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Results
Other: ML19120A057, ML19120A058, ML19120A059, ML19120A061, ML19120A062, ML19120A063, ML19120A064, ML19164A139, ML19295C569, ML19295C570, ML19295C572, ML19295C573, ML19295C574, ML19343B289, ML20052E052, ML20105A138, ML20279A501, ML20351A371, ML22019A130, ML22019A223, ML22098A270, ML22098A283, ML22110A111, ML23027A217, ML23137A410, ML23321A254, ML24040A029, ML24141A272
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MONTHYEARML19015A3332019-01-24024 January 2019 Letter to J. Tomlinson Amendment No. 14 to Certificate of Compliance No. 1014 for the HI-STORM 100 Multipurpose Canister Storage System - Request for Additional Information (W/Enclosure 1) Project stage: RAI ML19164A1392019-06-13013 June 2019 Letter to J. Tomlinson Amendment No. 14 to Certificate of Compliance No. 1014 for the HI-STORM 100 Multipurpose Canister Storage System - Updated Review Schedule Project stage: Other ML19184A0082019-07-0202 July 2019 Letter to J. Tomlinson Approval of Holtec International Request for Withholding Information from Public Disclosure - Certificate of Compliance No. 1014, Hi-Storm 100 Multipurpose Canister Storage System, Amendment Request No. 14 Project stage: Withholding Request Acceptance ML19120A0762019-07-0909 July 2019, 25 September 2019 User Need for Rulemaking for the Holtec HI-STORM 100 Cask System, Amendment No. 14 Project stage: Request ML19120A0572019-07-0909 July 2019 Memorandum to J. Cai User Need for Rulemaking for the Holtec HI-STORM 100 Cask System, Amendment No. 14 Project stage: Other ML19120A0642019-09-25025 September 2019 Reference 6: Preliminary CoC 1014 Amendment No. 14 SER (Memorandum to J. Cai User Need for Rulemaking for the Holtec HI-STORM 100 Cask System, Amendment No. 14) Project stage: Other ML19120A0632019-09-25025 September 2019 Reference 5: Proposed CoC 1014 Amendment No. 14 Appendix B-100U (Memorandum to J. Cai User Need for Rulemaking for the Holtec HI-STORM 100 Cask System, Amendment No. 14) Project stage: Other ML19120A0622019-09-25025 September 2019 Reference 4: Proposed CoC 1014 Amendment No. 14 Appendix A-100U (Memorandum to J. Cai User Need for Rulemaking for the Holtec HI-STORM 100 Cask System, Amendment No. 14) Project stage: Other ML19120A0612019-09-25025 September 2019 Reference 3: Proposed CoC 1014 Amendment No. 14 Appendix B (Memorandum to J. Cai User Need for Rulemaking for the Holtec HI-STORM 100 Cask System, Amendment No. 14) Project stage: Other ML19120A0592019-09-25025 September 2019 Reference 2: Proposed CoC 1014 Amendment No. 14 Appendix a (Memorandum to J. Cai User Need for Rulemaking for the Holtec HI-STORM 100 Cask System, Amendment No. 14) Project stage: Other ML19120A0582019-09-25025 September 2019 Reference 1: Proposed CoC 1014 Amendment No. 14 CoC (Memorandum to J. Cai User Need for Rulemaking for the Holtec HI-STORM 100 Cask System, Amendment No. 14) Project stage: Other ML19295C5722019-11-26026 November 2019 Enclosure 3: CoC 1014, Amendment No. 14, Appendix B Project stage: Other ML19295C5692019-11-26026 November 2019 Enclosure 1: CoC 1014, Amendment No. 14, Certificate of Compliance Project stage: Other ML19295C5702019-11-26026 November 2019 Enclosure 2: CoC 1014, Amendment No. 14, Appendix a Project stage: Other ML19295C5732019-11-26026 November 2019 Enclosure 4: CoC 1014, Amendment No. 14, Appendix A-100U Project stage: Other ML19295C5762019-11-26026 November 2019 Enclosure 6: CoC 1014, Amendment No. 14, Final Safety Evaluation Report Project stage: Approval ML19295C5672019-11-26026 November 2019 Issuance of Certificate of Compliance No. 1014, Amendment No. 14 for the HI-STORM 100 Multipurpose Canister Cask System (Dkt. 72-1014, CAC: 001028, EPID: L-2018-LLA-0292 Project stage: Request ML19295C5772019-11-26026 November 2019 Letter to Holtec: Issuance of CoC 1014, Amendment No.14 Project stage: Approval ML19295C5742019-11-26026 November 2019 Enclosure 5: CoC 1014, Amendment No. 14, Appendix B-100U Project stage: Other ML19343B2892019-12-0909 December 2019 Appendix a to Certificate of Compliance No. 1014 Amendment No. 14, as Corrected Project stage: Other ML20050D2592020-02-14014 February 2020 Interim Storage Partners (ISP) First Request for