis HT-STORE SAR 0 5.4.6 Subsection 5.4.6 and Table 9 HI-STAR 190 Horizontal Lift Beam Stress Analysis HI-STORE SAR 0 5.4.6 Fatigue Evaluation of HI-TRAC CS and Lifting Subsections 5.4.2 and 5.4.6 10 HI-STORE SAR 0 Ancillaries Tables CTB Slab and CTF Foundation Slab Structural Subsections 5.3.2 and 5.3.3 11 HI-STORE SAR 0 Evaluations Table 5.3.2 Subsection 5.4.6 and Table 12 Hl-TRAC CS Lift Links Stress Analysis HI-STORE SAR 0 5.4.6 Subsection 5.5.1 13 HI-STAR 190 Tilt Frame and Saddle Stress Analyses HI-STORE SAR 0 Table 5.5. 1 Evaluation of CTB Collapse on HI-TRAC CS and HI- Subsection 5.4.2 14 HI-STORE SAR 0 STAR 190 Figures 5.4.3 to 5.4.6 Twhere minor changes to a design parameter result in an insignificant effect on the computed safety factors, a revision of the results and associated data in the tables of the HI-STORE SAR [1 1.2.1] is not mandatory. The Unconditionally Safe Threshold (UST) value, as defined in Chapter 1 of HI-STORE SAR [11.2.1 ],
is set at 1.20 for all structural evaluations, i.e., only if a safety factor drops below 1.20 because of a design change, a revision to the results in the SAR is mandatory.
Page 19 of 19
.~2i'WC.- '
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEG PROPRle.TARY lt>I FORMAIION HOLTEC CALCULATION
Title:
HI-TRAC CS Lifting Analysis PROJECT No. - ECO No. - REV. No.: - 5025- -- -N/A- - -- -N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 1 CALCULATION
SUMMARY
INFORMATION Scope: This calculation involves the stress analysis of the lifting trunnions and the bottom lid of the HT-TRAC CS.
Method: The lifting trunnions and the bottom lid are analyzed using a mechanics of materials method with the trunnions considered as short beams and the bottom lid considered as a plate.
FSAR LOCATIONS Text (Chapter): Subsection 5.4.2 Tables: 5.4.2 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 ASK 03/16/2017 ARK& VRP 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5. 1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed change.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supportinri several ECOs.
Page 23 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMATION Project 5025 Heltee Preprietary Hl-2177585 SUPPLEMENT I - HI-TRAC CS LIFTING ANALYSIS 1.1 Introduction and Description This Appendix documents the structural analysis of the HI-TRAC CS under lifting conditions. The objective of this analysis is to demonstrate that under any lifting condition, the primary stresses in the lifting trunnions do not exceed allowable limits per [2.1]. In addition, the calculation also analyzes the H I-T RAC CS bottom lid under lifting loads. The Appendix is self contained; all references cited are listed in Section 1.5. All input dimensions are obtained from [ 1.5].
The HT-TRAC CS is equipped w ith four trunn ions (2 at top & 2 at bottom). T he top two trunnions are used for lifting and they must be capable of supporting a fu lly loaded HI-TRAC CS in a vertical orientation (i.e., a 2-point vertical lift). The bottom two trmrnions are used only for rotation during up-ending or down-ending the HI-TRAC CS.
The lifting trunnions are inserted into the hole on the cask which is welded to the body of the cask. The trunnions are welded to the cask she ll, the ribs and the inner shell wh ich prevents the trunnions from backing out.
The bottom lid is designed to withstand the weight of loaded MPC during lifting process.T he uniquely designed bottom lid slides and allow the loaded MPC to be transferred from HI-TRAC CS cask.
This Appendix is written using the Mathcad computer code [ 1.1]. The notation ":="
represents the equal sign for a defined calculation. The notation "=" represents a computed response or answer.
1.2 Methodology and Acceptance Criteria Methodology The lifting t:rnnnions are analyzed using mechanics of materials method with the trunnions considered as short beams. Stresses in both the trunnions and in the HI-TRAC CS cask are calculated under the specified load.
C lassical formulae of strength of materials and for plate stress are used fo r bottom lid.
Acceptance Criteria The two upper lifting trunn ions shall be designed to the meet the increased safety factors per ANS I N l 4.6 (i.e, lesser ofSy/6 and Su/ 10). Considering de sing safety factors against the material yield strength is conservative and is not mandated for the lifting attachments or points per [2. 1].
Supplement l - l of 13 Page 24 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HObTeC PROPRIETARY INFORMATION Project 5025 Holtes Proprietary Hl-2177585 A ll other steel members, includ ing welded connections, shall meet the Level A stress Limits per ASME Section III, Subsection NF.
The two bottom trnnnions shall meet the stress limits per ASME, Section ill, Subsection NF.
1.3 Materials and Material Properties l1.6)
The trnnnions are made ofSA-564 G r. 630 Hl 100 material.
The HI-TRAC CS cask material isA516 GRADE 70 matelial.
The shield gate spacer support material is A36.
The trnnnion material yield strength,@350°F [1.8] Sy:= 100.0-ksi The trnnnion material ultimate strength,@350°F [1.8] Su := 138.0* ksi The trnnnion material young modulus,@350°F [1.8] E := 29000-ksi The cask material yield strength,@350°F (Table 3.3.2 [1.6]) Syc := 33.05-ksi The cask material ultimate strength,@350°F (Table 3.3.2 [1.6]) Sue := 70.00* ksi The shield gate support material yield strength,@350°F ('fable 3.3.6 Sys := 31.30* ksi
[l .6])
The shield gate support material ultimate strength,@350°F (Table Sus := 58.00* ksi 3.3.6 [1.6])
1.3.1 Allowable stress 1.3.1.1 A llowable stress per ANSI N 14.6 [1.2] for trunnion (stress limits against material yield strength is conservatively considered).
Sy Su:
CTallowable := min ( - , - = 13800-psi 6 10 1.3.1.2 A llowable stress per ASME,Section III, Subsection NF [ 1.7] for Cask Bending, CTaJl_ben := 0.6Syc = 19830-psi Shear, CJall_shear := 0.40Syc = 13220-psi Supplement l - 2 of 13 Page 25 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLT EC PROPRIETARY llqfiORMATIOM Project 5025 Holtsc Proprietary Hl-2177585 Weld allowable, <:rall_weldl := min( 0.4*Syc, 0.3Suc) = 13220-psi CTall_weld2 := min(0.4*Sy5 , 0.3Sus) = 12520-psi 1.4 Assumptions (b)(4) 1.5 References
[1.1] MATHC AD 15.0, Parametric Technology Corporation, 201 1.
[1.2] ANSI N-14.6, Special Lifting Devices for Loads Over 10000 lbs.in Nuclear Plants, 1993.
[1.3] Crane Manufacturers A ssociation of America (CMAA), Specification #70, 1988, Section 3.3.
[ 1.4] J. Shigley and C. Mischke, Mechanical Engineering Design, McGraw-Hill, 5th Edition, 1989.
[ 1.5] Holtec drawing l 0868, HI-TRAC CS, Latest Revision.
[1.6] Holtec report Hl-2114830, HI-STORM FW FSAR, Revision 4.
[1.7] ASME Code,Section III, Division 1, Subsection NF, 2010.
[1.8] ASME Code, Section IT, Part D, 2010.
[1.9] Holtec drawing 10901 , HI-TRAC CS Lift Link, Latest Revision.
Supplement l - 3 of 13 Page 26 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATIOM Project 5025 Hellos Prnprietary Hl-2177585
[2.0] S.P T imoshenko, Strength of Materials, Part 1, 3rd Edition, McGraw-H ill, 1958, p.99.
[2.1] NUREG-0612, Control of H eavy Loads at Nuclear Power Plants Resolution of Generic Technical Activity A-36, Section 5.1.6(3), 1993.
1.6 Trunnion Analysis In this section, stresses in the tnmnion and the cask material are detennined. Stresses in the lifting trunnions (top trunnion) are compared to allowable strengths per ANSI N -14.6, and stresses in the cask are compared with appropriate allowable strengths from Subsection NF of the ASME Code.
1.6.1 Stresses in the Trunnion In this subsection, the geometry of the system is defined, and bending and shear stresses in the lifting trunnions are determined. The input lifted load is from Table 3.2.8 of [l .6].
1.6.1.1 Input Data (b)(4)
Supplement l - 4 of 13 Page 27 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMATION Project 5025 I loltec Proprietary Hl-2177585 (b)(4) 1.6.1.2 Bending Stress in the Trunnion (b)(4)
Supplement l - 5 of 13 Page 28 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 5025 I loltee Prowietary Hl-2177585 (b)(4) 1.6.1.3 Shear Stress in the Trunnion (b)(4) 1.7 Analysis of Bottom Trunnions The bottom two trunnions are used only as rotation trunnions for up-ending or down-ending for the HI-TRAC CS cask. They are not acting as lifting trunnions and therefore they need not be qualified as lifting trunnions per ANSI N 14.6 [1.2]. The bottom two trunnions may be used to suppo1t loads in excess of 50% (as the cg lies below of Centrex) of the loaded cask weight when it is lifted in a horizontal orientation and they need not be qualified per ASME,Section III, Subsection NF [ 1. 7].
Supplement l - 6 of 13 Page 29 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HObTe.C PROPRIETARY INFORMATION Project 5025 Holtes Prowietary Hl-2177585 Allowable stress per [ 1.2] is clearly bounding the allowable stress per [1. 7] which is shown in section 1.3.1.
As the design of the top andl bottom trunnions is same, hence, calculations for bottom trunnions are not warranted. The calculations for top trunnions presented above bounds for the bottom trunnions.
1.8 Bottom Lid Analysis In this section, bending stresses in the bottom lid is determined. Stress in the bottom lid is compared to allowable strengths per Subsection NF of the ASME Code.
1.8. 1 Input Data for bottom lid [l .5]
(b)(4) 1.8.2 Calculation of Bottom Lid Pressure Load (b)(4)
Supplement l - 7 of 13 Page 30 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOI TFC PROPRIETARY INFORMATION Project 5025 I k,ltes Propcieta[t_ Hl-2177585 (b)(4) 1.8.3 Calculation of Bottom Lid Stress (b)(4) 1.8.4 Weld between cask and shield gate top flange (b)(4)
Supplement l - 8 of 13 Page 31 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMA'flOlq Project 5025 Hallee Proprietary Hl-2177585 (b)(4)
Supplement l - 9 of 13 Page 32 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HQI TEC PROPRl5.TI\RY l~JJ;ORMATION Project 5025 Holtsc Proprietary Hl-2177585 (b)(4) 1.8.5 Weld between shield gate top flange and shield gate spacer support plates Supplement l - lO of l3 Page 33 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY lt<J fiORMAT ION Project 5025 I toltee Proprietary Hl-2177585 (b)(4)
Supplement l - 11 of 13 Page 34 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLT EG PROPRIETARY INFORMATION Project 5025 Hellos Proprietary Hl-2177585 (b)(4) 2.0 Computer files and locations Supplement l - 12 of l3 Page 35 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 5025 I leltec Proprietary Hl-2177585 3.0 Conclusion The HI-TRAC CS lifting trunnions and bottom lid meet the requirements of ANSI N14.6 and ASME, Section ID, Subsection NF for lifting heavy loads in a nuclear plant. Primary stresses in the top trunnions are less than one-tenth of the ultimate strength of the trunnion material.
Also, the stress in the bottom plate region meet the imposed stress limits from ASME section rn subsection NF [1.7].
Supplement 1 - 13 of 13 Page 36 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATIOM HOLTEC CALCULATION
Title:
HI-TRAC CS Tornado Wind and Missile Analyses PROJECT No. - ECO No. - REV. No.: - 5025- -- -N/A- - -- -N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 2 CALCULATION
SUMMARY
INFORMATION Scope: This objective of th is calculation is to determine the response of the Hf-TRAC CS to the combined load of the w i nd due to design basi s tornado and the l arge missile impact. It is demonstrated that under this loading condi tion, the cask w ill not tip over.
Method: The m ethodology i s described in Section 2.0 of thi s calculation.
FSAR LOCATIONS Text (Chapter): Subsection 5.4.2 and Figure 5.4.2 Tables: 5.4.3 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 ASK 03/16/2017 ARK& VRP 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5. 1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed change.
Note 1: All analyses performed to respond to a query or to initiate a desigrn change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supportinri several ECOs.
Page 37 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMAT IOt>l HOLTEC PROPRIETARY SUPPLEMENT 2 -HI-TRAC CS TORNADO WIND AND MISSILE ANALYSIS 1 Introduction The objective of this calcu lation is to detennine the response of the HT-TRAC CS to the combined load of the wind due to the design basis tornado and the large missile impact specified in HI-STORM FSAR[4.7]. It is demonstrated that under this loading condition, the cask will not tip over. The case oflarge missile impact plus the instantaneous pressure drop due to the tornado passing the cask is also considered. The two load cases need not be combined. Impacts from two types of smaller missiles are considered in Supplement 2A.
2 Method In this calculation, the cask is simultaneously subjected to a missile impact at the top of the cask and either a constant wind force or an instantaneous pressure drop leading to an impulsive adder to the initial angular velocity imparted by a missile strike. The configuration of the system just prior to impact by the missile is shown in Figure!.
The first step of the analysis is to determine the post-strike angular velocity of the cask, which is the relevant initial condition for the solution of the post-impact cask equation of motion. There are certain limiting assumptions that we can make to compute the post-impact angular velocity of the cask. There are three potential limiting options availab le.
- a. Assume a coefficient of restitution (ratio of velocity of separation to velocity of approach) = 1.
This assumption results in independent post impact motion of both the cask and the missile with the change in kinetic energy of the missile being entirely transmitted to the cask.
- b. Assume a coefficient of restitution = 0. This assumption resu lts in the missile and the cask moving together after the impact with a certain portion of the kinetic energy lost by the missile being dissipated during the collision so that the post impact kinetic energy is less than the energy change in the m issile.
- c. Assume a coefficient of restitution = mass of missile/mass of cask. This assumption b1ings the missile to rest after the impact. There is kinetic energy dissipated during the impact process but the kinetic energy acquired by the cask is larger than in case b.
Missile impact tests conducted under the auspices of the E lectric Power Research Institute [4. l]
have demonstrated that case c above matches the results of testing. Determination of the force on the cask due to the steady tornado wind is the next step. The primary tornado load is assumed to be a constant force due to the wind, acting on the projected area of the cask and acting in the direction that tends to cause maximum propensity for overturning.
Project 5025 Supplement 2-1 of 14 Hl-2177585 Page 38 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIET.A.RY lt>IFORMAIIQN HQLTEC PROPRIETARY The equation of motion of the cask under the wind loading is developed, and using the initial angular velocity of the cask due to the missile strike, the time-dependent solution for the post-impact position of the cask centroid is obtained.
In the second scenario, the missile impact occurs at the same instant that the cask sees the pressure drop due to the passing of the tornado.
3 Assumptions The assumptions for the analysis are stated here; further explanation is provided in the subsequent text.
(b)( 4)
Project 5025 Supplement 2-2 of 14 H l-2177585 Page 39 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY l~ffORMATIOM HOLTEC PROPRIETARY (b)(4) 4 References
[4.1] EPRI NP-440, Full Scale Tornado Missile Impact Tests, 1977.
[4.2] USNRC Regulatory Guide 1.76, Rev. 0.
[4.3] Fluid Mechanics w ith Engineering Applications, Daugherty, Franzini, and Finnemore, McGraw-Hill, 8th Edition, 1985.
[4.4] Hoerner Fluid Dynamics, 1965.
[4.5] Bechtel Topical Report BC-Top-9A, "Design of Structures for Missile Impact", Rev. 2.
[4.6] Holtec Drawing 10868, HI-TRAC CS, Rev.0.
[4.7] Holtec Report HI-2114830, HI-STORM FW FSAR, Revision 4.
[4.8] Holtec Report HT-2094392,Tomado Missile Analysis for HT-STORM FW System.
Project 5025 Supplement 2-3 of 14 Hl-2177585 Page 40 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HQI IEC PROPRIETARY lt>IFO~MA.TIOt>l HOLTEC PROPRIETARY 5 Input Data All dimensions and other inputs are taken from (4.6, 4.7& 4.8]. The input data necessary to perfo1m the analysis are as follows:
(b)(4)
Project 5025 Supplement 2-4 of 14 Hl-2177585 Page 41 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY l~ffORMAT IOM HOLTEC PROPRIETARY (b)(4) 6 Solution for Post-MissiMe Strike Motion of Cask (b)(4)
Project 5025 Supplement 2-5 of 14 Hl-2177585 Page 42 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY l~ffORMAT IOM I IOLTEG PROPRIETARY (b)(4) 7 Calculation of Pressure due to Tornado Wind (b)(4)
Project 5025 Supplement 2-6 of 14 Hl-2177585 Page 43 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTE:C F'F\OF'F\IE:T:A.Fh 11'1FO~MATIOM HOLTEC PROPRIETARY (b)(4) 8 Post Impact Plus Steady Wind Solution (b)(4) 9 Results for Impact Plus Steady Wind Project 5025 Supplement 2-7 of 14 Hl-2177585 Page 44 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMAT IOM I IOLTEG PROPRIETARY (b)(4) 10 Missile Impact Plus Pressure Drop (b)(4)
Project 5025 Supplement 2-8 of 14 Hl-2177585 Page 45 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION""
HOLTEC PROPRIETARY (b)(4) 11 Results for Impact plus Pressure Drop (b)(4) 12 Sliding under Large Missile Impact and Wind Load (b)(4)
Project 5025 Supplement 2-9 of 14 Hl-2177585 Page 46 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY l~ffORMAT IOM HOLTEC PROPRIETARY (b)(4)
Project 5025 Supplement 2-10 of 14 Hl-2177585 Page 47 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY IN FORMATION HOLTEG PROPRIETARY (b)(4) 13 Conclusion As is shown in Figure 2 and Figure 3, the maximum horizontal excursion of the cask midpoint (approximately equal to the cask center of gravity) under the given loading is less than 30 in. (Note that the only valid part of the figures is the region with positive angular movement). ln order for a cask tipover accident to occur, the centroid must undergo a horizontal displacement of 53 in. Therefore, the loadings from wind, tornado and missile strike events will not result in HI-TRAC tipover due to excessive sliding.
Project 5025 Supplement 2-1 I of 14 Hl-2177585 Page 48 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMAT IOt>l I IOLTEG PROPRIETARY (b)(4)
Figure 1 Free Body Diagram of Cask for Large Missile Strike/Tornado Event Project 5025 Supplement 2- 12 of 14 Hl-2177585 Page 49 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012
--; IOLTEC PROPRIET.A.RY lt>IFORMATION I IOLTEG PROPRIETARY (b)(4)
Figure 2 Centroid Motion - Impact/Wind Project 5025 Supplement 2-13 of 14 Hl-2177585 Page 50 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY l~ffORMATIOM HOLTEC PROPRIETARY (b)(4)
Figure 3 Centroid Motion - Impact/Pressure Drop Project 5025 Supplement 2- 14 of 14 Hl-2177585 Page 51 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMAT IOt>l HOLTEC PROPRIETARY SUPPLEMENT 2A-MISSILE PENETRATION ANALYSES FOR HI-TRAC CS 2A. l Introduction In this calculation, deformations and stresses in the HI-TRAC CS due to missile strikes are investigated. The objective of the analysis is to show that deformations in the HI-TRAC CS System due to the missile strike events do not compromise the containment boundary of the system, and that global stresses in the HI-TRAC outer shell that arise from the missile side strikes do not exceed the appropriate limits.
2A.2 References
[2A. 1] Holtec Report Hl-2167374, HI-STORE SAR, Revision 0.
[2A.2] Young, Warren C., Roark's Fonnulas for Stress and Strain, 6th Edition, McGraw-Hill, 1989.
[2A.3] Holtec Rep01t HI-2114830, HI-STORM FW FSAR, Revision 4.
[2A.4] Holtec Drawing 10868, H I-TRAC CS, Revision 0
[2A.5] Mathcad 15, Parametric Technology Corporation, 2011.
[2A.6] ASME Code,Section III, Appendix F, 2010.
[2A.7] American Concrete Institute, "Building Code Requirements for Structural Concrete", ACT-3 18-05.
2A.3 Composition This calculation was created using the Mathcad 15 [2A.5] software package. Mathcad uses the symbol':=' as an assignment operator, and the equals symbol'=' retrieves values for constants or variables. Mathcad's bu ilt-in equation solver is also used.
2A.4 General Assumptions and Bounding Missiles General assumptions that apply to all analyses in this calculation are stated here. Further assumptions are stated in the subsequent text.
(b)(4)
Project 5025 Supplement 2A-1 of 13 HI-2177585 Page 52 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012
-HOLTEC PROPRIETARY INFORMAT ION HOLTEC PROPRIETARY 2A.5 Impact of a 1-in Diameter Solid Sphere 2A.5.l Method The first step in the 1-in. diameter sphere missile impact analysis is an investigation of the elastic behavior of the cask component being impacted. By balancing the kinetic energy of the missile with the work done deforming the impacted surface, it is shown that the missile's energy w ill not be entirely absorbed by elastic defonnation. Therefore, the small missile will dent the cask. The elastic impact of the sphere is treated as a contact problem. The geometry is shown in Figure 2A. l.
For the 1-in Solid Sphere, the following impact is considered
- a. the outer shell of HJ-TR AC
- b. the closure lid of MPC Following the elastic investigation of the impact, a plastic analysis is perfo1med to detennine the depth of the dent.
2A.5.2 E lastic Analysis (b)(4)
Project 5025 Supplement 2A-2 of 13 H I-2177585 Page 53 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMAT IOM HOLTEC PROPRIETARY (b)(4)
Project 5025 Supplement 2A-3 of 13 HI-2177585 Page 54 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY IN FORMATION I IOLTEC PROPRIETARY (b)(4) 2A.5.3 Plastic Analysis (b)(4)
Project 5025 Supplement 2A-4 of 13 HI-2177585 Page 55 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY l~ffORMAT IOM I IOLTEC PROPRIETARY 2A.5.3.a. Strike on HI-TRAC CS outer shell (b)(4) 2A.5.3.b. Strike on top ofMPC closure lid (b)(4)
Project 5025 Supplement 2A-5 of 13 HI-2177585 Page 56 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMATIOt>l I IOLTEC PROPRIETARY 2A.5.4
Conclusion:
1-in. Diameter Sphere Missile Impact The depth of penetration of the small missile, which is required to absorb all of the impact energy, is less than the thinnest section of material on the exterior surface of the cask and MPC lid. Global stresses in the HI-TRAC that arise from the I-in. missile strike are assumed to be negligible.
2A.6 Impact of an 8-in. Diameter Rigid Cylinder 2A.6. l Method An 8-in. diameter cylindrical missile is postulated to impact the cask at the most vulnerable location, as shown in Figure 2A.2. The deformed shape is shown for the case where a steel shell formin g the HJ-TRAC outer shell is backed by concrete shielding.
The following two impact locations are investigated:
- a. Impact on the outer shell of HI-TRAC CS (with concrete backing)
- b. Impact on the closure lid of MPC Penetration is examined by balancing the kinetic energy of the missile with the work required to punch out a slug of the target material. Both the outer shell and the concrete neutron absorber material are considered to be active in resisting missile penetration in the case of a side strike.
Finally, global stresses in the HI-TRAC due to the 8-in. cylindrical missile impact are considered.
2A.6.2 Determination of Input Kinetic Energy (b)(4)
Project 5025 Supplement 2A-6 of 13 HI-2177585 Page 57 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY l~ffORMATIOM I IOLTEC PROPRIETARY (b)(4) 2A.6.3 Local Penetration Local penetration is examined by requiring that the impact force developed be balanced by only the resistance force developed in shear along the side area of a plug that would be punched out from an otherwise rigid mate rial. That is, a "shear plug" type of failure mechanism is assumed.
The failure mode is based on achievement of the ultimate stress in shear. If the steel plug is backed by additional load resisting material (the concrete shielding), then the confined compressive strength of the backing material also acts to resist the strike. The fo llowing two impact locations are examined:
- a. Penetration of the outer shell of HI-TRAC CS
Project 5025 Supplement 2A-7 of 13 HI-2177585 Page 58 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HObTeC PROPRIETARY INFORMATION HOLTEC PROPRIETARY (b)(4) 2A.6.3.b. Penetration of the MPC closure lid Local penetration is examined by requiring that the impact force developed is balanced by only the resistance force developed in shear along the side area of a plug that would be punched out from an otherw.ise rigid material. That is, a "shear plug" type of failure mechanism is assumed. The failure mode is based on achievement of the ultimate stress in shear.
Project 5025 Supplement 2A-8 of 13 HI-2177585 Page 59 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMAT ION HOLTEC PROPRIETARY (b)(4) 2A.6.4 Stresses in the HI-TRAC CS Due to 8-in. Rigid Cylinder Missile Strike (beam bending)
Global stresses in the HI-TRAC CS due to the side missile strike is examined in this subsection.
(b)(4)
Project 5025 Supplement 2A-9 of 13 HI-2177585 Page 60 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLT EG PROPRle.T.'\RY l~Ji;Q~MATION HOLTEC PROPRIET/\R¥ (b)(4) 2A. 7 Conclusion The above calculations demonstrate that the HI-TRAC CS provides an effective containment ban-ier for the MPC after being subjected to various missile strikes. No missile strike compromises the integrity of the boundary; furth er, global stress intensities arising from the side missile strikes satisfy ASME Code Level D allowable strengths away from the immediate vicinity of the loaded region.
Project 5025 Supplement 2A-l Oof 13 HI-2177585 Page 61 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY IN FORMAT ION I IOLTEC PROPRIETARY (b)(4)
Figure 2A. 1: Small Missile Impact Project 5025 Supplement 2A- I I of I 3 HI-2177585 Page 62 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOL'fEC PROPRIETARY IN FORMATION I IOLTEC PROPRIETARY (b)(4)
F igure 2A.2: Post Impact Deformation of HI-TRAC CS Outer Shell Backed by Concrete And Impacted by A Horizontal Missile Strike Project 5025 Supplement 2A- I2 of I 3 HI-2177585 Page 63 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETAR.'!' lt<J FO~MATION HOLTEC PROPRIETARY (b)(4}
Figure 2A.3: Missile Strike at Top of HI-TRAC CS Project 5025 Supplement 2A-l 3 of 13 HI-2177585 Page 64 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HObT eC PROPRleT.'\RY l~Ji;QRM.'\TIOt>l HOLTEC CALCULATION
Title:
ID-STAR 190 Lift Yoke Stress Analysis PROJECT No. - ECO No. - REV. No.: - 5025- . --N/A-- . --N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 3 CALCULATION
SUMMARY
INFORMATION Scope: This supplement presents the structural qualification of the lift yoke for lifting loaded HI-STAR 190 with its two upper trunnions.
Method: Strength of materials fonnulations is used for the analysis.
FSAR LOCATIONS Text (Chapter): Subsection 5.4.4 Tables: 5.4.4 REVISION LOG Rev. No. Prei;>arer Initials /Date Reviewer Initials /Date 0 YC 03/24/2017 VM 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HOP 5.1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed chan(le.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supportinq several ECOs.
Page 65 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIETARY l~ffORMATION HOLTEG PROPRIETARY Hl-21775851 SUPPLEMENT 3: HI-STAR 190 LIFT YOKE STRESS ANALYSIS
3.1 INTRODUCTION
The purpose of this supplement is to demonstrate that the load bearing parts of the Lift Yoke (LY) for HI-STAR 190 meet all requirements for the in-plant handling of heavy loads.
3.2 METHODOLOGY, ACCEPTANCE CRITERIA AND ASSUMPTIONS The analyses are carried out using strength of materials formulations for statically determinant components.
For design without redundant load paths, the maximum stress in any load bearing component, per [3.1) and [3.21, shall not exceed the minimum of one-tenth of the material ultimate tensile strength and one-sixth of the material yield strength.
60% of the tensile allowable is used as the shear allowable. There is no limit set on local bearing stress in (3.1) and (3.2) and also it is a secondary stress; the limit on bearing stress is set at yield strength to ensure that there is no change in hole shape during load testing of 3 times the lifted load without dynamic load factor.
(b)(4)
3.3 REFERENCES
(3.1] U.S. NRC NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, 1980.
[3.2] ANSI N14.6, Special Lifting Devices for Shipping Containers Weighing 10000 Pounds (4500 kg) or More, 1993.
(3.3] HI-STORM FW FSAR, Holtec Report Hl-2114830, Revision 4.
(3.4] Holtec Licensing Drawing 10902, Lift Yoke for HI-STAR 190, Revision 1.
(3.5] Holtec Licensing Drawing 9841, HI-STAR 190 Cask Assembly, Revision 0.
[3.6] CMAA Specification #70, Crane Manufacturers of America, 1988.
(3.7] ASME BTH-1-201 1, Design of Below-the-Hook Lifting Devices, January 2012.
(3.8] A514/A514M-14, Standard Specification for High-Yield-Strength, Quenched and Tempered Alloy Steel Plate, Suitable for Welding, ASTM International Standard Specification, 2014.
(3.9] ASME Boiler and Pressure Vessel Code,Section II, Part D, Properties, 2010.
[3.10] ASME Boiler and Pressure Vessel Code, Section 11 , Part A, Materials, 2010.
[3.11] Holtec Report Hl-2146286, Thermal Evaluations of HI-STAR 190 System, Revision 3.
Supplement 3: 3-1 of 3-20 Page 66 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLTEC PROPRIETARY INFORMATION I IOLTEC PROPRIETARY Hl-21775851 3.4 INPUT DATA 3.4.1 Lifted Weight (b)(4)
Supplement 3: 3-2 of 3-20 Page 67 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLTEC PROPRIETARY INFORMATION HOLTEC PROPRIETARY Hl-21775851 3.4.2 Material Properties (b)(4)
Supplement 3: 3-3 of 3-20 Page 68 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLTEC PROPRIETARY l~ffORMATIOM HOLTEC PROPRIETARY Hl-21775851 3.4.3 Dimensions 3.4.3.1 Strongback (Item 1 of [3.4])
(b)(4)
Supplement 3: 3-4 of 3-20 Page 69 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLTEC PROPRIETARY INFORMATIOt>l HOLTEC PROPRIETARY Hl-21775851 3.4.3.2 Lift Arm (Item 2 of [3.41)
(b)(4) 3.4.3.3Actuator Plates {Item 4 of [3.41)
(b)(4)
Supplement 3: 3-5 of 3-20 Page 70 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HObT!aC PROPRle.T.'\RY INFORMAT ION I IOLTEC PROPRIETARY Hl-21775851 (b}(4}
3.4.3.4 Pins (b}(4}
Supplement 3: 3-6 of 3-20 Page 71 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PR:Of3R:IETAR:'1' lt<JF'OR:MATIOM I IOLTEG PROPRIETARY Hl-21775851 3.5 CALCULATIONS 3.5.1 Allowable Stresses (b)(4)
Supplement 3: 3-7 of 3-20 Page 72 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLTEC PROPRIETARY IN FORMATION I IOLTEC PROPRIETARY Hl-21775851 3.5.2 Strongback Plates 3.5.2.1 Tension in Strongback Plates (b)(4) 3.5.2.2 Tearout in Strongback Main Pin hole (b)(4)
Supplement 3: 3-8 of 3-20 Page 73 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HObTeC PROPRIETARY lt>IFORMATION HOLTEC PROPRIETARY Hl-21775851 (b)(4) 3.5.2.3 Bearing stress in Strongback Main Pin hole (b)(4) 3.5.2.4 Single plane fracture in Strongback Main Pin hole (b)(4)
Supplement 3: 3-9 of 3-20 Page 74 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIETARY INFORMAT IOM HOLTEC PROPRIETARY Hl-21775851 (b)(4) 3.5.2.5 Strongback bending at Main Pin hole cross-section (b)(4)
Supplement 3: 3-10 of 3-20 Page 75 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIETARY lt<J f='O~MATION HOLTEC PROPRIETARY Hl-21775851 (b)(4) 3.5.3 Lift Arm Plates 3.5.3.1 Tension in Lift Arm Plates (b)(4) 3.5.3.2 Bearing Stress at Lift Arm Trunnion Holes (b)(4)
Supplement 3: 3-11 of 3-20 Page 76 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 AOL I EC PROF'~IETAR:Y lt~FORMATION HOLTEC PROPRIETARY Hl-21775851 (b)(4) 3.5.3.3 Single Plane Fracture at Lift Arm Trunnion Holes (b)(4)
Supplement 3: 3-12 of 3- 20 Page 77 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HObTeC PROPRleTARY l~Ji;QRMATIOt>l HOLTEC PROPRIETARY Hl-21775851 (b)(4) 3.5.3.4 Tearout at Lift Arm Tnunnion Holes (b)(4) 3.5.3.5 Shear in Lift Arm Tabs (b)(4)
Supplement 3: 3-13 of 3-20 Page 78 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIETAR'1 ll~FORMA I ION I IOLTEC PROPRIETARY Hl-21775851 (b)(4) 3.5.4 Actuator Plates 3.5.4.1 Tension in Actuator Plates (b)(4) 3.5.4.2 Bearing Stress in Lift Arm Tab hole (b)(4)
Supplement 3: 3-14 of 3-20 Page 79 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIE I AR V INFORMA I ION I IOLTEC PROPRIETARY Hl-21775851 (b)(4) 3.5.4.3 Tearout in Lift Arm Tab hole (b)(4) 3.5.4.4 Tearout in Actuator Pin hole (b)(4)
Supplement 3: 3-15 of 3-20 Page 80 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLTEC PROPRIETARY INFORMATION HOLTEC PROPRIETARY Hl-21775851 (b)(4) 3.5.4.5 Single Plane Fracture at the Actuator Pin hole (b)(4) e 3.5.5 Main Pins l(b)(4)
Supplement 3: 3-16 of 3- 20 Page 81 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLT EC PROPRIETAR:'!' lt<JF'O~MATION I lOLTEG PROPRIETARY Hl-21775851 3.5.5.1 Main Pin bending stress (b)(4) 3.5.5.1 Main Pin shear stress (b)(4)
Supplement 3: 3-17 of 3- 20 Page 82 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HObTeC PROPRleT.'\RY l~Ji;QRM.'\TIOt>l I IOLTEC PROPRIETARY Hl-21775851 (b)(4) 3.5.6 Actuator Pins 3.5.6.1 Actuator Pin bending stress (b)(4)
Supplement 3: 3-18 of 3-20 Page 83 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIETARY INFORMATION HOLTEC PROPRll::TAR v Hl-21775851 3.5.6.2 Actuator Pin shear stlJ'e ss (b)(4) 3.6 COMPUTER CODES .AND COMPUTER FILES MathCad 15.0 is used to prepare this supplement. The com puter files associated with this analysis are stored in Holtec's network at the following location:
3.7 FIGURES Direction of applied load Cu rved edge R
- - - + - - - - ' - CL hole Figure 3.1: Inputs Used for Single Plane Fracture and Double Plane Shear (from [3. 71)
Supplement 3: 3-19 of 3- 20 Page 84 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMA'flOM Project 5025 I IOLTEC PROPRIET,t1-.RY HI-2 177585 Strenx 900 General Product Descr iption Strelll( 900 is a general structural steel that. de~nd1ng on thickness. guarantees a m1n1mum yield strength of up to 900 MPo. Strenx 900 meets the requirements of EN IO 025 Gfor the S 890 grode and thicknesses. Typical applications ore demanding load bearing structures.
Avolloble dimensions Strerl( 900E 1s 011ciloble In plate lh1cknesses of 4 100 mm and Strenx 900f rs ovo1loble In the thickness range up to 80 mm. Both grades ore ovoilcole 1n widths up to 3350 mm and lengths up to 14630 mm depending on thickness. More detailed information on omens1ons 1s pr0111ded In the dimension program at www.ssob.com.
Mechanica l Properti es
- 4 . ~J (53)
- 100 Yield strength "
R or Min MPo 900 830 Tensile strength "
R.Mln MPo 940* 1100 880* I 100 FonrO!l!>l.1.'rse 1es1 f)jt'Cesoccord1ng to EN 10025.
- 12 12 Impact properlles W:*i**Cl*bMW:*i**ld*41 I mp.1ct energy (Jl for tC\tS on tramver,;c Charpy V !Ox 10 mm testS ~pccimens 21 27 J 27 J Meet the requ1rcmcntS for 890 QL S 890 QL I
'Unll'SSOther..i~!' O\YC'C'd transvNse 1111>oct trs11ng according to CN 10 02S-6 op1ion 30 ..ii ~ply. For 1hk:knesses bet..<'Pn 6
- 11.9 mm slAl-we Chorpyll-\peclm('ll!, ore ll'>ed. Thi' spec1ll cd mlnmum vo~e ~ tll.:in propationol to lhP cross-secuonol aco ol the specmen compacd too lll-sile spe>clmen (10 x 10 mm).
Chemical Composit ion (ladle analysis) 0.20 OJO 1.(,() 0.020 0.0 10 The s1ee1 ~ gron re110ed. *1n1enliono1 aloylng elements.
Maximum carbon equillolent CET (CEV) 0.80 O.JO 2.0 0.70 0.00.~
Thickness mm *--*1":rl!ll,@*11*1111!1!:ri!IIJ§*j,~j***
'lu e.nx 900: C. ld (O.V) 0.39 (OJS) 0.41 (0.63)
(E.T. C+ ~ + Cr + Cu
- NI CEV
- C+ -'iP- +
c, .. Mo
- II
- _Cul_*S_NI IU --Z0 -;j1f www.ssab.com I SSAB Figure 3.2: WELDOX Datasheet Supplement 3: 3-20 of 3-20 Page 85 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IOLT EC PROPRIETARY INFORMATION HOLTEC CALCULATION
Title:
HI-TRAC CS Lift Yoke Stress Analysis PROJECT No. - ECO No. - REV. No.: - 5025- . --N/A-- . --N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 4 CALCULATION
SUMMARY
INFORMATION Scope: This supplement presents the structural qualification of the lift yoke for lifting loaded HI-TRAC CS w ith its two upper trunnions.
Method: Strength of materials fonnulations is used for the analysis.
FSAR LOCATIONS Text (Chapter): Subsection 5.4.6 Tables: 5.4.6 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 YC 03/24/2017 VM 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5.1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed chanoe.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet} supporting several ECOs.
Page 86 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIETARY INFORMAT IOM HOLTEC PROPRIETARY Hl-21775851 SUPPLEMENT 4: HI-TRAC CS LIFT YOKE STRESS ANALYSIS
4.1 INTRODUCTION
The purpose of this supplement is to demonstrate that the load bearing parts of the Lift Yoke (LY) for HI-TRAC CS meet all requirements for the in-plant handling of heavy loads.
4.2 METHODOLOGY, ACCEPTANCE CRITERIA AND ASSUMPTIONS The analyses are carried out using strength of materials formulations for statically determinant components.
For design without redundant load paths, the maximum stress in any load bearing component, per [4.1] and [4.2], shall not exceed the minimum of one-tenth of the material ultimate tensile strength and one-sixth of the material yield strength.
60% of the tensile allowable is used as the shear allowable. There is no limit set on local bearing stress in [4.1] and [4.2] and also it is a secondary stress; the limit on bearing stress is set at yield strength to ensure that there is no change in hole shape during load testing of 3 times the lifted load without dynamic load factor.
(b)(4)
4.3 REFERENCES
(4.1] U.S. NRC NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, 1980.
[4.2] ANSI N14.6, Special Lifting Devices for Shipping Containers Weighing 10000 Pounds (4500 kg) or More, 1993.
(4.3] HI-STORM FW FSAR, Holtec Report Hl-2114830, Revision 4.
(4.4] Holtec Licensing Drawing 10900, Lift Yoke for HI-TRAC CS, Revision 1.
(4.5] Holtec Licensing Drawing 10868, HI-TRAC CS, Revision 0.
[4.6] CMAA Specification #70, Crane Manufacturers of America, 1988.
(4.7] ASME BTH-1-201 1, Design of Below-the-Hook Lifting Devices, January 2012.
(4.8] A514/A514M-14, Standard Specification for High-Yield-Strength, Quenched and Tempered Alloy Steel Plate, Suitable for Welding, ASTM International Standard Specification, 2014.
(4.9] ASME Boiler and Pressure Vessel Code,Section II, Part D, Properties, 2010.
[4.10] ASME Boiler and Pressure Vessel Code, Section 11 , Part A, Materials, 2010.
Supplement 4: 4-1 of 4-20 Page 87 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIETARY INFORMATION HOLTEC PROPRl6TARY Hl-21775851 4.4 INPUT DATA 4.4.1 Lifted Weight (b)(4)
Supplement 4: 4-2 of 4-20 Page 88 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HObTEC PROPRIET.'\RY l~Ji;QRM.'\TIOt>l I tOLTEC PROPRIETARY Hl-21775851 4.4.2 Material Properties (b)(4)
Supplement 4: 4-3 of 4-20 Page 89 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLT EG PROPRle.T.'\RY l~Ji;Q~MATION HOLTEC PROPRIETARY Hl-21775851 4.4.3 Dimensions 4.4.3. 1 Strongback (Item 1 of [4.4])
(b)(4)
Supplement 4: 4-4 of 4-20 Page 90 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025
---1 IOLTEC PROPRIET.A.RY lt>IFORMATION HOLTEC PROPRIETARY Hl-21775851 4.4.3.2 Lift Arm (Item 2 of [4.41)
(b)(4) 4.4.3.3Actuator Plates {Item 4 of [4.41)
(b)(4)
Supplement 4: 4-5 of 4-20 Page 91 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLTEC PROPRIETARY lt<J F'ORMATIOl<J HOLTEC PROPRIETARY Hl-21775851 (b)(4) 4.4.3.4 Pins (b)(4)
Supplement 4: 4-6 of 4-20 Page 92 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIETARY l~ffORMATION I lOLTEC PROPRIETARY Hl-21775851 4.5 CALCULATIONS 4.5.1 Allowable Stresses (b)(4)
Supplement 4: 4-7 of 4-20 Page 93 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLTEC PROPRIETARY l~ffORMATION HOLTEC PROPRIETARY Hl-21775851 4.5.2 Strongback Plates 4.5.2.1 Tension in Strongback Plates (b)(4) 4.5.2.2 Tearout in Strongback Main Pin hole (b)(4)
Supplement 4: 4-8 of 4-20 Page 94 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HObTeG PROPRIETARY lfqt='O~MATION HOLTEC PROPRIETARY Hl-21775851 (b)(4) 4.5.2.3 Bearing stress in Strongback Main Pin hole (b)(4) 4.5.2.4 Single plane fracture in Strongback Main Pin hole (b)(4)
Supplement 4: 4-9 of 4-20 Page 95 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOL'fEC f3R:Of3R:IE'fAR:'1' INFORMA'flOM HOLTEC PROPRIETARY Hl-21775851 (b)(4) 4.5.2.5 Strongback bending at Main Pin hole cross-section (b)(4)
Supplement 4: 4-10 of 4- 20 Page 96 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOL I EC F'F\Ol'IR:IETAR:Y INFORMATION HOLTEG PROPRIETARY Hl-21775851 (b)(4) 4.5.3 Lift Arm Plates 4.5.3. 1 Tension in Lift Arm Plates (b)(4) 4.5.3.2 Bearing Stress at Lift Arm Trunnion Holes (b)(4)
Supplement 4: 4-11 of 4- 20 Page 97 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLTEC PROPRIETARY llq t='ORMATIOM HOLTEC PROPRIETARY Hl-21775851 (b)(4) 4.5.3.3 Single Plane Fracture at Lift Arm Trunnion Holes (b)(4)
Supplement 4: 4-12 of 4-20 Page 98 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HGbTEG PROPRIETAFh INFORMA I ION I IOLTEC PROPRIETARY Hl-21775851 4.5.3.4 Tearout at Lift Arm Tnunnion Holes (b)(4) 4.5.3.5 Shear in Lift Arm Tabs (b)(4)
Supplement 4: 4-13 of 4- 20 Page 99 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLT EC PROPRIETARY lt<JF'ORMATIOM HOLTEC PROPRIETAR v Hl-21775851 4.5.4 Actuator Plates 4.5.4.1 Tension in Actuator Plates (b)(4) 4 .5.4.2 Bearing Stress in Lift Arm Tab hole (b)(4) 4.5.4.3 Tearout in Lift Arm Tab hole l[b)(4)
Supplement 4: 4-14 of 4-20 Page 100 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f21il8f21illET! !Ill!: 114Pelll!ruh ,.ie11 I liLTliw 12fiililiilfiillliT:R:fiilY Hl-21775851 (b)(4) 4.5.4.4 Tearout in Actuator Pin hole (b)(4) 4.5.4.5 Single Plane Fracture at the Actuator Pin hole (b)(4)
Supplement 4: 4-15 of 4- 20 Page 101 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 t liLTii 12JiilQl2~1iiTP ~)( ltl509'10IIOM I l@LTE!e F Fl!Oi ICIE!I AR I Hl-21775851 (b)(4) 4.5.5 Main Pin The Main Pins allow the lift yoke to be lifted by a crane hook. The pin is subjected to bending moments and shear forces. The bending stresses are evaluated by conservatively considering the pin as a simply-supported beam with the load acting as a point load at the center of the beam.
4.5.5.1 Main Pin bending stress (b)(4)
Supplement 4: 4-16 of 4-20 Page 102 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 IIOE I EC F P\OF ICIE!TJt" I 114P@lill:1/:'li,81l I IGiH,TliiiG RRORRlliiiIORX Hi-21775851 (b)(4) 4.5.5.1 Main Pin shear stress (b)(4) 4.5.6 Actuator Pins (b)(4)
Supplement 4: 4-17 of 4- 20 Page 103 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f21ii1JET;SJ~.\f IIJFBliill:1/:TIBIJ I IBl!TEB f2~8121iillliif:R:liill:' Hl-21775851 4.5.6.1 Actuator Pin bending stress (b)(4) 4.5.6.2 Actuator Pin shear stress (b)(4)
Supplement 4: 4-18 of 4- 20 Page 104 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!TE!e P~Bf2(iil:l[T;3 (iii)( ltlfiliill12li1Qtl IProject 5025 I IBl!Tl!:8 P~8P~IET; tli'.: Hl-21775851 (b)(4) 4.6 COMPUTER CODES AND COMPUTER FILES MathCad 15.0 is used to prepare this supplement. The computer files associated with this analysis are stored in Holtec's network at the following location:
4.7 FIGURES Direction of applied load Cu rved edge
,r-/ I I
R
- --+-- ~ CL hole Figure 4.1: Inputs Used for Single Plane Fracture and Double Plane Shear (from (4. 71)
Supplement 4: 4-19 of 4- 20 Page 105 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 1162126 F ICGI ICIEIAiCI 11&1 bi<IOIAIIOIQ Project 5025 J18Isifie0 PRQP~ UH O Q Y HI-2 177585 Strenx 900 General Product Descr iption Strelll( 900 is a general structural steel that. de~nd1ng on thickness. guarantees a minimum yield strength of up to 900 MPo. Strenx 900 meets the requirements of EN IO 025 Gfor the S 890 grade and thicknesses. Typical applications ore demanding load bearing structures.
Available dimensions Strerl( 900E1s ovciloble In plate thicknesses of 4 100 mm and Strenx 900f rs ovo1loble In the thickness range up to 80 mm. Both grades ore ovoil<ille 1n widths up to 3350 mm and lengths~ to 14630 mm depending on thickness. More detailed information on omens1ons 1s provided In the dimension program at www.ssob.com.
Mechanica l Properti es 4 -U (53)
- 100 Yield strength "
R or Min MPo 900 830 Tensile strength "
R.Mln MPo 940- 1100 880- 1100
.. 12 12 FonrO!l!>l.1.'rse 1es1 PH'Cesoccord,ng to EN 10025.
Impact properlles W:*i**Cl*bMW:*i**ld*41 I mp.ice energy (Jl for tc~ts on trmwcr,;c Charpy V IOx 10 mm resis ~pccimcns 21 27 J 27 J Mm the rcqurrcmencs for 890 QL S 890 QLI
'Unll'SSOther..isr O!YN'd transvNse 1"1)0Ct 11'\llllQ according to CN 10 02S-6 op1ion 30 ..ii ~ply. For 1hlcknesses bet..rrn 6
- 11.9 mm slAl-we ChorpyV-\peclmrn!, ore ll'>ed. The spec1ll cd mlnmum vo~e ~ tll.:in propationol to lhP cros~-secuonol aco ol 1he specmen compcrcd too lll-sile spe>clmen (10 x JO mm).
Chemical Composit ion (ladle analysis}
0.20 oso 1.60 0.020 0.0 10 The s1ee1 ~ gron re110ed. *1n1enliono1 aloylng elements.
Maximum carbon equivalent CET (CEV) 0.80 O.JO 2.0 0.70 0.00.~
Thickness mm *+**1":\l!'l*@*11*11ll!l!+"'ii*1,~1,1*
'lu enx 900: C. 1:..1 (Cl:.V) 0.39 (OS8) 0.4 t (0.6.l J (E.T. C+ ~ + Cr + Cu
- NI CEV*C + ~
c,
- Mo t V
- _Cu1_*5_NI IU -zrr- 4Q +
www.ssab.com I SSAB Figure 4.2: WELDOX Datasheet Supplement 4: 4-20 of 4-20 Page 106 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I liLTii 12Jiilil2JiilliT t Jiill' ltlFS.liilt12 TIS.ti HOLTEC CALCULATION
Title:
HI-TRAC CS Stack-up Analyses at CTF and UMAX PROJECT No. - ECO No. - REV. No.: - 5025- -- -N/A- - -- -N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 5 CALCULATION
SUMMARY
INFORMATION Scope: This supplement presents the Stack-up analyses of the HT-TRAC CS at HJ-STORE Canister Transfer Facility (CTF) and UMAX ISFSI pad in the event of a design basis earthquake.
