Text

Supplement to Holtec Decommissioning International, LLC, Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR Part 50, Appendix E Including Site-Specific Calculations
	ML22032A017
Person / Time
Site:	Indian Point
Issue date:	02/01/2022
From:	Fleming J; Holtec Decommissioning International
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML22032A117	List: ML22032A017;
References
	HDI-IPEC-22-013
	Download: ML22032A017 (49)
	v • d • e

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 HDI-IPEC-22-013 February 1, 2022 ATTN: Document Control Desk Nuclear Regulatory Commission Washington, DC 20555-0001 Indian Point Nuclear Generating Unit Nos. 1, 2, and 3 Docket Nos.50-003, 50-247, and 50-286 Provisional Operating License No. DPR-5 Renewed Facility License No. DPR-26 Renewed Facility License No. DPR-64

Subject:

Supplement to Holtec Decommissioning International, LLC (HDI) Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR Part 50, Appendix E for Indian Point Unit Nos. 1, 2, and 3 Including Site-Specific Calculations

References:

1)

Letter from Holtec International to US NRC, Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report, (ADAMS Accession No. ML20280A524) September 29, 2020.

2)

Letter from Holtec International to US NRC, Response to Request for Additional Information -Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report, (ADAMS Accession No. ML21148A289) dated May 28, 2021.

3)

Letter from Holtec International to US NRC, Revised Response to Request for Additional InformationHoltec Spent Fuel Pool Heat Up Calculation Methodology Topical Report, (ADAMS Accession No. ML21228A262) dated August 16, 2021.

4)

Letter from Holtec International to US NRC, Response to Request for Additional Information 10Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report, (ADAMS Accession No. 211291A161) dated October 18, 2021.

5)

Letter from Holtec Decommissioning International, LLC (HDI) to US NRC, Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR Part 50, Appendix E, (ADAMS Accession No. ML21356B693) dated December 22, 2021.

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 6)

Letter from US NRC to Holtec International, Draft Safety Evaluation ReportHoltec Spent Fuel Pool Heat Up Calculation Methodology Topical Report, dated December 20, 2021.

Dear Sir or Madam:

In Reference 1, Holtec Decommissioning International, LLC (HDI) submitted a Holtec International Topical Report providing a methodology for calculating Spent Fuel Pool heat up for NRC review and approval. Holtec believes the methodology will be a large benefit in reducing zirconium fire risks in the spent fuel pool.

In References 2, 3 and 4, Holtec provided responses to Requests for Additional Information (RAIs) concerning the Topical Report.

In Reference 6, the US Nuclear Regulatory Commission (NRC) issued a Draft Safety Evaluation for the Holtec Topical Report submitted in Reference 1.

In Reference 5, HDI submitted a request for exemptions from the following regulations:

Certain standards in 10 CFR 50.47(b) regarding onsite and offsite emergency response plans for nuclear power reactors; Certain requirements of 10 CFR 50.47(c)(2) to establish plume exposure and ingestion pathway Emergency Planning Zones (EPZs) for nuclear power plants; and Certain requirements of 10 CFR Part 50, Appendix E, which establish the elements that make up the content of Emergency Plans.

The requested exemptions would allow HDI to reduce Indian Point Energy Center (IPEC) emergency planning requirements consistent with the permanently shutdown and defueled condition of the IPEC facilities.

The HDI request for exemptions utilize the methodology developed by Holtec International and submitted for NRC review and approval in Reference 1.

This letter provides a Supplement to the pending request for exemptions submitted in Reference 5.

This supplement provides site-specific calculations for Indian Point Units 2 & 3 (IP2 & IP3) utilizing the Holtec methodology provided in the Holtec Topical Report as revised in responses to NRC Requests for Additional Information (RAIs) (References 2, 3 and 4). The calculations as documented in Enclosure 1 to this letter and utilized in the pending Indian Point exemption requests (Reference 5) were developed utilizing the methodology presented in the Holtec topical report (Reference 1) with appropriate adjustments from the RAI responses (References 2, 3 and 4).

Page 2 of 4 HDI-IPEC-22-013

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 The calculations are also in alignment with the NRC Draft Safety Evaluation Report (Reference 6).