Additional Information (RAI) Proposed Updated Submittal Schedule, Docket 72-1050 Cac/Epid 001028/L-2017-NEW-0002 Project stage: Request ML20052E0522020-02-14014 February 2020 Interim Storage Partners, LLC, RAI Responses Project stage: Other ML20064E6222020-03-0303 March 2020 U.S. Nuclear Regulatory Commission Approval of NAC International Request for Withholding Information from Public Disclosure for Coc 1025 Renewal (CAC No. 001028) Project stage: Withholding Request Acceptance ML20104C0482020-03-31031 March 2020 International - HI-STORM Umax Amendment 3 Responses to Requests for Additional Information Project stage: Response to RAI ML20105A1382020-04-0707 April 2020 Enclosure 7 - SAR Changed Pages Project stage: Other ML20100F2952020-04-0909 April 2020 Tn Americas LLC - Submittal of Renewal Application for the TN-68 Dry Storage Cask - CoC 1027 Project stage: Request ML20104A0402020-04-10010 April 2020 Request for Additional Information for HI-STAR 100 CoC Renewal Application Project stage: RAI ML20136A0522020-05-19019 May 2020 Final SER - Eos Amd 1 Project stage: Approval ML20181A2122020-06-30030 June 2020 Enclosure 1 - Request for Supplemental Information Project stage: Other ML20181A2112020-06-30030 June 2020 Request for Supplemental Information - Tn Americas Llc Renewal Application for the Tn-68 Dry Storage Cask System, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014) Project stage: Other ML20211L7072020-07-29029 July 2020 Response to Request for Supplemental Information - Tn Americas LLC, Renewal Application for the TN-68 Dry Storage Cask System, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014) Project stage: Supplement ML20212L8782020-07-30030 July 2020 Sunsi/Proprietary Review Determination Email to Tn TN-68 Renewal Rsi Response Project stage: Other ML20213C3252020-07-31031 July 2020 7-31-2020 Email Acknowledgement of NRC Receipt of GEH Morris Operation LRA and Start of Acceptance Review.Pdf Project stage: Acceptance Review ML20246G4822020-09-0202 September 2020 Acceptance Review Completed for CoC 1027 (TN-68) Renewal Project stage: Acceptance Review ML20279A5012020-11-23023 November 2020 U.S. Nuclear Regulatory Commissions Analysis of Exelon Generation Company, LLCs Decommissioning Fund Plan Update for Its Independent Spent Fuel Storage Installations Project stage: Other ML20344A3522020-12-10010 December 2020 CoC 1027 (TN-68) RAI Letter Project stage: RAI ML20344A3512020-12-10010 December 2020 CoC 1027 (TN-68) Renewal RAI Package Project stage: Request ML20344A3532020-12-10010 December 2020 CoC 1027 (TN-68) Renewal - Enclosure 1 Project stage: Other ML20351A3712020-12-16016 December 2020 Proprietary Determination Letter for HI-STAR 100 11-13-2020 Submittal Project stage: Other ML21014A0632021-01-14014 January 2021 Interim Storage Partners, LLC - Submittal of Supplemental Information to Support NRCs Continued Review of the Safety Case for the WCS CISF, Docket 72-1050 Cac/Epid 001028/L-2017-NEW-0002 Project stage: Supplement ML21040A4062021-02-0909 February 2021 Tn Americas LLC, Response to Request for Additional Information for the Application for Renewal of TN-68 Dry Storage Cask Project stage: Response to RAI ML21083A0292021-03-24024 March 2021 Supplemental Response to Request for Additional Information for the Tn Americas LLC Application for Renewal of TN-68 Dry Storage Cask, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014) Project stage: Supplement ML21334A5092021-12-21021 December 2021 Request for Additional Information for the Technical Review of the Application for Renewal of the Certificate of Compliance No. 1015 (Cac/Epid Nos. 001028/L-2020-RNE-0031) Project stage: RAI ML22004A1942022-01-12012 January 2022 3 Renewed CoC 1027 Amd 0 Tech Specs Project stage: Other ML22004A1952022-01-12012 January 2022 4 Renewed CoC 1027 Amd 1 Tech Specs Project stage: Other ML22004A1962022-01-12012 January 2022 5 Final SER - Renewed CoC 1027 Project stage: Approval ML22004A1902022-01-12012 January 2022 Issuance Letter - CoC 1027 Renewal Project stage: Other ML22004A1892022-01-12012 January 2022 Issuance Package for CoC 1027 Renewal Project stage: Request ML22019A2232022-04-25025 April 2022 HI-STORM FW Amendment 8 Proposed Appendix a Technical Specifications Project stage: Other ML22019A1302022-04-25025 April 2022 HI-STORM FW Amendment 8 Proposed Certificate of Compliance Project stage: Other 2020-04-10