In addition to evaluating the stability of the stack, structural evaluations of all components in the load path are also perfonned.
Method: The seismic analysis is performed using LS-DYNA. ANSYS and strength of materials formulations are used to perform structural evaluations of the HI-TRAC CS components in the load path.
FSAR LOCATIONS Text (Chapter): Subsection 5.4.2 Tables: Table 5.4.1 Figures: Figure 5.4.1 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 DS 03/24/2017 AB 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5. 1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed chanqe.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supporting several ECOs.
Page 107 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!Tl!e Plll.ePlll.ll!l:\~:V IIJFBlill:1:S.'lilBll Project 5025 Supplement 5 - Stack-up Analysis Hl-2 177585 SUPPLEMENT 5: HI-TRAC CS STACK-UP ANALYSIS AT CTF ANDUMAX REVISION LOG Revision O- Initial issue
1.0 INTRODUCTION
AND SCOPE This supplement presents the seismic analysis of the HI-TRAC CS (HT) [I ] at the Canister Transfer Facility (CTF) [2] and on the HI-STORM UMAX at the ISFSI pad location [3]. The HI-STAR 190 (without the lid) [1 2) is positioned in the CTF cavity with the Adapter Plate [2]
centered on top. The HI-TRAC CS is placed on top of the Adapter Plate and bolted down using the Anchor Rods [2] to the Cask Transfer Building (CTB) slab [4]. The fue l transfer operation is performed by lifting the sealed MPC, which contains spent fue l assemblies, into the empty HT-TRAC CS. The loaded HI-TRAC CS is subsequently transferred to the TSFST pad. The HI-STORM UMAX (without the lid), which is an in-ground Vertically Ventilated Module (VVM),
sits w ith its top just above the JSFSJ top grade level. To carry out the MPC transfer operation, the HT transfer cask is mounted atop the recipient HI-STORM UMAX. The fuel transfer operation is performed by lowering the sealed MPC into the empty HI-STORM UMAX storage module.
The seismic analyses are performed for the bounding case of MPC in the HI-TRAC C S at both locations.
This ca lculation package a lso presents the structural qualification of the HT Shield Gate weldment, the connections between HT and CTB slab, and between the HT and HJ-STORM UMAX Cavity Enclosure Container (CEC) under the design basis earthquakes.
The fo llowing are the objectives of the current supplement:
- 1. Perform a time history analysis to evaluate the stability of the Hi-STORM UMAX/Hl-TRAC stack using the applicable modified real recorded time history set in three Page 1 of 9 Page 108 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IIOE I EC F P\OF ICIE!TJt" I 114Pefll:1:S.'li,81l Project 5025 Supplement 5 - Stack-up Analysis Hl-2 177585 orthogonal directions (east-west, north-south, and vertical). A single time history analysis is appropriate as the system is linear with bolted HI-TRAC CS.
- 2. Determine the maximum loadings at the bolted connections under seismic conditions for the stack. Subsequently, perform a structmal evaluation of the HT Shield Gate weldment, and the bolted connections to demonstrate the ir structural adequacy and establish the corresponding margins of safety.
- 3. Determine the maximum bearing load imposed on the CTB slab and ISFSI pad by the stack during seismic activity. Subsequently, perform a structural evaluation of the CTB slab and ISFSI pad to demonstrate adequate concrete bearing capacity.
2.0 METHODOLOGY AND ANALYSIS (b)(4)
Page 2 of 9 Page 109 of 371
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 I liLTii 12!.Qlil~liiTP 9'6 ltl509'10IIOM Project 5025 Supplement 5 - Stack-up Analysis Hl-2 177585 (b)(4) 3.0 ASSUMPTIONS The fo llowing assumptions are made in the stack-up analysis:
(b)( 4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IQmifliiQ 121iilQl21iillliiif Pliil)( It IFQliilt10 ifIQt I Project 5025 Supplement 5 - Stack-up Analysis Hl-2 177585 4.0 RESULTS The maximum displacements recorded at the top of the Hf-TRAC CS in the X and Y directions (refer to Figure 1 for model orientation) are negligible (i.e. less than 0.1 inches). Hence, there is no potential for impact between the HT and VCT or other adjacent structures during stack-up.
Also, as the HI-TAC CS is bolted to the CEC/CTB slab and all connections are structurally qualified, there is no concern of the stack tipping over duting a design basis earthquake.
The bolted connections between the HI-TRAC CS and CEC/CTB slab anchor blocks are evaluated in Appendix B. The peak tensi le are shear loads from the DECE analysis are conservatively evaluated against Level B allowables to show that all safety factors are greater than 1.0.
The structural evaluation of the Shield Gate weldment is performed in Appendix C. Since the Shield Gate supporting plate structure is modeled in sufficient detail in LS-DYNA, all plate stresses are directly exported from the LS-DYNA results and compared with the stress allowable.
The Shield Gate itself is analyzed in ANSYS [ 11] using a bounding load from the LS-DYNA analysis. Other components and welds that are not explicitly modeled are evaluated using bounding loads obtained from the analysis results. All components are shown to have safety factors greater than 1.0.
Finally, the bearing load imposed by the HI-TRAC CS on the ISFSI pad through the CEC top cover plate is eva luated in Appendix D. The peak load between the HI-TRAC CS and the CEC top cover plate is used to calcu late the safety factor for bearing on the ISFSI pad concrete and is shown to be greater than 1.0. This envelopes the bearing stresses in the CTB slab as the contact area is greater on the CTB slab and concrete properties are identical.
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5.0 CONCLUSION
S The following conclusions are deduced from the detailed results presented in this calculation package:
- 1. The kinematic stability of the stack is satisfied under seismic conditions.
- 2. The HT to CEC/CTB slab interface bolted connections are structurally adequate to withstand the loads from the analysis.
- 3. The load bearing components and welds in the HT Shie ld Gate weldment are structurall y adequate to withstand the loads from the analysis.
- 4. The ISFSI pad and the CTB slab concrete has adequate bearing capacity to withstand the loads from the analys is.
- 5. The stack alo ng w ith its internals (MPC, fuel basket and fuel assemblies, as applicab le) will remain intact during and after a seismic event.
6.0 REFERENCES
[1] Holtec Drawing 10868, "HI-TRAC CS", Revision 0.
[2] Holtec Drawing I 0895, "Canister Transfer Facil ity (CTF)", Revision 0.
[3] Holtec Drawing 10875, "HI-STORE UMAX Vertical Ventilated Module Version C",
Revision 0.
[4] Holtec Drawing 10912, "Cask Transfer Building Floor Slab", Revision 0.
[5] Holtec Report HJ-2 167374, "Licensing Report on the HI-STORE C IS Facility",
Revisio n 0.
[6] Holtec Report HI-2146083, "Regulatory Guide 1.60 T ime Histories Using EZ-FRISK",
Revision 2.
[7] NUREG 0800, Standard Review Plan 3.7. I , Revisio n 3, March 2007.
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[8] Holtec Report Hl-2115090, "HI-STORM UMAX FSAR", Revision 3.
[9] LS-DYNA Version 971 , Livermore Software Technology, 2012.
[10] Holtec Generic Report Hl-2135676, "NRC-Concurred Seismic Analysis Methodology for the HI-STORM/HI-TRAC Stack using LS-DYNA", Revision 1.
[11] ANSYS Version 17.1, SAS IP, Inc., 2016.
[ 12] Holtec Drawing 9841, "HJ-STAR J90 Cask Assembly", Revision 0.
[13] ASME Boiler and Pressure Vessel Code,Section III, Subsection NF, 2010.
[14] ASME Boiler and Pressure Vessel Code,Section III, Appendices, 2010.
[15] ASME Boiler and Pressure Vessel Code,Section II, Part D, Properties, 2010.
[ 16] Building Code Requirements for Structural Concrete (ACI 3 18-05) and commentary (ACT 318R-05), American Concrete Institute, 2005.
[17] U.S. Nuclear Regulatory Commission, Regulatory Guide 1.61, "Damping values for Seismic Design of Nuclear Power Plants", Revision 1, March 2007.
[ 18] AISC Steel Construction Manual, 13111 Ed ition.
[19] Machinery's Handbook, 27:h Edition, 2004, Industrial Press, Inc.
[20] Holtec Report HI-2146279, "Seismic Analysis of Stack-up and HI-STORM's Egress and Structural Qualification of Floor and Mating Device for Clinton Power Station",
Revision 4.
[21] Holtec Report HI-2114830, "HI-STORM FW FSAR", Revision 4.
[22] Holtec Approved Computer Program List, Revision 342.
[23] Shigley's Mechanical engineering Design, 81h Edition.
[24] Holtec Position Paper DS-307, "Construction of True Stress-Strain Curve for LS-DYNA Si mulations", Revi sion 2.
[25] Holtec Report HI-2094353, "Analysis of the Non-Mechanistic Tipover Event of the Loaded HI-STORM FW Storage Cask", Revision 12.
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 I 162 I ec PROFRl2 I AR f IIQFORIVIA I IOIQ Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 7.0 FIGURES (b)(4)
Figure 1: LS-DYNA Model of Stack-up Page 8 of 9 Page 115 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f2(iilJ[lJtlll!: 114Pelll!ruh ,.ie11 Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 8.0 COMPUTER CODES AND FILES This safety analysis summary is prepared in Microsoft Office Word. The appendices of this calculatio n package are prepared in Matbcad. Finite Element analyses are performed using LS-DYNA [9] and ANSYS [11). Computers 141 6 and 141 7 are used for running LS-DYNA, and computer 1189 is used for running ANSYS. These computers are verified for the computer codes in question per [22).
All relevant computer files associated with this revision of the calculation package are archived on the Holtec Server under:
Revision 0: G:\ Projects\5025\REPORTS\Structural Reports\HI-2 177585 (HI-STORE C ISF Cale Package)\REV O\Supplement 5 9.0 APPENDICES Appendix A - Inputs used in the LS-DYNA Stack-up Model Appendix B - Stack-up Bolting and Anchor Block Evaluation Appendix C - Shield Gate Weldment Structural Evaluation Appendix D - ISFSI Pad Concrete Bearing Evaluation Page 9 of 9 Page 116 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I 1621 EC F ICOF l(IEIAiCI 11&1 Oi<IOIAI IOI&
Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 Appendix A: Inputs used in the LS-DYNA Stack-up Model (b)(4)
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Figure A.1 : Loaded HI-TRAC CS CG and Mass Properties from Solidworks APPENDIX A - Page A- 2 of 6 Page 118 of 371
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 HO! IEG RRORRliiTPliil:l6 ltlFiliillPlilitl Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 Appendix B: Stack-up Bolting and Anchor Block Evaluation Introduction The f inite element analysis of the HI-STORM UMAX/HI-TRAC stack provides the maximum load s realized by the HI-TRAC-to-HI-STORM UMAX CEC/CTB slab bolts during design extended conditions earthquake (DECE) and safe shutdown earthquake (SSE). Using the bounding loads at these bolted connections, out put from LS-DYNA , the following sections evaluate the bolts, anchor blocks, and supporting connections . Conservatively, the DECE results are compared with Level B allowables.
Hence, the SSE results do not need to be evaluated separately. The following points are noted:
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 Appendix C - Shield Gate Weldment Structural Evaluation C.1 - Shield Gate Weld Evaluation Under DECE Introduction The structural evaluation of the HT Shield Gate weldment [1] subjected to loads from the Stack-up during a design extended conditions earthquake (DECE) is presented in this section. The weld groups between the Spacer Supports (items 10, 11, 12) and Top/Bottom Flanges (items 9, 13), between the Mounting Hole Support Gussets (item 14) and the Top/Bottom Flanges (items 9, 13), and between the Mounting Hole Support Gussets (item 14) and the Spacer Supports (item 11) are evaluated here. The following points are noted:
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IQmifliiQ 121iilQl2liillliiift liil:Y ltlfiliilt 1tlilitJ Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 C.2 -Shield Gate Weld Evaluation Under SSE Introduction The structural evaluation of the HT Shield Gate weldment [1] subjected to loads from the Stack-up during a safe shutdown earthquake (SSE) is presented in this section. The weld groups between the Spacer Supports and Top/Bottom Flanges, between the Mounting Hole Support Gussets and the Top/Bottom Flanges, and between the Mounting Hole Support Gussets and the Spacer Supports are evaluated here.
The following points are noted:
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 C.3 - Shield Gate Plate Structure Evaluation Introduction In this section, the HT Shield Gate supporting plate structure is evaluated using LS-DYNA (except for the Shield Gate itself - see Section C.4). The primary components of the Shield Gate weldment in the load path are made of SA 516 Gr 70 and SA 36 [1]. Instead of qualifying each plate individually, the combined stress plots for the entire Shield Gate supporting structure are plotted and compared with the minimum stress allowable calculated below.
(b)(4)
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Figure C.1: Maximum Shear Stress Plot from LS-DYNA Analysis APPENDIX C - Page C - 18 of 24 Page 145 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IIBl!TEB f21i18f21i11ElJtlll!i 114Pe111.ru1:,.ie11 Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 C.4 -Shield Gate Evaluation Introduction In this section, the HT Shield Gate is evaluated using ANSYS by applying a bounding vertical load on the Shield Gate (360 kips) due to the MPC from the LS-DYNA DECE analysis. The primary load bearing component of the Shield Gate is the 3" thick bottom plate that is made of SA 516 Gr 70 (1).
The top three plates are conservatively ignored in the structural evaluations. The stress intensity in the Shield Gate is compared with the minimum stress allowable calculated below.
(b)(4)
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Figure C.3: Linearized Stress Intensity Plot from A NSYS Analysis APPENDIX C - Page C - 20 of 24 Page 147 of 371
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Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 C.5 -Shield Gate Locking Pin Assembly Evaluation Introduction The Shield Gate is locked in the closed position using a Lockirng Pin (item 22) that passes through the Shield Gate Top Flange (item 9) and through the Shield Gate Bar (item 23). During Stack-up, the lateral loads from the MPC sliding on the Shield Gate are taken by this assembly to prevent the Shield Gate from opening.
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 Project 5025 Supplement 5 - Stack-up Analysis Hl-2177585 Appendix D: ISFSI Pad Concrete Bearing Evaluation Introduction During stack-up, the HT Shield Gate Bottom Flange [1] sits on top of the UMAX CEC inlet plenum cover plate [3] . The outer edges of the cover plate are directly supported by the ISFSI pad concrete that surrounds the CEC. Hence, the impact load from the HT on the CEC cover plate is conservatively evaluated against the bearing capacity of the ISFSI pad concrete that directly supports the cover plate.
The bearing area for the HT on CTB slab at CTF location is greater that that at UMAX location.
Therefore, the calculation is not repeated for the CTB slab. The following points are noted:
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!TE8 Pliil:812liil:IETt liil:)( ltlFOR'IOIIOM HOLTEC CALCULATION
Title:
VCT, HI-TRAC CS and HI-STAR 190 Seismic Stability Evaluations PROJECT No. - ECO No. - REV. No.: - 5025- -- N/A- -- N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 6 CALCULATION
SUMMARY
INFORMATION Scope: This supplement presents the dynamic stability (tipping and sli ding) evaluation of a representative Vertical Cask Transporter (VCT) (empty and with empty/loaded HI-TRAC CS) when staged and during movement on Cask Transfer Building (CTB) slab, haul path and UMAX ISFSI pad at HI-STORE CIS facility in the event of a design basis earthquake. The supplement also presents the dynami c stability evaluations of freestanding HT-TRAC CS (empty and loaded) and HI-STAR 190 ( empty and loaded) when staged on CTB slab and Canister Transfer Facility (CTF) foundation slabs, respectively, in the event of design basis earthquake.
Method: VCT, HI-TRAC CS and HI-STAR 190 are assumed to be ri gid bodies which are first analyzed for the possibility of incipient tipping and sliding, where simple dynamic equations are formulated based on moment and force equilibrium. For any cases that do not pass the initial incipient tipping and sliding checks, the methodology per Appendix A.O of ASCE 43-05 is used to estimate the maximum rocking angle and the maximum sliding distance.
FSAR LOCATIONS Text (Chapter): Subsections 5.4.2 and 5.5.2 Tables: 5.4.7 and 5.5.2 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 AB 03/21/2017 YC 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5.1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed chanqe.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supporting several ECOs.
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1.0 INTRODUCTION
.................................................................................................................................................2 2.0 OBJECTIVE .......................................................................................................................................................... 3 3.0 METHODOLOGY AND ACCEPTANCE CRITERIA .....................................................................................4 3.1 M ETHODOLOGY ...... ........ .... .... ........ ................................ ............ ........................................ ............ ............... .4 3.2 A CCEPTANCE CRITERIA .. .... .................................................... .................................................... ............ ........ 5 4.0 ASSUMPTIONS ....................................................................................................................................................6 5.0 DESIGN INPUT ....................................................................................................................................................7 5.1 WEIGHTS .................... .... ........ ........................................................................ .................... ........ .... ............ .... 7 5.2 D rMENs:oNSANDC.G. 's .................................... ............................................................ ................................ 7 5.3 SEISMIC LOA DING .............................................................................. ........................ .................................... 8
6.0 REFERENCES
.................................................................................................................................................... 10 7.0 COMPUTER CODES AND FILES ................................................................................................................... 11 8.0 RESULTS ............................................................................................................................................................. 12 9.0
SUMMARY
AND CONCLUSIONS .................................................................................................................. 13 10.0 APPENDJCES.................................................................................................................................................... 14 Supplement 6: Page 1 of 14 Page 155 of 371
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1.0 INTRODUCTION
This supplement presents the dynamic stability (tipping and sliding) evaluation of a representative Vertical Cask Transporter (hereafter referred to as VCT) [6.4C], unloaded and carrying empty or loaded HI-TRAC CS [6.4A], when staged and during movement on Cask Transfer Building (CTB) slab [6.48], haul path and U MAX ISFSI pad at HI-STORE CIS facility. The supplement also presents the dynamic stability evaluation of empty and loaded HI-TRAC CS (freestanding) and empty and loaded HI-ST AR 190 (freestanding) [6.40] when staged on CTB slab and Canister Transfer Facility (CTF) foundation slab [6.4B], respectively. The driving loads for this evaluation are the applicable seismic response spectra and the 3-D time history motion at HI-ST ORE CIS facility (see Section 5.0). The results of the analyses in this supplement demonstrate that the VCT (unloaded/empty and carrying empty/loaded HI-TRAC CS), the HI-TRAC CS (empty and loaded) and the HI-STAR 190 (empty and loaded) remain stable and do not lift (or tip) under the app licable site-specific earthquake. The maximum sliding distance of the YCT anywhere on CTB slab, haul path and ISFSI pad is also computed. It is also demonstrated that the HI-TRAC CS (empty and loaded) and HI-STAR 190 (empty and loaded) will not slide on the CTB slab and the CTF foundation slab, respectively, in the event of a SSE.
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Proj ect 5025 I IQls+~C PRQPRJBTARY Report Hl-2177585 2.0 OBJECTIVE This supplement presents the analysis performed to ensure that:
- a. the VCT (without or with empty/loaded HI-TRAC CS) does not tip-over or slide excessively to impact adjacent safety related structures under the bounding site-specific earthquake when staged on or during movement on CTB slab, hau l path and UMAX ISFSI pad.
- b. the HI-TRAC CS ( empty and loaded) does not tip-over or slide excessively to impact adjacent safety related structures under the site-specific ea1t hquake when staged on CTB slab.
- c. the HI-STAR 190 (empty and loaded) does not tip-over or slide excessively to impact adjacent safety related structures under the site-specific eait hquake when staged on CTF foundation slab.
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- 3. 1 Methodology (b)(4)
Sunnlement 6: P::ure 4 of 14 Page 158 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I liLTii 12Jiilil2JiilliT t Jiill'. ltlFS.liilt12 TIS.ti Project 5025 IIE:H9f'Ee'. fil6f R.Jt!TJ!<R. i Report Hl-2177585 3.2 Acceptance Criteria During and after the design basis seismic event, the VCT (empty and with empty/loaded HI-TRAC CS), the HI-TRAC CS (empty and loaded) and the HI-STAR 190 (empty and loaded) must remain dynamically stable and not tip-over or slide off the supporting structure. The criteria for sliding is to ensure that the outside edge of VCT tracks and the outside edge of base of HI-TRAC CS and HI-STAR 190 remain supported by the structure underneath. Also, it is required to ensure that VCT, HI-TRAC CS and HI-STAR 190 do not impact any adjacent safety related structures. The gu idance and the acceptance criteria from Appendices A and B of [6.5] are followed.
Supplement 6: Page 5 of 14 Page 159 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOI IFG RPO RPI FTP liil:l6 ltlfilill:1/:"4ilel l Project 5025 t tetrl!e f.RPJUBThRY Report Hl-2177585 4.0 ASSUMPTIONS (b)(4)
~11nnlP.m~nt fi* P::iuP. 6 nf 14 Page 160 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I liLTii 12Jiilil2JiilliT t Jiill' ltlFS.liilt12 TIS.ti Project 5025 I 19 f:s'flsC PRQP~ 11.:T ARX Report Hl-2177585 5.0 DESIGN INPUT 5.1 Weights The weights of HI-TRAC CS, HI-STAR 190, MPC and VCT are listed below.
(b)(4) 5.2 Dimensions and C.G.'s The dimensions of HI-TRAC CS and HT-STAR 190 are listed below. The dimensions of the assumed VCT design are obtained from [6.4C]. The C.G. of the VCT with loaded HI-TRAC CS is calculated in Appendix 6A.
(b)(4)
Supplement 6: Page 7 of 14 Page 161 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IIOE,Ee FP\OFICILTJtP\i 114P!lill:1/:'li,81l Project 5025 1l@l9f'E@ PR9 Pft.llsT1a ~ Y Report Hl -2177585 Note: For the purpose of this analysis, a nominal HT-TRAC CS lift height of 12 inches, when carried by a VCT, is specified. This value of lift height must be controlled procedurally at the site.
Any greater lift heights wi ll either require further evaluation or techn ical justification.
5.3 Seismic Loading The site-specific response spectra for SSE (or DBE) and DECE are defined in Table 4.3.3 of [6.3C]
and are obtained from Appendix B of [6.3B]. SSE is used for stability evaluations of HI-TRAC CS ( empty and loaded) on CTB slab and HI-STAR 190 ( empty and loaded) on CTF foundation slab. Conservatively, DECE is used for stability evaluation of VCT (unloaded and carrying empty/loaded HT-TRAC CS) to account for any amplification on SSE input at the top ofTSFSI pad due to Soil-Structure Interaction (SSI) effects with loaded canisters in the UMAX ISFSI. It is noted that Operating Basis Earthquake (OBE) is bounded by SSE and DECE [6.3C].
Horizontal SSE ZPA E-W direction (top of CTB slab) 0.15 g Horizontal SSE ZPA N-S direction (top of CTB slab) 0.1 5 g Ve1tical SSE ZPA (top of CTB slab) 0.1 5 g Horizontal DECE ZPA E-W direction (top ofISFSI pad) 0.25 g Horizontal DECE ZPA N-S direction (top of ISFS I pad) 0.25 g Vertical DECE ZPA (top ofISFSI pad) 0.25 g (b)(4)
Suoolement 6: Page 8 of 14 Page 162 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOE I EC Fl<OP j(j[ I A:C I 114Fe lll!ruh '"81l Project 5025 I IQls+li!C PRQPRJBTARY Report Hl -2177585 The response spectra curves for 10% damping are required per [6.5] to calculate maximum sliding displacement, and are generated using SHAKE 2000 [6.2] from the Regulatory Guide 1.60 earthquake time histories scaled to applicable ZPA levels [6.38].
(b)(4)
F igure 5. I: CG He ight of Loaded HI-ST AR 190 ( obtained from CAD model)
Suoolement 6: Page 9 of 14 Page 163 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB Plll.ePlll.l!!!T: ti CI 114POl'ldCIA 11614 Project 5025 II EHsife@ PRElPJU STARY Report Hl-2177585
6.0 REFERENCES
[6.1] Mathcad 15.0, Parametric Technology Corporation, 20 11.
[6.2] SHAKE2000, Version 7.7.0.
[6.3] Holtec Reports:
A: HI-STORM FW FSAR, HI-2114830, Revision 4.
B: Regulatory Guide 1.60 Time Histories Using EZ-FR lSK, Hl-2146083, Revision 2.
C: Licensing Report on the HI-STORE CIS Facility, HI-2167374, Revision 0.
[6.4] Drawings:
A: 10868, Licensing Drawing for HI-TRAC CS, Revision 0.
B: 10912, Licensing Drawing for Cask Transfer Building Floor Slab, Revision 0.
C: VCT4 l 5W08 l , General Arrangement Drawing for Vertical Cask Transporter, Revision 0 (used for illustrative purposes).
D: 9841, Licensing Drawing for HI-STAR 190 Cask Assembly, Revision 0.
E: 10895, Licensing Drawing for Canister Transfer Facility (CTF), Revision 0.
[6.5] ASCE/SEI 43-05, Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities, ASCE, 2005.
[6.6] Holtec Approved Computer Program List, Revision 342.
S11nnlement 6: Pag:e 10 of 14 Page 164 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l~mifii 12Jiilil2JiilliH:\Jiil:V IIJFBIIUUh ,.ie11 Project 5025 I IQls+li!C PRQPRJBTARY Report Hl-2177585 7.0 COMPUTER CODES AND FILES Computer files associated with this supplement are stored on the HOLTEC network at:
G:\Projects\5025\REPORTS\Structural Reports\HI-2177585 (HI-STORE CISF Cale Package)\REV O\Supplement 6.
The main section of this supplement is written using Microsoft Word. All the calculations
{Appendices 6A through 6C) are perfonned using Mathcad 15.0 [6.1). The response spectra curves at 10% damping are generated using SHAKE 2000 [6.2] on Computer No. 1372 which is on the Holtec Approved Computer Program List [6.6].
Supplement 6: Page 11 of 14 Page 165 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I liLTii 1212Ql2~1iiTP 9'6 It IEAR' 1OIIOM Project 5025 IIEHsife@PRElPJUBT/cRY Report Hl-2177585 8.0 RESULTS Stability analyses are performed for a representative VCT (empty and with empty/loaded HI-TRAC CS), the HI-TRAC CS (empty and loaded) and the HI-STAR 190 (empty and loaded) at the HI-STORE CIS facility.
The analyses performed in Appendix 6A confirm that the VCT (empty and with empty/loaded HT-TRAC CS) will remain stable and will not lift under site's DECE when staged or during transport on CTB slab, haul path and UMAX ISFSI pad.1(b)(4)
(b)(4)
The analyses performed in Appendices 68 and 6C confi rm that the HT-TRAC CS (empty and loaded) and HI-STAR 190 (empty and loaded) wilt remain stable and will not lift under site's SSE when staged on CTB slab and CTF foundation slab, respectively. The HI-TRAC CS (empty and loaded) and the HI-STAR 190 (empty and loaded) will not begin to slide under site's SSE when staged on CTB slab and CTF foundation slab, respectively.
Supplement 6: Page 12 of 14 Page 166 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!TE8 Pliil:812liil:IETt liil:)( ltlFOR'IOIIOM Project 5025 H<5LTtse FREIPR.IJiT I) IU,'. Report Hl-2177585 9.0
SUMMARY
AND CONCLUSIONS In this supplement, seismic stabi lity analyses of a representative VCT (empty and with empty/loaded HI-TRAC CS), the HI-TRAC CS (empty and loaded) and the HI-STAR 190 (empty and loaded) at the HI-STORE CIS facility are performed . The results of the analyses demonstrate that the VCT, the HI-TRAC CS and the HI-ST AR 190 wi ll remain stablej(b)(4)
(b)(4) l.....- - - - - - - - - - - - -......I~ The HI-TRAC CS and the HI-STAR 190 will not slide (b)(4) under site-specific SSE.
Suoolement 6: Page 13 of 14 Page 167 of 371
ATTACHMENT 11 TO HOLTEC LETTER 50250 12 I 1QlsTli8 Pliij:8Pfi4:IETitli'!, 1141e1ue1x11614 Project 5025 IIQ~Tls PRQPIUETh.RY Report Hl-2177585 10.0 APPENDICES Appendix 6A - VCT Tipping and Sliding Calculations Appendix 68- HI-TRAC CS Tipping and Sliding Calculations Appendix 6C- HI-STAR 190 Tipping and Sliding Calculations Suoolement 6: Page 14 of 14 Page 168 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOLi EC FROPRIEIARY IIQFORIVIAIION I liLTliw 12~8P~IH/t~\C Report Hl-21775851 Appendix 6A - VCT Tipping and Sliding Calculations This appendix evaluates tipping and sliding of the VCT with empty/loaded Hi-TRAC CS on CTB slab, haul path and UMAX ISFSI pad. Conservatively bounding seismic input and grade/slope are used for all locations .
6A.1: Input Parameters (b)(4)
Appendix 6A: Page 6A-1 of 6A-6 Page 169 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f21ii1JET;SJ~.\f IIJFBliill:1/:TIBIJ I IGLTEB f2~8121iillliTO liilY Report Hl-21775851 6A.2: Tipping Calculations (b)(4)
Aooendix 6A: Paae 6A-2 of 6A-6 Page 170 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!T!!e F l"..er :Cl!!T)l(I CI 11&1 Ol<IOIA 1161&
I liLTE8 (ipl:@Ppl:IET)l(ft I Report Hl-21775851 (b)(4)
Appendix 6A: Page 6A-3 of 6A-6 Page 171 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HO! IEG OPQRliillEiiTt RN IIJFBlilhh 1.ie11 If Pl ISQ RliilQRliillliiiIO liilY Report Hl-21775851 6A.3: Sliding Calculations.
(b)(4)
Appendix 6A: Page 6A-4 of 6A-6 Page 172 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I liLTii 12Jiilil2JiilliT t JiillC ltlFS.liilt12 TIS.ti AGE I ee F rteP~IET/:liilY Report Hl-21775851 (b)(4)
Appendix 6A: PaQe 6A-5 of 6A-6 Page 173 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I l~mifiiiii 12Jiilil2Jiilllii!T/:Jiill;f IIJFBfUoh ,.ie11 I liLTiiiiv 12RORRIFIORX Report Hl-21775851 (b)(4) 6A.4: Conclusions The analysis performed in this appendix confirms that the empty VCT and the VCT with the empty/loaded HI-TRAC CS will remain stable and will not liift under bounding design basis seismic event when staned or travelinn on CTB slab haul nath and UMAX ISFSI nad.l...(b->l/4-ll _ __
(b)(4)
Appendix 6A: Page 6A-6 of 6A-6 Page 174 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 I 18LTlis RliilORPIEIORX Report Hl-21775851 Appendix 68 - HI-TRAC CS Tipping and Sliding Calculations This appendix evaluates tipping and sliding of the HI-TRAC CS [6.4A) freestanding on CTB slab [6.48) .
68.1 : Input Parameters (b)(4) 68.2: Tipping Calculations (b)(4)
Appendix 68 : Page 68-1 of 68-3 Page 175 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 118LTliw 12liil:Ql2liil:lliiiTORY Report Hl-21775851 (b)(4) 66.3: Sliding Calculations (b)(4)
Appendix 68 : Page 68-2 of 68-3 Page 176 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB Flll.eFf'tJ!!!TJ ti CI 114FOl'ltlOIA 11614 I IGiH,TliiiG RRORRlliiiIORX Report Hl-21775851 This indicates that the loaded HI-TRAC CS will remain stable and will not start to slide under the design basis seismic event. This conclusion is also applicable to empty HI-TRAC CS as the evaluation is independent of weight and CG.
6B.4: Conclusions The analysis performed in this appendix confirms that the HI-TRAC CS (empty and loaded) remains stable and will not lift in the event of a design basis earthquake when staged freestanding on CTB slab.
The analysis also confirms that the HI-TRAC CS (empty and loaded) will not start to slide in the event of a design basis earthquake when staged freestanding on CTB slab.
AnnAndix 68: Paae 68-3 of 68-3 Page 177 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 IIOE,te FP\OFICILTJtP\i 114Pefll:1:S.'li,81l I IOLTte F R8PR,ET; tii'.: Report Hi-21775851 Appendix 6C - HI-STAR 190 Tipping and Sliding Calculations This appendix evaluates tipping and sliding of the HI-STAR 190 [6.40] freestanding in CTF [6.4E] on CTF foundation slab [6.48] .
6C.1 : Input Parameters (b)(4) 6C.2: Tipping Calculations (b)(4)
Appendix 6C: Pa~e 6C-1 of 6C-3 Page 178 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 AOE,26 F l<OF:CIE!TJt~i IIJFBfiil11tlil2tl 112 ..Tliiiv lii'liil21ii'PlliiiTOPY Report Hl-21775851 (b)(4) 6C.3: Sliding Calculations (b)(4)
Appendix 6C: Page 6C-2 of 6C-3 Page 179 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB Flll.eFf'tJ!!!TJ ti CI 114FOl'ldOIA 11614 I IBl!Tliw Pliil:itPliil:lliiiTORY Report Hl-21775851 This indicates that the loaded HI-STAR 190 will remain stable and will not start to slide under the design basis seismic event. This conclusion is also applicable to empty HI-STAR 190 as the evaluation is independent of weight and CG.
6C.4: Conclusions The analysis performed in this appendix confirms that the HI-STAR 190 (empty and loaded) remains stable and will not lift in the event of a design basis earthquake when staged freestanding on CTF foundation slab.
The analysis also confirms that the HI-STAR 190 (empty and loaded) will not start to slide in the event of a design basis earthquake when staged freestanding on CTF foundation slab.
Aooendix 6C: Page 6C-3 of 6C-3 Page 180 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IIOE,Ee FP\OFICIE!!TJtP\i 114Pllill:1:S.'li,81l HOLTEC CALCULATION
Title:
MPC Lift Attachment Stress Analysis PROJECT No. - ECO No. - REV. No.: - 5025- -- -N/A- - -- -N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 7 CALCULATION
SUMMARY
INFORMATION Scope: This supplement presents the structural evaluation of the MPC Lift Attachment under normal lifting of a loaded MPC at the HI-STORE CIS faci lity. To account for lifting dynamics, a 15% increase in the load is considered.
Method: Strength of materials formulations are used to evaluate the Lift attachment.
FSAR LOCATIONS Text (Chapter): Subsection 5.4.5 Tables: Table 5.4.5 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 AR 03/22/2017 PN 03/22/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5. 1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed change.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supportinri several ECOs.
Page 181 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!T!!e Fl"..eF:cl!!T)l(ICI 11&1 Ol<IOIAI IOI&
IPmject 5025 I 18LTE8 Piiil8,iiliiillET:R:iiilY Hl-2177585 1 SUPPLEMENT-7 STRUCTURAL EVALUATION OF THE MPC LIFT ATTACHMENT FOR HI-STORE
- 7. 1 INTRODUCTION The purpose of this appendix is to demonstrate that the load bearing parts of the HI-STORE MPC Lift Attachment device meet all requirements for in-plant handling of heavy loads.
7.2 METHODOLOGY, ACCEPTANCE CRITERIA AND ASSUMPTIONS The analyses are carried out using strength of materials formulations for statically determinant components.
For a design without redundant load paths, the maximum stress in any load bearing component, per Refs. [7.1] and [7.2]. is limited to the minimum of either one-tenth of the material ultimate tensile strength or one-sixth of the material yield strength.
(b)(4)
7.3 REFERENCES
[7.1] USNRC NUREG-0612, 1980.
(7.2] ANSI N14.6, 1993.
[7.3] HI-STORM FW FS.AR, Holtec Report Hl-2114830, Revision 2.
(7.4] Holtec Drawing 10889, Revision 1 "MPC Lifting Device Extension" .
[7. 5] Holtec Drawing 10891, Revision 1 "MPC Lift attachment".
[7.6] CMAA Specification #70 (1988), Crane Manufacturers of America.
(7.7] AISC Steel Construction Manual, Ninth Edition.
[7.8] ASME BTH-1-2008, Design of Below-the-Hook Lifting Devices, January 2009.
(7.9] Machinery's Handbook, 27th Edition, 2004..
[7.10) ASME Sec II, Part D, 2010.
Supplement 7 - 1 of 13 Page 182 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOLi EC FROFRIEIAl<i 11&1 Ol'ltiehl<fl014 IPmject 5025 I IOLTte F fl!OF fl!ILT)l(fl! I Hl-2177585 1 7.4 INPUT DATA 7.4.1 Lifted Weight (b)(4) 7.4.2 Material Properties (b)(4) 7.4.3 Dimensions (b)(4)
Supplement 7 - 2 of 13 Page 183 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f2(iilJ[lJtlll!: 114Pelll!ruh ,.ie11 IPmject 5025 I l@l!Tliw liilliilORRIFIARX Hl-2177585 1 (b)(4)
Supplement 7 - 3 of 13 Page 184 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l~laTii f2Jiil8f2JiillHJ ti": I 114FOl":IM< 1161&
IPmject 5025 I IBLTEB f2~8f2JiilliT:R:JiilY Hl-2177585 1 8.5 ALLOWABLES STRESS (b)(4) 8.6 CALCULATIONS 8.6.1 Calculation for bolt thread (b)(4)
Supplement 7 - 4 of 13 Page 185 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I ,GEi EC F l<OF ICIE!T)l(IC, 114P"bltlel)l(Tlb,4 IPmject 5025 I l@LTE@ P~@P~IET; t~:
Hl-2177585 1 (b)(4)
Supplement 7 - 5 of 13 Page 186 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!T!!!e Plil:BPlil:IET;S:liil:lf ltlfiliill12li1Qtl IPmject 5025 I liLTlili liilliililiilliillliT;0:1iil\C Hl-2177585 1 7.6.2) Prying force calculation for Bolt {per AISC prying calculation method) (7.7):
(b)(4)
Figure 7.1: Lift Attachment Input dimensions Supplement 7 - 6 of 13 Page 187 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I liLTii 12Jiilil2JiilliT t Jiil)( ltlFS.liilt12 TIS.ti IPmject 5025 116' ..Tliw 12lil.8Plil.lET; tft I Hl-2177585 1 (b)(4)
Supplement 7 - 7 of 13 Page 188 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f21i18f21i11ET/J~.\f IIJFBlill:1/:TIBIJ IPmject 5025 I IBl!TEB f21i1812fiillliif:R:Jiill:'
Hl-2177585 1 (b)(4) 7.6.3) Tensile Stress in Lifting lug plate (b)(4)
Supplement 7 - 8 of 13 Page 189 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 AOL I EC F l<OF:CIE!TJt~: illFBliill:1:C*IQtl IPmject 5025 I IBLTEB PliilBPliillEV:liilY Hl-2177585 1 (b)(4) 7.6.4) Tearout at holes location in lifting Lug Tearout could occur in the two vertical planes at Lifting Pirn holes location in the Lifting lug Plates. The tearout stress and safety factor of the Lift arm Plate can be computed as (see Fig. 7.2):
Using the terminology and equation (3.51] from (7.8] (see Fig. 7.2),
Direction of applied load Curved edge R
+--~ Cl hole Figure 7.2: Terminology as per (7.8]
Supplement 7 - 9 of 13 Page 190 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HO! IEG RRQRliillEiiTtlil:Y IIJFBlill:1: :.ie11 IPmject 5025 I /Al ISQ RliilQRliillliiiIO Iii¥ Hl-2177585 1 (b)(4)
Supplement 7 - 10 of 13 Page 191 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f2(iilJ[lJtlll!: 114Pelll!ruh ,.ie11 IPmject 5025 I liLTliw 121iilil21iillliT:R:liilY Hl-2177585 1 7.6.5) S ingle plane fracture at pin hole location (b)(4)
Supplement 7 - 11 of 13 Page 192 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HO! IEG RRORRliiTPliil:l6 ltlFiliillPlilitJ IPmject 5025 I l@LTE8 121ii1QOPliiIORY Hl-2177585 1 7.6.5 Shear stress in flange (b)(4) 7.6.6 Bearing Stress at pin hole location in lifting lug (b)(4)
Supplement 7 - 12 of 13 Page 193 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 t liLTii 12Jiilil2JiilliT t Jill' ltlFS.liilt12 TIS.ti IPmject 5025 I liLTiw 12Jiilil2JiilliT:R:JiilY Hl-2177585 1 7.7 RESULTS (b)(4)
7.8 CONCLUSION
All safety factors are above the minimum of 1.0. Therefore, the MPC Lift Attachment is structurally adequate for its design purpose.
Supplement 7 - 13 of 13 Page 194 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IQmifliiQ 121iilQl21iillliiif Pliil)( It IFQliilt10 ifIQt I HOLTEC CALCULATION
Title:
MPC Lifting Device Extension Stress Analysis PROJECT No. - ECO No. - REV. No.: - 5025- -- -N/A- - -- -N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 8 CALCULATION
SUMMARY
INFORMATION Scope: T his supplement presents the structural evaluation of the MPC L ifting Device Extension under the normal lifting of a loaded MPC at the H T-STORE CTS facility. To account for lifting dynamics, a 15% increase in the load is considered.
Method: Strength of materials formulations are used to evaluate the MPC lifting device extension.
FSAR LOCATIONS Text (Chapter) : Subsection 5.4.6 Tables: Table 5.4.6 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 AR 03/22/2017 PN 03/22/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5. 1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed change.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supportinri several ECOs.
Page 195 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB Plll.ePlll.l!!!TJti CI 114POl'ldCIA 11614 IPmject 2504 I /Al ISC lii'liil/rlii'liil:lliiiIO Iii!¥ Hl- 2177585 1 SUPPLEMENT-8 STRUCTURAL EVALUATION OF THE MPC LIFTING DEVICE EXTENSION
8.1 INTRODUCTION
The purpose of this appendix is to demonstrate that the load bearing parts of the MPC Lifting extension device meet all requirements for in-plant handling of heavy loads.
8.2 METHODOLOGY, ACCEPTANCE CRITERIA AND ASSUMPTIONS The analyses are carried out using strength of materials formulations for statically determinant components.
For a design without redundant load paths, the maximum stress in any load bearing component , per Refs. [8.1] and [8.2], is limited to the minimum of either one-tenth of the material ultimate tensile strength or one-sixth of the material yield strength.
(b)(4)
8.3 REFERENCES
(8.1] USNRC NUREG-0612, 1980.
[8.2] ANSI N14.6, 1993.
(8.3] HI-STORM FW FS.AR, Holtec Report Hl-2114830, Revision 4.
(8.4] Holtec Drawing 10889, Revision 1 "MPC Lifting Device Extension" .
(8.5] Holtec Drawing 10891, Revision 1 "MPC Lift attachment".
(8.6] CMAA Specification #70 (1988), Crane Manufacturers of America.
(8. 7] A ISC Steel Constnuction Manual, Ninth Edition.
(8.8] ASME BTH-1-2008, Design of Below-the-Hook Lifting Devices, January 2009.
(8.9] ASME Sec II, Part D, 2010.
[8 .10] A514/A51 4M-05, ASTM International Standard Specification.
Supplement 8 - 1 of 15 Page 196 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l~laTii f21iil8f21iilJHJ ti": I 114FOl":IM< 1161&
IPmject 2504 I IBLTEB f2~8f21iilliT:R:liilY Hl- 2177585 1 8.4 INPUT DATA 8.4.1 Lifted Weight (b)(4) 8.4.2 Material Properties (b)(4) 8.4.3 Dimensions (b)(4)
Supplement 8 - 2 of 15 Page 197 of 371
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IPmject 2504 11en!!e r l"..er l"..l!!T)l(ft:
Hl- 2177585 1 (b)(4)
Supplement 8 - 3 of 15 Page 198 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I 1621 EC F ICOF l(IEIAiCI 11&1 Oi<IOIAI IOI&
IPmject 2504 11'1 ..Tliiiv lilliil:'11ii'RlliiiTO RX Hl- 2177585 1 8.5 ALLOWABLES STRESS (b)(4) 8.6 CALCULATIONS 8.6.1 Tensile Stress in Lift arm (b)(4)
Supplement 8 - 4 of 15 Page 199 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I liLTilil P~8Pfill!!!T)l(I CI 11&1 01<:0IA I IOIQ IPmject 2504 I /Al ISC lii'liil/rlii'liil:lliiiIO 1ii1'6 Hl- 2177585 1 (b)(4)
Supplement 8 - 5 of 15 Page 200 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB Flll.eFf'tJETJ ti CI 114F01:tel'A 11614 IPmject 2504 I let I ee F l"l!.8Pl"l!.IET:\Jiil)(
Hl- 2177585 1 (b)(4)
Supplement 8 - 6 of 15 Page 201 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!TE8 Pliil:812liil:IETO liil:l' ltlFOR'IOIIObl IPmjeot 2504 11el!TE!e F fifer fl!IE!T)l(fl! I Hl- 2177585 1 8.6.2 Tearout at upper hole location in lift arm Tearout could occur in the two vertical planes above the Lif ting Pin hole\ location in the Lift arms.
The tearout stress and safety factor of the lift arm can be computed as (see Fig. 8.1 ):
Using the terminology and equation [3.51] from [8.8] (see Fig. 8.1).
Direction of applied load I
I
- - - - - ~ CL hole Figure 8. 1: Terminology as per [8.8]
(b)(4)
Supplement 8 - 7 of 15 Page 202 of 371
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Supplement 8 - 8 of 15 Page 203 of 371
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Supplement 8 - 9 of 15 Page 204 of 371
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Supplement 8 - 10 of 15 Page 205 of 371
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IPmject 2504 I liLTliw 12fiililiilfiillliT:R:fiilY Hl- 2177585 1 8.6. 7) Bearing Stress at bottom pin hole
{b){4) 8.6.8) Lifting pin (upper pin) bending and shear (b)(4)
Supplement 8 - 11 of 15 Page 206 of 371
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Supplement 8 - 12 of 15 Page 207 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f21ii1JET;SJ~.\f IIJFBliill:1/:TIBIJ IPmject 2504 11etTE8 121ii10RRIFIARX Hl- 2177585 1 8.6) Lift arm pin (bottom pin) bending and shear
{b){4)
Supplement 8 - 13 of 15 Page 208 of 371
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Supplement 8 - 14 of 15 Page 209 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IQmifliiQ 121iilQl2liillliiift Iii\'. ltlfiliilt 1tlilitt IPmject 2504 IJAI IEC RRORRIEIORY Hl-2177585 1 7.7 RESULTS (b)(4)
7.8 CONCLUSION
All safety factors are above the minimum of 1.0. Therefore, the MPC Lifting Device Extension [8.4) is structurally adequate for its design purpose.
Supplement 8 - 15 of 15 Page 210 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l~mifiiiii 12Jiilil2JiillliiT;SJ~:V IIJFBAfOh ,.ie11 HOLTEC CALCULATION
Title:
HI-STAR 190 HORIZONTAL LIFT BEAM STRESS ANALYSIS PROJECT No. - ECO No. - REV. No.: - 5025- -- N/A- -- N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 9 CALCULATION
SUMMARY
INFORMATION Scope: The Horizontal Lift Beam, used to lift the HI-STAR 190 cask in the horizontal orientation, is evaluated against NUREG 0612 and ANSI N14.6 acceptance criteria.
Method: Strength of materials formulations and an ANSYS FEA model are used to evaluate the lifting ancillary.
FSAR LOCATIONS Text (Chapter): Subsection 5.4.6 Tables: Table 5.4.6 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 PN 03/24/2017 OS 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5. 1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed change.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supporting several ECOs.
Page 211 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB Flll.eFf'tJ!!!TJti CI 114FOl'ltlOIA 11614 I liLTliw 12~8P~IET:\~Y Hl-21775851 SUPPLEMENT 9: HI-STAR 190 HORIZONTAL LIFT BEAM STRESS ANALYSIS
9.1 INTRODUCTION
The purpose of this supplement is to demonstrate that the load bearing parts of the Horizontal Lift Beam meets all requirements for the in-plant handling of heavy loads.
9.2 METHODOLOGY, ACCEPTANCE CRITERIA AND ASSUMPTIONS The analyses are carried out using a finite element model in ANSYS 17.1 [9.3] and strength of materials formulations for statically determinant components.
For a design without redundant load paths, the following acceptance criteria are used per per [9.1] and
[9.2]:
Primary stress on any load bearing component mm . (Sy
- -Su) 6 ' 10 Shear stress on any load bearing component (conservative) _I -min(Sy Su) fj 6 ' 10 Su Shear stress on effective weld throat 10 The device is load tested to 300% of the design load. To prevent yielding during the load test an additional criteria is also used:
Sy Effective (Von-Mises) stress on any component 3
Sy Bearing stress 0.9*-
3 Note that these criteria are to be compared against the lift beam when it is loaded under the actual design load.
(b)(4)
Supplement 9: 1 of 34 Page 212 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB Plll.ePlll.l!!!TJti CI 114POl'ltlel'A 11614 I liLTliw P~BP~IET:\~Y Hl-21775851
9.3 REFERENCES
[9.1] USNRC NUREG-0612, 1980.