NRC final acceptance of the of the Draft Safety Evaluation is currently pending. Upon issuance of the NRC Final Safety Evaluation Report, HDI will confirm consistency with NRC conditions and limitations and will update the calculations, if necessary. provides a proprietary version of the following Holtec calculations used to develop the HDI requests for exemptions submitted in Reference 5:

HI-2210948, Spent Fuel Pool Heat Load Limits for lndian Point Unit 2 and 3.

HI-2210967, Assembly Decay Heat Calculations for Indian Point Unit 2 and 3 HI-2210972, Spent Fuel Pool Loading Plan for Indian Point Unit 2 and Unit 3 contains information proprietary to Holtec and is therefore supported by an affidavit signed by Holtec which is provided in Enclosure 3. The calculations provided in Enclosure 1 include appropriate markings identifying those portions that are proprietary. provides a non-proprietary, redacted version of the calculation.

I declare under penalty of perjury that the foregoing is true and correct. Executed on February 1, 2022.

If you have any questions, please contact me at 856-797-0900 ext. 3578.

Sincerely, Jean A. Fleming HDI Vice President, Regulatory and Environmental Affairs Holtec Decommissioning International, LLC Page 3 of 4 HDI-IPEC-22-013 Jean A. Fleming Digitally signed by Jean A.

Fleming Date: 2022.02.01 05:18:52 -05'00'

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 Page 4 of 4 HDI-IPEC-22-013

Enclosures:

Indian Point Unit Nos. 2 and 3 Spent Fuel Pool Calculations (Holtec Proprietary Withhold Information from Public Disclosure pursuant to 10 CFR 2.390):

o HI-2210948, Revision 3, Spent Fuel Pool Heat Load Limits for Indian Point Unit 2 and 3

o HI-2210967, Revision 1, Assembly Decay Heat Calculations for Indian Point Unit 2 and 3

o HI-2210972, Revision 3, Spent Fuel Pool Loading Plan for Indian Point Unit 2 and Unit 3

Indian Point Unit Nos. 2 and 3 Spent Fuel Pool Heat up Calculations (Non-proprietary):

o HI-2210948, Revision 3, Spent Fuel Pool Heat Load Limits for Indian Point Unit 2 and 3

o HI-2210967, Revision 1, Assembly Decay Heat Calculations for Indian Point Unit 2 and 3

o HI-2210972, Revision 3, Spent Fuel Pool Loading Plan for Indian Point Unit 2 and Unit 3

: Affidavit Pursuant to 10 CFR 2.390 to Withhold Information from Public Disclosure cc:

NRC Senior Project Manager, NRC NRR DORL NRC Region l Regional Administrator NRC Senior Regional Inspector, Indian Point Energy Center New York State Liaison Officer Designee, NYSERDA New York State (NYS) Public Service Commission

HOLTEC PROPRIETARY INFORMATION Indian Point Unit Nos. 2 and 3 Spent Fuel Pool Heat Up Calculations Proprietary Version Withhold Information From Public Disclosure Under 10 CFR 2.390 Submitted Separately (37 Pages not including this Cover Page)

Indian Point Unit Nos. 2 and 3 Spent Fuel Pool Heat Up Calculations Non-Proprietary (Redacted) Version (37 Pages not including this Cover Page)

Nuclear Power Division 3131 Sponsoring Company Project No.

HI-2210948 3

28 Jan 2022 Company Record Number Revision No.

Issue Date Report Proprietary Information Record Type Proprietary Classification Nuclear Quality Class No Export Control Applicability Record

Title:

Spent Fuel Pool Heat Load Limits for Indian Point Unit 2 and 3 Prepared by:

Reviewed by:

Approved by:

J.Rocheleau, 27 Jan 2022 P.Gowda, 28 Jan 2022 P.Gowda, 28 Jan 2022 Signature histories are provided here for reference only. Company electronic signature records are traceable via the provided Verification QR Code and are available for review within the secure records management system. A valid Verification QR Code and the presence of this covering page indicates this record has been approved and accepted.

Proprietary Classification This record is the property of and contains Proprietary Information owned by the Company. It is to be used only in connection with the performance of work by the Company, its designated subcontractors, or its client. Dissemination, reproduction, publication or representation, in whole or in part, for any other purpose by any other party is expressly forbidden.

Export Control Status Not applicable.

Spent Fuel Pool Heat Load Limits for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210948 Rev. 3 Page i of iii Copyright © 2021 Holtec International, all rights reserved Project 3131 Revision Log Revision Description of Changes 0

Initial issue.

1 Added md5 sum of significant calculation files to Section 7 to improve the quality pedigree of the document.

Removed absolute file path form Section 7.

2 Updated reference [1] revision from R0 to R2.

3 All previous changes accepted.

Updated reference [1] revision from R2 to R0.

Added references [6], [7], and [8] for RAI responses dated May 28, 2021, August 16, 2021 and October 18, 2021 respectively.

Spent Fuel Pool Heat Load Limits for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210948 Rev. 3 Page ii of iii Copyright © 2021 Holtec International, all rights reserved Project 3131 EXECUTIVE

SUMMARY

This report documents the calculation of the Spent Fuel Pool (SFP) assembly heat load limits for Indian Point Unit 2 (IP2) and Unit 3 (IP3). Heat load limits [

]4 a, 4b are developed to ensure the fuel cladding remains below the temperature limit that precludes a zirconium fire in the postulated event of an unexpected SFP drain. To the extent possible, the information in the Topical Report (TR), HI-2200750 Rev. 0, [1] and RAI responses [6], [7], and [8] are referenced and not repeated in this report.

Assumptions that need Verification The methodology presented in the topical report and any adjustments from the RAIs or additional limitations imposed on the methodology by the NRC is pending final acceptance by the NRC. It is assumed the methodology in the topical report [1] and adjustments from the RAIs, [6], [7], and [8] will be accepted as is without further adjustments.

Glossary IP2 Indian Point Unit 2 IP3 Indian Point Unit 3 PCT Peak Cladding Temperature SFP Spent Fuel Pool

[

] 4 a, 4b TR Topical Report

[

] 4 a, 4b

Spent Fuel Pool Heat Load Limits for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210948 Rev. 3 Page iii of iii Copyright © 2021 Holtec International, all rights reserved Project 3131 Table of Contents Executive Summary...................................................................................................................................... ii Purpose............................................................................................................................................. 1 Acceptance Criteria.......................................................................................................................... 1 Methodology.................................................................................................................................... 1 Assumptions..................................................................................................................................... 1 Input Data........................................................................................................................................ 1 Computer Programs......................................................................................................................... 2 Computer Files................................................................................................................................. 2 Calculations..................................................................................................................................... 2 Results.............................................................................................................................................. 3 Conclusion....................................................................................................................................... 3 References........................................................................................................................................ 3 Calculations............................................................................................................... A-1

Spent Fuel Pool Heat Load Limits for Indian Point Unit 2 and 3 WeUse Preflri@Bi:Y 1Bfe1matiea H O L T E C INTERNATIONAL 1.0 PURPOSE The purpose of this repo1t is to document the calculation of the Spent Fuel Pool (SFP) assembly heat load limits for Indian Point Unit 2 (IP2) and Unit 3 (IP3). The Topical Repo1t (TR) HI-2200750 Rev. 0 [1]

presents a methodology to establish r

]

4 a, 4b c1iteria for a SFP that can demonstrate a zirconium fire in the pool under a drain-down event is not credible. To the extent possible, the info1mation in the TR [1] and RAI responses, [6], [7], and [8] are referenced and not repeated in this repo1t.

2.0 ACCEPTANCE CRITERIA There are no specific acceptance c1iteria for the calculations presented here.

However, the heat load crite1ia dete1mined in the calculations presented here should satisfy the applicable criteria discussed in Section 2 of [1] that preclude a zirc fire in the SFP, namely that the fuel cladding must not exceed 900 °C within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

3.0 METHODOLOGY All calculations perfo1med use the methodology desc1ibed in Section 3 of [1], including the adjustments made in the Holtec responses to RAis, [ 6], [7] and [8]. Generally, these are (

.]

4 a, 4b 4.0 ASSUMPTIONS For a list of the main assumptions on the methodology, see Section 4 of [1].