[9.2] ANSI N14.6, 1993.
[9.3] ANSYS Mechanical , Release 17.1, 2016 SAS IP, .Inc.
[9.4] Holtec Drawing 10894, "Transport Cask Horizontal Lift Beam", Revision 0.
[9.5] ASME Boiler and Pressure Vessel Code,Section II, Part D, Properties, 2010.
[9.6] CMAA Specification #70, Crane Manufacturers of America, 1988.
[9.7] ASME BTH-1-2008, Design of Below-the-Hook Lifting Devices, January 2009.
[9.8] A514/A514M-05, ASTM International Standard Specification.
[9.9] Hl-2114830, HI-STORM FW FSAR, Revision 4.
[9. 10] Holtec Drawing 9841, "HI-STAR 190 Cask Assembly", Revision 0.
[9.11] Holtec Drawing 9848, "HI-STAR 190 Impact Limiter", Revision 0.
[9.12] A500/A500M-07, ASTM International Standard Specification.
[9.13] A53/A53M-07, ASTM I nternational Standard Specification.
[9.14] Hl-2115090, HI-STORM UMAX System FSAR, Revision 3.
[9.15] l&ISling, http://www.iandisling.com/twin_path_extra_covermax.htm , Accessed 2017.
[9.16] AISC Steel Construction Manual, 13th edition.
9.4 INPUT DATA 9.4.1 Lifted Weight (b)(4)
Supplement 9: 2 of 34 Page 213 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f2(iilJ[lJtlll!: 114Pelll!ruh ,.ie11 I liLTliw 121iilil21iillliT:R:liilY Hl-21775851 9.4.2 Material Properties (b)(4)
Supplement 9: 3 of 34 Page 214 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HO! IFS PliilQPliilliTtliil:Y IIJFBlill:1/t.ie11 I l@LTE@ P~@P~IET; t~: Hl-21775851 (b)(4) 9.4.3 Dimensions (b)(4)
Supplement 9: 4 of 34 Page 215 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB Plll.ePlll.l!!!TJ ti CI 114POl'ldCIA 11614 HOE I EC I I cer 111.l!!!TJ tli'. I Hl-21775851 (b)(4)
Supplement 9: 5 of 34 Page 216 of 371
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Supplement 9: 6 of 34 Page 217 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB Plll.ePlll.l!!!TJ ti CI 114POl'ldOIA 11614 I IBLTliw lii'liil/rl2RIFIORY Hl-21775851 9.5.2 Lift Arm Trunnion Plate (item 9)
(b)(4)
Supplement 9: 7 of 34 Page 218 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I 1621 EC F ICOF l(IEIAiCI 11&1 Oi<IOIAI IOI&
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Supplement 9: 8 of 34 Page 219 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I liLTlii8 P~8Pfill!!!T)l(I CI 11&1 01<:0IA I IOIQ I liLTliiw 12fiililiilfiillliiT:R:fiilY Hl-21775851 (b)(4)
Supplement 9: 9 of 34 Page 220 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I 1621 EC F ICOF l(IEIAiCI 11&1 Oi<IOIAI IOI&
I 18LTE8 Pliil8PliillET:R:liilY Hl-21775851 (b)(4)
Supplement 9 : 10 of 34 Page 221 of 371
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Supplement 9: 11 of 34 Page 222 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IQmifliiQ 121iilQl2liillliiift !iii\'. ltlfiliilt 1tlilitt I l@LTE@ P~@P~IET; t~: Hl-21775851 (b)(4)
Supplement 9: 12 of 34 Page 223 of 371
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Supplement 9: 13 of 34 Page 224 of 371
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(b)(4)
Figure 1: Quarter symmetric FEA model of Horizontal Lift Beam and associated Mesh (b)(4)
Supplement 9: 14 of 34 Page 225 of 371
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Figure 2: Quarter symmetric FEA model of Horizontal Lift Beam and associated Mesh (b)(4)
Figure 3: Remote displacement boundary conditions at sling interface with pipe, and spreader beam to adjusting pin joints Supplement 9: 15 of 34 Page 226 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11gmfiiQ 12liilgl2liil:lliift lill'. IPJFiliill191ilitJ I JOI IFS RRORPISIO RY Hl-21775851 (b)(4)
Figure 4: Equivalent Stress of Lift Beam components (b)(4)
Figure 5: Safety Factors against min(Sy/6, Su/10) - Global Supplement 9: 16 of 34 Page 227 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025
- 10* IEQ 12r;qg12'iil:'liil:st'iil:V '14Pen1e1.t<T16'&
I IGiJL,TliiiG RRORRlliiiIORY Hl-21775851 (b)(4)
Figure 6: Safety Factors against min(Sy/6, Su/10) - Stress concentration at Adjusting Pin location (b)(4)
Figure 7: Safety Factors against min(Sy/6, Su/10) - Stress concentration at Spreader Beam - Main Pipe joint Supplement 9: 17 of 34 Page 228 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!Te!e Plll.ePIII.IE!T:S:lil\f IIJFBlill:1:S.'lilBIJ IProject 5025 I JOI IE£ RRORPISIO RY Hl-21775851 (b)(4)
Figure 8: Safety Factors against min(Sy/6, Su/10) - Stress concentration in Spreader Beam and inner/outer support plates (b)(4)
Figure 9: Comparison against Sy - Cross section taken at half of the lift beam height to show internals Supplement 9: 18 of 34 Page 229 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11gmiliii 12Jiilil2Jiilllii!T:\Jiill;f IIJFBfll.fOh ,.ie11 I IBLTlis 121iiOPRIFIORX Hl-21775851 (b)(4) 9.5.6 Adjusting Qin (item 12)
(b)(4)
Supplement 9: 19 of 34 Page 230 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOE I EC PROFRl2 I AR f IIQFORIOIA I IOI&
I ICLTEB Pliil8PliillliiiTO liil'6 Hl-21775851 (b)(4)
Supplement 9 : 20 of 34 Page 231 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IQmTliQ 121iilQl2liilliT t liil:lf ltlfiliilt 1t Tlitl I 18LTil!i 121iil:Qf21ii1:lliT09'6 Hl-21775851 9.5.7 Weld Evaluations (b)(4)
Figure 12: Contact pressure for contact between Main beam and cross pipe Supplement 9 : 21 of 34 Page 232 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f2(iilJ[lJtlll!: 114Pelll!ruh ,.ie11 I JOI IE£ RRORPISIO RY Hl-21775851 (b)(4)
Supplement 9: 22 of 34 Page 233 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!T!!e P111.eP111.1!!T, ,111.: 11JPe111.ru1; ,,1e11 I IUTl!:8 Pfiil'wl2RIFIORX Hl-21775851 (b)(4)
Supplement 9: 23 of 34 Page 234 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f21i18f21i11ElJtlll!: 114P6111!1Uh 1.ie14 1121 ISC RRAPRIFIARX Hl-21775851 (b)(4)
Supplement 9: 24 of 34 Page 235 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HO! IFS 12!iilQl2liil!liiT:\R.\f !!4PeftlM<f!O!&
I *etTE!e F R.8PR.!l!TJ tR.: H!-21775851 (b)(4)
Supplement 9: 25 of 34 Page 236 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IOLTii f21iil8f21i11ElJ t~ I 114P"Of'lilM< 11614 I IBLTiQ RliilORPIEIORX Hl-21775851 (b)(4)
Supplement 9: 26 of 34 Page 237 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f21il8f21illET: :Ill!: 114Pelll!ruh ,.ie11 I l@LTE@ Plil@PlillET: tlil: Hl-21775851 (b)(4)
Supplement 9: 27 of 34 Page 238 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!T!!e P111.eP111.1!!T, ,111.: 11JPe111.ru1; ,,1e11 11enE!e r 111.er 111.IE!T)l(ft: Hl-21775851 (b)(4)
Supplement 9: 28 of 34 Page 239 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 HOE I EC PRUFRl2 I AR f IIQFORIOIA I IOI&
I 18LTliQ RliilORPIEIORX Hl-21775851 (b)(4)
Supplement 9: 29 of 34 Page 240 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 llel!TEC F lfoi RIEIARY IIQFORIVIAIION IProject 5025 I l~LTliw 12~8P~IH:\~Y Hl-21775851 (b)(4)
Supplement 9: 30 of 34 Page 241 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f21ii1JET;SJ~.\f IIJFBliill:1/:TIBIJ I IBl!Tliw Pliilif Pliil:lliiiTO RX Hl-21775851 (b)(4)
Supplement 9: 31 of 34 Page 242 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 IIOE I EC F l<Oi ICILT)l(P'IJ. I 114P"Of'liiol)l(Tl014 I l~LTliiiv RRARRIFIORX Hi-21775851 (b)(4)
Supplement 9: 32 of 34 Page 243 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!T!!e FICOP I& IAl(f IMORIOIAI IOIQ I l@LTE@ P~@P~IET; t~: Hl-21775851 (b)(4) 9.6 COMPUTER FILES The analyses described in this calculation are performed with ANSYS 17. 1 (9.3], in Computer ID#
1271 . This code and computer are both validated under Hoitec international's QA program per the Holtec ACPL, Revision 342, dated March 6, 2017. All relevant ANSYS files are stored in:
I Supplement 9: 33 of 34 Page 244 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!TE8 Pliil812liillETt liil:l' ltlF99'10IIAhl I letTE8 Pliil8Pliil1Eif:R:liill:' Hl-21775851 9.7 RESULTS The minimum final safety factors from the horizontal lift beam evaluation are presented below:
(b)(4)
9.8 CONCLUSION
A structural evaluation of the Horizontal Lift Beam was performed with a combination of strength of materials fonnulations and a finite element analysis in ANSYS Mechanical [9.3]. All safety factors with respect to the acceptance criteria are above the minimum of 1.0. Therefore, the horizontal lift beam is qualified as a special lifting device per NUREG 0612 [9. 1] and ANSI N14.6 [9.2] for loads up to:
wtot
- - = 418 -kip DLF Supplement 9: 34 of 34 Page 245 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IQmifliiQ 121iilQl2liillliiift liil:Y ltJFiliilt 1tlilitt HOLTEC CALCULATION
Title:
FATIGUE EVALUATION OF THE HI-TRAC CS AND LIFTING ANCILLARIES PROJECT No. - ECO No. - REV. No.: - 5025- -- N/A- -- N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 10 CALCULATION
SUMMARY
INFORMATION Scope: The fatigue life of the HI-TRAC and lifting ancillaries due to repeated lifting and handling loads is evaluated. Thermal cycling related fatigue is also considered.
Method: Allowable stress limits for the HI-TRAC are conservatively used to calculate the maximum number of loading cycles with S-N curves from Appendix I of ASME BPVC, Section Ill.
FSAR LOCATIONS Text (Chapter): Subsection 5.4.2 and 5.4.6 Tables: Tables 5.4.8 & 5.4.9 REVISION LOG Rev. No. Prei;>arer Initials /Date Reviewer Initials /Date 0 PN 03/24/2017 VM 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is assodated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5.1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed change.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supportinq several ECOs.
Page 246 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IQmifliiQ 121iilQl2liillliiift Iii\'. ltlfiliilt 1tlilitl I l@LTE@ P~@P~IET; tli'.: Hl-21775851 SUPPLEMENT 10: FATIGUE EVALUATION OF HI-TRAC CS AND LIFTING ANCILLARIES
10.1 INTRODUCTION
This supplement evaluates the fatigue life of the HI-TRAC CS and under lifting/handling operations.
Fatigue evaluations of the various HI-STORE lifting ancillaries are also presented.
10.2 METHODOLOGY The fatigue life of the HI-TRAC CS and the lifting ancillaries is calculated by comparing a bounding stress value with the cycle life curves defined in Appendix I of ASME BPVC Section Ill [10.3). The maximum stress is conservatively taken as the bounding allowable stress in the load bearing components during a lifting/ha:ndling operation.
(b)(4) 10.3 RE"'EPl=Nr~S
[10.1) USNRC NUREG-0612, 1980.
[10.2] ANSI N14.6, 1993.
[10.3] ASME BPVC, Section Ill, Appendix I, 2010.
[10.4] Hl-2167374, HI-STORE FSAR, Revision 0.
[10.5] ASME BPVC,Section II, Part A to D, 2010.
[10.6] Holtec Drawing 10894, "Transport Cask Horizontal Lift Beam", Revision 0.
[10.7] Holtec Drawing 10868, "HI-TRAC CS", Revision 0.
[10.8] A514/A514M-05, ASTM International Standard Specification.
[10.9] A336/A336M-09, ASTM International Standard Specification.
[10.10] A572/A572M-07, ASTM International Standard Specification.
[10. 11] A36/A36M-08, ASTM International Standard Specification.
[10.12] A500/A500M-07, ASTM International Standard Specification.
[10.13] A53/A53M-07, ASTM International Standard Specification.
[10. 14) Hl-2115090, HI-STORM UMAX System FSAR, Revision 3.
[10.15) ASME BPVC, Sectiorn Il l, Subsection NF, 2010.
[10. 16] Holtec Drawing 10900, "Lift Yoke for HI-TRAC CS", Revision 1.
[10.17) Holtec Drawing 10902, "Lift Yoke for HI-STAR 190", Revision 1.
[10.18] Holtec Drawing 10899, "Tilt Frame and Saddle", Revision 0.
[10.19) Holtec Drawing 10901 , "Lift Link for HI-TRAC CS" , Revision 0.
[10.20] Holtec Drawing 10891, "MPC Lift Attachment", Revision 0.
[10.21] Holtec Drawing 10889, "MPC Lifting Device Extension", Revision 0.
[10.22) Hl-2002444, HI-STORM 100 FSAR, Revision 13.
Supplement 10: 1 of 16 Page 247 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I l~LTii f2~8f21iilJHJ ti": I 114P"Ol":IM< 1161&
I IGiH,TEG RRORRIFIORX Hl-21775851 10.4 ASSUMPTIONS (b)(4) 10.4 INPUTS (b)(4)
Supplement 10: 2 of 16 Page 248 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!T!!e F l"..er :Cl!!T)l(I CI 11&1 Ol<IOIA 1161&
11en!!e r l"..er l"..l!!T)l(ft: Hl-21775851 (b)(4)
Supplement 10: 3 of 16 Page 249 of 371
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Supplement 10: 4 of 16 Page 250 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!TE8 Pliil812liillETt liil:l' ltlFOR'IOIIOM I liLTliw 121ii18PliillET:\liilY Hl-21775851 (b)(4)
Supplement 10: 5 of 16 Page 251 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I l~*Tii f21il8f21iilJHJ t~ I lldP"Ol'ltlelA 1161&
I JOI IE£ RRORPISIO RY Hl-21775851 (b)(4) 10.5.2 Fatigue Life of the Horizontal Lift Beam (10.61 (b)(4)
Supplement 10: 6 of 16 Page 252 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IQmifliiQ 121iilQl21iillliiif Pliil)( It IFQliilt10 ifIQt I If PmifliiQ 121iilitl21iilll!T:\~Y Hl-21775851 (b)(4)
Supplement 10: 7 of 16 Page 253 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 I l@l!TE@ P~SF 111.ll!!T)l(F\ I Hl-21775851 (b)(4)
Supplement 10: 8 of 16 Page 254 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!Tl!e Plll.ePlll.ll!l;S:~l;f IIJFB~l:1//4il81J I liLTliw liilfiililiilfiillliT:R:fiilY Hl-21775851 (b)(4)
Supplement 10: 9 of 16 Page 255 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IQmifliiQ 121iilQl21iillliiif Pliil)( It IFQliilt10 ifIQt I I JOI IE£ RRORPISIO RY Hl-21775851 (b)(4)
Supplement 10: 10 of 1,6 Page 256 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!Tl!e PlilBJ21i11ET;1:1;;1x 1tJFiliil11PilQt1 AGE I ee F l"l!.BPlillET:P:liilY Hl-21775851 10.5.3 Fatigue Life of the HI-TRAC CS Lift Yoke (10.16)
(b)(4) 10.5.4 Fatigue Life of the HI-STAR 190 Lift Yoke (10.17)
(b)(4)
Supplement 10: 11 of 1,6 Page 257 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IGilmifliiQ 121ii1Gi112liillliiift Iii\'. ltlfiliilt 1tlilitl I IGilmifliiw Pliil8Pliilll!TJ tft, Hl-21775851 (b)(4)
Supplement 10: 12 of 1,6 Page 258 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 IIBl!TEB f21i18f2lillETJtlll!i 114Pe111.ru1:,.ie11 I lwH,Tliiiv lii'liil<.?lii'liillliiiTO 9)( Hl-21775851 10.5.5 Fatigue Life of the MPC Lifting Device Extension (10.21)
(b)(4) 10.5.6 Fatigue Life of the HI-TRAC CS Lift links (10.19)
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f21iilJHJtlll!: 114PGlll!f0h t.i814 I lot I E!G P~Bf21iitlliTO liil'< Hl-21775851 10.5.7 Fatigue Life of the MPC Lif t Attachment [10.20)
(b)(4)
Supplement 10: 14 of 1,6 Page 260 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f21i18f21i11ET/J~.\f IIJFBlill:1/:TIBIJ I letTE8 f21i1Bf21i11Eif:R:Jiill:' Hl-21775851 (b)(4) 10.5.8 Fatigue Life of the HI-STAR 190 Tilt Frame & Saddle [10.18)
(b)(4) 10.5.9 Fatigue due to Thermal Cycling of the HI-TRAC CS and Lifting Ancillaries (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f2(iilJHJtlll!: 114Pelll!ruh ,.ie11 I IBl!Tliw 121ii1QlilliillliiiTOR>6 Hl-21775851 10.6 RESULTS (b)(4)
Supplement 10: 16 of 1,6 Page 262 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f21ii1JET;SJ~:V IIJFBliill:1/:TIBll HOLTEC CALCULATION
Title:
CTB Slab and CTF Foundation Slab Structural Evaluations PROJECT No. - ECO No. - REV. No.:
- 5025
- . --N/A-- . --N/A Calculation Package No.: Hl-2177585 Supplement No.: 11 CALCULATION
SUMMARY
INFORMATION Scope: This supplement presents the evaluation of Cask Transfer Building (CTB) and Canister Transfer Facility foundation slab under the loads from Crane, Rail Car, VCT, loaded HI-TRAC CS and loaded HI-STAR 190.
Method: Beams on elastic foundations formulations are used for the analysis.
FSAR LOCATIONS Text (Chapter): Subsections 5.3.2 and 5.3.3 Tables: Table 5.3.2 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 RJ 03/24/2017 YC/VRP 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5.1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed chanoe.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet} supporting several ECOs.
Page 263 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f21iilJHJtlll!: 114PClll!f0h t.i514 IPmject 5025 I lot I E!C P~BPlillliTO liil'G SUPPLEMENT 11 : CTB Slab and CTF Foundation Slab Structural Evaluations
1.0 INTRODUCTION
This supplement performs t he computations for the structural analysis of the Cask Transfer Building
{CTB) Floor Slab under the load combinations identified in Section 5.3.3 of HI-STORE SAR [1]. CTB floor slab is evaluated for loads from VCT, Crane, Rail Car and HI-TRAC CS. Since the CTB floor slab and Canister Transfer Facility Foundation Slab have the same design. A bounding evaluation is performed in this supplement.
2.0 METHODOLOGY All evaluations are performed using beams on elastic foundations based relationship from Chapter 9 of
[3]. Mathcad [2] is used for this evaluation.
3.0 ASSUMPTIONS The following assumptions are made in this analysis:
(b)(4)
Supplement 11- Page 1 of21 Page 264 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!Tl!e Plll.ePlll.ll!T;S:~l;f IIJFB~l:1//4il81J IPmject 5025 I IBLTlii!i 121iil'ellii'RlliiiTORY 4.0 ACCEPTANCE CRITERIA The CTB Floor slab is designed to meet the strength requirements of ACI 318-05 (4). Per the HI-STORE SAR (1), the CTB floor slab needs to be evaluated for the following load combinations:
Load Combination #1 : 1.40 Load Combination #2: 1.2D+ 1.6L Load Combination #3: 1.2D+L+E Where D is the dead load of the CTB slab, L is the live load acting on the CTB slab (including weight of VCT,Crane,Rail and HI-TRAC CS) and E is the Design Basis Earthquake for the site which is same as Safe Shutdown Earthquake (SSE).
5.0 INPUTS (b)(4)
Supplement 11- Page 2 of 21 Page 265 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB Flll.eFf'tJ!!!TJti CI 114FOl'ltlOIA 11614 IPmject 5025 I IOl!T!!!e F 111.er 111.l!!!TAIII. I (b)(4) 6.0 MOMENT AND SHEAR CAPACITY CALCULATION The moment and shear capacity of the CTB floor slab are calculated in this section using ACI code [4].
(b)(4)
Supplement 11- Page 3 of 21 Page 266 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f21ii1JET;SJ~.\f IIJFBliill:1/:TIBIJ IPmject 5025 I IBLTliQ RliilORPIEIORY (b)(4) 7.0 ANALYSIS In this section, the loading on the slab due to its self-weight and from each of the loading cases (viz.
crane, rail car, VCT and Loaded HI-TRAC CS are first individually calculated. Each of these loading cases are then combined using the load combinations identified in Section 4.0.
7.1 Loading from CTB Floor Slab (b)(4)
Supplement 11- Page 4 of21 Page 267 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!T!!e F l"..er :Cl!!T)l(I Cl 11&1 Ol<IOIA 1161&
IPmject 5025 I /GI IE£ RR ARR IEI OPY (b)(4) 7.2 Loading from Crane (b)(4)
Supplement 11- Page 5 of 21 Page 268 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f21iil:IET:S:~\f IIJFBliill:1/:TIBIJ IPmject 5025 HAI IE£ RRORRIFIABX Hl-21775851 (b)(4)
Supplement 11- Page 6 of 21 Page 269 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f21iit8f2(iilJ[lJtlll!: 114Pelll!ruh ,.ie11 IPmject 5025 I 16ilmTliii!i 12liil.Bf21iitlE!5TJ tR I (b)(4)
Supplement 11- Page 7 of21 Page 270 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IQmifliiQ 121iilQl2liillliiift liil:Y ltlfiliilt 1tlilitl IPmject 5025 I 18LTE8 121ii1812fiillliT:P:fiil.Y (b)(4) 7.3 Loading from Rail Car (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 I 181!TE8 Plil:8Plil:IH: tR I 114P61'Ubh c.i614 IPmject 5025 I liiLTE8 Plil:8Plil:l!ETAR I Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 IPmject 5025 I /GI IE£ RR ARR IEI OPY (b)(4)
Supplement 11- Page 10 of 21 Page 273 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOEi EC I l<OP l<IET)l(:CI 114Pefll.M/:'lil81l IPmject 5025 I 181!TE8 Plii1JjJ2~11iiiTOliil:Y (b}(4)
Supplement 11 - Page 11 of 21 Page 274 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I 1621 EC F ICOF l(IEIAiCI 11&1 Oi<IOIAI IOI&
IPmject 5025 J JO mTJiii Q J2 Jiil: iW Jiil: Jl!TJ\fi~J;C (b)(4)
Supplement 11 - Page 12 of 21 Page 275 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l~bTii f2~8f21iilJHJ ti": I 114FOl":IM< 1161&
IPmject 5025 I IGl!TE!B f2~8f2~11iTO liil:Y (b)(4)
Supplement 11- Page 13 of 21 Page 276 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 AOL I EC PRUFRIE ,Al< I 114P"O~f0h t"81l IPmject 5025 1181!TE8 jiilliil.Qjiilliil.,FIOPY (b)(4)
Supplement 11- Page 14 of 21 Page 277 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 11\iLTilil P~8Pfill!!!l)l(I CI 11&1 Ol(IOIA I IOIQ IPmject 5025 11eerE!e r filer fillE!T)l(fil:
7.4 Loading from the VCT (b)(4)
Supplement 11 - Page 15 of 21 Page 278 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IIOE,te FP\OFICILTJtP\i 114Pefll:1:S.'li,81l IPmject 5025 I iiiLTlii!i 12liil:iil2liil:iliT:R:iiil.Y (b)(4)
Supplement 11- Page 16 of 21 Page 279 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I 1Sill IFS RRORRIFIO RV ltlEORD4 OIIOM IPmject 5025 11el!TE!e F ..:er P\IE!TAP\,
7.5 Loading from the HI-TRAC CS (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 11el!Tl!e 12~BJ2lii1JET;2:1;;1x 1tJFiliil11Pi12t1 IPmject 5025 I 12miliiiQ (iiJ(iilQ(ii)QlliiiIOPY (b)(4) 8.0 BEARING AND PUNCHING SHEAR EVALUATION (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l~LTii f2~8f21iilJHJ ti": I 114FOl":IM<I IOI&
IPmject 5025 I 18LTliQ 12RARRIFIQBX (b)(4)
Supplement 11- Page 19 of 21 Page 282 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 IPmject 5025 I 181!TE!8 PR8PRIE!TJ tR I
!b)(4)
Supplement 11- Page 20 of 21 Page 283 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!T!!e FICOP I& IAl(f IMORIOIAI IOIQ IPmject 5025 I l'iilmTliiiG RR'iilRRlliiiIO PY (b)(4)
9.0 CONCLUSION
Structural analyses are performed to evaluate the structural integrity of the CTB floor slab. The results from the analysis demonstrate that the safety factors for the slab strength evaluation are greater than 1.0. Therefore, the CTB floor slab and Canister Transfer Facility foundation slab are adequate to support the crane, rail car, VCT and HI-TRAC CS/HI-STAR 190 loads.
10.0 COMPUTER FILES All files related to this calculation are saved in Holtec network under:
11.0 REFERENCES
(1) Holtec Report Hl-2167374, "Licensing Report on the HI-STORE CIS Facility, Revision 0.
(2) Mathcad 15.0, Parametric Technology Corporation, 201 1.
(3) Advanced Mechanics of Materials, A.P. Boresi, O.M.Sidebottom, F.B.Seely and J.O. Smith by John Wiley and Sons , Third Edition, 1978.
[4] ACI Standard Building Code Requirements for Structural Concrete and Commentary, AC, 318-05.
(5] Holtec Drawing 10912, "Cask Transfer Building Floor Slab", Revision 0.
(6) Holtec Drawing 9841 , "HI-STAR 190 Cask Assembly", Revision 0.
[7] Holtec Drawing 10899, "Tilt Frame and Saddle", Revision 0.
[8] Holtec Drawing 10868 "HI-TRAC CS", Revision 0.
[9] https ://www.wabtec.com/uploads/outli nedrawi ngs/Track_Components_Section.pdf 12.0 APPENDIX APPENDIX A -Representative Design Drawings of Crane, Rail Car and VCT Supplement 11 - Page 21 of 21 Page 284 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l~mifliQ 12JiilQl2JiillliiT;SJ~:V IIJFBfll.fOh ,.ie11 Project 5025 HO! IE<; PlilQPlilll!ifO RV Hl-2177585 APPENDIX -A REPRESENTATIVE DESIGN DRAWINGS OF CRANE, RAIL CAR AND VCT Page 285 of 371
(b)(4)
(b)(4)
(b)(4)
(b)(4)
ATTACHMENT 11 TO HOLTEC LETTER 5025012 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 HOLTEC CALCULATION
Title:
HI-TRAC CS Lift Links Stress Analysis PROJECT No. - ECO No. - REV. No.: - 5025- -- -N/A- - -- -N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 12 CALCULATION
SUMMARY
INFORMATION Scope: Th is supplement presents the evaluation of the HI-TRAC CS Lift Links subj ected to a bounding weight of the loaded HT-TAC CS.
Method: The analysis is performed using strength of materials formulations in Mathcad.
FSAR LOCATIONS Text (Chapter): Subsection 5.4.6 Tables: Table 5.4.6 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 SP 03/21/2017 OS 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5.1.
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed chanoe.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supporting several ECOs.
Page 290 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!T!!e F l"..er :Cl!!T)l(I CI 11&1 Ol<IOIA 1161&
HOLTl!!e Pff8PRll;iiAAY SUPPLEMENT NO. 12 - HI-TRAC CS LIFT LIN KS STRESS ANALYS IS A.1 INTRODUCTION The purpose of this appendix is to demonstrate that the load bearing parts of the HI-TRAC CS Lift Link for HI-STORE [A.6] meet all requirements of NUREG 0612 [A.1] and ANSI N14.6 [A.2].
A.2 METHODOLOGY The analyses are carried out using strength of materials formulations for statically determinant components.
A.3 ACCEPTANCE CRITERIA For a design without redundant load paths, the maximum stress in any load bearing component, per Refs. [A.1] and [A.2], is limited to the minimum of either one-tenth of the material ultimate tensile strength or one-sixth of the material yield strength.
(b)(4)
A.4 ASSUMPTIONS (b)(4)
A.5 REFERENCES (A.1J NUREG-0612, Control of Heavy Loads at Nuclear Power Plants .Section 5.1.6(3), 1993
[A.2] ANSI N14.6, American National Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 Kg) or More for Nuclear Materials, ANSI, 1993.
[A.3] ASME BTH-1-2008, Design of Below-the-Hook Lifting Devices, January 2009.
[A.4) ASME BPVC,Section II, Part D, 2010.
[A.5) CMAA Specification #70 (1988), Crane Manufacturers of America.
[A.6] Holtec Drawing 10901 , Revision 0, "HI-TRAC CS Lift link" (A.7) A ISC Steel Constnuction Manual, Ninth Edition.
[A.8) Holtec Drawing 10868, Revision 0, "HI-TRAC CS".
[A.9) Holtec Report Hl-2114830, Revision 4, "HI-STORM FW FSAR".
[A.1 OJ STRENX 900E Data Sheet, SSAB, 2010.
[A.11) ASTM A514/A514M - 05, Standard Specification for High-Yield Strength, Quenched Project No. 5025 Supplement No.12 - Page 1 of 8 Hl-2177585 Page 291 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 AOL I EC FROFR,E I Al< I 11&1 Ol'ltlehl<fl014 I 18LTee PR8PRIETARY A.6 INPUT DATA A.6.1 Lifted Weight (b)(4)
A.6.2 Material Properties (b)(4)
A.6.3 Lift Link (b)(4)
Project No. 5025 Supplement No.12 - Page 2 of 8 Hl-2177585 Page 292 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l~mTii f21il8f21iilJHJ ti": I 114FOl":IM< 1161&
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(b)(4)
A.7.0 CALCULATIONS A.7.1 Allowable Stresses (b)(4)
A.7.2 Tensile Stress The load on each Lift link is one-half of the total lifted load. The maximum tensile stress occurs at the section with the minimum cross-sectional area.
(b)(4)
Project No. 5025 Supplement No.12 - Page 3 of 8 Hl-2177585 Page 293 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2lil:8f2lil:IET:\~:V IIJFBlill:1/:TIBll I IQl:'fl!& PR8PRll!lJltRY (b)(4)
Direction of applied load Curved edge R
+--~ CL hole Figure 1: Inputs Used for Single Plane Fracture and Double Plane Shear (from [A.3]}
A.7.3 Lift Link Bottom Hole Tearout Tearout could occur in the two vertical planes at each lifting pin through the holes in the lift link. The load is taken as the total capacity and weight of the lift link combined. The tearout stress and safety factor of t he lift link can be computed as (see Fig. 1):
Project No. 5025 Supplement No.12 - Page 4 of 8 Hl-2177585 Page 294 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f2(iilJ[lJtlll!: 114Pelll!ruh ,.ie11 W'lills'fliii PA8PRIE7JiJltRY (b)(4)
A.7.4 Single Plane Fracture at Bottom hole Single plane fracture at bottom hole is bounding over top hole as diameter of bottom hole is more than top hole.
Using the terminology and equations used in [A.3], Single plane fracture for the lift link is Project No. 5025 Supplement No.12 - Page 5 of 8 Hl-2177585 Page 295 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I 162 I EC F ICOF 1(12 I AiC I 11&1 Oi<IOIA I IOI&
I 18LTee PR8PRIETARY calculated. Figure 1 shows an illustration of the inputs for the method.
(b)(4)
A.7.5 Bearing Stress at Top hole Bearing stress on top hole is bounding over bottom hole as top hole bearing area is smaller than bottom hole.
The bearing loads at the top pin are distributed to both the lift link and from lift link to holes, each of which is subjected to one-half the load. The material with the lower bearing stress allowable governs the calculation of the bearing stress safety factor.
Project No. 5025 Supplement No.12 - Page 6 of 8 Hl-2177585 Page 296 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IQmifliiQ 121iilQl21iillliiif Pliil)( It IFQliilt10 ifIQt I I 18L'fl!& PR8PRll!iAR¥ (b}(4}
A.7.6 Lift Link Top Hole Tearout (b}(4}
Project No. 5025 Supplement No.12 - Page 7 of 8 Hl-2177585 Page 297 of 371
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A.8 COMPUTER FILES The computer files associiated with this analysis are stored in Holtec's network at the following location:
G:\Projects\5025\REPORTS\Structural Reports\Hl-2177585 (HI-STORE CISF Cale Package)\REV O\Supplement 12 A.9 CONCLUSION The analysis performed in this supplement shows that the HI-TRAC CS lift link is structurally adequate as all safety factors are above 1.0.
Project No. 5025 Supplement No.12 - Page 8 of 8 Hl-2177585 Page 298 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I lel!T!!e F l"..er :Cl!!T)l(I CI 11&1 Ol<IOIA 1161&
HOLTEC CALCULATION
Title:
HI-STAR 190 TILT FRAME AND SADDLE STRESS ANALYSES PROJECT No. - ECO No. - REV. No.: - 5025_ -- -N/A- -- N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 13 CALCULATION
SUMMARY
INFORMATION Scope: In this calculation, tilt frame assembly for HI-STORE is analyzed under normal condition.
Method: Combination of finite element code (ANSYS) and formulation of strength of materials are used for evaluation.
FSAR LOCATIONS Text Modifications (Chapter): Subsection 5.5.1 Table Modifications: Table 5.5.1 REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 VM / 03-24-2017 AIS/ 03-24-2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5.1 .
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed change.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supporting several ECOs.
Page 299 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 I I 11\ e Prepsietas/ Hl-21775851 SUPPLEMENT 13: HI-STAR 190 Tilt Frame And Saddle Stress Analyses
- 13. 1 Introduction This supplement documents the structural evaluation undertaken to demonstrate that the HI-STAR 190 tilting plate and saddle assembly (hereafter referred as tilting frame assembly) (13.1] meets the applicable structural acceptance criteria. The tilting frame assembly will be used to rotate the loaded HI-STAR 190 cask (13.2] from vertical to horizontal, and from horizontal back to vertical orientation.
The loaded HI-STAR 190 cask with impact limiters arrives in the HI-STORE CIS facility on a rail cart in the horizontal orientation. The loaded cask with impact limiters is then lifted using the horizontal lift beam and staged on the tilting frame assembly. The tilting frame assembly is designed to support the loaded HI-STAR 190 cask with impact limiters along its length. The HI-STAR 190 trunnions on the saddle end engage with the lift yoke for the upending/downending operation of loaded HI-STAR 190 cask (without impact limiters). The HI-STAR 190 cask pivots about the bottom trunnions supported on the trunnion support block (item 9 of [13.1 1). Once the cask is upended, it is removed from the frame and positioned over CTF.
As the above operations are expected to span within a work shift, the tilt frame assembly is seism ic-exempt per (13.3]. Furthermore, if the above operations extends beyond a work-shift, the HI-STAR 190 cask will be staged on the tilt frame assembly with the impact limiters. Thus based on the above discussion, the tilt frame assembly is evaluated under the following loading cases:
- 1) Upending of HI-STAR 190 at 90 degrees from the ground
- 2) Upending of HI-STAR 190 at 45 degrees from the ground
- 3) HI-STAR 190 cask staged on tilt frame assembly with impact limiters For all the above load cases, appropriate bounding loads are considered.
13.2 References (13.1] Holtec Drawing 10899, Tilt Frame & Saddle, Revision 0.
(13.2] Holtec Drawing 9841 , HI-STAR 190 Cask Assembly, Revision 0.
(13.3] Licensing report on the HI-STORE CIS Facility, Hl-2167374, Revision 0.
(13.4] ANSYS, Version 17.1, ANSYS Inc. , 2017.
(13.5] HI -STORM UMAX FSAR, Hl-2115090, Revision 3.
(13.6] ASME Section Ill, Subsection NF, 2010.
(13.7] ASME Section II, Part D, 2010.
(13.8] AISC Steel Construction Manual, Thirteenth Edition.
(13.9] ASTM Standard Specification for High-Strength Low-Alloy Columbium-Vanadium Structuiral Steel, A572/A572M-07.
(13.1OJ Shigleys Mechanical Engineering Design, McGraw-Hill Publications, Eigth Edition.
[13. 11 ] Machinery's Hand Book, 27th Edition.
[13.12] Holtec Report Hl-2146286, latest revision.
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lglsfii f21il8f2lil.lHJ ti".. I 114Fel"..IM< 1161&
1111\11 l2r111riotssy Hl-21775851 13.3 Methodology The CAD models of the tilting frame assembly [13.1] (built in Solidworks) is imported into the finite element simulation code .ANSYS [13.4]. The tilting frame assembly is analyzed and qualified under the above mentioned load cases. The structural evaluations are carried out using a combination of strength of material formulations and finite element analysis. A CAD model of the tilting frame assembly is shown in Figure 13.1 below. Necessary dimensions to perform the strength of material evaluations are taken from CAD model directly. Minor deviations are noted between the final drawing (13.1] and the CAD model used in the analysis. However, these deviations have negligible affect on the safety conclusions drawing in this supplement.
(b)(4)
Figure 13.1 Tilting Frame Assembly 13.4 Acceptance Criteria Per [13.3). t ilting frame assembly is evaluated againstASME Section Ill , Subsection NF [13.6] .
For the normal downending/upending condition, the applicable stress limits of Level A shall not be exceeded. In lieu of considering individual stress components, the strength limits from [13.6] are compared with the tension, be11ding and shear stresses.
All safety factors of the tilting frame components, defined as the ratio of the allowable stress to the actual stress, must be larger than 1.0.
13.5 Assumptions (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f21i18f21i11ET/J~.\f IIJFBlill:1/:TIBIJ I lellse 12: ep: iela:; Hl-21775851 (b)(4) 13.6 Analysis 13.6.1 lnQut Data (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I l~mifii 12Jiilil2Jiilllii!T/:Jiill;f IIJFBflUUh ,.ie11 Holtes Rsopsietaw Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!Tl!e P~BP(iil:l[T;S:liil:lf ltlfiliill12i1Qtl I lellse 12: aµ: iela:; Hl-21775851 13.6.2 Analysis for u12ending of HI-STAR 190 at 90 degrees f rom the ground (Load Case 1}
(b)(4)
Figure 13.2 Load case 1- boundary and loading conditions Results :
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 11g1s:rmQ 12fiqg121ii111iiifa liil:lf 1tJFiliilt, tlilitt IProject 5025 Holtes Rmpsiotaw Hl-21775851 (b)(4)
Figure 13.3 Bending and shear stress in the mounting block plate (item 3 of [13.1))
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB Plil:BPlil:IHJtl'I!: 114Pel'l!ruh ,.ie11 I le Ilse 12: aµ: iela:; Hl-21775851 (b)(4)
Figure 13.4 Normal stress (Y-axis - vertical) in the trunnion support block (item 9 of [13.1))
(b}(4}
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 I Iii IFS RRORRIFIOPV ltlEORD40IIOM IProject 5025 I lellse 12: ep: iela:; Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I l~mifii 12Jiilil2Jiilllii!T/:Jiill;f IIJFBfll.fOh ,.ie11 Waltos RsopcietacH Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!Tl!e Plll.ePlll.ll!l;S:~l;f IIJFB~l:1//4il81J 1111\11 l2r111rotsw,r Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f21iilJET:\~\f IIJFBfiill:1/:TIBIJ I (ell I l2rBpsiB1aQ( Hl-21775851 (b)(4)
Figure 13.6 Bending stress in the gusset plates; item 6 & 18 on the left and item 8 on the right (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!T!!e Plll.ePlll.l!!l:\~l;f IIJFB~l:1:S.'lilBIJ I lell 1 12rBpsiBtaQ( Hl-21775851 (b)(4)
Figure 13.7 Force and Moment Reaction on Weld 2-12 from A NSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11-amliiiii 12liil:il2liil:llii!T:S:liil:\f IIJFBlll!IUIJ ,.ie11 I lblttc P: op *1ts7;r Hl-21775851 (b)(4)
Figure 13.8 Force and Moment Reaction on Weld 2-11 from ANSYS analysis (b)(4)
Figure 13.9 Force and Moment Reaction on Weld 2-11 (opposite side) from ANSYS analysis Supplement 13: 13-13 of 13-55 Page 312 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!H:e I l(OP 1(12 IAl(f IMORIOIAIIOIQ I lbiltt P: aµ; isl r; Hl-21775851 (b)(4)
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Figure 13.10 Combined Weld Group for weld between item 2 and item 3, item 7 and item 3, &
item 20 and item 3 (13.1]
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f21ii1JET;SJ~.\f IIJFBliill:1/:TIBIJ I lollco 12: (I rotssr Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!Tl!e Plll.ePlll.ll!l;S:~l;f IIJFB~l:1//4il81J I lollss 12: 11ri1t w,r Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!TE!e F P':.OF :CIE!T)l(P'l!I 11&1 Ol<ICIA 1161&
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Figure 13.11 Force and Moment Reaction on combine weld group (2-5 & 2-20) from ANSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 IIOEI EC F l<Oi ICILT)l(P'l!I 114P"Of'lilol)l(Tl014 I Jeltoc Rrepriotaqc Hl-21775851 (b)(4)
Figure 13.12 Force and Moment Reaction on Weld 2-3 from ANSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IQLTi8 P~8PflllE!T)l(P'IJ. I 11&1 01<:0IA I IOIQ I lbllcs 12FBprie1AD' Hl-21775851 (b)(4)
Figure 13.13 Force and Moment Reaction on Weld 2-1 from A NSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IQLTi8 Plil.ePRl!!TAI< I IMURIOIAI IOIQ I lollcs Pr prietai,r Hl-21775851 13.6.3 Anail'.sis for u12ending of Hi-STAR 190 at 45 degrees from the ground (Load Case 2}
(b)(4)
Figure 13.14 Load case 2- boundary and loading conditions Supplement 13: 13-21 of 13-55 Page 320 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!TE8 Pliil:812liil:IETt liil:l6 ltlFOR'IOIIOM Waltos RsopcietaQt Hl-21775851 Results:
(b)(4)
Figure 13. 15 Load Case 2: Bending and shear stress in the mounting block plate (item 3 of [ 13.11)
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!Tl!!e Plll.ePlll.ll!l:\fiill;f IIJFBfiill:1:S.'lilBIJ
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Figure 13.1 6 Load Case 2: Nonnal stress (Y-axis - vertical) in the trunnion support block (item 9 of (13.1])
(b)(4)
Figure 13.17 Load Case 2: Bending stress in the trunnion support block (item 9 of (13.1])
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I 1621 EC F ICOF l(IEIAiCI 11&1 Oi<IOIAI IOI&
Hallee Proorietao, Hl-21775851 (b)(4)
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Figure 13.18 Load Case 2: Bending stress in the boxed beam's strong axis direction (b)(4)
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Figure 13.19 Load Case 2: Bending stress in the gusset plate (item 5 of [13.11)
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f21i18f21i11ET/:lil\f IIJFBfiill:1/:TIBIJ I lellse 12: aµ: iela: J Hl-21775851 (b)(4)
Figure 13.20 Load Case 2: Bending stress in the top gusset plate (b)(4)
Figure 13.21 Load Case 2: Bending stress in the new top gusset plate Supplement 13: 13-27 of 13-55 Page 326 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11-amTii f2lil:8f21illHJt~ I 1141 Of'lilM\1161&
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Figure 13.22 Load Case 2: Force and Moment Reaction on Weld 2-1 1 from A NSYS analysis (b)(4)
Figure 13.23 Load Case 2: Force and Moment Reaction on Weld 2-11 (opposite side) from ANSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f2(iilJ[lJtlll!: 114Pelll!ruh ,.ie11 I lellse 12: ep: iela:; Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f21i18f2lillHJtlll!: 114P6111!1Uh 1.ie14 I lollss 12: 11ri1, i/ Hl-21775851 (b)(4)
Figure 13.24 Load Case 2: Force and Moment Reaction on combined weld group (shown in Figure 13.10) from ANSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IQmifliiQ 121iilQl2liillliiift Iii\'. ltlfiliilt 1tlilitl I lells 12r pristas/ Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 HAI ISG RRORRIFIOP)( ltlEOPD40Tliltl IProject 5025 11 Hes Rsegcietao, Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB Flll.ePf'tJ!!!TJ ti CI 114POl'ltlOIA 11614 I lellse 12: ep: iela:; Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 AOL I EC FROFRIE ,Al< I 11&1 Of'li,M(fl014 IProject 5025 I h 1\11 12; op; iota: 1 Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 IIOE,te FP':.OFICILTJtP':.i 114P!lill:1:S.'lii81l I ,silos 12: 11ri1,1 ,: Hi-21775851 (b)(4)
Figure 13.26 Load Case 2: Force and Moment Reaction on combined weld group (shown in Figure 13.25) from ANSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!Tl!e P~Bf2(iilJ[T;3:liil:\f ltlfiliill12i1Qtl I lollos 12: 11ri1t1F)I Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f21ii1JET;SJ~.\f IIJFBliill:1/:TIBIJ I l1lh Rmpsietasy Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!Tl!e Plll.ePlll.ll!T.S:~\f IIJFB~l:1//4il81J hbittc P: sµ rietosu Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!T!!e Plll.ePlll.l!!T:S:~\f IIJFB~l:1:S.'lilBIJ I lellse 12: ep: iels:; Hl-21775851 (b)(4)
Figure 13.27 Load Case 2: Force and Moment Reaction on weld 2-15 (top) from ANSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!Tl!e 12~BJ2lii1JET;2:1;;1x 1tJFiliil11PilQt1 I lells 12r prista": Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f21i18f21i11ET:S:lil\f IIJFBlill:1/:TIBIJ I /site !2r111ri1,111:, Ht-21775851 (b)(4)
Figure 13.28 Load Case 2: Force and Moment Reaction on Weld 2-14 from ANSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 IIOE,te FP\OFICILTJtP\i 114PeRl:1:S.'li,81l
, , ltn Rsopsis!aQ' Hi-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I lel!TE!e Fl"..eFP\IE!T)l(P'IJ.I 1141 bl<IOIAI IOI&
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Figure 13.29 Load Case 2: Combined Weld Group (weld 2-4, 2-9, 2-13) dimensions obtained from (13. 1] and calculations above (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11\iLTii P~8PfillE!Tl tl"I! I 11&1 01<:0IA I IOIQ I lellse 12: ep: iels:; Hl-21775851 (b)(4)
Figure 13.30 Load Case 2: Force and Moment Reaction on combine weld (2-4, 2-9, 2-13) from ANSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f21ii1JET;SJ~.\f IIJFBliill:1/:TIBIJ I lellse 12: ep: iela:; Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 IIOE I EC F l<Oi ICILT)l(flt I 114P"Ofltiol)l(Tl014 ti lh 1 12; op; iota: 1 Hi-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 AOL I EC FROFRIE ,Al< I 11&1 Of'li,M(f,614 IProject 5025 I loltco P: op: i **;s,* Hl-21775851 (b)(4)
Figure 13.31 Load Case 2: Force and Moment Reaction on weld between item 19 and item 8 from ANSYS analysis (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 I lblltc F :op: iota: y Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I 1621 EC F ICOF l(IEIAiCI 11&1 Oi<IOIAI IOI&
I lollcs 12r psistaQr Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f21ii1JET;SJ~.\f IIJFBliill:1/:TIBIJ I lellse 12: ep: iela:; Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IQmifliiQ 121iilQl2liillliiift liil:Y ltlfiliilt 1tlilitJ I l11tn RrepsietaQ' Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 I IBl!TEB f2~8f2(iilJ[TJtlll!: 114Pelll!ruh ,.ie11 1111\11 l2r1priotsw,r Hl-21775851 (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 IIOE,Ee Fl":.eFl":.ILTJtl":.i IIJPenr.1:n.,,811 I ioltca P: op:
- tu; Hi-21775851 13.6.4 Analysis of HI-STAR 190 cask staged on tilting frame assembly with impact limiters (Load Case 3)
(b)(4)
Figure 13.32 Load case 3- boundary and loading conditions for the saddle (b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IIOE I ee F l"..eFIC,Ll Jti".: 114P6fll:1;C(J,81l IProject 5025 I isllcs 12r psiotaQr Hi-21775851 (b)(4)
Figure 13.33 Load case 3- Equivalent (van-Mises) stress for the saddle (b)(4)
- 13. 7 Computer Codes and Computer Files MathCad 15.0 is used to prepare this supplement.
ANSYS 17.1 [13.4] is used for structural evaluation of the tilt frame assembly. ANSYS 17.1 is QA validated software under Holtec's QA program. The computer number used for the evaluation is noted below along with applicable Holtec's Approved Computer Program List (ACPL) revision.
Computer Number used for ANSYS analysis 1269 HoltecACPL Rev 341 , Feb 16, 2017 All computer files associated w ith this suoolement are stored under:
(b)(4)
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 IProject 5025 11el!Tl!e P111.eP111.1l!T, ,111., 11JPe111.ru1; ,,1e11 I lollos 12: 11ri1t w,r Hl-21775851 13.8 Conclusion All safety factors for the tilt frame assembly for the three load cases given in Section 13. 1 remains above 1.0. Thus the tilt frame assembly is structurally adequate for its intended use.