No site-specific assumptions are made in this repo1t.

5.0 INPUT DATA All generic inputs are documented in Section 5 of [1 ], specifically Table 5.1 and Table 5.2. The conse1vatively bounding site-specific inputs presented in the table below are taken from [2]. The last column presents the conse1vatively bounding inputs that will be used in the calculations. Parameters markedwith an asterisk(*) are calculated from the values in the table, Table 5.2 of [1], and [2].

Spent Fuel Pool Heat Load Limits for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210948 Rev. 3 Page 2 of 4 Copyright © 2021 Holtec International, all rights reserved Project 3131 Table 5.1: Site Specific Inputs The bounding inputs use the [

.] 4 a, 4b All other inputs are the same.

COMPUTER PROGRAMS All calculations were performed using Microsoft Excel. No computer codes or scripts requiring verification were used.

COMPUTER FILES All computer files that are used to perform the calculations are located on the Holtec International server under the project 3131 directory in the report HI-2210948 directory.

The md5 checksums of significant calculation files are provided below:

File name Md5

[

] 4 a, 4b

[

] 4 a, 4b

[

] 4 a,4b

[

] 4 a, 4b The calculation file remains unchanged from revision 0 of this document.

CALCULATIONS The methodology presented in [1] was implemented in a straightforward manner into a Microsoft Excel spreadsheet. [

.] 4 a, 4b The input, output, and one example calculation sheet are provided in Appendix A.

4a, 4b

Spent Fuel Pool Heat Load Limits for Indian Point Unit 2 and 3 WeUse Preflri@Bi:Y 1Bfe1matiea H O L T E C INTERNATIONAL 9.0 RESULTS The results are summarized in the table below.

4a,4b As expected, the (

.] 4 a, 4b

10.0 CONCLUSION

This report documents calculations and COITesponding results. r

] 4 a,4b

11.0 REFERENCES

[l]

"Method for Determining Spent Fuel Assembly Heat Up During a Theoretical Drain Down Event", HI-2200750 Rev. 0.

[2]

"Fuel Compatibility Report for Indian Point Unit 2 and Unit 3", HI-2210573 Rev. 3.

[3]

"Draft Limitations and Conditions for the Holtec Decommissioning International Topical Report HI-2200750, Revision O", EPID L-2020-TOP-0056. September 28, 2021.

[4]

"NUREG-1738 Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants (ML010430066)," 2001.

[5]

"NUREG/CR-0479 MATPRO-Version 11 (Revision 2) A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior," 1981.

[ 6]

Letter from Holtec to US NRC, "Response to Request for Additional Information-Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report," (ADAMS Accession No. ML21 l 48A289) dated May 28, 2021.

[7]

Letter from Holtec to US NRC, "Revised Response to Request for Additional Information Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report," (ADAMS Accession No. ML21228A262) dated August 16, 2021.

[8]

Letter from Holtec to US NRC, Response to Request for Additional Information 10Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report, (ADAMS Accession No. ML211291A161) dated October 18, 2021.

Report Proprietary Information Record Type Proprietary Classification Nuclear Quality Class No Export Control Applicability Record

Title:

Assembly Decay Heat Calculations for Indian Point Unit 2 and 3 Prepared by:

Reviewed by:

Approved by:

J.Rocheleau, 20 Dec 2021 B.Khorsandi, 20 Dec 2021 P.Gowda, 20 Dec 2021 Signature histories are provided here for reference only. Company electronic signature records are traceable via the provided Verification QR Code and are available for review within the secure records management system. A valid Verification QR Code and the presence of this covering page indicates this record has been approved and accepted.

Proprietary Classification This record is the property of and contains Proprietary Information owned by the Company. It is to be used only in connection with the performance of work by the Company, its designated subcontractors, or its client. Dissemination, reproduction, publication or representation, in whole or in part, for any other purpose by any other party is expressly forbidden.

Export Control Status Not applicable.

Nuclear Power Division 3131 Sponsoring Company HI-2210967 1

Project No.

20 Dec 2021 Company Record Number Revision No.

Issue Date

Assembly Decay Heat Calculations for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210967 Rev. 1 Page i of iii Copyright © 2021 Holtec International, all rights reserved Project 3131 Revision Log Revision Description of Changes 0

Initial issue.