Furthermore the upending of HI-STA R 190 using tilt frame assembly is a short-term operation. Such operations span within a work shift and as listed in [13.3] are seismically exempt. However, it should be noted that the design of tilt frame assembly is expected to be capable of withstanding the site specific SSE loads , which are only 0. 15g ZPA in all directions. The tilt frame assembly has been qualified to much higher loads and ASME NF Level A allowables during t he upending operations.
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ATTACHMENT 11 TO HOLTEC LETTER 5025012 HAI IEG PliilQPliillliiTt liil:Y IIJFBlilhh :.ie11 HOLTEC CALCULATION
Title:
EVALUATION OF CTB COLLAPSE ON HI-TRAC CS AND HI-STAR 190 PROJECT No. - ECO No. - REV. No.: - 5025_ -- -N/A- -- N/A_
Calculation Package No.: Hl-2177585 Supplement No.: 14 CALCULATION
SUMMARY
INFORMATION This supplement documents the analysis of the postulated CTB collapse accident to demonstrate that the HI-TRAC CS transfer cask and IHI-STAR 190 transport cask can protect the spent fuel inside the two casks under the governing impact scenarios without any unacceptable safety impact. The analysis is performed using LS-DYNA.
FSAR LOCATIONS Text Modifications (Chapter): Subsection 5.4.2 & Figures 5.4.3 to 5.4.6 Table Modifications: N/A REVISION LOG Rev. No. Preparer Initials /Date Reviewer Initials /Date 0 JZ 03/20/2017 VM 03/24/2017 1
2 The Calculation presented herein provides the analytical basis to adopt the proposed change contemplated by the ECO (see Note 1). The Design Verification Checklist (DVC) documenting the technical review of this calculation is associated with the applicable ECO in the computerized ECO network database.
This Calculation is technically reviewed and QA validated in accordance with HQP 5.1 .
This Calculation is archived in the above-referenced Calculation Package as a labeled supplement. This document may be shared as an autonomous piece of work with external organizations and revised, if necessary, to secure their concurrence to the proposed change.
Note 1: All analyses performed to respond to a query or to initiate a design change are archived in a new Calculation Package or added to an existing Calculation Package as a Supplement and the revision number of the Calculation Package is advanced.
A supplement to a Calculation Package may consist of one analysis or several discrete analyses (each containing this cover sheet) supporting several ECOs.
Page 355 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TE!e Plll.!F:CIE!TAl<I 11&1 ORIOIAI IOIQ
1.0 INTRODUCTION
Multi-Purpose Canisters loaded with spent fuels need to be transferred from the HI-STAR 190 transport cask to the HI-TRAC CS transfer cask at the Cask Transfer Building (CTB) before they can be stored at the HI-STORE underground spent fuel storage facility in New Mexico. Potential environmental and man-made hazards at the HI-STORE site, such as earthquake, could result in the collapse of the CTB and a significant safety impact to a loaded HI-STAR L90 transport cask or a loaded HI-TRAC CS transfer cask in the CTB. The objective of thi s calculation is to evaluate the consequences of the postulated CTB collapse accident.
The CTB collapse accident evaluation documented in this calculation is focused on the analysis of the falling CTB roof onto a horizontally positioned HI-STAR 190 and a vertically positioned HI-TRAC CS. As shown in the CTB floor slab layout [ 1], the Loaded HI-TRAC is expected to be placed between the Vertical Cask Transporter (VCT) supporting steel plates on the floor prior to being carried away by the VCT, and the horizontally positioned HT-STAR 190 on the cask cradle waiting for the MPC transfer operation is also aligned with the Canister Transfer Facility (CTF) and the expected HI-TRAC location. The CTB layout drawing also indicates that casks are expected to be at least 23 feet away from the CTB wall, which suggests that the impact between the falling CTB roof and the cask is a more realistic scenario.
2.0 METHODOLOGY AND ACCEPTANCE CRITERIA The finite element method is used to perform the analysis for the postulated impact be tween the falling CTB roof and the loaded HI-STAR 190 and HI-TRAC CS casks. LS-DYNA [2], a commercial computer code developed by the Livermore Software Technology Corporation and independently validated by Holtec International through its QA program [6], is used to perfonn the numerical simulation. This analysis methodology has been used to perform impact analyses for numerous USN RC licensed spent fuel wet and dry storage projects.
Project No. 5025 Page S 14-1 Report No. HJ-2177585 Page 356 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IQmifliiQ 121iilQl2liillliiift liil:Y ltJFiliilt 1tlilitl The acceptance criteria for the analyzed event are listed below. The ultimate goal is to demonstrate that both HI-STAR 190 and HT-TRAC CS casks can survive in the CTB collapse event without causing any sign ificant safety impact.
- l. The containment boundary of the HI-STAR 190 cask overpack shall not be breached or significantly deformed in the CTB collapse accident so that the spent fuel assemblies loaded inside the MPC will remain structurally intact and the MPC retrievability is not significantly affected.
- 2. The HI-TRAC CS transfer cask shall not overturn in the CTB collapse accident to provide continuous shielding function for the MPC.
- 3. The MPC enclosure vessel shall not be breached in the CTB collapse accident.
- 4. The shie lding capacity of the impacted HI-STAR 190 overpack and HI-TRAC CS overpack shall not be significantly compromised due to the CTB collapse accident.
3.0 ASSUMPTIONS (b)(4)
Project No. 5025 Page S 14-2 Report No. HJ-2177585 Page 357 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB Flll.eFf'tJ!!!TJti CI 11 4FOl'ltlOIA 11614 (b)(4) 4.0 INPUT DATA
- 4. 1 Geometric Input Data (b)(4) 4.2 Weight 4.3 Drop Height and Impact Velocity (b)(4) 4.4 Material Properties l(b)(4)
Project No. 5025 Page S 14-3 Report No. HJ-2177585 Page 358 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!T!!e Pl'l.§F:CIE!TAl<I 11&1 ORIOIAI IOIQ (b)(4)
5.0 REFERENCES
[ I] "Cask Transport Bui Idung F loor Slab," Holtec Drawing No. 1091 2, Revision 0.
[2] LS-DYNA 971, Livermore Software Technology.
[3] "Finite Element Analyses of the HI-STAR 190 Transport Cask Package Drop Accidents,"
Holtec Report HI-2146321, Revision 1.
[4] "HI-TRAC CS Stack-up Analysis at CTF and UMAX," Supplement 5 to this calculation package.
[5] "HI-TRAC CS Licensing Drawing," Holtec Drawing 10868, Revision 0.
[6] Holtec Approved Computer Program List (ACPL), Revision 341.
[7] "Structural Calculation Package for HT-STORM FW System," Holtec Report HI-2094418, Revision 19.
[8] HI-STAR 190 SAR, Holtec Report HI-2146214, Revision OD.
Note: The revision status ofHoltec documents cited above is subject to updates as the project progresses. This document will be revised ifa revision to any of the above-referenced Holtec work products materially affects the instructions, results, conclusions or analyses contained in this document. Otherwise, a revision to this document w ill not be made and the latest revision of the referenced Ho ltec documents shall be assumed to supersede the revision numbers cited above. The Holtec Project Manager bears the undivided responsibility to ensure that there is no intra-document conflict with respect to the information contained in all Holtec generated documents on a safety significant project.
6.0 COMPUTER FILES All computer files associated with this calculation are archived on the Holtec Server under the directories shown in following screen capture.
(b)(4)
Project No. 5025 Page S 14-4 Report No. Hl-2177585 Page 359 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I 162 I EC F ICOF 1(12 I AiC I 11&1 Oi<IOIA I IOI&
7.0 CALCULATIONS (b)(4) 8.0 RESULTS The LS-DYNA simulation results for the analyzed CSB collapse accident are presented in Figures 8.1 through 8.7.
(b)(4)
Proj ect No. 5025 Page S 14-5 Report No. HJ-2177585 Page 360 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f21ii1JET;SJ~:V IIJFBliill:1/:TIBll (b)(4)
Proj ect No. 5025 Page S 14-6 Report No. HJ-2177585 Page 361 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 AOE,26 F l<OF:CIE!TJt~i IIJFBlillPlil~tl
9.0 CONCLUSION
S This calculation evaluates the responses of the loaded HI-TRAC CS and HI-STAR 190 casks in the HI-STORE Cask Transfer Building due to the postulated building collapse accident. The impact event is ana lyzed using the LS-DYNA fin ite e lement analysis approach for the two governing impact scenarios based on conservative assumptions. The analysis resu lts presented in this calculation package demonstrate that the both casks can protect the MPC and its contents against the building collapse event without any adverse safety consequence and without violating any of the acceptance criteria listed in Section 2.
10.0 FIGURES Total Number of Figures = 9 Project No. 5025 Page S 14-7 Report No. HJ-2177585 Page 362 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 1121 ISO f21iqfi>f21iqlfif9 liq)( It lffi>!iqp 10 Tl'ilt I (b)(4)
Figure 7.1, LS-DYNA Model Used to Analyze the CTB collapse Accident Involving a Loaded HI-TRAC CS Transfer Cask Project No. 5024 Page S14-8 Report No. HI-2146321 Page 363 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 11e1:ff!!e p~eP~IE!TJt~ 1 IIIF8~M:'tTl8fJ (b)(4)
Figure 7.2, LS-DYNA Model Used to Analyze the CTB collapse Accident Involving a Loaded HI-STAR 190 Transport Cask Project No. 5024 Page S14-9 Report No. HI-2146321 Page 364 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 1121 ISO RRORRIEIORY IMFORD10IIODI (b) (4)
Figure 8.1, Deformation of the Falling Roofl-Beam on HI-TRAC CS at the End of the CTB Collapse Accident Simulation Project No. 5024 Page S14-10 Report No. HI-2146321 Page 365 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 HOE I EC p ICOP l( j[ I AiC I ii" e~reb tfl@;f J (b)(4)
Figure 8.2, Local Plastic Strain of the Impacted HT-TRAC CS Transfer Cask Project No. 5024 Page S14- l 1 Report No. HI-2146321 Page 366 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 IIOEIEC i 1(61 i<IEIAICI 1141 OICICIAIIOIQ (b) (4)
Figure 8.3, 1-Beam-to-MPC Impact Force Time History Project No. 5024 Page S14-12 Report No. HI-2146321 Page 367 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 1lel!.l:C8 P~iiiP~llifO ~V ltlFOPDCHIO'tl (b)(4)
Figure 8.4, Deformation of the Falling Roofl-Beam on HI-STAR 190 at the End of the CTB Collapse Accident Simulation Project No. 5024 Page S14- l3 Report No. HI-214632 1 Page 368 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l?bzTliiiiQ 121iil2121iillliT:S.liil\C IPJfiiiliilPs1:'tT18fd (b)(4)
Figure 8.5, Local Plastic Strain in the HI-STAR 190 Overpack Steel Shells and radial Ribs Project No. 5024 Page S14- l4 Report No. HI-214632 1 Page 369 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 11e1:ff!!e F"~eF"~IE!TJ (~: lllf8~M:'tT18fJ (b)(4)
Figure 8.6, Local Plastic Strain in the MPC Enclosure Vessel Project No. 5024 Page Sl4-15 Report No. HI-2146321 Page 370 of 371
ATTACHMENT 11 TO HOLTEC LETTER 5025012 I l'iilb*li" P~8PP\ll!!TJ ti( I 1141 61<10,A I ,OIQ (b)(4)
Figure 8.7, Local Plastic Strain at the Fuel Basket Bottom Outside of the Active Fuel Region Project No. 5024 Page S14-16 Report No. HI-2146321 Page 371 of 371
ATIACHMENT 13 TO HOLTEC LETIER 5025012 Holtec Center, 555 Lincoln Drive West, Marlton, NJ 08053 Telephone (856) 797- 0900 HOLTEC INTERNATIONAL Fax (856) 797 - 0909 Ho/tee International Generic Report REGULATORY GUIDE 1.60 TIME HISTORIES USING EZ-FRISK Holtec Report No: Hl-2146083 Holtec Project No: 1027 Sponsoring Holtec Division: NPD Report Class : SAFETY RELATED Notice of Non-disclosure & Confidentiality This report c ins vital intellectual property of Holtcc International developed by the Compa o provide technically robust m ation to its analysts that comports with the latest regulatory gui *nes, state-of- the-art analysis practices and met logics. A generic report has wide applicability acr multiple projects and is widely relied upon by the Compan ' nalysts in the preparation of their products. Reports on validation &
benchmarking of computer codes and on rehensive solution ods for performing safety evaluation of systems, structures and components arc typical s
- ct area generic reports. All generic reports arc classified as "privileged intellectual property of Holtcc lnterna
- 11 with attendant prohibition against their transmission to any external party. Under extenuating circu ances, to mee lient's programmatic needs, visual access to a generic report may be provided to a th* arty individual at Holtec's ises subject to the reviewer and the reviewer's employer executing " n-disclosure, non-use agreement II with ompany. All Holtec generic reports are made availab the USNRC's triermial inspection team at Holtec's pre
- for the regulator's review and inspcc * . External dissemination of this document by anyone without the wnt uthorization of Holtcc' s E tive Committee is unlawful.
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMATION HOLTEC INTERNATIONAL 1
DOCUMENT ISSUANCE AND REVISION STATUS DOCUMENT NAME: REGULATORY GUIDE 1.60 TIME HISTORIES USING EZ-FRISK DOCUMENT NO.: CATEGORY: ~ GENERIC HI-2146083 PROJECT NO.:
1027 D PROJECT SPECIFIC Rev. Date Author's 2
No. A Initia ls VIR #
2 .Bommarcdd 230692 DOCUMENT CATEGORIZATION In accordance with the Holtec Quality Assurance Manual and associated Holtec Quality Procedures (HQPs), this document is categorized as a:
~ Calculation Package3 (Per HQP 3.2) 0 Technical Report (Per HQP 3.2)
(Such as a Licensing Report)
D Design Criterion Document (Per HQP 3.4) 0 Design Specification (Per HQP 3.4)
D Other (S ecif ):
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:
DECLARATION OF PROPRIETARY STATUS El] Nonproprietary :J Holtec Proprietary D Privileged Inte llectual Property (PIP)
- 1. 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 on the company"s network. The Validation Identifier Record (VIR) 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 including revisions to references 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".
Page 2 of 139
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOL"fEC f3R:Of3R:IETAR:'1' INFORMATIOM Project 1027 HOLIECPROPRIETAR¥ Report HI-2146083
SUMMARY
OF REVISIONS Revision 0: Initial Issue.
Revision 1: Revised to add additional sets of time histories with shorter duration to reduce analysis time and/or improve response spectra matching in the Appendix.
Revision 2: Revised the report to include Appendix B to document a single time history set that envelops Regulatory Guide 1.60 response spectra in all three directions and satisfies the requirements for single set of modified real recorded time histories in SRP 3. 7. l [ 1]. All changes made to the report in this revision are indicated by revision bars in the right hand margin.
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMATION Project 1027 HOLTEC PROPRIETARY Report HI-2146083 TABLE OF CONTENTS Sununary of Revisions ..................................................................................................................... i Table of Contents ............................................................................................................................ ii INTRODUCTION .................................................................................................................. I 2 METHODOLOGY .................................................................................................................. 2 3 ACCEPTANCE CRITERIA ................................................................................................... 5 4 ASSUMPTIONS ..................................................................................................................... 8 5 INPUT DATA .......................................................................................................................... 9 6 COMPUTER CODES AND FILES ..................................................................................... 10 7 GENERATION OF TIME HISTORIES .............................................................................. 11 8 RESULTS ............................................................................................................................. 12 9 CONCLUS IONS .................................................................................................................... 13 10 REFERENCES ..................................................................................................................... 14 11 TIME HISTORY TNFORMATION FOR RG l.60 EARTHQUAKE .................................. 15 11.1 Target Response Spectra ............................................................................................ 15 11.2 Average Response Spectra vs. Target Response Spectra ........................................... 16 1 l.3 Seed Time History Selections ..................................................................................... 19 11 .4 Ti1ne History Results .................................................................................................. 21 11.5 Set 1 Time Histories (THs) ......................................................................................... 24 11.5.1 Seed 1 Time History Graphs ................................................................................... 25 11.5.2 Generated Set I Time History Graphs .................................................................... 3 1 11 .6 Set 2 Ti1ne Histories ................................................................................................... 37 11.6.1 Seed 2 Time History Graphs ................................................................................... 38 11.6.2 Generated Set 2 Time History Graphs .................................................................... 44 11.7 Set 3 Time Histories ................................................................................................... 50 Page ii
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATIOM Project 1027 HOLTEC PROPRIETARY Report HI-2 146083 11.7.l Seed 3 Time History Graphs ................................................................................... 51 11 .7.2 Generated Set 3 T ime Hi story Graphs .................................................................... 57 11.8 Set 4 Time Histories ................................................................................................... 63 11.8.1 Seed 4 Time History Graphs ................................................................................... 64 11.8.2 Generated Set 4 Time History Graphs .................................................................... 70 11.9 Set 5 Ti1ne Histories ................................................................................................... 76 11.9.1 Seed 5 Time History Graphs .................................................................................... 77 11.9.2 Generated Set 5 Time History Graphs .................................................................... 83 12 APPEN DICES ...................................................................................................................... 89 Appendix A - Time History Infonn ation for Alternate Sets 3 and 5 .............................. ........ A 1 Appendix B - Single Time History Set Information ................................................................ BI
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 1027 HOLTEC PROPRIETARY Report HI-2146083 1 INTRODUCTION The purpose of this report is to provide information on five sets of three directional time histories generated for 5% damped Regulatory Guide (RG) 1.60 design response spectra [7].
The target design response spectra are scaled to 0.26 g's in all three directions. For Plants that have RG 1.60 earthquake as the ir design basis spectra but with different intensities, the generated time histories and the corresponding response spectra can be linearly scaled to the applicable g-value.
Note that the response spectrum corresponding to each time history need not envelop the target response spectrum. The modified real acceleration time histories are required to meet the applicable requirements specified in NUREG-0800, SRP 3.7. 1 [1], including the spectra enveloping and the statistical independence.
A new time history set satisfying the requirements of SRP 3. 7. l [I] for a modified real recorded single set of time histories is documented in Appendix B. This time history set is generated for 5% damped RG 1.60 spectra scaled to 0.25g's in all three directions.
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOL I EC PF\OF'~IETAF\'1' lt<J t='ORMATIOM Project 1027 HOLTEC PROPRIETARY Report HI-2146083 2 METHODOLOGY Following are the steps involved in the development of the real time histories corresponding to the design spectra.
I.. Obtain the target response spectra over a frequency range of O. l Hz to 50 Hz from [7]
and scale them to 0 .26 g's in all three directions. The target spectrum in both horizontal directions will be identical. For single time history set documented in Appendix B, the target response spectra are scaled to 0.25 g's in all three directions.
- 2. Select at least five sets of the real recorded ground motions that match reasonably well with the shape of design response spectra in three directions. This is accomp lished using EZ-FRISK' ([2] and [l l]) seismic analysis software program.
The response spectra and the corresponding acceleration time histories in three directions are obtained for the seed real recorded ground motions. For single time history set documented in Appendix B, at least one set of real recorded ground motions that match reasonably well with the shape of design response spectra in three directions is selected ..
- 3. Use matching technique in EZ-FRISK' (based on RspMatch2009 method) to scale the selected real recorded ground motions to match with the target response spectra in all three directions. The response spectra and the corresponding acceleration time histories in three directions are then obtained for the generated time histories.
The second and third steps in the process are accomplished using the seismic analysis software program EZ-FRISK'. EZ-FRISK' (an NRC recommended program) is a software package used by engineers and seismologists to perform site-specific earthquake hazard analysis. In the current work, Spectral Matching module in EZ-FRISK' is used to select and match the real recorded ground motions that reasonably match the shape of design response spectra while maintaining a total duration of at least 20.0 seconds, a strong motion duration of at least 6.0 seconds, and a time step size less than or equal to 0.01 seconds [ 1].
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- ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOll EC PROPRIETAR'1' 11-dFORMATION Project 1027 HOLTEC PROPRIETARY Report HI-2146083 Spectral matching makes adjustments to an input accelerogram so that its response spectrum matches a target response spectrum. Spectral matching can be performed as a stand-alone task by directly providing the target spectrum, or in conjunction with a probabi listic seismic hazard analys is.
The spectral matching technique used in the cun-ent work is based on the well known RspMatch2009 spectral matching algorithm. It is based on the time domain method of Tseng and Lilanand ( 1988) ([2] and [ 11 ]), with modifications to preserve non-stationarity at long periods by using different functional forms for the modified time history.
A key benefit of usi ng EZ-FRISK' for spectral matching is that it has a powerful search feature which quickly provides key information in choosing an appropriate initial accelerogram. It contains a scoring feature to select the best accelerograms based on the initial response spectrum's match to the target spectrum, the degree of scaling required for the accelerogram, and the duration of the event. The search gives immediate feedback in the form of thumbnails of the unscaled and scaled accelerograms, as well as the response spectrum.
EZ-FRTSK' is a usefu l tool that allows users to search through more than ten thousand records in the PEER NGA database [3] and about a thousand records in the Central Eastern United States (CEUS) database [4] using built-in selection criteria and user-defined filters.
The records can be filtered out based on more than one hundred record attributes defined in EZ-FRISK' such as:
- Faulting Mechanism
- Earthquake Name
- Magnitude
- Distance Page3
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PR:Of3R:IETAR:'1' lt<J F'OR:MATIOM Project 1027 HOLTEC PROPRIETARY Report HI-2 146083 Based on the scoring importance defined by the user for each of the selection criteria, EZ-FRISK' selects real recorded ground motions and sorts them accordingly. The following selection criteria are available in EZ-FRTSKTM:
- Magnitude
- Distance
- Arias Duration
- RMS (Target- Scaled response)
- Scaling Factor It is noted that some of the time histories generated using EZ-FRfSK' are linearly scaled to meet all the enveloping requirements of SRP 3.7.l [1]. More than five sets of time hi stories were generated as some of the time histories did not meet the strong motion duration and the statistical independence requirements of[l]. All criteria, except for one, from [l] are satisfied as noted in Section 3.
The modified scaled acceleration time histories are adj usted in EZ-FRJSK' to have zero final displacements and velocities using a third order base line correction technique.
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTE:C F'F\OF'~IE:T:A.Fh 11'1FO~MATIOM Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 3 ACCEPTANCE CRITERIA The multiple sets of real acceleration-time histories can be generated in accordance with Section II.1.B, Option 2 of [ 1]. Specifically, the fo llowing criteria must be met when using multiple real time histories for a non-linear analysis:
- l. The minimum number of time histories must be greater than four.
- 2. The total duration of the ground motion time histories should be long enough such that adequate representation of the Fourier components at low frequency is included in the time history. The strong motion duration is defined as the time required for the Arias Intensity to rise from 5% to 75%. The minimum acceptable strong motion duration is six seconds.
- 3. Multiple sets of real ground motion time histories should be used to represent the design spectra. Each set of time histories shall be selected from real recorded ground motions appropriate for the characteristic low and high frequency events.
- 4. The multiple time histories are acceptable if the average calculated response spectra generated from these times histories envelope the design response spectra of the plant.
- 5. An acceptable method to demonstrate the adequacy of a set of multiple time histories, in tenns of enveloping requirements and having sufficient power over the frequency range of interest, is to follow the procedures described below (restated from Option I, Approach II of [l]):
(a) The time history shall have a sufficiently small time increment and sufficiently long duration. Records shall have a Nyquist frequency of at least 50 Hz (e.g., a time increment of at most 0.01 seconds) and a total duration of at least 20 seconds.
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOL'fEC PROPRIETARY INFORMATION Project 1027 JlOLTECPROPRIETARY Report HI-2146083 (b) Spectral acceleration shall be computed at a minimum of I 00 points per frequency decade, uniformly spaced over the log frequency scale from 0.1 Hz to 50 Hz or the Nyquist frequency. The comparison of the response spectrum obtained from the scaled ground motion time history with the target response spectrum shall be made at each freCJluency computed in the frequency range of interest.
(c) The average of the computed response spectrum of the accelerogram shall not fall more than 10% below the target response spectrum at any one frequency. To prevent response spectra in large frequency windows from falling below the target response spectrum, the response spectra within a frequency window of no larger than +/- 10% centered on the frequency shall be allowed to fall below the target response spectrum. This corresponds to response spectra at no more than 9 adjacent frequency points defined in (b) above from falling below the target response spectrum.
(d) In lieu of the power spectrum density requirement of Approach l of [ 1], the computed response spectrum of the modified real recorded ground motion time history shall not exceed the target response spectrum at any frequency by more than 30% (a factor of 1.3) in the frequency range of interest. If the response spectrum for the accelerogram exceeds the target response spectrum by more than 30% at any frequency range, the power spectrum density of the accelerogram needs to be computed and shown to not have significant gaps in energy at any frequency over this frequency range. The power spectrum density function represents the energy distribution at the frequencies of interest.
SRP 3.7.1 [1] requires Criteria 5(a) and 5(b) to be satisfied for each time histories.
However, Criteria 5(c) and 5(d) can be satisfied by utilizing the results for the average of the time histories.
- 6. The time history set (2 horizontal and 1 vertical) must be statistically independent.
This is demonstrated by calculating the cross correlation coefficient for each time history with each of the other two components. The absolute value of each of the three correlation coefficients must be less than 0.16.
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOL I EC PROF'RIET:A.~ '1' lt<J t='ORMATIOM Project 1027 HOLTEC PROPRIETARY Report H I-2 146083
- 7. The amplitude of the real recorded ground motions may be scaled but the phasing of Fourier components should be maintained to the maximum extent practical (i.e.,
minor distortion of the phase angle spectrum due to baseline correction is permissible
[5] and [12]).
- 8. Additionally, consistent with well-established industry practice (but not stated in [1]),
it is required that the acceleration time histories be baseline corrected to have final acceleration, final velocity and final displacement approaching zero.
The higher order baseline correction process invariably elimi nates strict adherence to the phase angle separation between the hannonics that exist in the seed ea rthquake. The Cr iteria l through 6 are set down as invio lable requirements. Criterion 8 is well founded in industry practice but is omitted in [ 1] and Criterion 7 is at odds with Criterion 8.
In the case of spectra with broadened peaks like the RG 1.60 earthquake, maintaining the phasing of Fourier components is often extremely tedious, if not impossible. Even if a Herculean effort is made to preserve it by delicately adjusting amplitudes in the frequency doma in, the subsequent baseline correction operation ends up corrupting it. Thus, higher order baseline correction and phase angle preservation are mutually incompatible requirements.
In the time history sets developed herein, five sets of time histories are generated using the public domain code, EZ-FRISK' (NRC recommended), which operates in the time domain, thus the phasing of Fourier components may be affected during scaling of time histories as well. As a result, while the higher order baseline correctio n is performed and a ll of the above mentioned Criteria I through 6 are followed, the phase angle correspondence with the real recorded seed earthquake is not assured.
A ll criteria above except for 1, 3 and 4 are applicable for single time history set documented in Appendix B.
ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY ll'ilf-ORMATION Project 1027 HOLTECPROPRIETARY Report HI-2146083 4 ASSUMPTIONS Assumptions used in the report are listed wherever applicable.
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 AOL I EC PROPRIE I ARV IIIJFOR.MATIOI\J Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 5 INPUTDATA Input data is defined in Section 11.
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY IN FORMATION Project 1027 I IOLTEC PROPRIETARY Report HI-2 146083 6 COMPUTER CODES AND FILES The time history generation is performed in Windows 7 environment. The analytical software program EZ-FRISK' ([2], [9] and [11]) is used to scale and modify the real recorded ground motions (acceleration time histories) to meet the acceptance criteria in Section 3.0.
The program EZ-FRlSK' Version 7.62, Build 001 [2] and EZ-FRISK' Version 7.65, Build 004 [ 11] is run on Computers 11 87 and 11 88 which are on the Holtec Approved Computer Program List (ACPL) [10]. The analytical software program MATLAB [6] is used to perform data and graphical processing.
All computer fi les relevant to the sets of acceleration time histories are saved on the Holtec network under the fo llowing directory:
l(b)(4)
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMATION Project 1027 HOLTECPROPRIETARY Report HI-2146083 7 GENERATION OF TIME HISTORIES EZ-FRISK' is used to modify the real recorded ground motions (acceleration time histories). One set of acceleration time histories consists of three component directions. EZ-FRISK' employs a target response spectrum as input and enables expansion of the digitized target response spectra to a number of equally spaced frequency intervals on a logarithmic scale. The total number of frequency points (frequency intervals) used in EZ-FRISK' fo r the current work is 500. Specific data for the time histories is contained in Section 11 and the Appendices.
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMATION Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 8 RESULTS The time history results are presented in Section 11 and Appendix A for the 5% damped RG 1.60 earthquake scaled to 0.26 g's in all three directions. Section 11 provides information on 5 sets of time histories. In addition, Appendix A provides information on alternate Set 3 and Set 5 which provide shorter duration and/or improve response spectra match. The a lternate Set 3 and Set 5 can be used in conjunction with Sets l, 2, and 4 time histories of Section 11 to fonn a complete 5 sets of time histories which meet the criteria listed in Section 3.
The single time history set results are presented in Appendix B for the 5% damped RG 1.60 earthquake scaled to 0.25 g's in all three directions.
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ATTACHMENT 13 TO HO LTEC LETTER 5025012 I IOLTEC PROPRIETARY l~JFORMATION Project 1027 HOLTECPROPRIETARY Report HI-2146083 9 CONCLUSIONS The acceleration time histories, generated using EZ-FRISK', presented in Section 11 and the Appendices, demonstrate adherence to acceptance criteria defined in Section 3. The data presented in Section 11 and Appendices, and saved on the network location given in Section 6 is suitable for use as input data for subsequent analyses.
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTE:C PROPRIETARY INFORMAflOl'>I Project 1027 HOLTEC PROPRIETARY Report HI-2146083 10 REFERENCES
[l ] U.S. Nuclear Regulatory Commission, "Standard Review Plan Chapter 3.7. 1 -
Seismic Design Parameters", Revision 3, March 2007.
[2] Risk Engineering, Inc., "EZ-FRISK' 7.62 Build 001, Software for Earthquake Ground Motion Estimation", 2011.
[3] PEER, "The Pacific Earthquake Engineering Research Center Ground Motion Database", http:!/peer.berkeley.edu/peer_ground_ motion_ database.
[4] CEUS-SSC, "The Central and Eastern United States Seismic Source Characterization for Nuclear Facilities Database", http://www.ceus-ssc.com/.
[5] Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards, "Summary of May 30, 2013, Meeting with Holtec International , Potential Re-Submittal of the Topical Report on a Freestanding Stack-up", Docket No. 72-1014, June 28,201 3.
[6] MathWorks, Inc., "MATLAB Release 201 lb".
[7] U.S. Nuclear Regulatory Commiss ion, Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants", Revision I , 1973.
[8] Risk Engineering, Inc., "NUREG/CR-6728, Technical Basis for Revision of Regulatory Guidance on Design Ground Motions: Hazard- and Risk - Consistent Ground Motion Spectra Guidelines", 2001.
[9] Holtec Report HI-2135536, "Validation of EZ-FR[SK Computer Code", Revision 2.
[10] Holtec Approved Computer Program List (ACPL), Revision 342, March 6, 201 7 .
[1 l] Risk Engineering, Inc., "EZ-FRISK' 7.65 Build 004, Software for Earthquake Ground Motion Estimation", 2015.
[ 12] US NRC Regulatory Issue Summary 2015-13, "Seismic Stability Analysis Methodologies for Spent Fu el Dry Cask Loading Stack-up Configuration", November 12, 2015.
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMATIOt>l Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 11 TIME HISTORY INFORMATION FOR RG 1.60 EARTHQUAKE 11.1 Target Response Spectra The design 5% damped RG 1.60 response spectra [7], scaled to 0.26 g's in horizontal and vertical directions, are used as the target. The spectra over 0.1 Hz to 50 Hz are used as the input. The input response spectra for horizontal and vertical directions (slightly conservative) are presented in Tables 11-1 and 11-2. It is noted that for frequencies in between the values given in Tables 11 -1 and 11-2, the spectral accelerations are interpolated on log/log scale within EZ-FRISKTM. Also, the time step size of the generated time histories is interpolated to 0.005 seconds (wherever applicable) to provide a consistent time step size for all five sets.
The target response spectra for single set of time histories in Appendix B are obtained by scaling the input spectral accelerations in Tables 11-1 and 11-2 by a factor of0.25/0.26.
Table 11 -1: Horizontal Design Response Spectrum Freq (Hz) HOR Accel (g's) 0.1 0.02 0.25 0.123 2.5 0.8138 9 0.6786 33 0.26 so 0.26 Table 11 -2: Vertical Design Response Spectrum Freq (Hz) VT Accel (g's) 0.1 0.014 0.25 0.088 3.5 0.7748 9 0.6786 33 0.26 50 0.26
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HObTeC PROPRleT.'\RY l~Ji;QRM.'\TIOt>l Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 11.2 Average Response Spectra vs. Target Response Spectra A total of 500 digitized response spectrum points, unifonnly spaced over the log frequency scale from 0.1 Hz to 50 Hz,. are used in all three directions. The plots for average response spectra vs. target response spectra are included in Figures 11-1 to 11-3 below for all three directions. Table 11 -3 provides a summary of the checking of criteria 5 (c) and 5 (d) of Section 3.
Table 11-3: Summary of Response Spectrum Checks for 5-Set Average (b)(4)
The target response spectra for E-W (or X) and N-S (or Y) directions is the horjzontal response spectrum from Table 11-1, and the response spectrum for VT (or Z) direction is the vertical response spectrum from Table 11-2.
All results for single set of time histories scaled to 5% damped RG 1.60 earthquake with a ZPA of 0.25g in all three directions are presented in Appendix B.
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 1027 HOLTEC PROPRIETARY Report HI-2146083 (b)(4)
(b)(4)
Figure 11-2: Five-Set Average Response Spectrum vs. Target Response Spectrum - N-S Page 17
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Project 1027 HOLTECPROPRIETARY Report HI-2146083 (b)(4)
Figure l l -3: Five-Set Ave rage Response Spectrum vs. Target Response Spectrum - VT Page 18 G:\Projects\1027\Reports\HI-2 14'62R.~ ¥.%0 Time Histories\Revision 2\
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 1027 HOLTEC PROPRIETARY Report HI-2146083 11.3 Seed Time History Selections The following five sets of real recorded ground motions (Table 11-4) are chosen for the current work. For each set, the three orthogonal component motions are obtained from the same earthquake. Table 11-5 provides the scale factors used on seed time histories to match target PGA.
Table 11-4: Seed Time History Information (b)(4)
Table 11-5: Scale Factors on Seed Time Histories to Match Target Spectra PGA (b)(4)
The seed earthquakes are selected based on their magnitude, RMS scale spectra score, as well as other criteria listed in Section 2.
Section II. l.B of SRP 3. 7.1 [ 1] requires the selected earthquakes to be appropriate for the characteristic low and high frequency events. Per Section 5.6 (page 5-13) of NUREG/CR-6728 [8], the low frequency deaggregated event is typically defined as a large magnitude, and large distance earthquake while the high frequency deaggregated event is typically a small magnitude and sma ll distance earthquake. The selected earthquakes envelope the small distance to large distance criterion, and have a magnitude greater than 6.50 approaching 8.0.
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 1027 HOLTECPROPRIETARY Report HI-2146083 The generated time history sets output from EZ-FRISK' are amplified slightly to ensure that the average response spectra of the modified time histories envelope the target spectra as described in Section 3.0 of this report. The scale factors used to satisfy the enveloping requirement are shown in Table l L-6.
Table 11-6: Summary of Scale Factors for Response Spectra Enveloping (b)(4)
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTE:C F'R0f3RIETARY l~ffORMATION Project 1027 IIOLTEC PROPRIETARY Report HI-2 146083 11.4 Time History Results Sections 11.5 through 11.9 provide the summary tables and graphs for five sets of time histories. The tables in those sections include Summary of Durations and Summary of Correlation Coefficients. The figures in those sections provide information on the seed and the generated time histories including acceleration, veloc ity and displacement plots. They also provide information on the percentage of Arias intensity, and the response spectra for the seed and generated time histories.
For each direction (N-S, E-W, and VT), the values of PGV/PGA and PGAxPGD/PGV2 from the five time history sets are calculated to obtain the representative values for the seismic input motion (Table 11 -8) where PGA is the maximum ground acceleration, PGV is the maximum ground velocity, and PGD is the maximum ground displacement. In the expression PGV/PGA, PGA is in g's and PGV is in inches/sec. In the PGA x PGD/PGV2 , PGA is in inches/sec2, PGV is in inches/sec, and PGD is in inches. The purpose of these ratios is to show that the generated time histories are consistent with characteristic values for the magnitude and distance of the appropriate controlling events defining the target spectra. The information for a particular site may be used to judge the applicability of generated time histories.
In addition, the PGA, PGV and PGD values for all five sets of time histories are presented in Table 11-7.
Table 11-9 shows the PGV/PGA mean+/- one standard deviation values, PGA xPGD/PGV2 mean (x) +/- one standard deviation (cr) values, and PGAxPGD/PGV2 mean +/- two standard deviations values for the earthquakes of magnitude bins of M6.4 l + with distance bins from 0 to 200 km at soil sites, using data provided in NUREG/CR-6728 [8], Table 3-6.
Page 21 1~26.~'113~
ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY l~ffORMATIOM Project 1027 HOLTEC PROPRIETARY Report HI-2146083 Table 11-7: Summary of Peak Values for Generated Time Histories (b)(4)
Table 11-8: Generated Time History PGV/PGA and PGA x PGD /PGV2 (b)(4)
Table 11-9: PGV/PGA and PGAxPGD /PGV2 Mean+/- Standard Deviation(s) Values (Obtained from Table 3-6 ofNUREG/CR-6728 rsn (b)(4)
Page 22 A~'.)'7.i;,f;'l,3~
ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY 11'1FO~MATION Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 From Tables 11-8 and 11-9, the average value of PGV/PGA from the modified time histories is within the mean ratio +/- one standard deviation values for 0-100 km distance bin.
The average value of PGAxPGD/PGV2 from the modified time histories is greater than the mean ratio - one standard deviation for all components. However, the average value of PGAxPGD/PGV2 in VT direction exceeds the mean + one standard deviation value for 0-10 km and 50-100 km distance bins. This is judged to be acceptable because NUREG/CR-6728
[8] states that there is a high degree of scatter associated with the PGAxPGD/PGV2 ratios, and the PGAxPGD/PGV2 ratios for all components are well below the mean ratio + two standard deviations value.
Page 23
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~Ji;QRM,ATION Project 1027 HOLTECPROPRIETAR¥ Report HI-2146083 11.5 Set 1 Time Histories (THs)
Table 11-10: Sununary of Duration for Set 1 (b)(4)
Table 11-11 : Summary of Correlation Coefficients for Set 1 (b)(4)
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Figure l l -4: E-W Seed Time Histories Set 1: Acceleration, Velocity, and Displacement Page 25
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Figure 11 -5: N-S Seed Time Histories Set 1: Acceleration, Velocity, and Displacement Page 26
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HObTeC PROPRl5.TARY lt>I FO~MATION Project 1027 HOLTEC PROPRIBTAR~ Report HI-2146083 (b)(4)
Figure 11 -6: VT Seed Time Histories Set 1: Acceleration, Velocity, and Displacement Page 27 1 ~ 2 . ~ 1i3S.
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Figure 11-7: E-W Scaled Seed Spectrum Set 1 vs. Target Spectrum (b)(4)
Figure 11-8: N-S Scaled Seed Spectrum Set l vs. Target Spectrum Page 28
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY IN FORMATION Project 1027 HOLTEC PROPRIETARY Report HI-2146083 (b)(4)
Figure 11 -9: VT Scaled Seed Spectrum Set 1 vs. Target Spectrum Page 29 t~ib0f. 1i3~.
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Figure 11-10: Percentage Arias Intensity for Seed THs Set 1 Page 30
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PR:Of3R:IETAR:'1' lt<J F'OR:MATIOM Project 1027 HOLTEC PROPRIBTAR¥ Report HI-2 146083 11.5.2 Generated Set 1 Time History Graphs (b)(4)
Figure 11- 11: E-W Generated THs Set 1: Acceleratio n, Velocity, and D isplacement Page 31
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Figure 11-12: N-S Generated THs Set 1: Acceleration, Velocity, and Displacement
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Figure 11- 13: VT Generated THs Set I: Acceleration, Velocity, and Displacement
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Figure l l-14: E-W Generated TH Set I Response Spectrum (b)(4)
Figure 11-15: N-S Generated TH Set 1 Response Spectrum
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Figure 11-16: VT Generated TH Set 1 Response Spectrum Page 35
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ATTACHMENT 13 TO HOLTEC LETTER 5025012
i=tOLTEC f3ROPRIETAR'!' l~ffORMATION Project 1027 J-IOLTEC PROPRIETARY Report HI-2146083 (b)(4)
Figure 11-17: P ercentage Arias Intensity for Generated THs Set 1 Page 36
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEG PROPRle.T.'\RY l~Ji;QRMATION Project 1027 HOLTECPROPRIBTARY Report HI-2146083 11.6 Set 2 Time Histories Tab]e 11-12: Summary of Duration for Set 2 (b)(4)
Table 11-13: Summary of Correlation Coefficients for Set 2 (b)(4)
ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY lt<J F'ORMATIOM Project 1027 HOLTECPROPRIETARY Report HI-2146083 11.6.J See,J 2 Time History Graphs (b) (4)
Figure l 1- 18: E-W Seed Time Histories Set 2: Acceleration, Velocity, and Displacement
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Figure 11-19: N-S Seed Time Histories Set 2: Acceleration, Velocity, and Displacement Page 39
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Figure 11-20: VT Seed Time Histories Set 2: Acceleration, Velocity, and Displacement Page 40
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Figure 11-21: E-W Scaled Seed Spectrum Set 2 vs. Target Spectrum (b)(4)
Figure 11-22: N-S Scaled Seed Spectrum Set 2 vs. Target Spectrum Page 41
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Figure 11-23: VT Scaled Seed Spectrum Set 2 vs. Target Spectrum Page 42 1~n~'h.3~
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Figure 11-24: Percentage Arias Intensity for Seed THs Set 2 Page 43
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY l~ffORMATIOM Project 1027 HOLTEC PROPRIETARY Report HI-2146083 11.6.2 Generated Set 2 Time History Graphs (b)(4)
Figure 11-25: E-W Generated THs Set 2: Acceleration, Velocity, and Displacement
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Figure 11 -26: N-S Generated THs Set 2: Acceleration, Velocity, and Displacement Page 45 t~'3>0f. 'h,3~
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Figure 11-27: VT Generated THs Set 2: Acceleration, Velocity, and Displacement
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Figure 11-28: E-W Generated TH Set 2 Response Spectrum (b)(4)
Figure 11-29: N-S Generated TH Set 2 Response Spectrum
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Figure 11-30: VT Generated TH Set 2 Response Spectrum
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Figure 11-3 1: P ercentage Arias Intensity for Generated THs Set 2 Page 49
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLT EG PROPRIETARY IN FORMATION Project 1027 HOLTECPROPRIETARY Report HI-2146083 11.7 Set 3 Time Histories Tab]e 11-14: Summary of Duration for Set 3 (b)(4)
Table 11-15: Summary of Correlation Coefficients for Set 3 (b}(4)
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- 11. 7.1 See,l 3 Time History Graphs (b)(4)
Figure l 1-32: E-W Seed Time Histories Set 3: Acceleration, Velocity, and Displacement
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Figure 11-33: N-S Seed Time Histories Set 3: Acceleration, Velocity, and Displacement Page 52 11taae,..9,m 1..19-
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Figure 11-34: VT Seed Time Hi stories Set 3: Acceleration, Velocity, and Displacement Page 53
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Figure 11-35: E-W Scaled Seed Spectrum Set 3 vs. Target Spectrum (b)(4)
Figure 11 -36: N-S Scaled Seed Spectrum Set 3 vs. Target Spectrum
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Figure 11-37: VT Scaled Seed Spectrum Set 3 vs. Target Spectrum Page 55
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Project 1027 HOLTEC PROPRIETARY Report HI-2 146083 (b)(4)
Figure 11-38: Percentage Arias Intensity for Seed THs Set 3 Page 56
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEG PROPRl!sT ARY INFORMATION Project 1027 HOLTEC PROPRIETARY Report HI-2146083
- 11. 7.2 Generated Set 3 Time History Graphs (b)(4)
Figure 11-39: E-W Generated THs Set 3: Acceleration, Velocity, and D isplacement
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Figure 11-40: N-S Generated THs Set 3: Acceleration, Velocity, and Displacement Page 58
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HObTeC PROPRleT.'\RY l~Ji;QRM.'\TIOt>l Project 1027 HOLTECPROPRIETARY Report HI-2146083 (b)(4)
Figure 11-41: VT Generated THs Set 3: Acceleration, Velocity, and Displacement
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Figure 11-42: E-W Generated TH Set 3 Response Spectrum (b)(4)
Figure 11-43: N-S Generated TH Set 3 Response Spectrum Page 60
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTE:C F'F\OF'~IE:T:A.Fh 11'1FO~MATIOM Project 1027 HOLTECPROPRIETARY Report HI-2 146083 (b)(4)
Figure 11-44: VT Generated TH Set 3 Response Spectrum Page 61
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY INFORMAT IOt>l Project 1027 HOLTEC PROPRIETARY Report HI-2146083 (b)(4)
Figure 11-45: P ercentage Arias Intensity for Generated THs Set 3 Page 62 1~-7.m1.3!l-,
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOL'fEC f3F\OF'~IE I ARV INFORMA I ION Project 1027 HOLTEC PROPRIETARY Report HI-2146083 11.8 Set 4 Time Histories Tab]e 11-16: Summary of Duration for Set 4 (b)(4)
Table 11-17: Summary of Correlation Coefficients for Set 4 (b)(4)
ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY lfqfiORMATIOM Project 1027 HOLTEC PROPRIETARY Report HI-2146083 11.8.J See,J 4 Time History Graphs (b)(4)
Figure 11-46: E-W Seed Time Histories Set 4 : Acceleration, Velocity, and Displacement
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Figure 11 -47: N-S Seed T ime H istories Set 4: Acceleration, Velocity, and D isplacement Page 65 1~?e.~ 'h,3~
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Figure 11-48: VT Seed Time Histories Set 4: Acceleration, Velocity, and Displacement
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Figure 11-49: E-W Scaled Seed Spectrum Set 4 vs. Target Spectrum (b)(4)
Figure 11-50: N-S Scaled Seed Spectrum Set 4 vs. Target Spectrum
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Figure 11-51: VT Scaled Seed Spectrum Set 4 vs. Target Spectrum Page 68
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY l~ffORMATIOM Project 1027 I IOLTEC PROPRIETARY. Report HI-2146083 (b)(4)
Figure 11-52: Percentage Arias Intensity for Seed THs Set 4 Page 69
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC f3R:Of3R:IETAR:'1' IN FORMATIOM Project 1027 HOLTECPROPRIETARY Report HI-2146083 11.8.2 Generated Set 4 Time History Graphs (b)(4)
Figure 11-53: E-W Generated THs Set 4: Acceleration, Velocity, and Displacement Page 70
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HObTeC PROPRleT.'\RY l~Ji;QRM.'\TIOt>l Project 1027 HOLTECPROPRIETARY Report HI-2146083 (b)(4)
Figure 11-54: N-S Gene rated THs Set 4: Acceleration, Velocity, and Displacement Page 71
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 rTOLT EC PROPRIETARY lt>IFORMAIIQN Project 1027 HOLTECPROPRIBTARY Report HI-2146083 (b)(4)
Figure 11-55: VT Generated THs Set 4: Acceleration, Velocity, and Displacement Page 72 11t;aruh7n~ '113~
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETAR.'!' lt<JF'O~MATION Project 1027 HOLTECPROPRIETARY Report HI-2146083 (b)(4)
Figure 11-56: E-W Generated TH Set 4 Response Spectrum (b)(4)
Figure 11-57: N-S Generated TH Set 4 Response Spectrum Page 73
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Figure 1 l-58: VT Generated TH Set 4 Response Spectrum
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Figure 11-59: Percentage Arias Intensity for Generated THs Set 4 Page 75
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMA'flOrq Project 1027 I IOLTEC PROPRIBTAR¥ Report HI-2146083 11.9 Set 5 Time Histories Tab]e 11-18: Summary of Duration for Set 5 (b)(4)
Table 11-19: Summary of Correlation Coefficients for Set 5 (b)(4)
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PR:Of3R:IETAR:'1' lt<J F'OR:MATIOM Project 1027 HOLTEC PROPRIETARY Report HI-2 146083 11.9.J See,J 5 Time History Graphs (b)(4)
Figure 11-60: E-W Seed Time Histories Set 5: Acceleration, Velocity, and Displacement Page 77 11taoP.,R;J.m IB~r
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Figure 11 -61: N-S Seed Time Histories Set 5: Acceleration, Velocity, and Displacement
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Figure 11-62: VT Seed Time Histories Set 5: Acceleration, Velocity, and Displacement Page 79
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMATION Project 1027 I IOLTEC PROPRIETARY Report HI-2146083 (b)(4)
Figure 11-63: E-W Scaled Seed Spectrum Set 5 vs. Target Spectrum (b)(4)
Figure 11-64: N-S Scaled Seed Spectrum Set 5 vs. Target Spectrum Page 80
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 1027 HOLTECPROPRIETABY Report HI-2146083 (b)(4)
Figure 11-65: VT Scaled Seed Spectrum Set 5 vs. Target Spectrum
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Figure 11-66: Percentage Arias Intensity for Seed THs Set 5 Page 82 1ltaoP.,R'7.m 1.3!tr
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMATION Project 1027 HOLTECPROPRIETARY Report HI-2146083 11.9.2 Generated Set 5 Time History Graphs (b)(4)
Figure 11-67: E-W Generated THs Set 5: Acceleration, Velocity, and Displacement Page 83
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Project 1027 HOLTEC PROPRIETARY Report HI-2146083 (b)(4)
Figure 11-68: N-S Generated THs Set 5: Acceleration, Velocity, and Displacement
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Figure 11-69: VT Generated THs Set 5: Acceleration, Velocity, and Displacement
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Figure 11-70: E-W Generated TH Set 5 Response Spectrum (b)(4)
Figure 11 -7 1: N-S Generated TH Set 5 Response Spectrum Page 86
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Figure 11-72: VT Generated TH Set 5 Response Spectrum
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Figure 11- 73: Percentage Arias Intensity for Generated THs Set 5 Page 88
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPR:11::TARV INFORMAi ION Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 12 APPENDICES Appendix A - Time History Information for Alternate Sets 3 and 5 Appendix B - Single Time History Set Information
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 1027 I IOLTEC PROPRIETARY Report HI-2146083 APPENDIX A - TIME IDSTORY INFORMATION FOR ALTERNATE SETS 3AND5 This appendix provides information on alternate Set 3 and Set 5 which provide shorter duration time and/or improve response spectra match. The alternate Set 3 and Set 5 can be used in conjunction with Sets 1, 2, and 4 time histories of Section 11 to form a complete 5 sets of time histories. This appendix also present the checking of Section 3 criteria of the 5 sets of time histories composed of Sets 1, 2, and 4 from Section 11 and Sets 3 and 5 from this Appendix.