1 Added md5 sum of significant calculation files to Section 7 to improve the quality pedigree of the document.

Removed absolute file path form Section 7.

Moved md5 sums of aheat2.csv files from Section 9 to Section 7.

Assembly Decay Heat Calculations for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210967 Rev. 1 Page ii of iii Copyright © 2021 Holtec International, all rights reserved Project 3131 EXECUTIVE

SUMMARY

This report documents the calculation of the assembly specific decay heats for Indian Point Unit 2 and Unit

3. [

] 4 a, 4 b Assumptions that need Verification There are no assumptions that need verification.

Glossary IP2 Indian Point Unit 2 IP3 Indian Point Unit 3

Assembly Decay Heat Calculations for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210967 Rev. 1 Page iii of iii Copyright © 2021 Holtec International, all rights reserved Project 3131 Table of Contents Executive Summary...................................................................................................................................... ii Purpose............................................................................................................................................. 1 Acceptance Criteria.......................................................................................................................... 1 Methodology.................................................................................................................................... 1 Assumptions..................................................................................................................................... 1 Input Data........................................................................................................................................ 2 Computer Programs......................................................................................................................... 3 Computer Files................................................................................................................................. 3 Calculations..................................................................................................................................... 4 Results.............................................................................................................................................. 5 Conclusion....................................................................................................................................... 5 References........................................................................................................................................ 5

Assembly Decay Heat Calculations for Indian Point Unit 2 and 3 Wel@s P-1*e131i@tftfy lft.FeHHeten H O L T E C 9.0 RESULTS This repo1t documents the generation of r

. ] 4a, 4b

10.0 CONCLUSION

This repo1t documents calculations that suppo1t subsequent analyses, [

4 a, 4 b There are no specific conclusions.

11.0 REFERENCES

INTERNATIONAL

[l]

"B.T. Rearden and M.A. Jessee, Eds., SCALE Code System, ORNLffM-2005/39, Version 6.2.1, Oak Ridge National Laborato1y, Oak Ridge, Tennessee (2016). Available from Radiation Safety Information Computational Center as CCC-834

[2]

Email fom Giancarlo Delfni (from Entergy) to Joseph Cascio (from Holtec), with the Subject of "Fuel Weights", Dated on 05/06/2021.

[3]

Design Input Record, EN-DC-14l Rl 7 210108, Document Revision 0, Prepared by Raw Williams (from Entergy), Dated on 01/08/2021.

[4]

Design Input Record, EN-DC-141Rl8 210629, Document Revision 0, Prepared by Rich Motko (from Entergy), Dated on 06/29/2021.

[5]

Design Input Record, EN-DC-141Rl8_210624, Document Revision 0, Prepared by Rich Motko (from Entergy), Dated on 06/24/2021.

Nuclear Power Division 3131 Sponsoring Company Project No.

HI-2210972 3

28 Jan 2022 Company Record Number Revision No.

Issue Date Report Proprietary Information Record Type Proprietary Classification Nuclear Quality Class No Export Control Applicability Record

Title:

Spent Fuel Pool Loading Plan for Indian Point Unit 2 and Unit 3 Prepared by:

Reviewed by:

Approved by:

J.Rocheleau, 27 Jan 2022 P.Gowda, 28 Jan 2022 P.Gowda, 28 Jan 2022 Signature histories are provided here for reference only. Company electronic signature records are traceable via the provided Verification QR Code and are available for review within the secure records management system. A valid Verification QR Code and the presence of this covering page indicates this record has been approved and accepted.

Proprietary Classification This record is the property of and contains Proprietary Information owned by the Company. It is to be used only in connection with the performance of work by the Company, its designated subcontractors, or its client. Dissemination, reproduction, publication or representation, in whole or in part, for any other purpose by any other party is expressly forbidden.

Export Control Status Not applicable.

Spent Fuel Pool Loading Plan for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210972 Rev. 3 Page i of iii Copyright © 2021 Holtec International, all rights reserved Project 3131 Revision Log Revision Description of Changes 0

Initial issue.

1 Added md5 sum of significant calculation files to Section 7 to improve the quality pedigree of the document.

Removed absolute file path form Section 7.