A.1. Target Response Spectra The target response spectra used fo r the 5 set of time history containing alternate Sets 3 and 5 are the same as the target response spectra in Section 1 l. I A.2. Average Response Spectra vs. Target Response Spectra A total of 500 digitized response spectrum points, unifo rmly spaced over the log frequency scale from 0. 1 Hz to 50 Hz, are used in all three directions. The plots for average response spectra vs. target response spectra are included in Figures A-1 to A-3 below for all three directions. Table A-1 provides a summary of the checking of criteria 5 (c) and 5 (d) of Section 3.
Table A-I: Summary of Response Spectrum Checks for 5-Set Average (b)(4)
Page A-1 of A-31
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTE:C F'F\OF'RIE I ARV INFORMATIOl"f" Project 1027 I IOLTEC PROPRIETARY Report HI-2146083 The target response spectra for E-W (or X) and N-S (or Y) directions is the horizontal response spectrum from Tab le 11-1, and the response spectrum for VT (or Z) direction is the vertical response spectrum from Tab le 11-2.
(b)(4)
Figure A F ive-Set Average Response Spectra vs Target Response Spectra - E-W Page A-2 of A-31
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Figure A Five-Set Average Response Spectra vs Target Response Spectra - N -S (b)(4)
Figure A Five-Set Average Response Spectra vs Target Response Spectra - VT Page A-3 of A-31
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY l~ffORMATIOM Project 1027 I IOLTEC PROPRIETARY Report HI-2146083 A.3. Seed Time H istory Selections The following five sets of real recorded ground motions (Table A-2) are chosen fo r the cunent work. For each set, the three orthogonal component motions are obtained from the same earthquake. Table A-3 provides the scale factors used on seed time histories to match target PGA. As noted previously, Sets 1, 2, and 4 are the same sets in Section 11 .
Table A-2: Seed Time History Information (b)(4)
Table A-3: Scale Factors on Seed Time Histories to Match Target Spectra PGA (b)(4)
The seed earthquakes are selected based on their magnitude, RMS scale spectra score, as well as other criteria listed in Section 2.
Section TI.1.B of SRP 3.7.1 [l] requires the selected earthquakes to be appropriate for the characteristic low and high frequency events. Per Section 5.6 (page 5-13) of NUREG/CR-6728 [8], the low frequency deaggregated event is typicall y defined as a large magn itude, and large distance earthquake while the high frequency deaggregated event is typically a small magnitude and small distance earthquake. The selected earthquakes envelope the small distance to large distance criterion, and have a magnitude greater than 6.50 approaching 8.0.
Page A-4 of A-31
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY IN FORMATION Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 Some of the generated time history sets output from EZ-FRISK' are amplified slightly to ensure that the average response spectra of the modified time histories envelope the target spectra as described in Section 3.0 of this report. The scale factors used to satisfy the enveloping requirement are shown in Table A-4.
Table A-4: Summary of Scale Factors for Resp onse Spectra Enveloping (b)(4)
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PR:Of3R:IETAR:'1' lt<J F'OR:MATIOM Project 1027 I IOLTEC PROPRIETARY Report HI-2 146083 A.4. Time History Results Sections A.5 and A.6 provide the summary tables and graphs for the alternate Sets 3 and 5 of time histories. The tables in those sections include Summary of Durations and Summary of Correlation Coefficients. The figures in those sections provide information on the seed and the generated time histories including acceleration, velocity and displacement p lots. They also provide information on the percentage of Arias intensity, and the response spectra for the seed and generated time histories.
For each direction (N-S, E-W, and VT), the values of PGV/PGA and PGAxPGD/PGV2 from the five time history sets are calculated to obtain the representative values for the seismic input motion (Table A-6) where PGA is the maximum ground acceleration, PGV is the maximum ground velocity, and PGD is the maximum ground displacement. In the expression PGV/PGA, PGA is in g's and PGV is in inches/sec. In the PGA x PGD/PGV2, PGA is in inches/sec2, PGV is in inches/sec, and PGD is in inches. The purpose of these ratios is to show that the generated time histories are consistent with characteristic values for the magnitude and distance of the appropriate controlling events defining the target spectra. The information for a particular site may be used to judge the applicabi lity of generated time hi stories.
In addition, the PGA, PGV and PGD values for all five sets of time histories are presented in Table A-5.
Table A-5: Summary of Peak Values for Generated Time Histories (b)(4)
Page A-6 of A-31 P.Me106l.of 139"
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY l~ffORMATIOM Project 1027 I IOLTEC PROPRIBTAR¥ Report HI-2 146083 Table A-6: Generated Time Hi story PGV/PGA and PGA x PGD /PGV2 (b)(4)
From Tables A-6 and 11 -9, the average value of PGV/PGA from the modified time histories is w ithin the mean ratio +/- one standard deviation values for 0-100 km distance bin.
The average value of PGAxPGD/PGV2 from the modified time histories is greater than the mean ratio - one standard deviation for all components. However, the average value of PGAxPGD/PGV2 in VT direction exceeds the mean + one standard deviation value for 0-10 km and 50-100 km distance bins. This is judged to be acceptable because NUREG/CR-6728
[8] states that there is a high degree of scatter associated with the PGAxPGD/PGV2 ratios, and the PGAxPGD/PGV2 ratios for all components are well below the mean ratio + two standard deviations value.
Page A-7 of A-31
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATION Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 A.5. Alternate Set 3 Time Histories Table A Summary of Duration for Set 3 (b)(4)
Table A Summary of Correlation Coefficients for Set 3 (b)(4)
Page A-8 of A-31
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMATIOM Project 1027 I IOLTEC PROPRIETARY Report HI-2146083 (b)(4)
Figure A E-W Dir. Acceleration Time History Set 3 Page A-9 of A-31 fMe1(ljd 13,Sr
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Figure A N-S Dir. Acceleration Time History Set 3 Page A-10 of A-3 1
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Figure A YT Dir. Acceleration Time History Set 3 Page A-11 of A-3 1
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Figure A E-W Dir. Generated THs Set 3 Response Spectrum (b)(4)
Figure A N-S Dir. Generated THs Set 3 Response Spectrum Page A-12 of A-3 1
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HObTeC PROPRleTARY l~Ji;QRMATIOt>l Project 1027 IIOLTEC PROPRIETARY Report HI-2146083 (b)(4)
Figure A VT Dir. Generated THs Set 3 Response Spectrum Page A-13 of A-3 1
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Figure A E-W Dir. Generated vs Seed Time Histories (Velocity and Displacement) Set 3 Page A-14 of A-3 1
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Figure A N-S Dir. Generated vs Seed Time Histories (Velocity and Displacement) Set 3 Page A-15 of A-3 1
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Figure A YT Dir. Generated vs Seed Time Histories (Velocity and Displacement) Set 3 Page A-16 of A-3 1
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Figure A E -W Scaled Seed Spectrum Set 3 vs Target Spectrum (b)(4)
Figure A N-S Scaled Seed Spectrum Set 3 vs Target Spectrum Page A-17 of A-3 1
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Figure A VT Scaled Seed Spectrum Set 3 vs Target Spectrum Page A-18 of A-3 1
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Figure A Percentage Arias Intensity for Seed THs Set 3 Page A-19 of A-3 1
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HObT!aC PROPRl!aTARY l~Ji;QRMATIOt>l Project 1027 HOLTEC PROPRIETARY Report HI-2146083 A.6. Alternate Set 5 Time Histories Table A Summary of Duration for Set 5 (b)(4)
Table A Summary of Correlation Coefficients for Set 5 (b)(4)
Page A-20 of A-3 1
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 AOL I EC PROPRIETAFh 11'1FORMA'flOM Project 1027 HOLTEC PROPRIETARY Report HI-2146083 (b)(4)
Figure A E-W Dir. Acceleration Time History Set 5 Page A-21 of A-3 1
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Figure A N-S Dir. Acceleration Time History Set 5 Page A-22 of A-3 1
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Figure A VT Dir. Acceleration Time History Set 5 Page A-23 of A-3 1
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Figure A E-W Dir. Generated THs Set 5 Response Spectrum (b)(4)
Figure A N-S Dir. Generated THs Set 5 Response Spectrum Page A-24 of A-3 1 PMe1'\8d 13.ar
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Figure A VT Dir. Generated THs Set 5 Response Spectrum Page A-25 of A-3 1
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Figure A E-W Dir. Generated vs Seed Time Histories (Velocity and Displacement) Set 5 Page A-26 of A-3 1 Pi&te136Lof 1390 -
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Figure A N-S Dir. Generated vs Seed Time Histories (Velocity and Displacement) Set 5 Page A-27 of A-3 1
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Figure A YT Dir. Generated vs Seed Time Histories (Velocity and Displacement) Set 5 Page A-28 of A-31
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Figure A E -W Scaled Seed Spectrum Set 5 vs Target Spectrum (b)(4)
Figure A N-S Scaled Seed Spectrum Set 5 vs Target Spectrum Page A-29 of A-3 1
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Figure A VT Scaled Seed Spectrum Set 5 vs Target Spectrum Page A-30 of A-3 1
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Figure A Percentage Arias Intensity for Seed THs Set 5 Page A-3 1 of A-3 1
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HQI IEC PROPRle.TARY INFORMATIOl<l Project 1027 HOLTEC PROPRIETARY Report HI-2146083 APPENDIX B - SINGLE TIME HISTORY SET INFORMATION This appendix provides infom1ation on si ngle set of time histories developed to match 5%
damped RG 1.60 earthquake scaled to 0.25 g's in all three directions. The time history set satisfies the requirements of Approach 2 of Option 1 in Section II of SRP 3. 7.1 [ 1]. The methodology and acceptance criteria are also defined in Sections 2 and 3, respectively, of main body of this report.
B.1 Target Response Spectra The target response spectrum for E-W (or X) and N-S (or Y) directions is the horizontal response spectrum from Table 11 - 1 scaled by a factor of 0.25/0.26, and the response spectnnn for VT (or Z) direction is the vertical response spectrum from Table 11-2 scaled by a factor of 0.25/0.26.
B.2 Scaled Response Spectra vs. Target Response Spectra A total of 500 digitized response spectrum points, uniformly spaced over the log frequency scale from 0.1 Hz to 50 Hz, are used in all three directions. The plots for scaled response spectrum vs. target response spectrum are included in Figures B-1 to B-3 below for all three directions. Table B-1 provides a summary of the checking of criteria 5 (c) and 5 (d) of Section 3.
Table 8-l: Summary of Response Spectra Checks (b)(4)
Page B-1 of B-14
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Figure B Scaled Response Spectrum vs. Target Response Spectrum - E-W (b)(4)
Figure B Scaled Response Spectrum vs. Target Response Spectrum - N-S Page B-2 of B-14 PNt"' ~ ::fl r,f 13Br
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLTEG PROPRIETARY l~ffORMATIOM Project 1027 HOLTECPROPRIETARY Report HI-2146083 (b)(4)
Figure B Scaled Response Spectrum vs. Target Response Spectrum - VT B.3 Seed Time History Set Selection The below set of real recorded ground motion (Table B-2) is chosen for the current work.
The three orthogonal compo nent motions are obtained from the same earthquake. Table B-3 provides the scale factors used on seed time histories to match target PGA.
Table B-2: Seed Time History Set Infonnation (b)(4)
Table B-3: Scale Factors on Seed Time Histories to Match Target Spectra PGA l(b)(4) I Page B-3 of B-14
-- * ,P.t1t1A ~ ::m r,f 139r
ATTACHMENT 13 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY lt<J F'ORMATIOt<J Project 1027 I IOLTEC PROPRIETARY Report HI-2 146083 The seed earthquake is selected based on its magnitude, RMS scale spectra score, as well as other criteria listed in Section 2. The generated time history sets output from EZ-FRISK' are amplified slightly to ensu re that the response spectra of the modified time histories envelope the target spectra as described in Section 3.0 of this report. The scale factors used to satisfy the enveloping requirement are shown in Table B-4.
Table B-4: Summary of Scale Factors for Response Spectra Enveloping r )(4)
B.4 Time History Results Section B.5 provides the summary tables and graphs for the single time history set. T he tables in Section B.5 include Summary of Durations and Summary of Correlation Coefficients. The figures in Section B.5 provide infonnation on the seed and the generated time histories including acceleration, velocity and displacement plots. They also provide information on the percentage of Arias intensity, and the response spectra for the seed time histories.
For each direction (N-S, E-W, and VT), the values of PGV/PGA and PGAxPGD/PGV2 are calculated to obta in the representative values for the seismic input motion (Table B-6) where PGA is the maximum ground acceleration, PGV is the maximum ground velocity, and PGD is the maximum ground displacement. In the expression PGV/PGA, PGA is in g 's and PGV is in inches/sec. In the PGA x PGD/PGV2, PGA is in inches/sec2, PGV is in inches/sec, and POD is in inches. The purpose of these ratios is to show that the generated time histories are consistent with characteristic values for the magnitude and distance of the appropriate controlling events defining the target spectra. The infonnation for a site may be used to judge the applicability of generated time histories.
In addition, the PGA, PGV and PGD values for all three directions are presented in Table B-5.
Page B-4 of B-14
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HeL'fEC 13F\OF'"IE I AR V INFORMA I ION Project 1027 HOLTEC PROPRIETARY Report HI-2146083 Table B-5: Summary of Peak Values for Generated Time Histories (b)(4)
Table B-6: Generated Time History PGV/PGA and PGA x PGD /PGV2 (b)(4)
From Tables B-6 and 11-9, the value of PGV/PGA from the modified time histories is within the mean ratio +/- one standard deviation values for 0-100 km distance bin.
The value of PGA xPGD/PGV2 from the modified/scaled time histories is slightly beyond the range of mean ratio - one standard deviation to mean + one standard deviation but well within two standard deviations. This is judged to be acceptable because NUREG/CR-6728
[8] states that there is a high degree of scatter associated with the PGAxPGD/PGV2 ratios.
B.5 Generated Time Histories Table B Summary of Durations (b)(4)
Table B Summary of Correlation Coefficients (b)(4)
Page B-5 of B-14
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Figure B E-W Seed and Scaled Acceleration Time Histories Page B-6 of B-14
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Figure B N-S Seed and Scaled Acceleration Time Histories Page B-7 of B-14
- p.,.,. .. A ~ .,..f 1 '.'\9r
ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOL"fEC f3R:Of3R:IETAR:'1' IN FORMATIOM Project 1027 HOLTEC PROPRIETAR¥ Report HI-2 146083 (b)(4)
Figure B V T Seed and Scaled Acceleration Time Histories Page B-8 of B-14
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ATTACHMENT 13 TO HOLTEC LETTER 5025012 HOLT EC PROPRIETARY l~Ji;QRMATION Project 1027 HOLTECPROPRIBTABY Report HI-2146083 (b)(4)
Figure B E-W Scaled vs. Seed Time Histories (Velocity and Displacement)
Page B-9 of B-14
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Figure B N-S Scaled vs. Seed Time Histories (Velocity and Displacement)
Page B-10 of B-14
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Figure B VT Scaled vs. Seed Time Histories (Velocity and Displacement)
Page B-11 ofB-14
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Figure B E-W Scaled Seed Spectrum vs. Target Spectrum (b)(4)
Figure B-1 1 - N-S Scaled Seed Spectrum vs. Target Spectrum Page B-12 of B-14
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Figure B VT Scaled Seed Spectrum vs. Target Spectrum Page B-13 of B-14
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Figure B Percentage Arias Intensity for Scaled THs Page B-14 of B-14
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ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEe PR:SPR:IETJltR:Y lldl"O~fo1>'<1"10f4 Holtec Center, One Holtec Drive, Marlton, NJ 08053 Telephone (856) 797- 0900 HOLTEC INTERNATIONAL Fax(856)797-0909 THERMAL ANALYSIS OF HI-TRAC CS TRANSFER CASK FOR GENERIC Holtec Report No: Hl-2177553 Holtec Project No: 5025 Sponsoring Holtec Division: NPD Report Class : SAFETY RELATED Page 1 of 71
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DOCUMENT ISSUANCE AND REVISION STATUS DOCUMENT NAME: THERMAL ANALYSIS OF HI-TRAC CS TRANSFER CASK DOCUMENT NO.: CATEGORY: ~ GENERIC HI-2177553 PROJECT NO.:
5025 D PROJECT SPECIFIC Rev. Date Author's No. 2 A Initials VIR #
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- 2. A revision to this document will be ordered by the Project Manager and carried out if any of its contents including revisions to references 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.
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ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~ffORMAT ION IIOL'ftsC fR:Ofttf'E'fAll'I' n~ ~OftMATIOl<J PREFACE Th is section contains quality related information on this document in conformance with the provisions in Holtec's Quality Assurance program docketed with the USNRC (Docket # 7 1-0784).
Th is document is classified as "Safety Significant" under Holtec International's quality assurance system.
In order to gain acceptance as a safety significant document in the company's quality assurance system, this document is required to undergo a prescribed review and concurrence process that requires the preparer and reviewer(s) of the document to answer a long list of questions crafted to ensure that the document is purged of all errors of any material significance. A record of the review and verification activities is maintained in electronic form within the company's network to enable future retrieval and recapitulation of the programmatic acceptance process leading to the acceptance and release of this document under the company's QA system. Among the nume rous requirements that this document must fu lfi ll, as applicable, to muster approval within the company's QA program are:
- The preparer(s) and reviewer(s) are technically qualified to perform their activities per the applicable Holtec Quality Procedure (HQP).
- The input information utilized in the work effort 1s drawn from referenceable sources. Any assumed input data is so identified.
- Significant assumptions are stated or provided by reference to another source.
- The analysis methodology is suitable for the physics of the problem.
- Any computer code and its specific versions used in the work are formally admitted for use with in the company's QA system.
- The content of the document is in accordance with the applicable Holtec quality procedure.
- The material content of the calculation package is understandable to a reader with the requisite academic training and experience in the underlying technical disciplines.
Once a safety significant document, such as this calculation package, completes its review and certification cycle, it should be free of any materially significant error and should not require a revision unless its scope of treatment needs to be altered. Except fo r regulatory interface documents (i.e., those that are submitted to the regulator in support of a license amendment and request), editorial revisions to Holtec safety significant documents are not made unless such ed itorial changes are deemed necessary by the Holtec Project Holtec Report Hf-2 177553 J Holtec Project 5025 Page 3 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOI IEC PBOPBIFIABY INFQRMATIQN HOL'ftsC FROPR:lETARY rNFOR:MATIO~J Manager to prevent erroneous conclusions from being inferred by the reader. In other words, the focus in the preparation of this document is to ensure correctness of the technical content rather than the cosmetics of presentation.
Furthermore, th is Calculation Package is focused on providing technical results that demonstrate compliance w ith the applicable safety limits. Informational material that does not bear upon reach ing a safety conclusion is minimized in this document to the extent possible. Because of its function as a repository of all analyses performed on the subject of its scope, this document will require a revision only if an error is discovered in the computations or the equipment design is modified. Additional analyses in the future may be added as numbered supplements to this Package. Each time a supplement is added or the existing material is revised, the revision status of this Package is advanced to the next number and the Tabfo of Contents is amended. Calculation Packages are Holtec proprietary documents. They are shared with a cl ient only under strict controls on their use and dissemination. This Calculation Package will be saved as a Permanent Record under the company's QA System.
Generic Reports Holtec International maintains a number of so-called "generic reports" which provide the methodology, computer models and associated modeling assumptions for a specific physical problem. The technical content of a generic report is fully aligned with the System FSAR, Reg. Guides, NUREGs, etc., as applicable. In other words, the generic report contains Holtec's standardized analysis approach, method and model to analyze a technical problem. Developed under Holtec' s self-funded R&D program, the generic reports are treated as "vital intellectual property" of the Company and are accordingly prohibited from dissemination to any external entity. The generic reports are subject to inspection by the NRC's staff at Holtec's corporate headquarters during NRC's triennial inspection of Holtec. The Calculation Package can invoke a Generic Report in whole or in part (see table below) to improve conciseness and to enable it to be submitted un-redacted to the Company's clients.
Holtec Report Hf-2177553 Jl Holtec Project 5025 Page 4 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IQl..:rsc RROPBIFJABY INFORMATION 1:101 T"EiC PROPRIEIA RY INEORMATTQN Holtec Approved Computer Program List (ACPL)
Holtec International maintains an active list of QA validated computer codes on the Company's network that are approved for use in Safety significant projects. The table below identifies the Codes and applicable versions (listed in the ACPL) that have been used in this work effort.
Generic Report & AC PL Information Generic Report# invoked in this Cale Package, if NIA applicable Code(s) name(s) (must be listed in the ACPL) Fluent Code(s) version# (must be approved in the ACPL) 14.5.7 Computer ID #(s) (must be approved in the ACPL for (b)(4) the applicable code name and version)
ACPL Revision # & Date of Issue Quality Validation Questionnaire The questionnaire below is a distilled version of the vast number of questions that the preparer and reviewer of a Holtec safety-significant report must answer and archive in the Company's network to gain a VJR number (the identifier of QA pedigree in Holtec' s electronic configuration control system).
An affirmative answer (unless the question is "not applicable" or NA) to each of the following questions by the preparer of the report (or editor of a multi-author document) is an essential condition for thi s document to merit receiving a QA validated status.
Response
Criterion Yes or No Are you qualified per HQP 1.0 to perform the analysis 1 Yes documented in this report?
Are you aware that you must be specifically certified if you 2 use any Category A computer code (as defined in HQP 2.8 in Yes the preparation of this document?
Holtec Report Hf-2 177553 Jll Holtec Project 5025 Page 5 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 PIOLT!!e PRSPRIH:0.lil.>< l~llaORD1AIIOM HOLT~C PROPRLEIARi' INFORMAllON Are you fully conversant with the pertinent sections of the 3 Yes applicable Specification invoked in this report?
Is the input data used in this work fully sourced (i.e.,
4 Yes references are provided)?
Are you fully conversant w ith the user manual and validation 5 Yes manual of the code(s) used in this report, if a ny?
Is (Are) Category A computer code(s) (if used) listed in the 6 Yes Company's "Approved Computer program List"?
Are the results clearly set down and do they meet the 7 Yes acceptance criteria set down in the governing Specification?
Are you aware that you must observe all internal requirements on needed margins of safety published in Ho ltec 's internal 8 Yes memos, if applicable (which may exceed those in the reference codes and standards or the specification)?
Have you performed numerical convergence checks to ensure 9 Yes that the solution is fu lly converged?
Ts it true that you did not receive more than 10 quality 10 Yes infraction points in the past calendar year or thus far this year?
Holtec Report Hf-2 177553 JV Holtec Project 5025 Page 6 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEe PROPRIET.A:RV ltJFQfilt1A+IO~I I-191-.T"EiC P80PRifJARV [NFORMATION TABLE OF CONTENTS
1.0 INTRODUCTION
............................................................................................................................... 1 2.0 METHODOLOGY AND ASSUMPTIONS ......................................................................................... 4 3.0 ACCEPTANCE CRITERIA ................................................................................................................ 5 4.0 INPUT DATA ...................................................................................................................................... 6 5.0 COM.PUTER CODES AND FILES ..................................................................................................... 7 6.0 CALCULATION AND RESULTS ..................................................................................................... 8
7.0 REFERENCES
.................................................................................................................................... 9 Appendix A: Thermal Analysis of HI-TRAC CS During Normal Onsite Transfer Appendix B: Thermal Analysis of HI-TRAC CS During Hypothetical Accident Scenarios Appendix C: Calculation of Liquid Phase Fire Duration Appendix D: Calculation of Heat Flux from Uti lity Vehicle Tire Fire
SUMMARY
OF REV ISIONS Revision 0: Initial Issue Holtec Report Hf-2 177553 V Holtec Project 5025 Page 7 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IQls+aC RRORRIEIARY lt::clFQBM8IIQN IIOLTEC PROPRUHFRY I~I~OPMAIJON
1.0 INTRODUCTION
The HI-TRAC CS is the transfer cask to carry out all the onsite transfer operations of the MPC (Multi-Purpose Canister) at the HI-STORE CIS fac ility [l]. The HI-TRAC CS is a variation of HI-TRAC VW transfer cask licensed in docket number 72-1032 for the HI-STORM FW system and later adopted for the HI-STORM U MAX system in docket number 72-1040. HI-TRAC CS utilizes stee l and densified concrete to provide dose attenuation [2]. HT-TRAC CS is also characterized by a split bottom hd (sh ield gate) configuration with each half designed to retract (open)/approach (close) symmetrically. The key thermal design feature of the HI-TRAC CS is the inlet vents provided mn the shield gates that allow air to enter the HI-TRAC-to-MPC annular space. This allows for enhanced dissipation of decay heat from the MPC during transfer operations through natural convection.
The major onsite transfer operations involving HI-TRAC CS are as follows [l]:
(b)(4)
The purpose of this report is to evaluate and document the thermal performance of the HI-TRAC CS cask during the onsite transfer operations at the HI-STORE CIS facility and the associated hypothetical accident scenarios. Thermal analyses are carried out using three-dimensional models constructed using ANSYS FLUENT [8]. The HI-TRAC CS thermal evaluation adopts NUREG-1536 [6] and ISG-11 guidelines [7] to demonstrate the safe transfer of Commercial Spent Fuel (CSF). These guidelines are stated b elow:
- 1. The fuel cladding temperature for short-term operations shall be limited to 400°C (752°F) for high burnup fue l and 570°C (1058°F) for moderate burnup fue l.
- 2. The fuel cladding temperature should be maintained below 570°C ( I 058°F) for off-normal and accident conditions.
- 3. The internal pressure of the MPC should remain within its design pressures for normal, off-normal, and accident conditions.
- 4. The component materials should be maintained within their minimum and maximum temperature criteria under normal, off-normal, and accident conditions.
Holtec Report Hl-2177553 Holtec Project 5025 Page 8 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 FIOLT!!e P~9PlwllETO RY lb1F0BM8IIQN I IOUPEC PROPRJ ETARY I~* FORMATJO~J This calculation package serves as the thermal design justification for the HI-TRAC CS system loaded with MPC-37 and MPC-89 canisters under normal and accident cond itions to support the HI-STORE CIS Licensi ng Report [ l].
1.1 MPC Decay Heat As discussed in Section A. I of Appendix A, the MPC-37 canister with PWR 14x l4 Short Fuel (as defined in HI-STORM FW FSAR [3]) is the most limiting for casks in vertical orientation and is hence adopted for thermal analyses of HI-TRAC CS at HI-STORE site.
The HI-TRAC CS is analyzed for the bounding heat load pattern (Pattern l) from Table 4. l.l of HI-STORE CIS SAR [l]. As demonstrated in Table 3.3.4 of [5], this pattern is limiting for both the peak cladding temperature and MPC internal pressure and is hence adopted for all thermal evaluations of HI-TRAC CS documented herein.
1.2 Helium Backfill Pressure The MPC is pressurized with Helium before transportation to the HI-STORE CIS site in a HI-STAR 190 transport cask to provide an inert atmosphere and to enhance heat transfer. The backfill pressure range for MPC-37s transferred at the HI-STORE site is specified in Table 4.1.3 of HI-STORE CIS SAR [I] and duplicated in Table 1.2 of this report.
1.3 Design Ambient Conditions The HI-TRAC CS thermal evaluations are performed for site specific ambient conditions defined in Chapter 2 of the HI-STORE Site Specific Licensi ng Report [1]. The ambient conditions used for the normal onsite transfer scenario are listed in Table 1.1.
Holtec Report Hl-2177553 2 Holtec Project 5025 Page 9 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLT!!e I' llllt.01' Pll!.I !!TAPU II~ l'ORIVIA I ivi<J AOLT~C flKOfR::IET11\RY A'.JFORi,fATJO~J Table l .l: Site Specific Parameters Applicable to T!hermal Analyses of HI-TRAC CS Parameter Value A mbient Temperature for Short Term Operations 91°F (b)(4)
Site Elevation Note l : Elevation above sea level adopted for thermal evaluations conservatively bounds the site maximum elevation o~(b)(4) ~l ].
Table 1.2 Helium Backfill Range for MPCs Stored at HI-STORE CIS Site (Reproduced from [1])
MPC Type Pressure Range (Note 1)
MPC-37 :::, 39.0 psig and S 46.0 psig Note 1: Helium used for backfill of MPC shall have a purity of:::, 99.995%. The pressure range is based on a reference temperature of 70°F.
Holtec Report Hl-2 177553 3 Holtec Project 5025 Page 10 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTES PR.QPR.IET:A f;l>< l~JFQf;lP 1OTIQ~I l"IOLfEC PROPR:EE'fARY RffOR*MA:TIO~I 2.0 METHODOLOGY AND ASSUMPTIONS The overall thermal analysis principles and methodology adopted here is based on the HI-STORM FW FSAR [3] and the HI-STORM UMAX FSAR [4]. The detailed methodology and assumptions u ed for the evaluations are discussed in the respective appendices.
Holtec Report HI-2177553 4 Holtec Project 5025 Page 11 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 AOL I EC PROPRIE I ART IIQFORIVIA I IOIQ ttOLTt!C PltOPRI£TARY ~1¥0~4 AI!ON 3.0 ACCEPTANCE CRITERIA The acceptance criteria applicable for the various scenarios during the onsite transfer for MPC in the HI-TRAC CS is outlined in the corre ponding Appendices.
Holtec Report HI-2177553 5 Holtec Project 5025 Page 12 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTES Pl;;J;SPR.IETO~Y 1~11:0PDOAIIOM HOL'fEC fltO:Pltffl'f';tt'lt i fi\JFORMA I ION 4.0 INPUTDATA The input data necessary for the thermal analysis of normal onsite transfer scenario is listed in Section A.4 and the input infonnation used for the accident condition analyses are listed in Section B.4.
Holtec Report HI-2177553 6 Holtec Project 5025 Page 13 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IQbUiQ PR.QPR.Iii.TO~¥ l~JJ;Q~P4 OTIQ~I HOLIEC PROPRIEIARx n<JFORMAIION 5.0 COMPUTER CODES AND FILES All them1aI calculations documented in this report are perfonned using FLUENT Version 14.5 code [8].
The input/output files used in the HI-TRAC CS analyses are presented in the individual appendices.
Holtec Report HI-2177553 7 Holtec Project 5025 Page 14 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 AOL I EC PROPRll'.'.T)!(P,: I ii~l"aR:lo1'*-TIE,f4 HQI IEC PROPRIETARY CNF0~4ATI0l>I 6.0 CALCULATION AND RESULTS All the normal onsite transfer and accident conditions are evaluated and presented in the appendices of this report. The predicted results demonstrate that the peak fuel temperature, HI-TRAC and MPC component temperatures, and MPC internal pressure during normal onsite transfer scenario are in compliance with the acceptance criteria listed in HT-STORE CTS SAR [1].
Holtec Report HI-2177553 8 Holtec Project 5025 Page 15 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IQb+iQ PR.Oli!R.llii.TORY lblEORMAIIOM HOL'l'EC PROPRIElARY INFORMA llUN
7.0 REFERENCES
[1] Licensing Report on the HI-STORE CIS Facility Holtec Report HI-2167374, Revision 0.
[2] HI-TRAC CS Licensing Drawing, Holtec Drawing l 0868, Revision 0.
[3] Final Safety Analysis Report on the HI-STORM FW MPC Storage System, Holtec Report HI-2114830 Revision 4.
[4] "Final Safety Analysis Repo1t on the HI-STORM UMAX Storage System", Holtec Report HI-2 11 5090, Revision 3.
[5] Safety Analysis Report on the HI-STAR 190 Package, Holtec Report HI-2146214, Revision O.D.
[6] NUREG- 1536, "Standard Review Plan for Dry Cask Storage Systems," USNRC, Revision l (July 2010).
[7] "Cladding Considerations for the Transportation and Storage of Spent Fuel", Interim Staff Guidance
- 11 , Revision 3, 2003.
[8] Fluent 14.5, ANSYS Theory Guide 11 7 (20 12).
[9] MPC-37 Enclosure Vessel, Holtec Drawing 6505, Revision 17.
[10] Assembly, MPC 37 Fuel Basket, Holtec Drawing 6506, Revision 12.
[11 ] Effective Thermal Properties of PWR Fuel to Support Thennal Evaluation of HI-STORM FW, Holtec Report HI-2094356, Revision 5.
[1 2] HT-STORM FW License Amendment Request, 1032-5.
[13] Thermal Evaluations of HI-STORM UMAX at HISTORE CIS Facility, HI-2177591 Revision 0.
Holtec Report Hl-2177553 9 Holtec Project 5025 Page 16 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IE9LTEe PR.eJl"P'!.l!!T)!(P'!., 11~1"0,._IOIATIOl'J HOLFf~C Pl.t~PlttEIARr INFORMAllvi<J Appendix A:
Thermal Analysis of HI-TRAC CS During Normal Onsite Transfer Holtec Report HJ-2 177553 A- I Holtec Project 5025 Page 17 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 1101::TEe Pfii.OPRIEl'.A:RV ltJFQfilt1ATIO~I I IOLTEG PROPR:lE'fARY IHFORMAflON A.1 INTRODUCTION The thermal analysis of the HI-TRAC CS during normal onsite transfer is presented in this Appendix . One of the central objectives of this report is to establish that the MPCs transported to the storage site in the HI-STAR 190 casks can be safely transferred to the UMAX storage systems using the HI-TRAC CS. The HI-TRAC CS is analyzed under a bounding configuration during the onsite transfer of MPC from the HT-STAR 190 cask to the VVM for storage. The bounding scenarios for onsite transfer are established based on the configurations evaluated in the HI-STAR 190 SAR [5] and the HI-STORM UMAX FSAR [4].
The bounding configuration includes the following:
- 1. Limiting MPC Type and Heat Load Pattern: As discussed in Section 2.0 of UMAX storage report [13], MPC-37 loaded with the PWR short fuel under the heat load pattern 1 from Table 4. 1.l of HI-STORE CIS SAR [ l] is the most limiting thermal configuration.
Therefore, this bounding configuratio n is adopted for a ll analyses presented in this report.
(b)(4) 2.
- 3. Solar insolation: The HI-TRAC is assumed to be outdoors and subjected to IOCFR71 solar insolation levels. 24-hour averaged insolation is ap plied considering the high thermal inertia of the system.
A 3-D thermal model is developed for the above configuration using the ANSYS Fluent [8]
as described in the following sections. Although the onsite transfer would preclude the HI-TRAC CS/MPC reaching steady state due to the high thermal inertia of the system , a steady state analysis of HI-TRAC CS, with MPC in vertical orientation, during onsite transfer is performed here.
Ho ltec Report HJ-2 177553 A-2 Ho ltec Project 5025 Page 18 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTE9 Pfi!:OPfi!:IETJltR., 11~1"0,._IOIATIO'l'l HOL'fEC PllOPJtfE'fAll'I' t,qFOllMA'flOJq A.2 METHODOLOGY To ensure an adequate representation of the thennally significant features of the HI-TRAC CS package such as air flow, fuel basket, basket shims, MPC and the various components of the cask, three-dimensional computational fluid dynamics (CFD) models of the MPC-37 loaded with the PWR Short Fuel (discussed in Section A.1) p laced in the HI-TRAC CS cask are constructed.
The MPC-37 model is adopted from the HI-STORM FW LAR [12]. The HI-TRAC CS cask is modelled around the existing MPC-37 mode l. The overall modelling approach and solution methodology used here is largely adopted from the thermal evaluations presented in the HI-STORM FW FSAR [3] and HI-STORM UMAX FSAR [4].
These HT-TRAC CS/MPC-3 7 3-D models have the following kev features:
(b)(4)
Holtec Report HJ-2 177553 A-3 Holtec Project 5025 Page 19 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IE9LTEe PR.Sl"P'!.l!!TAP'!., 11~1"0,._IOIATIOl'J IIOLTEG PROPRH!iTARY ~lf0~U4TI0l>J (b)(4)
Holtec Report HJ-2 177553 A -4 Holtec Project 5025 Page 20 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOI TEC PROPRIETARY lb1EORD1AIIOM IIOLTEG PROPR:lETARY ~Jf0J;lJl.1ATI0~J A.3 ASSUMPTIONS The HI-TRAC CS thermal analysis employs an array of conservatisms to predict the maximum fue l, basket, MPC, and cask component temperatures. Following is a list of key features and conservative assumptions made in the thermal analysis of HI-TRAC CS during normal onsite transfer:
- 1. Axial heat transfer through fuel pellets is neglected i.n accordance with NUREG 1536.
(b)(4)
Holtec Report HJ-2 177553 A-5 Holtec Project 5025 Page 21 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lEfO fiil.¥ l~llaORU HIO~I I IOL'fEC PROPRlET,\RY FNF0J;lJl.1ATI0~J (b)(4)
Holtec Report HJ-2 177553 A-6 Ho ltec Project 5025 Page 22 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOI IFC PROPRIFIOPY lblEORD10IIOM IIOLTEG PROPRUHA~Y ~J~QUUATION A.4 INPUT DATA The principal geometric input data for the thermal-hydraulic evaluations of the HI-TRAC CS cask, used in these analyses, are taken from design drawing [2]. The geometric data for the MPC-37 with the PWR shortt fuel is adopted from the HI-STOR FW FSAR [3].
Materials present in the HJ-TRAC CS cask include structural steels, and concrete. The physical properties of these materials are adopted from [4]. The properties of the MPC-37 component materials are adopted from H I-STORM FW FSAR [3].
(b)(4)
As outlined in Section Al.1 , the heat load Pattern l from HT-STORE SAR [2] is used for the analyses presented here.
The natural convection surface heat transfer coefficient on the cask external surface, used in the quarter-symmetric models, is based on the cotTelations provided in Chapter 4 of HI-STORM FW FSAR [3]. Conservatively understated convection coefficient (h) is used in the thermal model.
Solar insolation, that bounds the 10CFR71 prescribed insolation data (see Table A.2.1), have been applied to all external surfaces of the HI-TRAC CS cask.1(b)(4) l(b)(4) I* ---------
The site specific ambient temperature is listed in Table 1. 1.
Holtec Report HJ-2 177553 A-7 Holtec Project 5025 Page 23 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOL'f!!e 1'"-0PR:IETJltR:Y lldFSR:li11JltTl8Pl I IOL'fEC PROPR:lE'fARY l~ff0RMNFI0t4 A.5 ACCEPTANCE CRITERIA The HI-TRAC CS thermal evaluation acceptance criteria are listed below:
- l. The peak cladding temperature under normal onsite transfer must be below 400°C for MPCs containing one or more high bumup fuel assemblies and 570°C for MPCs containing all moderate burnup fue l assemblies [7].
- 2. The HT-TRAC CS steel and concrete temperatures must be within the temperature limits presented in Table 4.4.1 of HI-STORE CJS SAR [ 1].
- 3. The MPC component temperatures and internal cavity pressure must be below the limits discussed in Section 4 .3 of HI-STORE CIS SAR [ l].
Holtec Report HJ-2 177553 A -8 Holtec Project 5025 Page 24 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEe PFi.OPFi.lH.A:Fi.V ltJFQfilMATIO~I IIOLTEG PROPRH!iTARY ~lf0~U4TI0l>J A.6 COMPUTER PROGRAM AND FILES The commercial CFO code, FLUENT version 14.5.7 [8] is used in these thermal calculations. A list of the computer fi les supporting the calculations is provided below.
(b)(4)
Holtec Report HJ-2 177553 A-9 Holtec Project 5025 Page 25 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 AOL I EC l"jllt_Ol"P'!.INJltR:\C itJF9RMO+IQM IIOLTEG PROPR:lETARY ~lYORHi1 TIOl>l A.7 RESULTS AND CONCLUSIONS A.7.1 Normal Onsite Transfer A.7.1.1 Maximum Temperatures during Normal Onsite Transfer Steady state analysis is performed using the 3-D thermal model described in Section A.2. The computed temperatures are listed in Table A.7.1 The peak cladding temperature, MPC and HI-TRAC component temperatures are well within the limits outlined in Section A.5.
The temperature contours for the normal onsite transfer scenario are provided in Figure A.7.l through A.7.8.
A.7.1.2 Maximum Normal Operating Pressure {MNOP) during Nonnal Onsite Transfer Per the HI-STAR 190 SAR [5], the MPC cavity is de-moisturized and backfilled with dry helium after fuel loading and prior to MPC lid closures. During the onsite transfer, the MPC internal pressure reaches a value depending upon the steady state temperature. The steady state MPC cavity pressure during onsite transfer in HI-TRAC CS is calculated using the Ideal Gas Law.
The MPC cav ity pressure calculated using Ideal Gas Law and based on the max imum in itia l backfill pressure from Table 1.2 of this report, is reported in Table A.7.2 of this Appendix. The maximum cavity pressure is below the MPC design pressure limit under normal conditions specified in Chapter 4 of HI-STORE CIS SAR [ l ].
A.7.1.3 Thennal Expansion Computations In this subsection, thermal expansion of free-standing HI-TRAC CS/MPC-37 components in the radia l and axial directions is computed fo r the bounding scenario described in Section A. l. The calculations address the fo llowing thermal expansions:
a) Fuel Basket-to-MPC Rad ial Growth b) Fuel Basket-to-MPC Axial Growth c) MPC-to-Cask Radial Growth d) MPC-to-Cask Axial Growth Holtec Report HJ-2 177553 A- 10 Holtec Project 5025 Page 26 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY l~Ji;Q~MATIQN t!OLTEC PROPRl:ETARY INFORMATION (a) Fuel Basket-to-MPC Radial Growth The radial growth (01) of the fuel basket relative to the MPC shell upon heating from a 2 1°C (70°F) reference temperature (To) to steady state temperatures is computed as fo llows:
l....._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _....,(Eq.
'.b)(4) I A.7. 1)
(b)(4)
The fuel basket radial growth is computed in the spreadsheet listed in Section A.6, and reported in Table A.7.3. This differential growth is bounded by the minimum design gap engineered between the fue l basket and the MPC shell (see Table A .7 .3).
(b)(4)
(b) Fuel Basket-to-MPC Axial Growth The axial growth of the fuel basket relative to the MPC shell (02) upon heating from a 2 1°C (70°F) reference temperature to steady state temperatures is computed as follows:
4 l(b)( ) --------------- (Eq. A. 7 .2)
(b)(4)
Holtec Report HJ-2 177553 A-1 1 Holtec Project 5025 Page 27 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIET.A:RV ltJFORJ.1.9.TIOtJ MOLT~C PltOPJtIE'fAltY l~ffORMXFION (b)(4)
The net fuel basket axial growth is computed in the spreadsheet listed in Section A.6, and reported in Table A.7.3. This differential growth is bounded by the design gap engineered between the fuel basket and the MPC lid (see Table A.7.3).
(c) MPC-to-Cask Radial Growth The radial growth (fo) of the MPC shell residing in the HI-TRAC CS cask relative to the cask upon heating from a 21 °C (70°F) reference temperature (To) to steady state temperatures is computed as follows:
,----------------,I r b)(4)
(Eq. A. 7. 3)
(b)(4)
The fuel basket radial growth is computed in the spreadsheet listed in Section A.6, and reported in Table A.7.3. This differential growth is bounded by the design gap engineered between the MPC and H I-TRAC CS cask (see Table A.7.3).
(d) MPC-to-Cask Axial Growth The axial growth of the fuel relative to the HI-TRAC inner shell (04) upon heating from a 2 1°C (70°F) reference temperature to storage temperatures is computed as follows:
l(b)(4)
(Eq. A.7.4) rb)(4)
Holtec Report HJ-2 177553 A- 12 Holtec Project 5025 Page 28 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOLT!!O 1'"-e:'Jl'R:IETJltR:Y ltJF8RJ.1.A.il"l9N HOLlBC PROPRLEIARi' INFORMAllON (b)(4)
The net MPC ax ial growth is computed in the spreadsheet listed in Section A.6, and reported in Table A.7.3. This differential growth is bounded by the design gap engineered between the MPC and cask shield ring (see Table A.7.3).
A.7.2 Additional Discussions:
A.7.2.1 Acceptability of Sub-Design Heat Load:
A sub-design basis (SDB) heat load pattern with wider helium backfill range is defined for both MPC-37 and MPC-89 is also permitted to be transpo1ied in the HI-STAR 190 cask as discussed in Section 3.3.5 of HT-STAR 190 SAR [5]. Since the SOB heat load pattern allows a higher backfill upper limit, explic it analysis was performed in the HI-STAR 190 SAR [5] (Table 3.3.8) demonstrating that the design basis MNOP is higher than the sub design basis MPC pressure.
This conclusion therefore can be extended to the normal onsite transfer scenario in HI-TRAC CS. Additionally, the MPC cavity pressure during onsite transfer, reported in table A. 7 .3 is lower than the normal transport condition pressures reported in Table 3.1.5 of HI-STAR 190 SAR [5].
Therefore, the temperatures and pressures under SDB heat load patterns defined in HI-STAR 190 SAR will meet the acceptance criteria in Section A.5 for onsite transfer in HI-TRAC CS.
A.7.2.2 I 6x 16A Intact Fuel in Damage Fuel Containers (DFCs):
The HI-STAR 190 is permitted to transport of 16x16A intact fuel assemblies placed within DFCs and loaded in MPC-37 canisters as discussed in section 3.3.6 of HI-STAR 190 SAR [5]. The PCT, component temperatures and MPC cavity pressures are all bounded by the licensing basis normal transport scenario reported in Table 3.1.l of the HI-STAR 190 SAR [5]. Therefore, it can also be concluded that the maximum temperatures and cavity pressure during onsite transfer MPC-37 loaded w ith 16x l6A intact fuel assemblies placed in DFCs, in HI-TRAC CS is bounded by the bounding onsite transfer scenario evaluated in Section A.7.1.
Holtec Report HJ-2 177553 A-13 Holtec Project 5025 Page 29 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOI IFC PROPRIFIOPY lblEORD10IIOM HOC l ~C Plt~Pltf'E'fAll'I' 1HF0ftMA'fI0t4 Table A.2.1: 24 Hours Averaged Solar Insolation Data from 10CFR71 Total insolation averaged over a 24-hour Form and location of surface period (g cal/cm2)
Flat surfaces transported horizontally; Base None Other surfaces 400 Flat surfaces not transported horizontally 100 Curved surfaces 200 Holtec Report HJ-2 177553 A- 14 Holtec Project 5025 Page 30 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 l"IOLT!!e l'~SPR:IETARY ltJF9Rt1A+IQM FIOLTEC f'R:OfR:lE'fARY FNFOJ;lMATIQl>J Table A.7 ..1 Maximum Temperatures for HI-TRAC CS/MPC-37 loaded with PWR Short Fuel under Heat Load Patter 1 during Normal Onsite Transfer Maximum Temperatures Temperature Limits Material/Components oc (OF) oc (OF)
Fuel Cladding 354 (669) 400 (752) or 570 (1058) Notc 2 Fuel Basket 324 (615) 500 (932)
Basket Shims 264 (507) 500 (932)
MPC Shell 238 (46 l) 427 (800)
MPC Lid Note I 213 (416) 427 (800)
MPC Baseplate Note 1 173 (343) 427 (800)
H T-TRAC Concrete Note 1 133(271) 149 (300)
HI-TRAC Outer Shell 93 (200) 316 (600)
HI-TRAC Inner Shell 178 (352) 316 (600)
Shield Gate Top Flange 142 (288) 316(600)
Shield Gate Door 169 (336) 316(600)
Note 1: Maximum Section Average Temperature is reported fo r this component.
Note 2: The 1058°F temperature limit applies to MPCs containing all moderate burnup fuel. The limit for MPCs containing one or more high burnup fuel assemblies is 752°F.
Holtec Report HJ-2 177553 A- 15 Holtec Project 5025 Page 31 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOI IFC RRORRIEIAPX H>IEORDQAIIO'>I l"IOL!JS:C PR:OPR:H3TARY :R>IPORJ MTIO~I Table A.7.2 MPC Cavity Pressure during Normal Onsite Transfer in HI-TRAC CS Pressure Pressure Limit kPa (psig) kPa (psig)
Condition Normal Onsite Transfer 661.6 (96.0) 827.1 (120)
Holtec Report HI-2177553 A-16 Holtec Project 5025 Page 32 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIET.A:RV ltJFORJ.1.9.TIOtJ IIOLTEG PROPR:lETARY ~WORHATIOl>l Table A.7.3 Differential Thermal Expansions during Normal Onsite Transfer Differential Is Free Expansion Nominal Gap Gap Description Expansion (V), Criteria Satisfied?
(U), mm (inch) mm (inch) (i.e. U > V)
Fuel Basket-to-MPC 2.845 to 7. 14 2.33 Yes Radial Gap (0.11 2 to 0.281) (0.092)
Fuel Basket-to-MPC Axial 38.1 8.41 Yes Gap ( 1.5) (0.331) 9.52 2.51 MPC-to-Cask Radia l Gap Yes (0.375) (0.099) 57.15 8.56 MPC-to-Cask Axial Gap Yes (2.25) Nole I (0.337)
Note 1: The MPC height used for the thermal evaluations is that corresponding to the PWR short fuel as explained in Section A. l resulting in bounding temperatures. However, the minimum cold gap obtained using the longest MPC-37 height of 2 13" is used as the acceptance criteria, here. This is conservative.
Holtec Report HJ-21 77553 A- 17 Holtec Project 5025 Page 33 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOL'f!!e 1'"-SPR:IETJltR:Y lldFSR:li11JltTISPl HOL'fEC ~ltOflUE'fAltY IHFOltMNFION (b)(4)
Figure A.3 .1: HI-TRAC CS/MPC-37 Thennal Model Holtec Report HJ-2 177553 A - 18 Holtec Project 5025 Page 34 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 F!OLT!!C 1'"-e:'JPR:IETARY ltJF9filt1A+IO~I IIOL'fEC PROPR:lE'fARY l~ff0RMNFI0t4 (b)(4)
Figure A.7.1 Temperature Contours of HI-TRAC CS/MPC-37 under the Normal Onsite Transfer Holtec Report HJ-2 177553 A- 19 Holtec Project 5025 Page 35 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 t tetTE8 Plol:9Pliil.lETO liil.¥ lblEORMAIIQN IIOLTEG PROPRH!iTARY ~lf0~U4TI0l>J (b)(4)
Figure A.7.2 Temperature Contours at hottest cross sectio n of HT-TRAC CS/MPC-37 under the Normal Onsite Transfer scenario.
Holtec Report HJ-2 177553 A-20 Holtec Project 5025 Page 36 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lifO liil.¥ l~llaORU HIO~I I10t'ftsC fROf:ltlE'fARY 1~4FORMATION (b)(4)
Figure A.7.3 Temperature Contour ofMPC Shell under the Normal Onsite Transfer scenario.
Holtec Report HJ-2 177553 A-2 1 Holtec Project 5025 Page 37 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 t tetTE8 Plol:9Pliil.lETO liil.¥ lblEORMAIIQN AOLT'EC FR:OPR:lETARY ~Jf0~U1TI0N (b)(4)
Figure A.7.4 Temperature Contour of MPC Baseplate under the Normal Onsite Transfer scenario.
Holtec Report HJ-2 177553 A-22 Holtec Project 5025 Page 38 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOL'f!!e l'P'!.Ol'P'!.l!!'f)!(P'!., 1141'0~fol)!('fl0f4 IIOLTEG PROPRUHARY lltl:Ei'ORMATTQN (b)(4)
Figure A.7.5 Temperature Contour ofMPC Lid under the Normal Onsite Transfer scenario.
Holtec Report HJ-2 177553 A-23 Holtec Project 5025 Page 39 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 AOL I EC PROPRIE I ARY ii<JFORIVIA I IOl<J J.IObT~C PROPRl~T i\RY ~J~QIU44TIQN (b)(4)
Figure A.7.6 Temperature Contour of MPC Lid top surface under the Normal Onsite Transfer scenario.
Holtec Report HJ-2 177553 A -24 Holtec Project 5025 Page 40 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEO PFl:OPFl:IET.A:Fl:V ltJFORJ.1.9.TIOtJ MObT~C PROPRUHARY ~J~QIU44TIQl>J (b)(4)
Figure A.7.7 Temperature Contour of HI-TRAC CS components in the vicinity of trunnions.
Holtec Report HJ-2 177553 A-25 Holtec Project 5025 Page 41 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 lafOl..+aC li'fiil.Oli'fiil.la::ro fiil.¥ l~llaORU HIO~I HOL'ftsC PROPRlET,\RY ~WORHATIOl>l (b)(4)
Figure A.7.8 Temperature Contours of HI-TRAC CS bottom shield gate assembly under the Nom1al Onsite Transfer scenario. Bulk temperature of this component is 142°C.
Holtec Report HJ-2 177553 A -26 Holtec Project 5025 Page 42 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTES Plil.OPlil.lETAfiil.¥ l~llzARD10IiOM I IOLTEG PROPRlET,\RY R.JF0RMNFI0t4 Appendix B:
Thermal Analysis of HI-TRAC CS Hypothetical Accident Scenarios Holtec Report HI-2 177553 B-1 Holtec Project 5025 Page 43 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 AOL I EC PP'!.01' P'!.i !!TJltR:\C itJ F9Rt 1o+10~1 IIOLTEG PROPR:lETARY ~Jf0J;lJl.1ATI0~J B.1 INTRODUCTION The thermal analysis of the HI-TRAC CS during hypothetical accident scenarios postulated in
[ l] is presented in this Appendix.
B.1.1 VCT Fire Accident:
During the Onsite Transfer, the HT-TRAC CS loaded with MPC is transported from the CTB to the UMAX Storage Modules using a VCT. The hypothetical fire accident is assumed to be occurred during this onsite transport of HI-TRAC CS using the VCT, with a gator/uti lity vehicle nearby. The relative position of HI-TRAC CS, VCT and a gator/utility vehicle cask considered for the ana lysis is illustrated in Figure D.l.
The liquid fire duration is calculated based on the fuel and hydraulic fluid inventory of the VCT as well as a gator/go lf cart/utility vehicle in the vicinity. To evaluate the effect of liquid fire on HI-TRAC CS and loaded MPC, a transient CFD analysis is performed and the calculation is continued after the postulated fire duration, until the peak cladding temperature reaches its maxima and starts decreasing. The fire evaluations are performed based on the require ments set forth in 10CFR71 (outlined in Chapter 6 of [l]).
The effect of solid fire resulting from the hypothetical scenario of the gator/utility vehicle wheels being ignited is also evaluated following the methodology outlined in Section B.2.
The sources of combustible materials considered for the evaluation include:
(b}(4)
The quantities of these combustibles are listed in Table B.1.1. The assumed parameters for the utility vehicle wheels are listed in Table B. 1.2.
B.1.2 Canister Transfer Building (CTB) Collapse Accident~
Holtec Report HI-2177553 B-2 Holtec Project 5025 Page 44 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 AOL I EC Pl'\OPRll'.'.T)!(P,: I il~FSR:lo1'*-TISl4 HOLi EC PROPRIEIARi INFORMAIIUN As outlined in Chapter 6 of [1] , the CTB is assumed to collapse and the aluminum sheets from the CTB roof is assumed to block pmts of the HI-TRAC CS cask. The effect of flow blockage due to the corrugated sheets, as well as the radiation blockage are captured in the thermal model in a bounding manner. A steady state analyses is performed under this condition to ensure that the bounding temperatmes are predicted. The design basis accident as defined in the HT-STORE CTS Licensing Report [ 1] is adopted for the evaluations of the CTB collapse event.
The bounding fuel assembly type, heat load and MPC type as justified in Appendix A is used for all the analyses presented here.
Holtec Repmt HI-2177553 B-3 Holtec Project 5025 Page 45 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I ISLTEe PR:SPR:IETJltR:Y lldP'O~fo1>'<1"10f4 MObT~G PROPRUHARY ~J~QIU44TIQl>J B.2 METHODOLOGY AND ASSUMPTIONS The thermal model used for the accident analyses are directly adopted from the normal onsite transfer calculations presented in Appendix A. Changes are made to the boundary conditions to evaluate the specific accidents. The changes made to the model and assumptions involved in the analyses are listed in this section.
B.2.1 Hypothetical Fire Accident:
The fire event involving the VCT and gator/utility vehicle is postulated to consist of three phases as fo llows:
(b)(4)
Holtec Report HI-2177553 B-4 Holtec Project 5025 Page 46 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEe PRSPRIETARY ltJF8RP:1.A.Tl9tl IIOLTEG PRQPRUHARY ~J~OUUATION B.2.1.1 Liquid Phase Fire:
The methodology and major assumptions adopted for liqu id fire analysis is listed below:
(b)(4)
B.2.1.2 Solid Phase Fire:
The following methodology is adopted for evaluating the temperature difference due to the solid phase fire:
Holtec Report HI-2 177553 B-5 Holtec Project 5025 Page 47 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HAI IEC RRORRIFIOPY lb1EOP&4AIIOM I IOL'fEC PROPR:lE'fARY l~ff0RMNFI0t4 (b)(4)
Holtec Report HI-2 177553 B-6 Holtec Project 5025 Page 48 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEO PFl:OPFl:IET.0,Fl:Y 1*JFQfilt4ATIO~I I IOL'fEC fltOflUE'fAltY IHFOltMA'flOJq (b)(4)
B.2.2 Hypothetical CTB Collapse event:
The 3-D thermal model used for the CTB collapse event is adopted from the thermal model for normal onsite transfer analysis. The boundary conditions are altered in the Fluent model to reflect the design basis event. The following modifications and assumption are involved in the thermal analysis:
(b)(4)
Holtec Report HI-2177553 B-7 Holtec Project 5025 Page 49 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IQbUiQ PR.QPR.lli:TO~Y l~JJ;Q~P40TIQ~I IIOL'fEC PR:OPR:IE'fARY fN:PORioh\'fiON l(b)(4)
A steady state analysis is performed for the hypothetical CTB collapse accident to obtain bounding maximum temperatures.
Holtec Repmt HI-2177553 B-8 Holtec Project 5025 Page 50 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 f.lQI..TliiC f21ilQf2R,lliiTO f;l>< l~JFQf;lpqo TIQ~J
.WOLT~C :PROPRlsTA RY ~l~OR,U,ATIO~I B.3 INPUT DATA The thermal model is directly adopted from Appendix A of this report. The source and quantity of liquid and solid cornbu tibles used for the fire analysis are listed in Table B.1.1 . The relevant parameters of the gator/utility vehicle adopted for the solid phase fire are listed in Table B.1.2.
The additional input data used for the calculation of fire durations are listed in Appendix C and Appendix D.
Holtec Repmt HI-2177553 B-9 Holtec Project 5025 Page 51 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTES Plil.OPliil.lETOliil.¥ l~llaORD10IIOM AOLlEC PROPRLEIARt n~~OttMAfI014 B.4 ACCEPTANCE CRITERIA The acceptance criteria for the HI-TRAC CS accident scenarios are outlined in Section 4.3 of the HI-STORE CIS SAR [1]. Specifically, under accident scenarios:
- l. The Peak Cladding Temperature must be below 570°C (1058°F) during accident conditions [7].
- 2. The HT-TRAC CS component temperatures must be be low the limits specified in Table 4.4.1 of [1]. The portion of concrete that exceeds the limit of 1100°F will be considered unavailable for shield ing as per Table 4.4.1 of HT-STORE CIS SAR [ I].
- 3. For the fire accident, the temperature of carbon steel components directly exposed to the fire must be below 50% of the melting point given in [B-2], as per the requirement set forth in Table 4.4.1 of[I].
- 4. The MPC component temperatures and internal pressure must be below the accident conditions lim its discussed n Section 4.3 of the HI-STORE SA R [I].
Holtec Report HI-2 177553 B- 10 Holtec Project 5025 Page 52 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I 19LTE9 PR9PRIETAR\' lldFSRli11....,.lel4 HQI-.T~C PROPRlETARY IHFO!tMATIOl~
B.5 COMPUTER PROGRAM AND FILES The commercial CFO code, FLUENT version 14.5.7 [8] is used in these thermal calculations. A list of the computer fi les supporting the calculations is provided below.
(b)(4)
Holtec Report HI-2177553 B-11 Holtec Project 5025 Page 53 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOLT!!C P' P'!.e:'Jl"P'!.IETJltR:Y IIJF8RM,C.i1"19Pl HOLFf~C Pl.t~PltLE I ARr IN FORMA llON B.6 RESULTS AND CONCLUSIONS B.6.1 Maximum Temperatures and MPC Pressure During the VCT Fire Event:
B.6.1.1 Liquid Phase Fire The bounding steady state HI-TRAC CS nonnal on-site transfer temperatures (see Table A.7.1) are adopted as the initial condition for the transient fire accident (fire and post-fire) evaluation.
The transient study was conducted for a sufficiently long period to allow temperatures in the overpack to reach their maximum values and begin to recede. The maximum temperature for each component during and after the fire accident is obtained from the transient analysis and reported in Table B.6. l. I .
As shown in Figure B.6. 1. 1, the peak cladding temperature reaches the maximum value at about l(b)(4) !after the start of the fire event.
4 The MPC cavity bulk temperature reaches its maxima at aroun1(b)( ) !after the start of fire.
The maximum MPC pressure during the post fire duration is listed in Table B.6.1.2.
Due to direct exposure to the hypothetical fire (modelled as 1475°F heat source), some part of the HI-TRAC CS concrete exceeds the temperature limit. As stated in Chapter 4 of the HI-STORE CIS Licensing Report [l], the concrete that exceeds l 100°F shall be considered unavailable for shielding. The regions of concrete that exceed this limit is shown in Figure B.6.1 .2. As shown in the figure a negligible portion of concrete exceeds 1100°F at the end of fire.
The peak cladding temperature, maximum component temperature and MPC cavity pressures reported in Tables B.6.1.1 and B.6.1.2 are within their respective limits provided in Chapter 4 of
[ 1].
B.6.1.1 Solid Phase Fire The total heat flux incident on HJ-TRAC CS cask from the solid phase fire is calculated in Appendix D. Based on the calculations presented in the spreadsheet!(b ...-)(4_) _ _ _ _ _ _ ____,
(b)(4)
Holtec Report HI-2177553 B-12 Holtec Project 5025 Page 54 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOL'f!!e l'P'!.Ol'P'!.l!!'f)!(P'!., 1141'0~fol)!('fl0f4 AOL l BC ~ItOfR:lET,\RY ~IfQR U APON temperatures will essentially be the same as that reported in Table B.6.1.1 and the maximum MPC cavity pressure will be essentially same as that reported in Table B.6.1.2.
B.6.2 Maximum Temperatures and MPC Pressure During CTB Collapse Event:
A steady state analysis is performed using the thermal model described in Section B.2 for the CTB collapse accident. The maximum peak cladding temperature and Hl-TRAC/MPC component temperatures are presented in Table B.6.2. 1. The maximum MPC pressure for the CTB collapse event is reported in Table B.6.2.2. The PCT, component temperatures and MPC internal pressures are within their respective accident condition limits specified in Chapter 4 of the HI-STORE CIS Licensing Report [l].
Holtec Report HI-2177553 B-13 Holtec Project 5025 Page 55 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTES Pl;;J;OPR.IETO ~¥ l~JlaORD1AIIOM HOL I EC PROPRIE I AR 2 INF ORMA I ION B.7
REFERENCES:
[B-1] "Thermal Measurements in a Series of Large Pool Fires", SAND85-1096, Sandia National Laboratories, (August 1987).
[B-2] "Carbon Steel Handbook", EPRI, Palo Altom CA: 2007. 1014670.
Holtec Repmt HI-2177553 B-14 Holtec Project 5025 Page 56 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HAI IEC PROPRIETARY INEOBMATION I IOL'fEC fltOflUE'fAltY IHFO!tMA'flOl<I Table B.1.1 Source and Quantity of Combustible for the Hypothetical Fire Accident Source Quantity Reference (b)(4)
VCT Diesel Fuel VCT Hydraulic Fluid Utility Vehicle Diesel Fuel Total Rubber Mass from Utility Vehicle Tires Table 8.1.2 Gator/Utility Vehicle Parameters adopted for Solid Phase Fire Parameter Value (b)(4)
Tire Diameter Number of Wheels Holtec Report HI-2177553 B-15 Holtec Project 5025 Page 57 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 AOL I EC PROPRIE I ARY INFORMA I ION IIOLTEG PROPRHHARY FNFOR:MATIO~i Table B.6.1.1 Maximum Temperatures for HI-TRAC CS/MPC-37 during VCT Fire Accident Temperature Temperature Limit Material/Components oc (OF)
~C (°F) 111 End of Fire Post Fire Fuel 354 (670) 372 (701) 570 ( 1058)
Fuel Basket 324 (615) 343 (650) 570 (1058)
Basket Shims 264 (508) 281 (537) 570 (1058)
MPC Shell 267 (512) 267(512) 570 (1058)
MPC Lid Note I 245 (474) 245 (474) 570 (1058)
MPC Baseplate Note 1 219 (426) 275 (527) 570 (1058)
HI-TRAC Concrete 749 (1380) 749 (1380) 593 (1100)
HI-TRAC Outer Shell Note 3 589 (1092) 589 (1092) 713 ()3l5t0 *e4 HI-TRAC Inner Shell 474 (886) 474 (886) 713 ()315) Note 4 Shield Gate Top Flange Note 3 371 (700) 371 (700) 713 (1315) Note 4 Note I: Maximum Section Average Temperature is reported for this component.
Note 2: The volume of concrete that exceeds the temperature limit is shown in Figure B.6.2. l and shall be considered unavailable for shielding.
Note 3: Bulk temperature reported for this component.
Note 4: 50% of melting point of carbon steel from [B-2].
Table B.6.1.2 Maximum MPC Pressure during VCT Fire Accident Bulk Temperature Pressure Condition oc (OF) kPa (psig)
VCT Fire Accident 284 (542) Note 1 691 (100.2)
Note 1: The maximum cavity average temperature is obtained atl(b)(4) r fter the start of fire.
Holtec Report HI-2 177553 B- 16 Holtec Project 5025 Page 58 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 IIQb+iQ 12R.012R.llii.TOPY lbl50PD10IIOM HOLTEC PROPRtEIARf 1NP0ftMA'fI0t'4 Table B.6.2.l Maximum Temperatures for Hl-TRAC CS/MPC-37 after the CTB Collapse Accident Maximum Temperatures Temperature Limits 11)
Material/Components oc (OF) oc (OF)
Fuel 492 (918) 570 (1058)
Fuel Basket 465 (869) 570 (1058)
Basket Shims 403 (757) 570 ( 1058)
MPC Shell 38 1 (718) 570 (1058)
MPC Lid Note 1 343 (649) 570 (1058)
MPC Baseplate Note 1 339 (642) 570 (1058)
HI-TRAC Concrete 338 (640) 343 (650)
HI-TRAC Outer She ll 177(35 1) 371 (700)
HI-TRAC Inner Shell 339 (642) 37 1 (700)
Shield Gate Top Flange 293 (559) 37 1 (700)
Shield Gate Door 336 (637) 371 (700)
Note 1: Maximum Section Average Temperature is reported for this component.
Table B.6.2.2 Maximum MPC Pressure after the CTB Collapse Accident Bulk Temperature Pressure Condition oc (OF) kPa (psig)
VCT Fire Accident 408 (766) Note 1 867 (125.8)
Holtec Report HI-2177553 B- 17 Holtec Project 5025 Page 59 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I 16L'ft:6 PI\OPl\h! I Al\ I ll<JFORIVIA I ION IfOLrEC PROPRH3L°tRY RffO~oL\TIO:N (b)(4)
Figure B.6.1.1: Time history of peak cladding temperature for the VCT Fire Accident.
Holtec Report HI-2177553 B-18 Holtec Project 5025 Page 60 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 i-.,01..::r.c li'fiil.Oli'fiil.la::ro fiil.¥ l~llaORU HIO~I I IOLTEG PROPRlET,\RY FNFORMATIO~i (b)(4)
Figure B.6.1.2: Region of HT-TRAC CS Concrete that exceeds 1100°F.
Holtec Report HI-2 177553 B-19 Holtec Proj ect 5025 Page 61 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOI IFC PROPRIETARY 1NF0Bb4ATl0N IIOLTEG PROPRH!iTARY ~lf01U44 TIOl>l Appendix C:
Calculation of Liquid Phase Fire Duration Holtec Report HI-2177553 C-1 Holtec Project 5025 Page 62 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIET.A:RV ltJFORJ.1.9.TIOtJ I IOLTEC PROfltlE'fAll'I' ll<f~ORiviA I JON C.1 WORKSHEET-SPECIFIC INTRODUCTION The purpose of this calculatiorn is to determine the duration of a combustible liquid fire involving a tracked VCT carrying a HI-TRAC CS cask. The procedure is as follows :
(b)(4)
This approach to calculating the duration of the fire is consistent with the methodology described in the HI-STORM FW FSAR [B-1 ) which is in accordance with NRC Regulations, 10CFR71 .
C.2 WORKSHEET-SPECIFIC REFERENCES
[C-1] "HI-STORM FW Final Safety Analysis Report," Holtec Report Hl-2114830, Revision 4.
[C-2] "Lift-N-Lock Vertical Cask Transporter Crawler Type Model VCT-415-260," J&R Engineering Operating & Maintenance Manual , Revision 1.
[C-3] "HI-TRAC CS Licensing Drawing" Holtec Drawing 10868RO.
[C-4] "General Arrangement Vertical Cask Transporter," J&R Engineering Conpany, Inc, Drawing No.
VCT415W081, Revision 0.
[C-5] NRC Regulations (1 OCFR), Part 71. 73.
[C-6] "Thermal Measurements in a Series of Large Pool Fires", SAND85-1096, Sandia National Laboratories, (August 1987).
[C-7] Gator Utility specifications provided by vendor (publicly available):
http://www.deere.com/en_US/products/equ ipment/gator_utility_vehicles/traditional_utility_vehicles/t_series/th_6 x4_diesel/th6x4diesel.page C.3 WORKSHEET-SPECIFIC INPUT DATA (b)(4)
Holtec Report HI-2 177553 C-2 Holtec Project 5025 Page 63 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEe PR:SPR:IETJltR:Y lfdl"O~fo1>'<1"10f4 IfOL'fEC PROPR:IETARY I~WOR~44TIQ~J C.4 WORKSHEET-SPECIFIC CACULATIONS C.4.1 Calculate Area of Fuel Spread (b}(4)
Holtec Report HI-2 177553 C-3 Holtec Project 5025 Page 64 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 MOl..::rac RliilORliillaTAR.>< l~IFQfilt10+1QM HOLi EC PRO.PJtJE'fAltY fHFORMA'f.IOH (b)(4)
Holtec Report Hl-2177553 C-4 Holtec Project 5025 Page 65 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I 19LH.8 PR:9PR:IETJltf':, 11~1"0,._IOIATIOl'J HOL'fEC filtOPJtlr!'fAlt'I' J~qf"OltMAfJO,q (b)(4)
Holtec Report HI-2 177553 C-5 Holtec Project 5025 Page 66 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOL'f!!e 1'"-0l'R:IETJltR:Y lldFSR:li11JltTISfl AOL l EC PROPlt:f'E'fAflY RffORMATIO~J Appendix D:
Calculation of Heat Flux from Utility Vehicle Tire Fire Holtec Report HI-2177553 D-1 Holtec Project 5025 Page 67 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lEfO fiil.¥ l~llaORU HIO~I Appendix-D-Tire-Fire.xmcd IIOLTIZG PROPRIIZTAzR:Y RWOllMATION D.1 WORKSHEET-SPECIFIC INTRODUCTION The purpose of this calculatiorn is to determine the heat flux from the burning gator/golf cart tire rubber that impinges on the HI-TRAC cask. The procedure is as follows:
rb)(4)
The duration of the burning tire rubber is also determined.
D.2 WORKSHEET-SPECIFIC REFERENCES (D-1] "General Arrangement Vertical Cask Transporter," J&R Engineering Conpany, Inc, Drawing No.
VCT415W081 , Revision 0.
[D-2] Not used (D-3] "HI-TRAC CS Licensing Drawing", Holtec Drawing 10868 Revsion 0.
[D-4] "Fire Test With a Front Wheel Loader", SP Report P801596, 15 October 2008.
[D-5] Howell , J.R. , "A Catalog of Radiation Heat Transfer Configuration Factors," 3rd Edition, online at www. engr. uky. edu/rtl/Catalog/.
D.3 WORKSHEET-SPECIFIC INPUT DATA FOR GATOR TIRE FIRE (b)(4)
Holtec Report HI-2 177553 D-2 Holtec Project 5025 Page 68 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 HOl..:rac PPIQPPIIH.0:RY ltJFBR~1.*:'fl014 Appendix-D-Tire-Fire.xmcd IIOLTEG PROPIHET10rR:Y J.}WORM:ATION D.4 WORKSHEET-SPECIFIC CACULATIONS FOR GATOR TIRE FIRE (b)(4)
Holtec Report Hl-2 177553 D-3 Holtec Project 5025 Page 69 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 IIQbfi<; li'J.ORRIFJO PY lblEORMAIIQN Appendix-D-Tire-Fire.xmcd IIOL'fEC fROFR:iE'fAR:¥ HWORMA'.'fIOH (b)(4)
Holtec Report HI-2 177553 D-4 Holtec Project 5025 Page 70 of 71
ATTACHMENT 15 TO HOLTEC LETTER 5025012 I IOLTEe PRSPRIETARY ltJF9Rt.1.A.Tl9tl Appendix-D-Tire-Fire.xmcd IIOL'fEC F~FR:iE'fARY HWORlolir'fION Attachment 0-1: View Factor Calculation from Reference [D-5):
SECTIONB Factors From Differential Elements to Finite Areas B-11: Pltme element to right circ11lor cyliuder of finite length llllff l'(lt/ius, 11ormlll to element passes Ill rough one end ofo cylinder 011d is perpendicular to cyli11der axis.
OoHlll.llli equation .
Holtec Report HI-2 177553 D-5 Holtec Project 5025 Page 71 of 71
ATTACHMENT 16 TO HOLTEC LETTER 5025012 HOI IFC RRORRIFIORY l~llaQfiilt10 +1QM Holtec Center, One Holtec Drive, Marlton, NJ 08053 Telephone (856) 797- 0900 HOLTEC INTERNATIONAL Fax(856)797-0909 THERMAL EVALUATIONS OF HI-STORM UMAX AT HISTORE CIS FACILITY FOR GENERIC Holtec Report No: Hl-2177591 Holtec Project No: 5025 Sponsoring Holtec Division: NPD Report Class : SAFETY RELATED COMPANY PRIVATE Page 1 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOL'f!!6 PRSPRIETARY ltJF8RJ.1.A.il"l9tl HOLTEC INTERNATIONAL 1
DOCUMENT ISSUANCE AND REVISION STATUS DOCUMENT NAME: THERMAL EVALUATIONS OF HI-STORM UMAX AT HISTORE CIS FACILITY DOCUMENT NO.:
HI-2177591 CATEGORY: D GENERIC PROJECT NO.: PROJECT SPECIFIC 5025 Rev. Date Author's No. 2 A Initials VIR #
0 .Mohammad 918519 DOCUMENT CATEGORIZATION In accordance with the Holtec Quality Assurance Manual and associated Holtec Quality Procedures (HQPs), this document is categorized as a:
~ Calculation Package3 (Per HQP 3.2) 0 Technical Report (Per HQP 3.2)
(Such as a Licensing Report)
D Design Criterion Document (Per HQP 3.4) 0 Design Specification (Per HQP 3.4)
D Other (S ecif ):
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:
DECLARATION OF PROPRIETARY STATUS
[TI Nonproprietary ::J Holtec Proprietary D Privileged Intellectual Property (PIP) niTsaotom
- 1. 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 on the company"s network. The Validation Identifier Record (VIR) 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 including revisions to references 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".
Page 2 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 11etTEe PR:OPR:IHP.R.Y IMlaQPD10IIOM Table of Contents 1.0 Introduction ........................................................................................................................... 1 1.1 Quality Essentials Appl icable to this Report......................................................................... 2 2.0 Methodology and Assumptions ......................................................................................... 12 3.0 Inputs ......................................................................................................................... ......... 19 4.0 Acceptance Criteria ............................................................................................................ 20 5.0 Computer Codes and Calculation Files .............................................................................. 20 6.0 Results and Conclusions .................................................................................................... 20
- 6. 1 Maxi1nu1n Te1nperatures ................................................................................................ 20 6.2 Maximum MPC Cavity Pressures .................................................................................. 2 1 6.3 D ifferential Therma l Expansion ...................................................................................... 22 6.4 Effect of Sustained W ind ............................................................................................... 23 6.5 Thermal Evaluations of Sub-Design Basis Heat Load ................................................... 23 6.6 Fire Accident Condition ................................................................................................. 23 6.7 Off-Normal and Accident Conditions ............................................................................ 24 7.0 References ............................................................. ............................ ................................. 28 Summary of Revisions Revision 0: Initial revision.
Report HI-2 177591 Page i Project 5025 Page 3 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOL'f!!e 1'"-0PR:IETJltR:Y lldFSR:li11JltTl8Pl l.O Introduction This report documents the s ite-specifi c thermal evaluatio ns of HT-STORM UMAX System [1 ]
deployed for long-term storage at HI-STORE CIS facility [2]. The calculations presented in thi s report support the evaluations related to UMAX in Chapter 6 of HI-STORE SAR [2]. HI-STORM UMAX, certified in the USNRC docket # 72-1040 [3], [16] is an underground vertical ventilated system with openings for air ingress and egress and internal air flow passages fo r ventilation cooling ofloaded MPC.
1t is designed to have an MPC sitting inside a thick steel divider shell. The divider shell is insulated to reduce the transmission of decay heat from th e MPC to the down-coming cool air in the annular gap between div ider shell and container shell (CEC). Large inlet passageway allows air flow from the ambient environment to the annular space between MPC shell and divider shell, through !(b)(4) ~ he cooling air rises through the annulus between the divider shell and the MPC enclosure vessel due to the chimney effect created by the transfer of heat from the MPC shell to the air. Th (b)(4)
(b)(4)
_, Large gap between the MPC lid and the VVM closure lid allows efficient heat d issipation from the MPC lid. !(b)(4) I l(b)(4) I
!(b)(4) ~
Two different types of MPCs, MPC-37 and MPC-89, that are licensed previously for storage in HI-STORM FW [4] and HI-STORM U MAX [3] are allowed for storage in UMAX cavity at HI-STORE [l]. The MPCs deployed in HJ-STORM UM AX cavity are exactly the same as those previously approved in HI-STORM FW FSAR [4] and HI-STORM U MAX FSAR [3].
With respect to normal storage in the HI-STORM U MAX Version C cav ities at HI-STORE, it is recognized that the max imum heat load in any canister cannot exceed the limit in the transport cask that will be used to bring the canisters to the HI-STORE CIS site. These canisters are already backfi lled w ith helium and some already under dry storage at power p lants from where they are transported to the H I-STORE faci lity. As the heat removal capacity of the ventilated H I-STORM UMAX system is s ubstantially in excess of the (unventilated) transport cask (viz., HI-STAR 190 [5]) that will be used to fetch the canisters, the peak cladding temperatures are expected to remain well below the normal, off-normal and accident conditions of storage postulated in NUREG-1567 [6] and NUREG-1536 [7]. The max imum allowable decay heat for storage in MPC-37 and MPC-89 are provided in Tables 1.1 and 1.2 respectively. Initial helium backfill range to which these canisters were backfilled is provided in Tables 1.3 and 1.4.
The interim storage of the canisters w ill occur in the H I-STORM U MAX Version C VVMs. The thermal-hydraulic configuration of the HI-STORM UMAX Version C VVMs at HI-STORE is essentially identical to Version B that is certified in the HI-STORM UMAX ECO [16].
Therefore, its heat rej ection capacity would be virtually identical under identical conditions to Report HI-2177591 Page 1 Project 5025 Page 4 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIETARY ltJFORM,\TIOtl that analyzed and certified in [3] under all operation modes. However, the Design Basis heat load and the ambient temperature metrics for the HI-STORE ISFSI are less challenging than those for which the system is certified in [3]. Therefore, it is expected that the heat rejection performance of the canisters at the HI-STORE ISFSI will have even greater margins to the regulator-prescribed limit than that established in [3]. To ascertain this, long-term storage of can isters in HI-STORM UMAX with site-specific conditions from Table 1.5 is evaluated in th is report.
1.1 Quality Essentials Applicable to this Report This section contains quality related information on this document in conformance with the provisions in Holtec's Quality Assurance program.
1.1.1 Document Classification and QA Protocol This document is classified as "Safety Significant" under Holtec International 's quality assurance system. In order to gain acceptance as a safety-significant document in the company's quality assurance system, this document is required to undergo a prescribed review and concurrence process that requires the preparer and reviewer(s) of the document to answer a long list of questions crafted to ensure that the document is purged of all errors of any material significance. A record of the review and verification activities is maintained in e lectronic form within the company's network to enable future retrieval and recapitulation of the programmatic acceptance process leading to the acceptance and release of this document under the company's QA system. Among the numerous requirements that this document must fulfill, as applicable, to muster approval within the company's QA program are:
- The preparer(s) and reviewer(s) are technically qualified to perform their activities per the applicable Holtec Quality Procedure (HQP).
- The input infonnation utilized in the work effort is drawn from referencable sources. Any assumed input data is so identified.
- All significant assumptions are stated.
- The analysis methodology is consistent with the physics of the problem.
- Any computer code and its specific versions used in the work are forma lly admitted for use within the company's QA system.
- The fonnat and content of the document is in accordance with the applicable Holtec quality procedure.
- The material content of the calculation package is understandable to a reader with the requisite academic training and experience in the underlying technical disciplines.
Report HI-2177591 Page 2 Project 5025 Page 5 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 lafOl..+aC li'R.Oli'R.laH.R.Y 1*JFQfilt10+IQM Once a safety significant document, such as this calculation package, completes its review and certification cycle, it should be free of any materially significant error and should not require a revision unless its scope of treatment needs to be altered. Except for regulatory interface documents (i.e., those that are submitted to the NRC in support of a license amendment and request), editorial revisions to Holtec safety-significant documents are not made unless such editorial changes are deemed necessary by the Holtec Project Manager to prevent erroneous conclusions from being inferred by the reader. In other words, the focus in the preparation of this document is to ensure correctness of the technical content rather than the cosmetics of presentation.
In accordance with the foregoing, this Calculation Package is prepared pursuant to the revisions of Holtec Quality Procedures HQP 3.0 and 3.2, which require that all anal yses utilized in support of the design of a safety-related or important-to-safety structure, component, or system be fully documented such that the analyses can be reproduced at any time in the future by a specialist trained in the discipline(s) involved. HQP 3.2 sets down a rigid format structure for the content and organization of Calculation Packages that are intended to create a document that is complete in tenns of the exhaustiveness of content. The Calculation Packages, however, lack the narrational smoothness of a Technical Report, and are not intended to serve as a Technical Report.
Because of its function as a repository of all analyses performed on the subject of its scope, this document will require a revision only if an error is discovered in the computations or the equipment design is modified. Additional analyses in the future may be added as numbered supplements to this Package. Each time a supplement is added or the existing material is revised, the revision status of this Package is advanced to the next number and the Table of Contents is amended. Calculation Packages are Holtec proprietary documents. They are shared with a client only under strict controls on their use and dissemination.
This Calculation Package will be saved as a Permanent Record under the company's QA System.
1.1.2 Quality Validation Questionnaire The questionnaire below is a distilled version of the vast number of questions that the preparer and reviewer of a Holtec safety-significant report must answer and archive in the Company's network to gain a VIR number (the identifier of QA pedigree in Ho Itee's electronic configuration control system).
An affirmative answer (unless the question is "not applicable" or NA) to each of the following questions by the preparer of the report (or editor of a multi-author document) is an essential condition for this document to merit receiving a QA validated status.
Report HI-2177591 Page 3 Project 5025 Page 6 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 HOI IFC PROPRIETARY lb1EOP&4AIIOM
Response
Criterion Yes or No 1 Are you qualified per HQP 1.0 to perform the analysis documented in Yes this report?
Are you aware that you must be specifically certified if you use any 2 Category A computer code (as defined in HQP 2.8 in the preparation Yes of this document?
3 Are you fully conversant with the pertinent sections of the appli cable Yes Specification invoked in this report?
4 Ts the input data used in this work fully sourced (i.e., references are Yes provided)?
5 Are you fully conversant with the user manual and validation manual Yes of the code(s) used in this report, if any?
6 Are Category A computer code(s) (if used) listed in the Company's Yes "Approved Computer program list"?
7 Are the resu lts clearly set down and do they meet the acceptance Yes criteria set down in the governing Specification?
Are you aware that you must observe all internal requirements on 8 needed margins of safety published in Holtec's internal memos, if Yes applicable (which may exceed those in the reference codes and standards or the specification)?
Have you performed numerical convergence checks to ensure that the 9 Yes solution is fu lly converged?
10 ls it true that you did not receive more than 10 qual ity infraction points Yes in the past calendar year or thus far this year?
1.1.3 Computer Codes Used in this Work Holtec International maintains an active list of QA validated computer codes on the Company's network that are approved for use in Safety significant projects. The table below identifies the Code and its version (listed in the ACPL) that has been used in this work effort.
Report HI-2177591 Page4 Project 5025 Page 7 of 31
ATTACHMENT 16 TO HO LTEC LETTER 5025012 WQI..TliiC f21ilQf2R,l liiTO r.,y l~J J;QR, P4 OTIQ~I Generic Report & ACPL Information Generic Report # invoked in this Cale Package, NIA if applicable Code name (must be listed in the ACPL) FLUENT Code version# (must be approved in the ACPL) 14.5.7 Computer ID # (must be approved in the ACPL (b)(4) for the applicable code name and version)
ACPL Rev # & date of issue Report HI-2177591 Page 5 Project 5025 Page 8 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOLTEe PR.OPRIET.A:RV ltJFQfilt1ATIO~I Table .1.1: MPC-37 Allowable Decay Heat Load Patterns [2]
Maximum Decay Heat Region Total Canister Heat Load Pattern Load per Assembly (kW)
(Note 1) (kW)
(Note 2) 1 0.38 1 2 1.7 3 1.82 3 0.50 1 0.42 2 2 1.54 32.02 3 0.61 1 0.61 3 2 1.23 32.09 3 0.74 1 0.74 4 2 1.05 32.06 3 0.8 I 0.8 5 2 0.95 32.04 3 0.84 I 0.95 6 2 0.84 3 1.43 3 0.8 Note 1: For basket region numbering scheme refer to Figure 1.1.
Note 2: Sub-Design Basis Heat Load is defined as 80% of the design basis heat load in every storage location defined herein.
Report HI-2 177591 Page 6 Project 5025 Page 9 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 HAI IEC PROPRIETARY INEORb4AIION Table 1..2: MPC-89 Allowable Decay Heat Loads r2J Maximum Decay Heat Region Total Canister Heat Load Pattern Load per Assembly (kW)
(Note 1) (kW)
(Note 2) 1 0.15 l 2 0.62 32.15 3 0.15 1 0.18 2 2 0.58 32.02 3 0.18 l 0.27 3 2 0.47 32.03 3 0.27 l 0.32 4 2 0.41 32.08 3 0.32 l 0.35 5 2 0.37 31.95 3 0.35 Note I : For basket region numbering scheme refer to Figure 1.2.
Note 2: Sub-Design Basis Heat Load is defin ed as 80% of the design basis heat load in every storage location defined herein.
Report HI-2177591 Page 7 Project 5025 Page 10 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IQb+aC li'RORRIEIARY l!>IFOBMAIIQN Table 1.3: Initial MPC Helium Backfill Specification Requirements for Design Basis Heat Loads [2], [5]
MPCType Pressure Range (Note 1)
MPC-37 2: 39.0 psig and :::: 46.0 psig MPC-89 2: 39.0 psig and :::: 47.5 psig Note 1: Helium used for backfill of MPC shall have a purity of 2: 99 .995%. The pressure range is based on a reference temperature of 70°F.
Table 1.4: Initial MPC Helium Backfill Specification Requirements for Sub-Design Basis Heat Loads [2] , [5]
MPCType Pressure Range (Note 1)
MPC-37 2: 39.0 psig and :::: 50.0 psig MPC-89 2: 39.0 psig and :::: 50.0 psig Note l : Helium used for backfill of MPC shall have a purity of 2: 99.995%. The pressure range is based on a reference temperature of 70°F.
Note 2: Sub-Design Basis Heat Load is defined as 80% of the design basis heat load in every storage location defined in Tables 1.1 and 1.2 for MPC-37 and MPC-89 respectively.
Report HI-2 177591 Page 8 Project 5025 Page 11 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOL'f!!e 1'"-0P:R:IETJltR:Y lldFSR:li11JltT1SPl Table 1.5: Thermally Significant Parameters for the HI-STORM UMAX ISFSI at HI-STORE CIS Facility Thermally Significant ISFSI parameter Value (2)
Maximum Aggregate Heat Load, kW Tables 1.1 and 1.2 Normal Ambient Temperature, °F 62 Elevation, ft 5000 (Note I)
Minimum Ambient Temperature, °F -1 I Off-normal Ambient Temperature, 0 P 91 Accident Ambient Temperature, 0 P 108 Note l: Elevation above sea level adopted for thermal evaluations conservatively bounds the site maximum elevation of 3540 feet [2].
Report HI-2177591 Page 9 Project 5025 Page 12 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 lafOl..+aC li'fiil.Oli'fiil.la::ro fiil.¥ l~llaORU HIO~I 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 1.1: MPC-37 Region-Cell Identification Report HI-2 177591 Page 10 Project 5025 Page 13 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 IIQb+iQ PR.Oli!R.llii.TORY lbl50PD1AIIOM 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 2-17 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 Legend Region-3-38 3-39 3-40 Cell ID Figure 1.2: MPC-89 Region-Cell Identification Report HI-2177591 Page 11 Project 5025 Page 14 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 HOI IEC PBOPBIFIABY INFQRMATION 2.0 Methodology and Assumptions Thermal evaluations of MPC-89 are bounded by MPC-37 under heat load patterns provided in Tables 1.1 and 1.2 as has been demonstrated in Section 3.3 of HT-STAR 190 SAR [5 . (b)(4)
(b)(4)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _....Thermal analyses of normal storage conditions are carried out for three different active fuel assembly lengths referred to as short, standard and long fuel in Chapter 4 of HI-STORM UMAX FSAR [3]. The licensing basis MPC corresponds to MPC-37 with short fuel i.e.!(b)(4) I as was demonstrated in Chapter 4 of HI-STORM UMAX FSAR [3] and HI-STORM FW FSAR [4]. The storage cavity depth is made fixed (not variable, as permitted in the general UMAX certification
[2]) at two discrete dimensions [l]. MPCs up to a certain maximum height can be placed within Type SL of UMAX Version C while MPCs taller than that will be placed within Type XL. See Table 2.1 which shows the maximum MPC heights allowed in each type and the minimum axial gap between the MPC and UMAX VVM cavity. As can be seen from Table 2.1, axial gap between the tallest MPC and UMAX cavity is still at or below the axial gap used in the licensing basis calculations presented in generic UMAX FSAR [3], [16]. Therefore, this change in depth of UMAX cavity between versions B and C will have no negative impact. This report presents the most limiting thermal scenario i.e. MPC-37 with short fuel placed in UMAX Version C Type SL. The justification on why this scenario is thermally most lim iting is provided below:
- a. MPC-37 with short fuel results in highest PCT and component temperatures as demonstrated in Section 4.4 of HI-STORM UMAX FSAR [3].
- b. Active fuel height of short fuel is lowest among short, reference and long fue l assemblies.
For the same heat load, lower active height results in higher heat load density.
- c. Additionally, MPC-37 with short fuel also bounds the MPC-37 with ""'(b"""' ! )(4'")'---------.
!(b)(4) Ias has been demonstrated by thermal evaluations in Section 4.5 of HI-STORM FW FSAR [4].
The axial air gap does not have a significant impact on heat diss ipation from the MPC, as long as it is large enough to accommodate the airflow from the annular gap between MPC and divider shell to the open channel inside the closure lid. Therefore, the airflow resistance in UMAX version C design is expected to be similar or lower than the UMAX version B design. However, the variation of axial gap in Version C design due to the different MPC heights is expected to have a small effect on the airflow, considering the large gap existing for all MPC heights in version C.
The thermal model is exactly the same as that adopted in HI-STORM UMAX FSAR [ 16] except the following changes:
Report HI-2177591 Page 12 Project 5025 Page 15 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 F!OLT!!C 1'"-e:'JPR:IETARY ltJF9Rt1 A+IO~I l(b)(4)
For each type of MPC, the model of fuel assembly, basket and MPC vessel follows the same methodology and assumptions presented in Chapter 4 of HI-STORM FW FSAR [4]. The methodology used in this report is essentially same as that in HI-STORM UMAX FSAR [3]. To ensure an adequate representation of the features of MPC-37, fuel basket within MPC-37 and the HI-STORM UMAX system,. a quarter-symmetric 3-D geometric model is constructed using the FLUENT CFD code pre-processor (GAMBIT) [10], as shown in Figures 2. 1 and 2.2. A 3-D model is constructed for thermally most limiting MPC i.e. MPC-37 with short fuel. The 3-D model implemented to analyze the HI-STORM UMAX Version C system has the following key attributes:
(b)(4)
The cross-section view of the quarter-symmetric 3-D geometric model is shown in Figure 2. 1.
An isometric view is shown in Figure 2.2. The 3-D model has the following major assumptions that render the results conservative. In addition to the assumptions that are relevant to MPC Report HI-2177591 Page 13 Project 5025 Page 16 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOLTEe PR:OPR:IH.0.i;iy 1*JFQliWOIIOM thennal model (presented in Section 4.4 of HI-STORM FW FSAR [4]) and UMAX VVM thennal model (presented in Section 4.4 of HI-STORM UMAX FSAR [3]), following assumptions are made in thermal evaluations presented in this report:
(b)(4)
Report HI-2177591 Page 14 Project 5025 Page 17 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOLTEe PR:SPR:IETJltR:Y lfdl"O~fo1>'<1"10f4 (b)(4)
Thermal evaluations presented in Chapter 3 of HI-STAR 190 SAR [5] clearly demonstrate that heat load pattern 1 in MPC-37 resu lts in bounding peak cladding temperatures. Therefore, heat load pattern 1 presented in Table 1.1 above is adopted for Jong-term storage evaluations presented in this report.
Report HI-2 177591 Page 15 Project 5025 Page 18 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I ISLTEe 1'"-el'"-l!!TAPU il<JFURIVIA I IOIQ Table 2.1: Allowable MPCs in Different Types of UMAX Version C Minimum Axial Gap UMAX Version UMAX Cavity Maximum Allowable Between MPC and CType Height (in) [1] MPC Height (in) [1]
UMAX Lid (in)
(b)(4)
SL XL NotP 1* The minimum axial gap between MPC and HI-STORM UMAX in [3] isl(b)(4) I 4
(b)( ) I. Therefore the minimum axial gap between MPC and UMAX at HI-STUK..b 1s larger than that was adopted for licensing basis calculations in generic UMAX FSAR [3].
Report HI-2 177591 Page 16 Project 5025 Page 19 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I 19LTE9 PR:9PR:IET.A:R:Y ltJF8RMNfl8tl (b)(4)
Figure 2.1: Cross-Sectional View of 3D Quarter Symmetric Model of HI-STORM UMAX Version C with MPC-37 Report HI-2177591 Page 17 Project 5025 Page 20 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 HOI IFC PROPRIFIOPY lblEORD10IIO~I (b)(4)
Figure 2.2: Isometric View of 3D Quarter Symmetric Model of HI-STORM UMAX Version C Type SL with Short MPC-37 Report HI-2 177591 Page 18 Project 5025 Page 21 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 AOL I ee l'llllt.Ol'Pll!.IET)!(llllt., il~l'SRli11..."fiSl4 3.0 Inputs As mentioned earlier, the M PC model is the same as that previously approved by USNRC in HT-STORM UMAX FSAR [3] and HI-STORM FW FSAR [4]. The principal input data for the storage overpack i.e. HI-STORM UMAX VVM at HI-STORE CIS facility, used in these analyses, are taken from design drawing [l ].
A ll physical properties of the materials used for the simulation of the fuel assemblies, basket and MPC-37 vessel are specified in Section 4.2 of HI-STORM UMAX FSAR [3]. The physical properties of the common materials present within Hi-STORM UMAX, such as carbon steel and concrete are same as that specified in specified in Section 4.2 of HI-STORM UMAX FSAR [3].