2 Added reference [8].

Loading plan modified in accordance with the requested changes in [8]. SFP map and move list updated to reflect changes.

Updated md5 sum of calculation file archive.

3 All previous changes accepted.

Updated citation for reference [6].

Updated revision for reference [1].

Spent Fuel Pool Loading Plan for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210972 Rev. 3 Page ii of iii Copyright © 2021 Holtec International, all rights reserved Project 3131 EXECUTIVE

SUMMARY

This report documents the [

] 4 a, 4 b Spent Fuel Pool of Indian Point Unit 2 and Unit 3. [

] 4 a, 4 b.

Assumptions that need Verification There are no assumptions that need verification.

Glossary IP2 Indian Point Unit 2 IP3 SFP

[

L HLL

[

Indian Point Unit 3 Spent Fuel Pool

] 4 a, 4 b Heat Load Limit

] 4 a, 4 b

Spent Fuel Pool Loading Plan for Indian Point Unit 2 and 3 Holtec Proprietary Information HI-2210972 Rev. 3 Page iii of iii Copyright © 2021 Holtec International, all rights reserved Project 3131 Table of Contents Executive Summary...................................................................................................................................... 2 Purpose............................................................................................................................................. 1 Acceptance Criteria.......................................................................................................................... 1 Methodology.................................................................................................................................... 1 Assumptions..................................................................................................................................... 1 Input Data........................................................................................................................................ 2 Computer Programs......................................................................................................................... 2 Computer Files................................................................................................................................. 2 Calculations..................................................................................................................................... 4 UAL Threshold................................................................................................................... 4 SFP Loading Configuration................................................................................................ 4 Conclusion....................................................................................................................................... 5 References........................................................................................................................................ 5 IP3 SFP Loading Configuration.......................................................................................... 5

Appendix A:

HI-2210972 Rev. 3 Spent Fuel Pool Loading Plan for Indian Point Unit 2 and 3 Wel)es Pt*e13rt0t£1ey I-tiffltma)ten r

HOLTEC INTERNATIONAL Project 3131 4.a, 4.b

HOLTEC INTERNATIONAL Project 3131 4.a,4.b

HOLTEC INTERNATIONAL Project 3131 4.a, 4.b

HOLTEC INTERNATIONAL 4.a,4.b Project 3131

HOLTEC INTERNATIONAL Project 3131 4.a, 4.b

HOLTEC INTERNATIONAL Project 3131 4.a,4.b

Affidavit for Withholding Pursuant to 10 CFR 2.390 Non-Proprietary (5 Pages not including this Cover Page)

U.S. Nuclear Regulatory Commission ATTN: Document Control Clerk Non-Proprietary Enclosure 3 AFFIDAVIT PURSUANT TO 10 CFR 2.390 I, Jean A. Fleming, being duly sworn, depose and state as follows:

1) I have reviewed the information provided in the Enclosure 1 to HDI-IPEC-22-013 which is sought to be withheld, and am authorized to apply for its withholding.

2) The information sought to be withheld is in the calculations provided in to HDI-IPEC-22-013 dated February 1, 2022. The calculations contain information that is proprietary to Holtec International.

3) In making this application for withholding of proprietary information of which it is the owner, Holtec International relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b )( 4) and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR Part 9.17(a)(4), 2.390(a)(4), and 2.390(b)(l) for "trade secrets and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4). The material for which exemption from disclosure is here sought is all "confidential commercial information", and some portions also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280 (DC Cir. 1983).

Page 1 of 5

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EPID:L-2022-LLA-0072, Cyber Security Plan (Open)
Initiation Request, Request, Request Acceptance Supplement Administration Questions 21 October 2022 21 October 2022 Answers Results Approval... Other: ML22144A047, ML22242A259, ML22269A345, ML23100A117
MONTHYEAR2022-06-16 [Table View]

ML22032A017

Text

Subject:

References:

Dear Sir or Madam:

Enclosures:

Title:

SUMMARY

10.0 CONCLUSION

11.0 REFERENCES

Title:

SUMMARY

10.0 CONCLUSION

11.0 REFERENCES

Title:

SUMMARY

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