The physical properties of insulation are also provided in Section 4.2 of H I-STORM UMAX FSAR [3]. Thermal conductivity of insulation adopted in the thermal evaluations presented in this report j(b)(4) jpresented in the UMAX FSAR [9].
The design ambient temperature used in the analysis of long-term storage is provided in Table 1.5. The bottom of the HI-STORM UMAX overpack base is assumed supported on a sub grade at the same temperature as the ambient temperature (Section 2.7 of HI-STORE SAR [2]). Surface emissivity data for key materials of construction are specified in Reference [2]. The thermal loads and applicable environmental conditions are summarized in Table 1.5.
(b)(4)
(b)(4) he effective planar an ea capac1 y o fue l assembly are calculated in Reference (b)(4)
Report HI-2 177591 Page 19 Project 5025 Page 22 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 HOI IFC RROli!R.llii.TO R.Y 1*JF9RM.O.:fl8Pl 4.0 Acceptance Criteria The acceptance criteria are stated below:
- 1. The fuel cladding temperature for long term storage shall be limited to 400°C (752°F).
- 2. The fue l cladding temperature for short-term operations shall be limited to 400°C (752°F) for high burnup fu el and 570°C (I 058°F) for moderate burnup fuel.
- 3. The fuel cladding temperature should be maintained below 570°C (1058°F) for off-normal and accident conditions.
- 4. The internal pressure of the system should remain within its design pressures for normal, off-normal, and accident conditions. The design pressure is specified in Chapter 4 of HI-STORE SAR [2].
- 5. The MPC and UMAX component materials should be maintained within their minimum and maximum temperature criteria under nonnal, off-normal, and accident conditions.
Material temperature limits are provided in Section 4.4 of Chapter 4 of SAR [2].
5.0 Computer Codes and Calculation Files ANSYS FLUENT version 14.5.7 is used to perform CFO calculations documented in this report.
A list of computer fil es supporting the calculations is provided below:
(b)(4) 6.0 Results and Conclusions 6.1 Maximum Temperatures A steady state thermal analysis of the governing "thermal configuration" (meaning the combination of canister type, heat load pattern and fuel type that produces highest fuel cladding Report HI-2177591 Page 20 Project 5025 Page 23 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 AOL I EC PP'!.0" P'!.i !!TJltR:Y itJ F9Rt 1o+10~1 temperature) was perfonned using the 3-D FLUENT model described in Section 2.0 to quantify the thermal margins under long term storage conditions. To summarize, thermal analyses of the MPC-37 with short fuel under heat load pattern l provided in Table 1.1 is perfonned.
The maximum spatial values of the computed temperatures of the fuel cladding, the fuel basket material, the divider shell, the closure lid concrete, the MPC lid, the MPC shell and the average air outlet temperature are summarized in Table 6.1 . The following conclusions are reached from the solution data:
- a. The PCT is well below the temperature limit set forth in ISG-1 1 Rev 3 [11].
- b. The maximum temperatures of all MPC and VVM constituent parts are also below their respective limits set down in Section 4.4 of HI-STORE FSAR [2].
It is therefore concluded that the HI-STORM UMAX system provides a thermally acceptable storage environment for all eligible MPCs under all allowable heat load patterns. It should also be noted that the PCT and other component temperatures are well below the licensing basis results presented in Section 4.4 of generic HI-STORM UMAX FSAR [3]. This confirms the assertion made in Section m.0 that the heat rejection performance of the canisters at the HI-STORE ISFSI has even greater margins to the regulator-prescribed lim it than that established in
[3].
6.2 Maximum MPC Cavity Pressures The MPC from HI-STAR 190 is already fi lled with dry pressurized helium. During normal storage in UMAX VVM, the gas temperature within the MPC rises to its maximum operating basis temperature. The gas pressure inside the MPC will also increase with rising temperature.
The pressure rise is determined using the ideal gas law. The MPC gas pressure is also subj ect to substantial pressure rise under hypothetical rupture of fuel rods.
The MPC maximum gas pressure is computed for a postulated release of fission product gases from fuel rods into this free space. The amount of fission gas and fi ll gas release due to rod rupture is exactly the same as that adopted in HI-STORM UMAX FSAR [3] and HT-STORM FW FSAR [4]*. For these scenarios, the amounts of each of the release gas constituents in the MPC cavity are summed and the resulting total pressures determined from the ideal gas law. A concomitant effect of rod ruptures is the increased pressure and molecular weight of the cavity gases with enhanced rate of heat dissipation by internal helium convection and lower cavity temperatures. As these effects are substantial under large rod ruptures the 100% rod rupture accident is evaluated without any credit for increased heat dissipation under increased pressure and molecular weight of the cavity gases. Based on fission gases release fractions (NUREG 1536
- The actual values of fission and :fill gas are provided in input/output files supporting Reference (1 2].
Report HI-2 177591 Page 21 Project 5025 Page 24 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 lafOl..+aC li'R.Oli'R.la::ro i;;i,y 1*JFQfilt10+IQM criteria), rods' net free volume and initial fill gas pressure, maximum gas pressures with 1%
(normal), 10% (off-normal) and 100% (accident condition) rod rupture are given in Table 6.2.
The maximum calculated gas pressures reported in Table 6.2 are all below the MPC internal design pressures for normal., off-normal and accident conditions specified in Chapter 4 of HI-STORE SAR [2]. It should also be noted that the MPC cavity pressure is also bounded by the licensing basis results presented in Section 4.4 of generic HI-STORM UMAX FSAR [3].
6.3 Differential Thennal Expansion Since the component temperatures presented in Section 6. 1 under long-term storage at HI-STORE are bounded by the temperatures presented for the licensing basis scenario in Section 4.4 of HI-STORM UMAX FSAR [3], the differential thern1al expansions will also be bounded by those presented in Section 4.4 of the FSAR [3]. Therefore, it can be concluded that differential growth at HI-STORE is bounded by the design cold gaps.
The differential thermal expansion between basket, basket shims and MPC Shell is explicitly determined fo llowing the methodology provided in previously approved Holtec re port [12]
supporting UMAX FSAR [3]. This calculation is performed to support the basket periphery region hot gap adopted in the thermal evaluations presented in this report. The result from this evaluation is presented in Table 6.3 ~(b)(4)
(b)(4)
(b)(4) __,,!The overstated gap increases the heat resistance and is therefore conservative.
Additional basket design options using solid shim plates between the basket and basket shims are permitted as described in Chapter 1 of HI-STORM FW FSAR [4] and MPC drawing [13].
However, as also noted in Section 4.5 of HI-STORM FW FSAR [4], the most limiting thermal design scenario corresponds to the case when solid shim plates are not present. Therefore, based on those thermal evaluations, it can be concluded that the all design options provided in Chapter 1 of FW FSAR [4] are also acceptable and ensure safe integrity of fuel and MPC confinement boundary.
Report HI-2 177591 Page 22 Project 5025 Page 25 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 lfQLTES PR:9PR:IET.A:R:V ltJF8RMNfl8Pl 6.4 Effect of Sustained Wind Thermal evaluation of sustained wind on HI-STORM UMAX cask arrays at HI-STORE CIS is bounded by that in Sub-section 4.4.9 of the HI-STORM UMAX FSAR [3] due to the follow ing facts:
- The MPC and VVM component temperatures at HI-STORE are lower than that presented for the same MPC in Section 4.4 of the HI-STORM UMAX FSAR [3] under normal long-term storage condition.
- Wind effects at the site [2] are bounded by those evaluated in Sub-section 4.4.9 of the HI-STORM UMAX FSAR [3] due to UMAX evaluation under worst case combination of wind speed and direction.
- The airflow path design ofUMAX Version C [l ] is the same as UMAX Version B [15].
Therefore, the effect of winds summarized in Sub-section 4.4.9 of the HI-STORM UMAX FSAR
[3] remains bounding and is adopted herein. The PCT and other component temperatures under sustained wind cond itions a re confirmed to remain below their respective temperature lim its.
Moreover, the MPC cavity pressure accounting for the effect of wind is also calculated and presented in Table 6.4. Results confirm that it is below the design pressure limit.
6.5 Thermal Evaluations of Sub-Design Basis Heat Load Thermal evaluations in Section 3.3.5 of Hl-STAR I 90 SAR [5] demonstrate that the predicted temperatures and cavity pressures under sub-design basis heat loads is bounded by design maximum heat load scenario. Therefore, the conclusions drawn for design basis heat loads in Sections 6.1 and 6.2 remain appl icable to sub-design basis heat loads also.
6.6 Fire Accident Condition The HT-STORM UMAX fire accident is evaluated for the same conditions described in a separate Holtec report that evaluates the effects of VCT fire on HT-STORM FW System [14].
The fire evaluation for limibng MPC-37 with short fuel length stored in HI-STORM UMAX is bounded by the analysis reported in this report [14] due to the following facts:
- The initial PCT and component temperatures of MPC stored in HI-STORM UMAX at HI-STORE are lower than that of the same MPC in the HI-STORM FW system [4].
- HI-STORM UMAX system has much less surface directly exposed to fire than that of the above-ground system.
Report HI-2 177591 Page 23 Project 5025 Page 26 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOLTEe PR.SPRIET:2:RV ltJFQfilt1A+IO~I
- Amount of combustibles that can cause a YCT fire is the same.
Consequently, the conclusion that PCT and components' ternperatmes and MPC pressure are below temperature and pressure limits for the Design Basis Fire event drawn in th is fire report
[14] wi ll remain valid for the HI-STORM UMAX system.
6.7 Off-Normal and Accident Conditions The predicted temperatures and MPC cavity pressures presented for all the off-normal and accident conditions in Section 4.6 of HI-STORM UMAX FSAR [3] are bounding due to the fo llowing reasons:
- As stated in Section 6.1 of this report, PCT and component temperatures at HI-STORE under long-term storage condition are bounded by those presented for generic UMAX system (Section 4.4 of FSAR [3]).
- As stated in Section 6.2 of this report, MPC cavity pressure at HI-STORE under long-term storage condition is bounded by that presented for MPCs in generic UMAX system (Section 4.4 of FSAR [3]).
- Design basis heat loads (Tables l.1 and l.2) at HI-STORE are well below the design basis maximum heat loads in generic FSAR [3].
Report HI-2 177591 Page 24 Project 5025 Page 27 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 lafOb+m.'3 PR9PRIETJltR., ll~f'O,._lv,A I lvi<J Table 6.1: HI-STORM UMAX Normal Long-Term Storage Temperatures for MPC-37 with Short Fuel under Heat Load Pattern 1 Temperature Temperature Component Limit [3]
oc (OF) oc (OF)
Fuel Cladding 323 (6 13) 400 (752)
MPC Basket 289 (552) 400 (752)
Basket Periphery 244 (471) 400 (752)
Aluminum Basket Shims 224 (435) 400 (752)
MPC Shell 189 (372) 343 (650)
MPC Baseplate' 151 (304) 400 (752)
MPCLid 1 187 (369) 400 (752)
Divider Shell 134 (273) 343 (650)
CEC Shell 44 ( 111) 343 (650)
Closure Lid Concrete2 69 (156) 177 (350)
Insulation 132 (270) 343 (650)
Average Air O utlet3 67 (153) -
1 Maximum section average temperature reported.
2 Maximum section average tempe rature reported.
3 Section average temperature on the cross section area of outlet duct below the outlet vent screen reported.
Reported herein for the option of temperature measurement surveillance of outlet duct air temperature as set forth in the Technical Specifications.
Report HI-2 177591 Page 25 Project 5025 Page 28 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I 19LTE8 PFWPR:IETJl<Fr, IIQl"O~IOIATIOIQ Table 6.2: Summary of MPC Cavity Pressure for Limiting MPC-37 with Short Fuel under Heat Load Pattern 1 MPC Cavity Average Gauge Pressure, Condition Temperature psig 1 oc (OF) no rods mpture 88.2 Normal condition l % rods ruptured 89.2 226 (439)
Off-nonnal (10% rods ruptured) 98.3 Accident ( 100% rods ruptured) 188.7 Note 1: The MPC pressure reported in this table do not include the effect of wind.
Table 6.3: Differential Thermal Expansion during Long-Term Storage for Limiting MPC-37 with Short Fuel under Heat Load Pattern 1 Minimum Gap 113), Differential Expansion, Gap Description mm (inch) mm (inch)
(b)(4)
Fuel Basket-to-MPC Radial Gap 1
The pressures reported in this table are computed assuming the helium backfill pressure is at its upper bound limit (Table 1.3).
Report HI-2177591 Page 26 Project 5025 Page 29 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOLTEO PFl:OPFl:IElP.Fl:Y 1*JFQfiU4ATIO~I Table 6.4: Summary of MPC Cavity Pressure for Limiting MPC-37 with Short Fuel under Heat l oad *eattern 1 nuder Sustained Wind MPC Cavity Average Gauge Pressure, Condition Temperature psig 1 oc (OF) no rods rupture 91.5 Normal condition 1% rods ruptured 92.5 242 (468)
Off-nonnal (10% rods ruptured) 101.8 Accident (100% rods ruptured) 195.0 Note I: The MPC pressure reported in this table includes the effect of wind.
1 The pressures reported in this table are computed assuming the helium backfill pressure is at its upper bound limit (Table 1.3).
Report HI-2177591 Page 27 Project 5025 Page 30 of 31
ATTACHMENT 16 TO HOLTEC LETTER 5025012 I IOLTE9 PPIQPR.IEJORY lb1FORM8IIQN 7.0 References
[1] "HT-STORM UMAX Vertical Venti lated Module Version C", Holtec Drawing l 0875, Revision 0.
[2] HJ-STORE SAR, Holtec Report Hl-2167374, Revision 0.
[3] HI-STORM UMAX FSAR, Holtec Report HI-2115090, Latest Revision.
[4] HI-STORM FW FSAR, Holtec Report HI-2114830, Latest Revision.
[5] HI-STAR 190 SAR, Holtec Report HI-2146214, Latest Revision.
[6] NUREG-1567, Latest Revision.
[7] NUREG-1536, Latest Revision.
[8] "Effective Thermal Properties of PWR Fuel to Support Thermal Evaluation of HI-STORM FW", Holtec Report Hl-2094356, Revision 5.
[9] Holtec Engineering Change Order (ECO) 5021-26, Revision 0.
[10] ANSYS FLUENT Computational Fluid Dynamics Software.
[II] Interim Staff Guidance, ISG-1 I , Revision 3.
[12] "Thermal-Hydraulic Evaluation of HI-STORM UMAX", Holtec Report HI-2114807, Latest Revision.
[l 3] "MPC 37 Enclosure Vessel, Holtec Drawing 6505, Revision 17.
[14] "Evaluation of Effects of Tracked VCT Fire on HI-STORM FW System", Holtec Report HT-2135677, Revision 5.
[15] "HI-STORM UMAX VVM Vertical Ventilated Module Version B", Holtec Drawing 10017, Revision 4.
[16] Holtec Engineering Change Order (ECO) 5021-24, Revision 0.
Report HI-2177591 Page 28 Project 5025 Page 31 of 31
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IOLTES Plil.OPlil.lETAR.¥ l~llaQPD10IIOM Holtec Center, One Holtec Drive, Marlton, NJ 08053 Telephone (856) 797- 0900 HOLTEC INTERNATIO N A L Fax(856)797-0909 HI-STORE CTF THERMAL EVALUATION FOR GENERIC Holtec Report No: Hl-2177597 Holtec Project No: 5025 Sponsoring Holtec Division: NPD Report Class : SAFETY RELATED COMPANY PRIVATE Page 1 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIETARY ltJFORM,\TIOtl HOLTEC INTERNATIONAL 1
DOCUMENT ISSUANCE AND REVISION STATUS DOCUMENT NAME: HI-STORE CTF THERMAL EVALUATION DOCUMENT NO.: CATEGORY: ~ GENERIC HI-2177597 PROJECT NO.:
5025 D PROJECT SPECIFIC Rev. Date Author's No. 2 A Initials VIR #
0 .Huang 67289 DOCUMENT CATEGORIZATION In accordance with the Holtec Quality Assurance Manual and associated Holtec Quality Procedures (HQPs), this document is categorized as a:
~ Calculation Package3 (Per HQP 3.2) 0 Technical Report (Per HQP 3.2)
(Such as a Licensing Report)
D Design Criterion Document (Per HQP 3.4) 0 Design Specification (Per HQP 3.4)
D Other (S ecif ):
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:
DECLARATION OF PROPRIETARY STATUS
[Z] Nonproprietary D Holtec Proprietary D Privileged Intellectual Property (PIP)
This doc ins extremely valuable intellectual property of Holtec International. Holtec'
- e ideas, methods, models, and prec 'bed in this document are protected a ai onzed use, in whole or in part, by any other party under the U.S. and internat10
- al s. Unauthorized dissemination of any part of this document by the recipient will be deemed to a will u ontract governing this project. The recipient of this document bears sole r
- 1y to honor Holtec's unabridged ownership n
- document, to observe its confiden i * , o 1mit use to the purpose for which it was delivered to the recipient. Portions o nt may be Ject to copyright protection against unauthorized reproduction by a third party.
Notes
- 1. 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 on the company"s network. The Validation Identifier Record (VIR) 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 including revisions to references 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".
Page 2 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY lfqfiORMATION IIOUFEC PROPR:fE'fAR:Y IMFOR:MA'.'fI01q PREFACE This section contains quality related information on this document in conformance with the provisions in Holtec's Qual.ity Assurance program docketed with the USN RC (Docket # 71-0784).
This document is classified as "Safety Significant" under Holtec International 's quality assurance system. In order to gain acceptance as a safety significant document in the company's quality assurance system, this document is required to undergo a prescribed review and concurrence process that requires the preparer and reviewer(s) of the document to answer a long list of questions crafted to ensure that the document is purged of all errors of any material significance. A record of the review and verification activities is maintained in e lectronic form within the company's network to enable future retrieval and recapitulation of the programmatic acceptance process leading to the acceptance and release of this document under the company's QA system. Among the numerous requirements that this document must fulfill, as applicable, to muster approval within the company's QA program are:
- The preparer(s) and reviewer(s) are technically qualified to perform their activities per the applicable Holtec Quality Procedure (HQP).
- The input information utilized in the work effort is drawn from referenceable sources.
Any assumed input data is so identified.
- Sign ificant assumptions are stated or provided by reference to another source.
- The analysis methodology is suitable for the physics of the problem.
- Any computer code a nd its specific versions used in the work are formally admitted for use within the company's QA system.
- The content of the document is in accordance with the applicable Holtec quality procedure.
- The material content of the calculation package is understandable to a reader with the requisite academic training and experience in the underlying technical disciplines.
Once a safety significant document, such as this calculation package, completes its review and certification cycle, it should be free of any materially sig nificant error and should not require a revision unless its scope of treatment needs to be altered. Except for regulatory interface documents (i.e., those that are submitted to the regulator in support of a license amendment and request), editorial revisions to Holtec safety significant documents are not made unless such ed itorial changes are deemed necessary by the Holtec Project Manager to prevent erroneous conclusions from being inferred by the reader. In other words, the focus in the preparation of this Report Hl-2 177597 I Project 5025 Page 3 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I 19LTE9 PR:9PR:IET.A:RY ltJF8RMNfl8tl IIOL'fEC PR:OPR:IE'fAR:Y RWOR:f\lb'{'fJOH document is to ensure correctness of the technical content rather than the cosmetics of presentation.
Furthermore, this Calculation Package is focused on providing technical results that demonstrate compliance with the applicable safety limits. Informational material that does not bear upon reaching a safety conclusion is minimized in this document to the extent possible. Because of its function as a repository of all analyses perfonned on the subject of its scope, this document will require a revision only if an error is discovered in the computations or the equipment design is modified. Additional analyses in the future may be added as numbered supplements to this Package. Each time a supplement is added or the existing material is revised, the revision status of this Package is advanced to the next number and the Table of Contents is amended.
Calculation Packages are Holtec proprietary documents. They are shared with a client only under strict controls on their use and dissemination. This Calculation Package will be saved as a Permanent Record under the company's QA System.
Generic Reports Holtec International maintains a number of so-called "generic reports" which provide the methodology, computer models and associated modeling assumptions for a specific physical problem. The technical content of a generic report is fully aligned with the System FSAR, Reg.
Guides, NUREGs, etc., as applicable. In other words, the generic report contains Holtec's standardized analysis approach, method and model to analyze a technical problem. Developed under Holtec's self-funded R&D program, the generic reports are treated as "vital intellectual property" of the Company a nd are accordingly prohibited from dissemination to any external entity. The generic reports are subject to inspection by the NRC's staff at Holtec's corporate headquarters during NRC's triennial inspection of Holtec. The Calculation Package can invoke a Generic Report in whole or in part (see table below) to improve conciseness and to e nable it to be submitted un-redacted to the Company's clients.
Holtec Approved Computer Program List (ACPL)
Holtec International maintains an active list of QA validated computer codes on the Company's network that are approved for use in Safety significant projects. The table below identifies the Codes and applicable versions (listed in the ACPL) that have been used in this work effort.
Generic Report & ACPL Information Generic Report # invoked in this Cale Package, HI-2167374 if applicable Code(s) name(s) (must be li sted in the ACPL) FLUENT Code(s) version# (must be approved in the 14.5.7 ACPL)
Computer ID #(s) (must be approved in the (b)(4)
ACPL for the applicable code name and Report Hl-2 177597 II Project 5025 Page 4 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I 19LTE9 PR:9PR:IET.A:R:Y ltJF8RMNfl8tl vers10n (b)(4)
ACPL Revision # & Date oflssue Quality Validation Questionnaire The questionnaire below is a distilled version of the vast number of questions that the preparer and reviewer of a Holtec safety-significant report must answer and archive in the Company's network to gain a VIR number (the identifier of QA pedigree in Holtec's electronic configuration control system).
An affirmative answer (unless the question is "not applicable" or NA) to each of the following questions by the preparer of the report (or editor of a multi-author document) is an essential condition for this document to merit receiving a QA validated status.
Response
Criterion Yes or No Are you qualified per HQP 1.0 to perform the analysis l Yes documented in this report?
Are you aware that you must be specifically certified if you 2 use any Category A computer code (as defin ed in HQP 2.8 in Yes the preparation of this document?
Are you fully conversant with the pertinent sections of the 3 Yes applicable Specification invoked in this report?
Is the input data used in this work fully sourced (i.e.,
4 Yes references are provided)?
Are you fully conversant with the user manual and validation 5 Yes manual of the code(s) used in this report, if any?
Is (Are) Category A computer code(s) (if used) listed in the 6 Yes Company's " Approved Computer program List"?
Are the results clearly set down and do they meet the 7 Yes acceptance criteria set down in the governing Specification?
Are you aware that you must observe all internal requirements on needed margins of safety published in Holtec 's internal 8 Yes memos, if applicable (which may exceed those in the reference codes and standards or the specification)?
Have you perfonned numerical convergence checks to ensure 9 Yes that the solution is fully converged?
Ts it true that you did not receive more than l O quality 10 Yes infraction points in the past calendar year or thus far this year?
Report Hl-2 177597 111 Project 5025 Page 5 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IE9LTE8 PR:9PR:IHP.R.Y IMlaQliWOIIOM IIOLTEC PROPREETARY ~WORMA:TIO:H TABLE OF CONTENTS 1.0 PURPOSE AN.D SCOPE ..................................................................................................... I 2.0 METHODOLOGY AN D ASSUM PTIONS ........................................................................ 3 3 .0 INPUT DATA ...................................................................................................................... 6 4.0 ACCEPTANCE CRITERIA ................................................................................................ 8 5.0 COMPUTER CODES AND FILES .................................................................................... 9 6.0 RES UL TS AND DISCUSSIONS ...................................................................................... I 0
7.0 REFERENCES
.................................................................................................................. 18 Summary of Revisions Revision 0: Original Issue Report Hl-2 177597 IV Project 5025 Page 6 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIET.A:RV ltJFORJ.1.9.TIOtJ HOL l'EC PROPRIE I AR r INF OltMA'.'flOM 1.0 PURPOSE AND SCOPE At New Mexico consolidated interim storage facility, the loaded MPCs are transferred from HI-STAR 190 [l] to HI-TRAC CS [2] using Canister Transfer Facility (CTF) [3]. This report documents evaluations to demonstrate compliance of all short-term operations involving HI-STAR 190 to the thermal requirements in Chapter 4 of HI-STORE SAR [4].
Before the HI-STAR 190 cask is placed into the CTF, the impact limiters are removed and the cask cavity is evacuated and backfi lled with nitrogen. After the HI-STAR 190 cask is placed into the CTF, the HI-TRAC CS alignment plate is installed on top of the CTF. A thermal evaluation is performed for the therma lly limiting short-term operation condition of HT-STAR 190 inside the CTF as described below:
(1) HI-STAR 190 with MPC is placed inside the CTF. The HI-TRAC CS alignment plate is installed on the CTF.
(2) The Hl-STAR 190 cask closure lid is in place. The HT-TRAC CS cask is not placed in the stack-up position above the CTF.
(3) The cask cavity is filled with nitrogen.
The closure lid of the HI-STAR 190 cask is then removed. The HI-TRAC CS cask is placed on the alignment plate with its bottom shield gates open. After the MPC is lifted into the HI-TRAC CS cask, the HI-TRAC CS shield gates are closed and the MPC is rested on the shield gates.
The HI-TRAC CS cask is then lifted and placed at a location on the floor that is accessible to the VCT.
After the closure lid is removed, the HT-STAR 190 cask cavity is filled with air. The thermal conductivity of nitrogen is slightly lower than that of air. Therefore, the thermal performance of the HT-STAR 190 cask after its closure lid is removed and before the MPC is lifted into the Hf-TRAC CS cask is bounded by that under the short-term operation condition described above.
Once the MPC is lifted into the HI-TRAC CS cask, the th ermal performance is bounded by those evaluated in Ref. [7].
For hypothetical accident, the worst cask transfer building (CTB) collapse scenario is evaluated as described be low:
( 1) HI-STAR 190 with MPC is placed inside the CTF. The HI-TRAC CS alignment plate is installed on the CTF.
(2) The HI-STAR 190 cask closure lid is in place. The HI-TRAC CS cask is not placed in the stack-up position above the CTF.
Report Hl-2 177597 Project 5025 Page 7 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IQbUiQ PR.QPR.Iii.TO~¥ l~JJ;Q~P4 OTIQ~I IIOLTEC PROPIHETARY :QeJ:fO~ 4.ATIQ}tT (3) The cask cavity is filled with nitrogen.
(4) 90% of the CTF pipe vents and 90% of the CTF cavity top open are blocked by debris
[4].
Report HI-2177597 2 Project 5025 Page 8 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 AOL I EC PROPRIE I ARY IIQFORIVIA I IOl<J 2.0 METHODOLOGY AND ASSUMPTIONS To accommodate all BWR and all PWR canisters, the HI-STAR 190 cask is available in two discrete lengths: Version SL (standard length) and Version XL (extended length) [ l ]. The HI-STAR 190 Version XL has a larger external surface for heat dissipation than that of HI-STAR 190 Version SL, and thus the thermal performance of HI-STAR 190 Version XL is bounded by that of HI-STAR 190 Version SL. According to Ref. [8], the bounding configuration of MPC in 4
vertical orientation is MPC-37 loaded wit~(b)( ) I Therefore, the HI-STAR 190 Version SL containing MPC-37 loaded withl(b)(4) lis adopted to yield bounding results. It bounds the configurations below.
(1) Short fuel in MPC-37 within HI-STAR 190 Version SL (2) Standard fuel in MPC-37 within HI-STAR 190 Version SL (3) Long fuel in MPC-37 within HI-STAR 190 Version XL (4) MPC-89 within HI-STAR 190 Version SL In Appendix F of Ref. [9], HI-STAR 190 Version SL in an open space (without the CTF) 4 containing MPC-37 loaded wit~ (b)( ) lis evaluated. This model is the same as that provided in Section 3.3 of HI-STAR 190 SAR [5]. The 3D quarter-symmetric model of HI-STAR 190 in Appendix F of Ref. [9] is adopted and modified as follows:
(b)(4)
Report Hl-2 177597 3 Project 5025 Page 9 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIETARY ltJFORM,\TIOtl HOLIEC PROPRIE IARl' INFORivlAIION 4
The HI-STAR 190 Version SL is placed r_ _)( _) _ _ _linside CTF [3]. The 3D quarter-symmetric model of HI-STAR 190 Version SL inside CTF is ill ustrated in Figure 2.1 and a 20 cross-section of the CTF cavity is presented in F igure 2.2. The CTF geometry added to the Hl-STAR 190 4
model includes (b)( )
- l. . 4 (b-)( _) _ _ _ _ _ _ _ _ _ ____,~ ith the following key attributes.
(b)(4)
Following Ref. [8], the thermal evaluations are performed fo r the bounding heat load pattern, i.e.
heat load pattern l presented in Table l . l of Ref. [8]. The MPC is initially backfi lled w ith helium in the pressure range specified in Table 1.3 of Ref. [8]. Inside the CTF, the MPC cavity pressure Report Hl-2 177597 4 Project 5025 Page 10 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IQLTES PR.OPR.IETftR.Y lldfSR.lo1'*-Tl514 HOLTJ!C 'PltC'Pltil!'fitlt't tifFOR'lolPr'fIOH increases with the MPC cavity temperature. Using the minimum backfill pressure specified in Table 1.3 of Ref. [8] and the MPC cavity average temperature predicted in Section 6.0, the minimum MPC cavity pressure under the operation conditions is computed by ideal gas law. The MPC cavity pressure adopted in the simulations is slightly lower than the calculated minimum MPC cavity pressure, which understates the thermo-siphon effect inside the MPC cavity and thereby overestimates the peak cladding temperature.
Report HI-2177597 5 Project 5025 Page 11 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 IIQb+aC li'J:.ORRIFIORY lblEORMAIIQN MOL'fr'.C 'PltOl'Itll!TAlt i l!~J\'OltMA I ION 3.0 INPUT DATA The principal geometric parameters for HI-STAR 190, CTF, MPC-37 and basket are taken from design drawings [l], [3], [12] and [13]. Materials present in the HI-STAR 190 cask include (b)(4) l(b)( 4) !The physical properties of these materials are obtained from HI-STAR 190 SAR [5]. The properties of air are also obtained from HI-STAR 190 SAR [5]. The properties of nitrogen are obtained from Ref. [14] and presented in Table 3.1. It is noted that the temperatures of Holtite-8 may be higher than its design temperature li mit under the CTB collapse accident. (b)(4) l(b)(41 The surface emissivities are obtained from HT-STAR 190 SAR [5]. For the HT-STAR 190 cask cavity surface, the emissivity of carbon steel without paint is assumed for conservatism.
(b)(4)
The CTF is inside the cask transfer building and thus there is no insolation. The ambient temperature adopted in the evaluations is 32.8°C (91 °F), as specified in HT-STORE SAR [4]. The ambient pressure adopted in the evaluations isl(b)(
4
) I which is conservatively lower than the actual ambient pressure at the site elevation specified in HI-STORE SAR [4]. The limiting heat load pattern and the corresponding MPC backfill pressure range as descried in Section 2.0 are adopted to yield bounding results.
Report Hl-2177597 6 Project 5025 Page 12 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 AOL I EC PROPRIE I AR i ii~P'O,._IOIATIOl4 IIOUFEC PR:OPRIB'fAftY f!qP'OJtMkTION Table 3.1 Properties of Nitrogen (14]
Thermal Viscosity Temperature Conductivity 6 oc (OF) 10" N-s/m W/m-°C (Micropoise)
(Btu/ft-hr-°F) 76.85 0.0293 20.00 (170.33) (0.0169) (200.0) 126.85 0.0327 22.04 (260.33) (0.0189) (220.4) 226.85 0.0389 25.77 (440.33) (0.0225) (257.7) 326.85 0.0446 29.08 (620.33) (0.0258) (290.8)
Density (Ideal Gas Law) kg/m 3 (lbm/ft3 )
Specific Heat 1041 (0.249)
J/kg-°C (Btu/lbm-°F)
Report Hl-2 177597 7 Proj ect 5025 Page 13 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 HOLT!!C P: P'!.e:'Jl"P'!.IETJltR:Y ltJF8RPeV.il"l9tl HOLT~C 'PltOPIUJ!l'AftY tNfOft~tATION 4.0 ACCEPTANCE CRITERIA The thermal evaluation acceptance criteria are listed below:
I. The fue l cladding temperature during short-term operations and accident conditions must be below the ISG-11 Revision 3 temperature limit [6].
- 2. The component temperatures of basket, MPC and HI-STAR 190 must be below their respective design temperature limits specified in Ref. [4] for short-term operations and accident conditions.
- 3. The MPC cavity pressure (MNOP) must be below the design pressure specified in Ref.
[4] for short-term operations and accident conditions.
- 4. The CTF component temperatures must be below the design temperature limits specified in Ref. [4] for short-term operations and accident conditions.
Report HI-2 177597 8 Proj ect 5025 Page 14 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IOL'fEe PRSPRIETARY ltJF8RJ.1.A.Tl9tl IIOL"FEC PROPRIE'fARY RWOR:f\lf!{'fJOH 5.0 COMPUTER CODES AND FILES The computer code FLUENT Version 14.5 [1 1) is employed in all thermal calculations involving fluid motion. A list of computer files is provided below.
(b)(4)
Report Hl-2 177597 9 Proj ect 5025 Page 15 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lEfO Iii.¥ 1*JFQfilt10+IQM HOC'r~c 'PftO'Pftfr'.'fAtt7f fl~FOltMA'.'flOH 6.0 RESULTS AND DISCUSSIONS 6.1 Thermal Evaluation o(Short-Term Operation A steady state simulation is performed for the short-term operation scenario described in Section 1.0. The evaluation is performed for most limiting thermal configuration under the bounding heat load pattern, as described in Section 2.0. The predicted fuel temperature and component temperatures are presented in Table 6.1. The fuel temperature and component temperatures are below their limits specified in Section 4.0 for short-term operation.
6.2 Thermal Evaluation of CTB Collapse Accident A steady state simulation is performed for the worst CTB collapse accident scenario described in Section 1.0. The evaluation is performed for most limiting thermal configuration under the bounding heat load pattern, as described in Section 2.0. The predicted fuel temperature and component temperatures are presented in Table 6.2. The fuel temperature and component temperatures are below their limits specified in Section 4.0 for accident condition.
6.3 Maximum Normal Operation Pressure (MNOP)
For heat load pattern 1 presented in Table 1.1 of Ref. [8], the MPC is initially backfilled with he lium in the pressure range spec ified in Table 1.3 of Ref. [8]. Inside CTF, the MPC cav ity pressure increases as the MPC cavity temperature increases. Using the maximum backfill pressure specified in Table 1.3 of Ref. [8] and the MPC cavity average temperatures predicted in Sections 6. 1 and 6.2, the maximum MPC cavity pressures are determined by ideal gas law and presented in Table 6.3.
6.4 Differential Thermal Expansion In this section, thermal expansion of components inside HI-STAR 190 in the radial and axial directions is computed. The calculations address the following thermal expansions:
a) Basket-to-MPC Radial Growth b) Basket-to-MPC Axial Growth c) Fuel-to-MPC Axial Growth d) MPC-to-Cask Radial Growth e) MPC-to-Cask Axial Growth (a) Basket-to-MPC Radial Growth Report Hl-2 177597 10 Project 5025 Page 16 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I 19LTE9 PR:9PR:IET.A:R:l/ ltJF8RMNfl8tl MOL'fr'.C 'r!tOPIUJ!'fAtt7f f!qP'O!tMA'.'fI01q The radial growth of the fuel basket relative to MPC cavity upon heating from a 21 °C (70°F) reference temperature (T0 ) to hot operation temperatures is computed as follows:
(b)(4)
I (Eq. 6.1 )
(b) Basket-to-MPC Axial Growth The axial growth of the fuel basket relative to MPC cav ity upon heating from a 21 °C (70°F) reference temperature to bot operation temperatures is computed as follows:
(b)(4)
I (Eq. 6.2)
(c) Fuel Axial Growth The axia l growth of the fuel relative to MPC cavity upon heating from a 21 °C (70°F) reference temperature to hot operation temperatures is computed as follows:
11')(4) I (Eq. 6.3)
Report Hl-2 177597 11 Project 5025 Page 17 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 HAI I EC RRORRIFIOPY lb1EOP&4AIIOM HOLTE( PR.QPlUIH ARY Il>IFOR MA IIQN (b)(4)
(d) MPC-to-Cask Radial Growth The radial growth ofMPC relative to HI-STAR 190 cask cavity upon heating from a 21°C (70°F) reference temperature to hot operation temperatures is computed as follows:
l(b)(4) I (Eq. 6.4)
(b)(4)
(e) MPC-to-Cask Axial Growth The axial growth of MPC relative to HI-STAR 190 cask cavity upon heating from a 21°C (70°F) reference temperature to hot operation temperatures is computed as follows:
(b)(4)
I (Eq. 6.5)
Report Hl-2 177597 12 Proj ect 5025 Page 18 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIET.A:RV ltJFORJ.1.9.TIOtJ I IOL'fEC f'ftOf'IUB'fAftY flqf?6JtMA'.'fI01q
- 6. 5 Discussion and Conclusion Based on the results presented in Sections 6.1 thru 6.4, the following conclusions are drawn:
- l. During short-term operation inside CTF, the fuel cladding temperature and the MPC and cask component temperatures remain below their short-term temperature limits indefinitely. The MPC cavity pressure also remains below its short-term pressure limit.
- 2. Under CTB collapse accident event, the fuel cladding temperature and the MPC and cask component temperatures remain below their accident temperature li mits. The MPC cavity pressure also remains below its accident pressure limit.
- 3. Free thermal expansion is ensured for fuel, basket and MPC for both short-term operation and CTB collapse accident event.
Thermal evaluations in Section 3.3.5 of HI-STAR 190 SAR [5] demonstrate that the predicted temperatures and cavity pressures under sub-design basis heat loads is bounded by design maximum heat load scenario. Therefore, the above conclusions remain applicable to sub-design basis heat loads also.
Report Hl-2 177597 13 Project 5025 Page 19 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 AOL I EC PP'!.0" P'!.I !!TJltR:Y ltJ F9RMO +IQM IIOLTEC PROPRIE'fARY RWOltMA'.'fI01q Table 6.1 Maximum Temperatures of HI-STAR 190 and MPC-37 during Short-Term Operation inside CTF Temperature Material/Components oc (OF)
Fuel C ladding 380 (716)
Fuel Basket 353 (667)
Basket Shims 292 (558)
MPC Shell 262 (504)
MPC Baseplate (Section Average) 202 (396)
MPC Lid (Section Average) 257 (495)
Containment Shell 196 (385)
Lead Shield 194 (38 1)
Intermediate Shell 192 (378)
Holtite-B Shield 191 (376)
Enclosure Shell 169 (336)
Bottom Forging (Maximum) 199 (390)
Bottom Forging (Volumetric Average) 160 (320)
Bottom Forging Lead Shield 197 (387)
Bottom Forging Holtite-B Shield 157 (315)
Bottom Forging Cover Plate 154 (309)
Bottom Holtite-B Shield 196 (385)
Top Forging (Maximum) 144 (291)
Top Forging (Volumetric Average) 129 (264)
Top Forging Holtite-B Shield 142 (288)
Spacer Ring 208 (406)
Closure Lid Spacer 148 (298)
Closure Lid (Maximum) 128 (262)
Closure Lid (Section Average) 122 (252)
CTF Structures 147 (297)
Report Hl-2 177597 14 Proj ect 5025 Page 20 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 lafOl..+aC li'R.Oli'R.la::ro i;;i,y 1*JFQfilt10+IQM IIOLTEG PROPFdE'fARY RWOltMA'.'fI01q Table 6.2 Maximum Temperatures of HI-STAR 190 and MPC-37 under CTB Collapse Accident inside CTF Temperature Material/Components oc (OF)
Fuel C ladding 461 (862)
Fuel Basket 434 (813)
Basket Shims 376 (709)
MPC Shell 351 (664)
MPC Baseplate (Section Average) 277(53 1)
MPC Lid (Section Average) 332 (630)
Containment Shell 311 (592)
Lead Shield 309 (588)
Intermediate Shell 307 (585)
Enclosure Shell 288 (550)
Bottom Forging (Maximum) 273 (523)
Bottom Forging (Volumetric Average) 228 (442)
Bottom Forging Lead Shield 271 (520)
Bottom Forging Cover Plate 210 (410)
Top Forging (Maximum) 264 (507)
Top Forging (Volumetric Average) 250 (482)
Spacer Ring 299 (570)
Closure Lid Spacer 266 (51 1)
Closure Lid (Maximum) 253 (487)
Closure Lid (Section Average) 246 (475)
CTF Structures 276 (529)
Note: T he temp erature of Ho ltite is above its design temperature limit a nd is therefore replaced with air in the thermal model.
Report Hl-2 177597 15 Project 5025 Page 21 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IE,LTEeJ FR:eJF"1.ll'.'.T)!("1. I IIQFORIMI ldl<l HOLi EC PROPRIEIARr INFORlvvtllON Table 6.3 MNOP of Helium in MPC and ID-STAR 190 inside CTF Cavity Average Gauge Pressure Condition Temperature kPa (psig) oc (OF)
Short-term Operation 705 .3 (102 .3) 294(561)
CTB Collapse Accident 817.7 (118 .6) 373 (703)
Report HI-2177597 16 Project 5025 Page 22 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 HQI IFC PBOPRIFJORY l~l laQfilM.*.il"l9Pl IIOUFEC PR:OPRIB'fAfFf f!qP'OltMkTION Table 6.4 Differential Thermal Expansion of MPC and HI-STAR 190 inside CTF Differential Expansion (V)
Cold Gap (U) mm (inch) Is Free Expansion Gap Description mm (inch) Criteria Satisfied CTB (note- l ) Short-Term (i.e. U > V)
Collapse Operation Accident Fuel Basket-to-MPC (b)(4)
Radial Gap (minimum)
Fuel Basket-to-MPC Axial Gap (nominal)
Fuel-to-MPC Axial Gap (nominal)
MPC-to-Cask Radial Gap (nominal)
MPC-to-Cask Axial Gap (nominal)
(b)(4)
Report Hl -2 177597 17 Project 5025 Page 23 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 PIOLT!!e PR.8PFl:IH.0,i;;iy l~lliiARMAI!OM IIOL'fEC PROPRIETARY H'ffORMA:TIO:H
7.0 REFERENCES
[ I] "HI-STAR 190 Cask Assembly," Holtec Drawing 9841, Revision 0.
[2] "HI-TRAC CS," Holtec Drawing 10868, Revision 0.
[3] "Canister Transfer Facility (CTF)," Holtec Drawing I 0895, Revision 0.
[4] "Licensing Report on the HT-STORE CTS Facility., " Holtec Report HT-2167374, Revision 0.
[5] "Safety Analysis Report on the HT-STAR 190 iPackage," Holtec Report HI-2146214, Latest Revision.
[6] "Cladding considerations for the Transportation and Storage of Spent Fuel," Interim Staff Guidance-I 1, Revision 3, USNRC, Washington, DC
[7] "Thermal Analysis for HI-TRAC CS Transfer Cask," Holtec Report HT-2177553, Revision 0.
[8] "Thermal Evaluations of HT-STORM UMAX at HT-STORE CIS Facility," Holtec Report HI-2177591, Revision 0.
[9] "Thermal Evaluations of HI-STAR 190 System," Holtec Report Hl -2 146286, Revision 3.
[ 1O] "Flow of Fluids through Valves, Fittings, and Pipe," Crane Co., 1988.
[ 11] FLUENT Computational Fluid Dynamics Software, ANSYS Inc.
[12] "MPC 37 Enclosure Vessel," Holtec Drawing 6505, Revision 17.
[ 13] "Assembly, MPC 37 Fuel Basket," Holtec Drawing 6506, Revision 12.
[14] F. P. Incropera and D. P. DeWitt, "Fundamentals of Heat and Mass Transfer," 4th ed ition, John Wi ley & Sons, New York, 1996
[15] "Final Safety Analysis Report on the HI-STORM FW MPC Storage System," Holtec Report HT-2114830, Latest Revision.
[16] "Final Safety Analysis Report on the HI-STORM UMAX Canister Storage System,"
Holtec Report Hl-2115090, Latest Revision.
[17] "Effective Thermal Properties of PWR Fuel to Support Thermal Evaluation of HI-STORM FW," Holtec Report HI-2094356, Revision 5.
Report HT-2 177597 18 Project 5025 Page 24 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIET.A:RV ltJFORJ.1.9.TIOtJ IIOLTEG PROPREEThRY RffORMNflOH (b)(4)
Report Hl-2 177597 19 Project 5025 Page 25 of 26
ATTACHMENT 17 TO HOLTEC LETTER 5025012 I IOLT!!C l'llllt.Ol'RIE I ARY IIQFORIVIA I ION IIOLTEC PROPREETARY ~WORMA:TIO:H (b)(4)
Report Hl-2 177597 20 Project 5025 Page 26 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 lafOl..+aC li'lil.QPlil.11.:::ro RN ltJF9RMNfl8Pl Holtec Center, One Holtec Drive, Marlton, NJ 08053 Telephone (856) 797- 0900 HOLTEC INTERNATIONAL Fax(856)797-0909 HI-STORE CIS Facility Site Boundary Dose Rates Calculations for HI-STORM UMAX System FOR Holtec Report No: Hl-2177599 Holtec Project No: 5025 Sponsoring Holtec Division: NPD Report Class : SAFETY RELATED COMPANY PRIVATE Page 1 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lifO liil.¥ l~llaORU HIO~I HOLTEC INTERNATIONAL 1
DOCUMENT ISSUANCE AND REVISION STATUS DOCUMENT NAME: HI-STORE CIS Facility Site Boundary Dose Rates Calculations for HI-STORM UMAXSystem DOCUMENT NO.:
HI-2177599 CATEGORY: D GENERIC PROJECT NO.: PROJECT SPECIFIC 5025 Rev. Date Author's No. 2 A Initials VIR #
0 .Tinker 623731 DOCUMENT CATEGORIZATION In accordance with the Holtec Quality Assurance Manual and associated Holtec Quality Procedures (HQPs), this document is categorized as a:
~ Calculation Package3 (Per HQP 3.2) 0 Technical Report (Per HQP 3.2)
(Such as a Licensing Report)
D Design Criterion Document (Per HQP 3.4) 0 Design Specification (Per HQP 3.4)
D Other (S ecif ):
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:
DECLARATION OF PROPRIETARY STATUS 0 Nonproprietary D Holtec Proprietary D Privileged Intellectual Property (PIP)
TfiTsaocom ntains extremely valuable intellectual property of Holtec International. Holte '
- o e ideas, methods, models, an p scribed in this document are protected a a* orized use, in whole or in part, by any other party under the U.S. and intern *
- llectual s. Unauthorized dissemination of any part of this document by the recipient will be deemed to aw h of contract governing this project. The recipient of this document bears sole re *
- y to honor Holtec's unabridged owner *
- of this document, to observe its confidential' 1mit use to the purpose for which it was delivered to the recipient. Po 1
- document may be c to copyright protection against unauthorized reproduction by a third party.
Notes
- 1. 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 on the company"s network. The Validation Identifier Record (VIR) 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 including revisions to references 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".
Page 2 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 I IOLTEe 12R:l12R:IET1'R:Y lldf"5p;(:fol>'<Tl514 Summary of Revisions Revision O- Original issue Report: HI-2177599 Moltec f1op1icta1y h1fu1matisn Page: 1 Revision 0 Page 3 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 I IQb+aC li'RORRIEIARY lt::clFQBMAIIQN Table of Contents Safety Analysis Summary............................................................................................................. 3
- 1. Introduction ........................................................................................................................... 9
- 2. General Methodology ........................................................................................................... 9
- 3. Acceptance Criteria .............................................................................................................. 9
- 4. Assumptions......................................................................................................................... 10
- 5. Input Data .......................................................................................................................... 10
- 6. Computer Codes.................................................................................................................. 10
- 7. Analysis and Resu Its ........................................................................................................... 10
- 8. Computer Files .................................................................................................................... 11
- 9. Summary .......................................................................................................................... 11
- 10. References .......................................................................................................................... 11 10.1 Drawings ....................................................................................................................... 11 Appendix A: SAS2H/ORIGEN-S Source Terms (total of 1 page) ................................... A-1 Appendix B: MCNP Filenames and Tally Specificat ions (total of 2 pages) ................... B-1 Appendix C: MCNP Modeling of Casks (total of 6 pages) .............................................. C-1 Attachment A: Quality Essentials Applicable to this Calculation Package (total of 4 pages)
............................................................................................ Att. A-1 Report: HI-2 177599 Ilsltss Prs~ristr.u:y INt°Qrrnatioo Page:2 Revision 0 Page 4 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lEfO Iii.¥ 1*JFQfilt10+IQM Safety Analysis Summary (Source Document lD: Hl-2l 77599RO)
Project title HI-STORE CIS Facility HI-STORE CIS Facility Site Boundary Dose Rates Report title Calculations for the HT-STORM UMAX System Name of the Site HI-STORE CIS Facility Name of the SSC (acronym fo r "system, HI-STORM UMAX Version C System structure or component") HI-TRAC CS Applicable NRC docket number 72-1040, 72- 1051 Ref Holtec FSAR report number HI-2167374, Revision 0 Ref. Purchasing Spec. JD (if applicable) NA Pertinent technical disciple Shielding Name of department head Dr. Stefan Anton Names of the analyst & reviewer (of the Robert Tinker latest revision) Behrooz Khorsandi This Safety analysis summary is intended to provide the necessary information to demonstrate that the SSC identified above will render its intended safety function established within the purview of the above- referenced technical discipline under all applicable normal, off- normal and extreme environmental (accident) conditions. This safety summary is limited to demonstrating compliance in the specific area (technical discipline) of evaluation noted above and does not purport to cover other safety considerations that may apply to the subject SSC. The principal objective of this summary document is to provide a concise input to a safety significant Plant document such as a "design modification package" or a multi- disciplinary comprehensive safety evaluation (such as that required under 72.212) needed to implement a planned Plant initiative in accordance with the Plant's established safety confirmation protocol.
The summary information provided below is shared with the client and is archived as a part of the Holtec proprietary document (viz., a "Calculation package" which has imbedded Holtec intellectual property and is hence prohibited from external dissemination) in the Company's configuration control system. The main body of the parent document may make reference to this summary document, as appropriate, to prevent the need to repeat the same information. This document is QA validated along with its parent report and is subject to revision (and re-submittal to the client) if a ny significant change in the input parameters to the analysis so warrant. To serve its role as an authoritative input to the Plant, it is intended to be self-contained and entirely focused on safety. For this purpose, this summary document is organized in a series of sections to provide a succinct and concise safety assessment, as follows:
Report: HI-2 177599 Ilaltee Prafjri@tr.u:y J.nfocm atioo Page: 3 Revision 0 Page 5 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 I 19LTE9 PR:9PR:IET.A:R:V ltJF8RMNfl8tl
- 1. Scope ofAnalysis This report calculates the dose rates as a function of distance for 500 loaded UMAX VVMs containing fully loaded MPC-37 canisters at the HI-STORE CIS Facility. The dose rates as a function of distance are calculated for the source term case which have the bumup, cooling time, and initial enrichment combination shown in Table 7.1.1 of Reference [8]. Using a single UMAX VVM model, dose rates as a function of distance, with occupancy factors, are calculated at distances in the range of 10 meters to 1000 m to demonstrate compliance with 10CFR72.I04 [9].
Additionally a fire accident with the transfer cask, the HI-TRAC CS is considered with the density of the concrete reduced to account for degradation from the fire. The dose is calculated for a 30-day accident duration and a 100 meter distance to demonstrate compliance with 10CFR72. l06 [9].
- 2. Acceptance Criteria The acceptance criteria for this analysis are dictated by 10CFR72.104 and 10CFR72.106 [9].
- 3. Computer codes and their benchmarking status Holtec International maintains an active list of QA validated computer codes on the Company's network that are approved for use in Safety significant projects . The table below identifies the Code and its version (listed in the ACPL) that has been used in this work effort.
Generic Report & ACPL Information (b)(4)
Generic Report #
Code name (listed in the ACPL)
Code version# (approved in the ACPL)
Computer ID # (approved in the ACPL for the applicable code name and version)
Report: HI-2177599 Iloltcc Propt ietttt) Infenalttien Page: 4 Revision 0 Page 6 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 I IOLT!!C l'llllt.Ol'RIE I ARY IIQFORIVIA I ION
- 4. Principal references
[l] J.C. Gauld, O.W. Hermann, "SAS2H: A Coupled One-Dimensional Depletion and Shielding Analysis Module," ORNL/TM-2005/39, Version 5.1, Vol. I, Book 3, Sect. S2, Oak Ridge National Laboratory, November 2006.
[2] LC. Gauld, O.W. Hermann, R.M. Westfall, "ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms," ORNL/TM-2005/39, Version 5.1 , Vol. II, Book 1, Sect. F7, Oak Ridge National Laboratory, November 2006.
[3] X-5 Monte Carlo Team, "MCNP - A General Monte Carlo N-Particle Transport Code, Version 5", LA-UR-03-1987, Los Alamos National Laboratory April 2003 (Revised in 2008).
[4] USNRC Docket 72-1040, "Final Safety Analysis Report on The HI-STORM UMAX Canister Storage System", Holtec Report No. HT-2 115090, Revision 3.
[5] Shielding Analysis of the HJ-STORM UMAX Hl-2125 194 Latest Revision. Holtec International.
[6] USNRC Docket 71-9373, "Safety Analysis Report on the HI-STAR 190 Package", Holtec Report No. 2 1462 14, Revision 0.
[7] Final Safety Analysis Report for the HT-STORM FW Cask MPC Dry Storage System, HI-2114830 Latest Revision. Holtec International.
[8] USNRC Docket 72-105 1, "Licensing Report on The HI-STORE CIS Facility" HI-2 167374 RO. Holtec International.
[9] 10CFR72, Code of Federal Regulations, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor Related Greater than Class C Waste," USNRC, Washington, DC.
[10] Thermal Analysis of HI-TRAC CS Transfer Cask. HI-2177553 Revision 0. Holtec International.
Report: HI-2177599 Page: 5 Revision 0 Page 7 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 AOL I ee l'llllt.Ol'llllt.i!!T)!(llllt., il~l'OR.li11..."f1Sfd 4.1 Drawings The fo llowing drawings were used to develop the MCNP models in this report.
Drawing Number Title Rev.
10868 HI-TRAC CS 0 10875 HI-STORM UMAX Vertical Ventilated Module Version C 0 6505 Assembly, MPC-37 Fuel Basket L icensing Drawing 17
- 5. Approach and major assumptions to btsure conservative results The site boundary analysis of the HI-STORE CIS Facility with the ISFSI containing 500 loaded UMAX VVMs, can be separated into two distinct parts. The first is the generation of the radiation source terms to represent the spent nuclear fuel at the appropriate bumup and cooling time. The second part is the radiation transport simulation to calculate the dose rates near and far from a single cask.
The source terms are calculated using the computer codes SAS2H and ORIGEN-S from SCALE 5.1 [1], [2]. These codes are a widely accepted means of generating radiation source terms from spent nuclear fuel. The dose rates are calculated using the computer code MCNP5 Version I .5 I [3]. MCNP5 is a state of the a1t Monte Carlo code that offers coupled neutron-gamma transport using continuous energy cross sections in a full three-dimensional geometry.
The distance dose rate calculations use the same methodology employed in the site boundary MCN P cask model in Reference [4] w ith tallies at greater distances in the 10 meter to I000 meter range.
The HI-STORM UMAX VVM model includes several key assumptions, as follows:
- 1. A standard 17x 17 PWR design basis fuel assembly as defined in the HI-STORM UMAX FSAR [4], as shown in Table 5.2.l of [4] is used for both the source term and MCNP calculations.
- 2. The cobalt-59 imRurit level is assumed to be 0.8 k for the hardware above and below the active fuel region. (b)(4)
(b)(4)
- 3. The fuel enrichment is conservatively assumed to be 5.0 wt% in the MCNP models. The 5.0 wt% enrichment is utilized in the MCNP calculations (b)(4)
(b)(4)
- 4. It is conservatively assumed that each loaded HT-STORM UMAX VVM conta ins 37 fuel assemblies each with a design basis BPRA present consistent with Section 5.2 of Reference
[4].
Report: HI-2 177599 Holter Proprietary Toformation Page: 6 Revision 0 Page 8 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 AOL I EC PROPRIE I ARY IIQFORIVIA I IOl<J
- 5. Two separate occupancy factors are assumed: 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week, 50 weeks per year) and 8760 hr, which is full time occupancy for the entire year.
- 6. The dose rates as a function of distance for the HT-STORM UMAX casks are calculated for the source term case presented in Table 7 .1.1, which has a heat load of approximately 32 kW, consistent with the maximum allowable heat load of the HJ-STAR 190 (Table 7.C.7 of Reference [6]).
- 7. No credit is taken for self-shie lding of the UMAX VVM closure lids (i.e. one UMAX VVM closure lid above ground is not credited for shielding another UMAX VVM's dose contribution to the site boundary).
Additional modeling assumptions, modeling deviations and discussion can be found in references
[4] and [5].
The HI-TRAC CS fire accident model includes several key assumptions, as follows:
- 1. The material composition of the HI-TRAC CS fire accident degraded concrete de nsity is as described in Table 7.3. l [8] and conservatively bounds the calculated degradation due to the fire accident calculated in Appendix B of Reference [10].
- 2. The accident duration is assumed to last 30 days, consistent with Reference [4].
- 3. The distance of the HI-TRAC CS under accident conditions to the Controlled Area Boundary is assumed to be 100 meters, consistent with Reference [4].
- 4. The height of the tally at 100 meters is 5 feet ( 1.524 meters) above ground level.
- 6. Input ,Lata & source The input data and material compositions for SAS2H, ORIGEN-S and MCN P models are from references [4] and [5]. The UMAX VVM pitch in both the x and y directions of 17 feet (5 .1 816 meters) is shown in Table I. l.1 of [8]. The lSFST array for 500 loaded UMAX VVMs is modeled as a 20 x 25 array, crediting the additional x and y distances to the site boundary.
The distance from the nearest loaded UMAX VVM to the site boundary is a distance of 400 meters as is shown in Table 1.0.1.
The material concrete and s.o il compositions and densities are as described in Table 7.3.1 [8].
Additional material compositions and material properties of the storage system are provided in Subsection 5.3.2 and Table 5.3.2 in [4].
Report: HI-2 177599 Ileli@e Prgprietary Toformation Page:7 Revision 0 Page 9 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 AOL I EC PRO,.Ri!!TAR I ii~,.ORIOIA"l'lel4
- 1. Results and Safety Findings The HI-STORM UMAX VVM ISFSI site boundary shielding ana lysis at the HI-STORE CIS Facility is presented in this report. The dose rates and annual dose (for occupancy factors of 2000 hrs/yr and 8760 hrs/yr) as a function of distance for the HI-STORM UMAX VVM ISFSI are presented in Table 7.4.3 of Reference [8]. The dose rates and annual doses are calculated at distances ranging from I 00 meters to 1000 meters from the casks. Figure 7.4.3 of Reference [8]
shows ISFSI dose rates as a function of distance.
The maximum controlled area boundary dose rate (assuming an occupancy of 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> per year) is below the 25 mrem annual dose limit of I OCFR72.104 [9].
The nearest residence is 1.5 miles from the HJ-STORE CTS Faci lity. The dose calculations conservatively assume a full-time resident (8760 hour0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />s/year) is only I 000 meters from the nearest loaded UMAX VVM. In the case of this nearest residence, the dose is calculated to be below the 25 mrem annual dose limit prescribed in l OCFR72. l 04 [9].
The HT-TRAC CS fire accident results are presented in Table 7.4.4 of Reference [8], with the resulting accident dose (assuming a 30-day accident duration) at 100 m from the cask showing compliance with the requirements of I OCFR72.106 [9].
Report: HI-2 177599 Hoitec Proprietary lnformauon Page: 8 Revision 0 Page 10 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 I IOLTES Plil.OPlil.lETAR.¥ l~llaORD10IIOM
- 1. Introduction The Jntroduction and scope of the analysis is presented in Section 1 of the Safety Analysis Summary.
This report is organized with a very short front section followed by detailed appendices. The actual calculations and evaluations are presented in the appendices.
- 2. General Methodology The analysis of the HI-STORE ClS Facility UMAX VVM lSFSJ can be separated into two di stinct parts. The first is the generation of the radiation source terms to represent the spent nuclear fuel at the appropriate bumup and cooling time. The second part is the radiation transport simulation to calculate the dose rates near and far from a single cask.
The radiation source tem1s are calculated using the SAS2H and ORIGEN-S modules from the SCALE 5.1 [l ] and [2] code system from Oak Ridge National Laboratory. This is a widely accepted means of generating radiation source terms from spent nuclear fuel.
The radiation transport simulation in the HI-STORM UMAX shielding models is performed with MCNP5 1.51 [3] from Los Alamos National Laboratory. MCNP is a Monte Carlo code that offers coupled neutron-gamma transport using continuous energy cross sections in a full three-dimensional geometry.
The reader is also referred to references [4], [5] for additional discussion of the methodology and calculation of the source terms.
- 3. Acceptance Criteria The acceptance criteria for this analysis are dictated by 10CFR72.104 and 10CFR72.106, and are summarized here.
Normal condition requirements from 10CFR72.104 [9].
- 1. During normal operations and anticipated occurrences, the annual dose equivalent to an individual who is located beyond the controlled area, must not exceed 0.25 mSv (25 mrem) to the whole body, 0. 75 mSv (75 mrem) to the thyroid and 0.25 mSv (25 1mem) to any other critical organ.
- 2. Operational restrictions must be established to meet as low as reasonably achievable (ALARA) objectives for radioactive materials in effluents and direct radiation.
Report: HI-2177599 Iloltee P1at3ria~ary Trformation Page: 9 Revision 0 Page 11 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lEfO Iii.¥ 1*JFQfilt10+IQM Accident condition requirements from 10CFR72. 106 [9]
Any individual located on or beyond the nearest boundary of the controlled area may not receive from any design basis accident the more limiting of a total effective dose equivalent of 0.05 Sv (5 Rem), or the sum of the deep-dose equivalent and the committed dose equivalent to any individual organ or tissue (other than the lens of the eye) of 0.50 Sv (50 rem). The lens dose equ ivalent shall not exceed 0.15 Sv (15 rem) and the shallow dose equivalent to skin or to any extremity shall not exceed 0.50 Sv (50 rem). The min imum distance from the spent fuel or high level radioactive waste handling and storage facilities to the nearest boundary of the controlled area shall be at least l 00 meters.
As discussed in Subsection 5. 1.2 of the HI-STORM UMAX FSAR [4], the dose requirement of 10CFR72. l 06 is satisfied for the design basis accident, and no additional site specific analyses are requ ired.
- 4. Assumptions The major assumptions are listed in Section 5 of the Safety Analysis Summary.
- 5. Input Data Input data are presented in Section 6 of the Safety A nalysis Summary, and appropriately referenced within each Appendix.
- 6. Computer Codes Computer Codes are li sted in Section 3 of the Safety Analysis Summary.
- 7. Analysis and Results The steps to determine dose rate as a function of distance from the HI-STORM UMAX VVM are outlined in Chapter 5 of Reference [4]. Results and safety findings are presented in Section 7 of the Safety Analysis Summary.
This section provides a brief description of the contents of each Appendix. Please note that the resu lts sections in the appendices might be page numbered separately from the Appendix.
Appendix A. SAS2H/ORTGEN-S Source Terms: This Append ix provides the neutron, fuel gamma, and Cobalt-60 hardware source terms of SAS2H and ORIGEN-S calculations.
Appendix B. MCNP Filenames: This Appendix briefly describes the nomenclature used for MCNP calcu lations. With that, the content of each fi le can be derived from the fi lename.
Report: HI-2 177599 Iloltcc F1op1 ictaty htfornratien Page: lO Revision 0 Page 12 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 HOLT!!C l"P'!.e:'Jl"P'!.l!!TJltR:Y IIJF8 RP.V:il"l9 Pl Appendix C. MCNP Modeling of Casks: The MCN P modeling methodology and tally descriptions are provided. The results for a single cask dose vs. distance, and single cask 1 meter dose rates at the top, bottom, and side mid-height various sources (neutrons, ganunas, etc.) are also provided.
- 8. Computer Files 4
All fi les are stored on the Holtec com uter server in Camden NJ (b)( )
(b)(4)
The specific input file names are li sted or described in the individual appendices.
I EXCEL File I Description
- 9. Summary The HI-STORE CIS Facility shielding analysis of the UMAX VVM ISFSI is presented in this report.
The hourly and annual dose rates from the UMAX VVM lSFST are presented in Table 7.4.3 of Reference [8]. The annua l dose rates are specified for occupancy factors of 2000 hrs/yr and 8760 hrs/yr. The doses are calculated at distances ranging from l 00 meters to 1000 m from the casks.
The results of this calculation demonstrate compliance with 10CFR72. l 04 [9).
Additionally, a HI-TRAC CS fire accident condition was considered in which the concrete is considered to be degraded. The dose at 100 meters from a single HI-TRAC CS for the fire accident is presented in Table 7.4.4 of Reference [8]. The results of th is calculation demonstrate compliance with 10CFR72.106 [9].
- 10. References The references are listed in Section 4 of the Safety Analysis Summary.
10.1 Drawings The drawings are listed in Section 4.1 of the Safety Analysis Summary.
Report: HI-2 177599 lloltcc Ptel'r ietary ln*erR:latioo Page: 11 Revision 0 Page 13 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lEfO R.¥ l~llaORU HIO~I Appendix A: SAS2H/ORIGEN-S Source Terms (total of 1 page) 4 The SAS2H and ORIGEN-S som-ce term calculations are documented in Reference [5]. l(b)( )
(b)(4)
I Report: HI-2177599 Il9ltec Pr9prietai,c lnfurnaatioo Page: A-1 Revision 0 Page 14 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lEfO Iii.¥ 1*JFQfilt10+IQM Appendix B: MCNP Filenames and Tally Specifications (total of 2 pages)
The fo llowing generic MCNP file naming convention is used for the HI-STORM UMAX:
(b)(4)
Report: HI-2177599 1-I@lt@c Proprietary Toformation Page: B-1 Revision 0 Page 15 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lifO liil.¥ l~llaORU HIO~I The fo llowing generic MCNP file naming convention is used for the HI-TRAC CS:
(b)(4)
Report: HI-2177599 Holtec Proptletaiy htfonnation Page: B-2 Revision 0 Page 16 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 AOL I EC PROPRIE I All': t ii~l"eRli11hfi8P4 Appendix C: MCNP Modeling of Casks (total of 6 pages)
(b)(4)
Report: HI-2177599 llelti~ J?n~prietary !ofocruariao Page: C-1 Revision 0 Page 17 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 I IQbUiQ PR.QPR.Iii.TO~¥ l~JJ;Q~P4 OTIQ~I (b)(4)
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ATTACHMENT 19 TO HOLTEC LETTER 5025012 AOL I EC PROPRIE I ARY INFORMA I ION (b) (4)
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ATTACHMENT 19 TO HOLTEC LETTER 5025012 I 19b.+eQ Plil9PlillH a~¥ IMlrO~P 1aIIObl (b)(4)
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ATTACHMENT 19 TO HOLTEC LETTER 5025012 HOI IFC RRORRIFIOPY IMFOR~4AIIOM (b)(4)
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ATTACHMENT 19 TO HOLTEC LETTER 5025012 I 19LH.9 PR9PRIH:A:RV IPJF8Rle1Nfl8PJ (b)(4)
Report: Hl-2177599 Ileltee .l?n~prietary Ioformatiao Page: C-6 Revision 0 Page 22 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIETARY ltJFORM,\TIOtl Attachment A Quality Essentials Applicable to this Calculation Package (total of 4 pages)
This attachment contains quality related information on this document in conformance with the provisions in Holtec's Quality Assurance program docketed with the USNRC (Docket # 71-0784).
A.1 Document Classification and QA Protocol This document is classified as "Safety Significant" under Holtec International 's quality assurance system. In order to gain acceptance as a safety sign(ficant document in the company's quality assurance system, this document is required to undergo a prescribed rev iew and concurrence process that requires the preparer and reviewer(s) of the document to answer a long list of questions crafted to ensure that the document is purged of all errors of any material significance.
A record of the review and verification activities is maintained in electronic form within the company' s network to enable future retrieval and recapitulation of the programmatic acceptance process leading to the acceptance and release of this document under the company's QA system.
Among the numerous requirements that this document must fulfill, as applicable, to muster approval within the company's QA program are:
- The preparer(s) and reviewer(s) are technically qualified to perform their activities per the applicable Holtec Quality Procedure (HQP).
- The input information utilized in the work effort is drawn from referencable sources. Any assumed input data is so identified.
- Significant assumptions are stated or provided by reference to another source.
- The analysis methodology is suitable for the physics of the problem.
- Any computer code and its specific versions used in the work are formally admitted for use within the company's QA system.
- The content of the document is in accordance with the applicable Holtec quality procedure.
- The material content of the calculation package is understandable to a reader with the requisite academic training and experience in the underlying technical disciplines.
Report: HI-2 177599 Iloltec froprietaty InftJ11natio11 Page: Att. A-1 Revision 0 Page 23 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 I IOLTES Plil.QPlil.lETOJiil.¥ l~llaORD10POM Once a safety significant document, such as this calculation package, completes its review and certification cycle, it should be free of any materially significant error and should not require a revision unless its scope of treatment needs to be altered. Except for regulatory interface documents (i.e., those that are submitted to the regulator in support of a license amendment and request), editorial revisions to Holtec safety significant documents are not made unless such editorial changes are deemed necessary by the Holtec Project Manager to prevent erroneous conclusions from being inferred by the reader. In other words, the focus in the preparation of this document is to ensure correctness of the technical content rather than the cosmetics of presentation.
Furthermore, this Calculation Package is focused on providing technical results that demonstrate compliance with the applicable safety limits. Informational material that does not bear upon reaching a safety conclusion is minimized in this document to the extent possible.
Because of its function as a repository of all analyses performed on the subject of its scope, this document wi ll require a revision on ly if an error is discovered in the computations or the equipment design is modifi ed. Additional analyses in the future may be added as numbered supplements to this Package. Each time a supplement is added or the existing material is revised, the revision status of this Package is advanced to the next number and the Table of Contents is amended. Calculation Packages are Holtec proprietary documents. They are shared with a client only under strict controls on their use and dissemination. This Calculation Package will be saved as a Pem1anent Record under the company's QA System.
A.2 Generic Report Applicable to the Calculation Package Holtec International maintains a number of so-called "generic reports" which provide the methodology, computer models and associated modeling assumptions for a specific physical problem. The technical content of a generic report is fully aligned with the System FSAR, Reg.
Guides, NUREGs, etc., as applicable. In other words, the generic report contains Holtec 's standardized analysis approach, method and model to analyze a technical problem. Developed under Holtec's self-funded R&D program, the generic reports are treated as "vital inteIIectual Report: HI-2177599 HQlti@ P1*et3rie~a,, InieP1n1ttien Page: Att. A-2 Revision 0 Page 24 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIET.A:RV ltJFORJ.1.9.TIOtJ property" of the Company and are accordingly prohibited from dissemination to any external entity.
The generic repo1t s are subject to inspection by the NRC's staff at Holtec's corporate headquarters during NRC's triennial inspection of Holtec.
The Calculation Package can invoke a Generic Report in whole or in part, (see table below) to improve conciseness and to enable it to be submitted un-redacted to the Company's clients.
A.3 Approved Computer Program List (ACPL)
Holtec International maintains an active list of QA validated computer codes on the Company's network that are approved for use in Safety significant projects. The table in Section 3 of the Safety Analysis Summary identifies the Code and its versi.on (listed in the ACPL) that has been used in this work effort.
A.4 Quality Validation Questionnaire The questionnaire below is a distilled version of the vast number of questions that the preparer and reviewer of a Holtec safety-significant report must answer and archive in the Company's network to gain a VIR number (the identifier of QA pedigree in Holtec's electronic configuration control system).
An affirmative answer (unless the question is "not applicable" or NA) to each of the following questions by the preparer of the report (or editor of a mu lti-author document) is an essential condition for this document to merit receiving a QA validated status.
Report: HI-2177599 lleltee Prer,rietaty Infermatien Page: Att. A-3 Revision 0 Page 25 of 26
ATTACHMENT 19 TO HOLTEC LETTER 5025012 lafOl..+aC li'R.Oli'R.la::ro i;;i,y 1*JFQfilt10+IQM
Response
Criterion (Yes or No)
Are you qualified per HQP 1.0 to perform the analysis I Yes documented in this report?
Are you aware that you must be specifically certified if you 2 use any Category A computer code (as defined in HQP 2.8 in Yes the preparation of this document?
Are you fu lly conversant with the pertinent sections of the 3 Yes applicable Specification invoked in this report?
Is the input data used in this work fully sourced (i.e.,
4 Yes references are provided)?
Are you full y conversant with the user manual and validation 5 Yes manual of the code(s) used in this report, if any?
Are Category A computer code(s) (if used) listed in the 6 Yes Company's "Approved Computer program list"?
Are the resu lts clearly set down and do they meet the 7 Yes acceptance criteria set down in the governing Specification?
Are you aware that you must observe all internal requirements on needed margins of safety published in Holtec's internal 8 Yes memos, if app licable (which may exceed those m the reference codes and standards or the specification)?
Have you performed numerical convergence checks to ensure 9 Yes that the solution is fully converged?
ls it true that you did not receive more than 10 quality 10 Yes infraction points in the past calendar year or thus far this year?
Report: HI-2177599 Page: Att. A-4 Revision 0 Page 26 of 26
ATTACHMENT 20 TO HOLTEC LETTER 5025012 I IBl!TEB f2~8f21ii1JET;SJ~:V IIJFBliill:1/:TIBll Holtec Center, One Holtec Drive, Marlton, NJ 08053 Telephone (856) 797- 0900 HOLTEC INTERNATIO N A L Fax(856)797-0909 HI-STORE CIS Facility Occupational Dose Calculation FOR Holtec Report No: Hl-2177600 Holtec Project No: 5025 Sponsoring Holtec Division: NPD Report Class : SAFETY RELATED COMPANY PRIVATE Page 1 of 20
ATTACHMENT 20 TO HOLTEC LETTER 5025012 HOLTEC PROPRIETARY INFORMAT IOM HOLTEC INTERNATIONAL 1
DOCUMENT ISSUANCE AND REVISION STATUS DOCUMENT NAME: HI-STORE CIS Facility Occupational Dose Calculation DOCUMENT NO.:
HI-2177600 CATEGORY: D GENERIC PROJECT NO.: PROJECT SPECIFIC 5025 Rev. Date Author's No. 2 A Initials VIR #
0 .Tinker 823 127 DOCUMENT CATEGORIZATION In accordance with the Holtec Quality Assurance Manual and associated Holtec Quality Procedures (HQPs), this document is categorized as a:
~ Calculation Package3 (Per HQP 3.2) 0 Technical Report (Per HQP 3.2)
(Such as a Licensing Report)
D Design Criterion Document (Per HQP 3.4) 0 Design Specification (Per HQP 3.4)
D Other (S ecif ):
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:
DECLARATION OF PROPRIETARY STATUS
~ Nonproprietary D Holtec Proprietary D Privileged Intellectual Property (PIP)
This ntains extremely valuable intellectual property of Holtec International. Holtec's r* e ideas, methods, models, an p cribed in this document are protected agains nzed use, in whole or in part, by any other party under the U.S. and interna
- ctual pro . nauthorized dissemination of a ny part of this document by the recipient will be deemed to co I f contract governing this project. The recipient of thi s document bears sole res o * *
- onor Holtec's unabridged owners 1
- is document, to observe its confidentialit
- 1 use to the purpose for which it was delivered to the recipient. Portions men! may be copyright protection against unauthorized reproduction by a third party.
Notes
- 1. 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 on the company"s network. The Validation Identifier Record (VIR) 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 including revisions to references 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".
Page 2 of 20
ATTACHMENT 20 TO HO LTEC LETTER 5025012 HOLTEC PR.OPR.IETAR.V IIIJFOR.MATIOIIJ Summary of Revisions Revision O- Original issue Report: HI-2177600 Holtec Proprietary Information Page: 1 Revision 0 Page 3 of 20
ATTACHMENT 20 TO HOLTEC LETTER 5025012 I IOLTEC PROPRIETARY l~ffORMAT IOM Table of Contents Safety Analysis Summary............................................................................................................. 3
- 1. Introduction ........................................................................................................................... 8
- 2. General Methodology ........................................................................................................... 8
- 3. Acceptance Criteria .............................................................................................................. 8
- 4. Assumptions........................................................................................................................... 8
- 5. Input Data ............................................................................................................................ 8
- 6. Computer Codes.................................................................................................................... 8
- 7. Analysis and Results ............................................................................................................. 9
- 8. Computer Files ...................................................................................................................... 9
- 9. Summary .......................................................................................................................... 10
- 10. References .......................................................................................................................... 10 10.1 Drawings ....................................................................................................................... 10 Appendix A: SAS2H/ORIGEN-S Source Terms (total of 1 page) ................................... A-1 Appendix B: MCNP Filenames and Tally Specifications (total of 3 pages) ................... B-1 Attachment A: Quality Essentials Applicable to this Calculation Package (total of 4 pages)
............................................................................................ Att. A-1 Report: HI-2177600 Holtec Proprietary Information Page:2 Revision 0 Page 4 of 20
ATTACHMENT 20 TO HOLTEC LETTER 5025012 I IOLTEO PROPRIET/tRY 114FSRli11...TISl4 Safety Analysis Summary (Source Document lD: Hl-2l 77600RO)
Project title HI-STORE CIS Facility HI-STORE CIS Facility Occupational Dose Report title Calculation Name of the Site HI-STORE CIS Facility Name of the SSC (acronym fo r "system, HI-STORM UMAX Version C System structure or component") HI-TRAC CS Applicable NRC docket number 72-1040, 72- 1051 Ref Holtec FSAR report number HI-2167374, Revision 0 Ref. Purchasing Spec. JD (if applicable) NA Pertinent technical disciple Shielding Name of department head Dr. Stefan Anton Names of the analyst & reviewer (of the Robert Tinker latest revision) Behrooz Khorsandi This Safety analysis summary is intended to provide the necessary information to demonstrate that the SSC identified above will render its intended safety function established within the purview of the above- referenced technical discipline under all applicable normal, off- normal and extreme environmental (accident) conditions. This safety summary is limited to demonstrating compliance in the specific area (technical discipline) of evaluation noted above and does not purport to cover other safety considerations that may apply to the subject SSC. The principal objective of this summary document is to provide a concise input to a safety significant Plant document such as a "design modification package" or a multi- discipl inary comprehensive safety evaluation (such as that required under 72.212) needed to implement a planned Plant initiative in accordance with the Plant's established safety confirmation protocol.
The summary information provided below is shared with the client and is archived as a part of the Holtec proprietary document (viz., a "Calculation package" which has imbedded Holtec intellectual property and is hence prohibited from external dissemination) in the Company's configuration control system. The main body of the parent document may make reference to this summary document, as appropriate, to prevent the need to repeat the same information. This document is QA validated along with its parent report and is subject to revision (and re-submittal to the client) if a ny significant change in the input parameters to the analysis so warrant. To serve its role as an authoritative input to the Plant, it is intended to be self-contained and entirely focused on safety. For this purpose, this summary document is organized in a series of sections to provide a succinct and concise safety assessment, as follows:
Report: HI-2 177600 Iloltee Pr 61'I ietary IH~erM1a.fo~A Page: 3 Revision 0 Page 5 of 20
ATTACHMENT 20 TO HOLTEC LETTER 5025012 HAI ISC li'R.Oli'R.lliiiTA R.Y 1*JFQRJ.1.A.il"l9PJ
- 1. Scope of Analysis This report provides a shielding eva luation for the HI-STORE CIS Faci lity Occupational dose rates. Specifically, evaluations and calculations are presented here for the following conditions and configurations:
- Occupational dose rates at the surface and l meter from a single HI-STORM UMAX Version C.
- Occupational dose rates at the surface, 0.5 meters, 1 meter, and 2 meters from the HI-TRAC CS.
- Estimated personnel exposures for loading operations of one canister at the HI-STORE CIS Facility.
The dose rates for the UMAX VVM Version C and the HI-TRAC CS are calculated for the source term case which have the burnup, cooling time, and initial enrichment combination shown in Table 7.1.1 ofReference [8].
- 2. Acceptance Criteria There are no specific acceptance criteria for this analysis. Occupational doses to individuals are administratively controlled to ensure that they are maintained below 10CFR20.120l(a)(l) annual limits [11] i.e. the more limitting of:
- 1. The total effective dose equivalent being equal to 5 rem (0.05 Sv); or
- 11. The sum deep-dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye being equal to 50 rem (0.5 Sv).
Additionally, qualitatively a determination that the HI-STORM UMAX and HI-TRAC CS provide "suitable shielding" in accordance with 10CFR72.I28(a)(2) [9].
- 3. Computer codes and their benchmarking status Holtec International maintains an active list of QA validated computer codes on the Company's network that are approved for use in Safety significant projects. The table below identifies the Code and its version (listed in the ACPL) that has been used in this work effort.
Generic Repo rt & ACPL Information (b)(4)
Generic Report #
Code name (listed in the ACPL)
Code version # (approved in the ACPL)
Computer lD # (approved in the ACPL for the applicable code name and version)
Report: HI-2 177600 L(g)tec Pcopcietacy Trformation Page:4 Revision 0 Page 6 of 20
ATTACHMENT 20 TO HOLTEC LETTER 5025012 lolQl..+aC li'J.Of2RIFHRY INFORMAIIOM
- 4. Principal references
[l] J.C. Gauld, O.W. Hermann, "SAS2H: A Coupled One-Dimensional Depletion and Shie lding Analysis Module," ORNL/TM-2005/39, Version 5.1, Vol. I, Book 3, Sect. S2, Oak Ridge National Laboratory, November 2006.
[2] LC. Gauld, O.W. Hermann, R.M. Westfall, "ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms," ORNL/TM-2005/39, Version 5.1 , Vol. II, Book 1, Sect. F7, Oak Ridge National Laboratory, November 2006.
[3] X-5 Monte Carlo Team, "MCNP - A General Monte Carlo N-Particle Transport Code, Version 5", LA-UR 1987, Los Alamos National Laboratory April 2003 (Revised in 2008).
[4] USNRC Docket 72-1040, "Final Safety Analysis Report on The HI-STORM UMAX Canister Storage System", Holtec Report No. HT-2115090, Revision 3.
[5] Shielding Analysis of the HJ-STORM UMAX Hl-2125 194 Latest Revision. Holtec International.
[6] USNRC Docket 7 1-9373, "Safety Analysis Report on the HI-STAR 190 Package", Holtec Report No. 2 1462 14, Revision 0.
[7] Final Safety Analysis Report for the HT-STORM FW Cask MPC Dry Storage System, HI-21 14830 Latest Revision. Holtec International.
[8] USNRC Docket 72-1051 , "Licensing Report on The HI-STORE CIS Facility" HI-2 167374 RO. Holtec International.
[9] 10CFR72, Code of Federal Regulations, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor Related Greater than Class C Waste," USNRC, Washington, DC.
[10] Thermal Analysis of HI-TRAC CS Transfer Cask. HI-2177553 Revision 0. Holtec International.
[11] 10 CFR Part 20 "Standards for Protection Against Radiation," Title 10, of the Code of Federal Regulations - Energy, Office of the Federal Register, Washington, D.C.
Report: HI-2177600 Ilsltss Prst3ri@t!.H) It1fe1m1ttien Page: 5 Revision 0 Page 7 of 20
ATTACHMENT 20 TO HOLTEC LETTER 5025012 HOI IFC RROli!RIEl:A:RV ltJFBR~l>'<l"IOIQ 4.1 Drawings The fo llowing drawings were used to develop the MCNP models in this report.
Drawing Number Title Rev.
10868 HI-TRAC CS 0 10875 HI-STORM UMAX Vertical Ventilated Module Version C 0 6505 Assembly, MPC-37 Fuel Basket L icensing Drawing 17
- 5. Approach and major assumptions to btsure conservative results The occupational dose shielding analysis of the HI-STORE CIS Facility, can be separated into two distinct parts. The first is the generation of the radiation source terms to represent the spent nuclear fuel at the appropriate bumup and cooling time. The second part is the radiation transport simulation to calculate the dose rates near and far from a single cask.
The source terms are calc ulated using the computer codes SAS2H and ORIGEN-S from SCALE 5.1 [I], [2]. These codes are a widely accepted means of generating radiation source terms from spent nuclear fuel. The dose rates are calculated using the computer code MCNP5 Version 1.51 [3]. MCNP5 is a state of the art Monte Carlo code that offers coupled neutron-gamma transpo1t using continuous energy cross sections in a full three-dimensional geometry.
The occupational dose rate calculations use the same calculational methodology employed in Reference [4].
The HI-STORM UMAX VVM model includes several key assumptions, as follows:
- 1. A standard l 7x 17 PWR design basis fuel assembly as defined in the HI-STORM UMAX FSAR [4], as shown in Table 5.2.l of [4] is used for both the source term and MCNP calculations.
- 2. The cobalt-59 imP,uritv level is assumed to be 0.8 !l/h: for the hardware above and below the active fuel reeion.l(b)(4) I (b)(4)
- 3. The fuel enrichment is conservatively assumed to be 5.0 wt% in the MCNP models. The 5.0 wt% enrichment is utilized in the MCNP calculations (b)(4)
(b)(4)
- 4. 1t is conservatively assumed that each loaded HI-STORM UMAX VVM contains 37 fuel assemblies each with a design basis BPRA present consistent with Section 5.2 of Reference
[4].
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ATTACHMENT 20 TO HOLTEC LETTER 5025012 HOI IFC li'J.QPlil.lH.0:Fl:Y lldFS~fol>'<TIOl4
- 5. The dose rates as a function of distance for the HI-STORM UMAX casks are calculated for the source term case presented in Table 7 .1 .1, which has a heat load of approximately 32 kW, consistent with the maximum allowable heat load of the HI-STAR 190 (Table 7.C.7 of Reference [6]).
Additional modeling assumptions, modeling deviations and discussion can be found in references
[4] and [5].
The HI-TRAC CS normal conditions model includes several key assumptions, as follows:
- 1. There are some steel components at the bottom of the HI-TRAC CS that extend beyond the outermost radius of the main overpack. These components are conservatively not credited.
- 2. Conservatively the walls of the HI-TRAC CS are s horter than the dimensions shown in Section 1.5 Licensing Drawings [8].
- 3. The HI-TRAC CS optional shield ring is not credited.
- 6. Input ,Jata & source The input data for SAS2H, ORIGEN-S and MCNP models are from references [4] and [5].
The concrete and soil compositions and densities are as described in Table 7.3.1 [8]. Additional material compositions and material properties of the storage system are provided in Subsection 5.3.2 and Table 5.3.2 in [4].
- 1. Results and Safety Findings Dose rates around a HI-TRAC CS and around a single HI-STORM UMAX storage module, loaded w ith the MPC-37 and design basis fue l, are presented in Table 7.4.1 and 7.4.2 of Reference [8] respectively.
The estimated personnel exposw-es for loading operations of one canister at the HI-STORE CIS Facility are presented in Table 11.3.1 of Reference [8].
It is concluded from the shielding analysis and results that the HI-TRAC CS and HI-STORM UMAX provide suitable shielding in accordance with 10CFR72. l 28(a)(2) [9].
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ATTACHMENT 20 TO HOLTEC LETTER 5025012 I IOLTES PfilQPliil.llii.TORY lblEORMAIIOM
- 1. Introduction The Jntroduction and scope of the analysis is presented in Section 1 of the Safety Analysis Summary.
This report is organized with a very short front section followed by detailed appendices. The actual calculations and evaluations are presented in the appendices.
- 2. General Methodology The shielding analysis of the HI-STORE CIS Facility UMAX VVM Version C and HI-TRAC CS can be separated into two distinct parts. The fi rst is the generation of the radiation source terms to represent the spent nuclear fuel at the appropriate bumup and cooling time. The second part is the radiation transport simulation to calculate the dose rates at various locations around a single cask.
The radiation source terms are calculated using the SAS2H and ORIGEN-S modules from the SCALE 5.1 [l] and [2] code system from Oak Ridge National Laboratory. This is a widely accepted means of generating radiation source terms from spent nuclear fuel.
The radiation transport simulation in the HI-STORM UMAX shielding models is performed with MCNP5 1.51 [3] from Los Alamos National Laboratory. MCNP is a Monte Carlo code that offers coupled neutron-gamma transport using continuous energy cross sections in a full three-dimensional geometry.
The reader is also referred to references [4], [5] for additional discussion of the methodology and calculation of the source terms.
- 3. Acceptance Criteria The acceptance criteria are presented in Section 2 of the Safety Analysis Summary.
- 4. Assumptions The major assumptions are listed in Section 5 of the Safety Analysis Summary.
- 5. Input Data Input data are presented in Section 6 of the Safety Analysis Summary, and appropriately referenced within each Appendix.
- 6. Computer Codes Computer Codes are listed in Section 3 of the Safety Analysis Summary.
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ATTACHMENT 20 TO HOLTEC LETTER 5025012 I IOLTES PPIOlilliillFJORY lt>IFOBMATIQN
- 7. Analysis and Results The steps to determine dose rate as a function of distance from the HI-STORM UMAX VVM are outlined in Chapter 5 of Reference [4]. Results and safety findings are presented in Section 7 of the Safety Analysis Summary.
This section provides a brief description of the contents of each Appendix.
Appendix A. SAS2H/ORIGEN-S Source Terms: This Appendix provides the neutron, fuel gamma, and Cobalt-60 hardware source terms of SAS2H and ORIGEN-S calculations.
Appendix B. MCNP Filenames: This Appendix briefly describes the nomenclature used for MCNP calculations. With that, the content of each file can be derived from the filename.
Appendix C. MCNP Modeling of Casks: The MCNP modeling methodology and tally descriptions are provided. The results for a single cask dose vs. distance, and single cask 1 meter dose rates at the top, bottom, and side mid-he ight various sources (neutrons, gammas, etc.) are also provided.
- 8. Computer Files All files are stored on the Holtec computer server in Camden, N~(b)(4)
(b)(4)
The specific input fi le names are listed or described in the individua l appendices.
EXCEL File I Description (b)(4)
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ATTACHMENT 20 TO HOLTEC LETTER 5025012 AOL I EC PRO,.Pll!.l!!T)S(~, ildFSRMNfi8P4
- 9. Summary A summary of the results and safety findings is provided in Section 7 of the Safety Analysis Summary.
- 10. References The references are listed in Section 4 of the Safety Analys is Summary.
10.1 Drawings The drawings are listed in Section 4. l of the Safety Ana lysis Summary.
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ATTACHMENT 20 TO HOLTEC LETTER 5025012 AOL I EC P jllt_O,. P'!.i !!TJl<R:Y itJ F9 RM O+IQM Appendix A: SAS2H/ORIGEN-S Source Terms (total of 1 page)
The SAS2H and ORIGEN-S som-ce term calculations are documented in Reference (b)(4) rs1. l(b)(4) J Report: HI-2177600 Holtec t'1op1icta1y h1fu1111ation Page: A-1 Revision 0 Page 13 of 20
ATTACHMENT 20 TO HOLTEC LETTER 5025012 IIQb+iQ Plil.QPlil.lifO liil.¥ l~llaORU HIO~I Appendix B: MCNP Filenames and Tally Specifications (total of 3 pages)
B.1 MCNP Filenames:
The fo llowing generic MCNP file naming convention is used for the HI-STORM UMAX:
(b)(4) u . . . 1..... n..
Report: HI-2 177600 - T £'.
Page: B-1 Revision 0 Page 14 of 20
ATTACHMENT 20 TO HOLTEC LETTER 5025012 HOI IFC RROli!RIETC R:V ltJFBRfo1>'<1"101Q The following generic MCNP file naming convention is used for the HI-TRAC CS:
(b)(4)
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ATTACHMENT 20 TO HOLTEC LETTER 5025012 I IOLTEe PRSPRIET:A:RV ltJFQfilt1A+IO~I B.2 Tally Specifications B.2.1 UMAX VVM Version C Tally Specifications (b)(4)
B.2.2 HI-TRAC CS Tally Specifications l(b)(4)
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ATTACHMENT 20 TO HOLTEC LETTER 5025012 Rut I EC PROPRIE I AR i ii~P'O"-fo1>'<1"1814 Attachment A Quality Essentials Applicable to this Calculation Package (total of 4 pages)
This attachment contains quality related information on this document in conformance with the provisions in Holtec's Quality Assurance program docketed with the USNRC (Docket # 71-0784).
A.1 Document Classification and QA Protocol This document is classified as "Safety Significant" under Holtec International 's quality assurance system. In order to gain acceptance as a safety sign(ficant document in the company's quality assurance system, this document is required to undergo a prescribed review and concurrence process that requires the preparer and reviewer(s) of the document to answer a long list of questions crafted to ensure that the document is purged of all errors of any material significance.
A record of the review and verification activities is maintained in electronic form within the company's network to enable future retrieval and recapitulation of the programmatic acceptance process leading to the acceptance and release of this document under the company's QA system.
Among the numerous requirements that this document must fulfill, as applicable, to muster approval within the company's QA program are:
- The preparer(s) and reviewer(s) are technically qualified to perform their activities per the applicable Holtec Quality Procedure (HQP).
- The input information utilized in the work effort is drawn from referencable sources. Any assumed input data is so identified.
- Significant assumptions are stated or provided by reference to another source.
- The analysis methodology is suitable for the physics of the problem.
- Any computer code and its specific versions used in the work are formally admitted for use within the company's QA system.
- The content of the document is in accordance with the applicable Holtec quality procedure.
- The material content of the calculation package is understandable to a reader with the requisite academic training and experience in the underlying technical disciplines.
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ATTACHMENT 20 TO HOLTEC LETTER 5025012 HOI IFC PRORRllii.TO R.Y ltJF9 RMNFISt~
Once a safety significant document, such as th is calculation package, completes its review and certification cycle, it should be free of any materially significant error and should not require a revision unless its scope of treatment needs to be altered. Except for regulatory interface documents (i.e., those that are subm itted to the regulator in support of a license amendment and request), editorial revisions to Holtec safety significant documents are not made unless such editorial changes are deemed necessary by the Holtec Project Manager to prevent erroneous conclusions from being inferred by the reader. In other words, the focus in the preparation of this document is to ensure correctness of the technical content rather than the cosmetics of presentation.
Furthermore, this Calculation Package is focused on providing technical results that demonstrate compliance with the app licable safety lim its. Informational material that does not bear upon reaching a safety conclusion is minimized in this document to the extent possible.
Because of its function as a repository of all analyses performed on the subject of its scope, this document wi ll require a revision on ly if an error is d iscovered in the computations or the equipment design is modified. Additional analyses in the futu re may be added as numbered supplements to this Package. Each time a supplement is added or the existing material is revised, the revision status of this Package is advanced to the next number and the Table of Contents is amended. Calculation Packages are Holtec proprietary documents. They are shared with a client only under strict controls on the ir use and dissemination. This Calculation Package will be saved as a Pem1anent Record under the company's QA System.
A.2 Generic Report Applicable to the Calculation Package Holtec International maintains a number of so-called "generic reports" which provide the methodology, computer models and associated modeling assumptions for a specific physical problem. The technical content of a generic report is fully aligned with the System FSAR, Reg.
Guides, NUREGs, etc., as applicable. In other words, the generic report contains Holtec' s standardized analysis approach, method and model to analyze a technical problem. Developed under Holtec's self-funded R&D program, the generic reports are treated as "vital inteilectual Report: HI-2 177600 Ileltee Preprictary Info11natio11 Page: Att. A-2 Revision 0 Page 18 of 20
ATTACHMENT 20 TO HOLTEC LETTER 5025012 HQI IEC PBOPRIFIARY lbl EORUO+IQM property" of the Company and are accordingly prohibited from dissemination to any external entity.
The generic repo1ts are subject to inspection by the NRC's staff at Holtec's corporate headquarters during NRC's triennial inspection of Holtec.
The Calculation Package can invoke a Generic Report in whole or in part, (see table below) to improve conciseness and to enable it to be submitted un-redacted to the Company's clients.
A.3 Approved Computer Program List (ACPL)
Holtec International maintains an active list of QA validated computer codes on the Company's network that are approved for use in Safety significant projects. The table in Section 3 of the Safety Analysis Summary identifies the Code and its versi.on (listed in the ACPL) that has been used in this work effort.
A.4 Quality Validation Questionnaire The questionnaire below is a distilled version of the vast number of questions that the preparer and reviewer of a Holtec safety-significant report must answer and arch ive in the Company's network to gain a VIR number (the identifier of QA pedigree in Holtec's electronic configuration control system).
An affirmative answer (unless the question is "not applicable" or NA) to each of the following questions by the preparer of the report (or editor of a mu lti-author document) is an essential condition for this document to merit receiving a QA validated status.
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ATTACHMENT 20 TO HOLTEC LETTER 5025012 I IOLTEe PR:SPR:IETJltR:Y lfdl"O~fo1>'<1"10f4
Response
Criterion (Yes or No)
Are you qualified per HQP 1.0 to perform the analys is I Yes documented in this report?
Are you aware that you must be specifically certified if you 2 use any Category A computer code (as defined in HQP 2.8 in Yes the preparation of this document?
Are you fu lly conversant with the pertinent sections of the 3 Yes applicable Specification invoked in this report?
Is the input data used in this work fully sourced (i.e.,
4 Yes references are provided)?
Are you full y conversant with the user manual and validation 5 Yes manual of the code(s) used in this report, if any?
Are Category A computer code(s) (if used) listed in the 6 Yes Company's "Approved Computer program list"?
Are the resu lts clearly set down and do they meet the 7 Yes acceptance criteria set down in the governing Specification?
Are you aware that you must observe all internal requirements on needed margins of safety published in Holtec's internal 8 Yes memos, if app licable (which may exceed those m the reference codes and standards or the specification)?
Have you performed numerical convergence checks to ensure 9 Yes that the solution is fully converged?
ls it true that you did not receive more t han 10 quality 10 Yes infraction points in the past calendar year or thus far this year?
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