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Category:Letter
MONTHYEARML22004A1902022-01-12012 January 2022 Issuance Letter - CoC 1027 Renewal ML21083A0292021-03-24024 March 2021 Supplemental Response to Request for Additional Information for the Tn Americas LLC Application for Renewal of TN-68 Dry Storage Cask, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014) ML21040A4062021-02-0909 February 2021 Tn Americas LLC, Response to Request for Additional Information for the Application for Renewal of TN-68 Dry Storage Cask ML20366A1062020-12-29029 December 2020 Tn Americas LLC Updated Licensing Plans ML20344A3522020-12-10010 December 2020 CoC 1027 (TN-68) RAI Letter ML20246G4822020-09-0202 September 2020 Acceptance Review Completed for CoC 1027 (TN-68) Renewal ML20211L7072020-07-29029 July 2020 Response to Request for Supplemental Information - Tn Americas LLC, Renewal Application for the TN-68 Dry Storage Cask System, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014) ML20181A2112020-06-30030 June 2020 Request for Supplemental Information - Tn Americas Llc Renewal Application for the Tn-68 Dry Storage Cask System, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014) ML20100F2952020-04-0909 April 2020 Tn Americas LLC - Submittal of Renewal Application for the TN-68 Dry Storage Cask - CoC 1027 ML19105A0082019-04-15015 April 2019 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML18187A0132018-07-0505 July 2018 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML18157A2822018-06-0505 June 2018 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML17194A4022017-07-13013 July 2017 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML17167A0732017-06-16016 June 2017 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML17101A5412017-04-11011 April 2017 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML16169A0122016-06-17017 June 2016 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML15156A4112015-06-0505 June 2015 ISFSI - Registration of Use of Independent Spent Fuel Storage Installation Casks ML15147A0792015-05-22022 May 2015 Registration of Use of Independent Spent Fuel Storage Installation Casks ML15146A0052015-05-22022 May 2015 Registration of Use of Independent Spent Fuel Storage Installation Casks RS-14-167, Registration of Use of Cask to Store Spent Fuel2014-05-29029 May 2014 Registration of Use of Cask to Store Spent Fuel ML14015A0102014-01-14014 January 2014 Letter to P. R. Simpson Exemption Request for Transnuclear, Inc., TN-68 Casks Loaded with Fuel Bundles with Incorrect Cooling Times at the Peach Bottom Independent Spent Fuel Storage Installation - Acknowledgment of Withdrawal (TAC No. L247 ML13351A2552013-12-17017 December 2013 Letter to P. R. Simpson Peach Bottom Exemption Request (TAC No. L24749) ML13228A3992013-08-12012 August 2013 Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109 ML13196A3842013-07-12012 July 2013 Letter to P. R. Simpson Peach Bottom Exemption Request - Accepted for Review (TAC No. L24749) ML13162A7352013-06-11011 June 2013 Registration of Use of Cask to Store Spent Fuel RS-13-167, Peach Bottom, Units 2 and 3, Registration of Use of Cask to Store Spent Fuel2013-06-11011 June 2013 Peach Bottom, Units 2 and 3, Registration of Use of Cask to Store Spent Fuel RS-13-154, Registration of Use of Cask to Store Spent Fuel2013-05-31031 May 2013 Registration of Use of Cask to Store Spent Fuel RS-13-094, Registration - Application of Amended Certificate of Compliance to Loaded Spent Fuel Storage Casks2013-04-0202 April 2013 Registration - Application of Amended Certificate of Compliance to Loaded Spent Fuel Storage Casks ML13058A0432013-02-22022 February 2013 Submittal of Independent Spent Fuel Storage Installation (ISFSI) Cask Event Report RS-12-090, Registration of Use of Cask to Store Spent Fuel2012-05-25025 May 2012 Registration of Use of Cask to Store Spent Fuel ML11172A3192011-06-20020 June 2011 Submittal of Registration for Independent Spent Fuel Storage Installation, Casks #53 and #54 ML11158A0552011-06-0303 June 2011 Submittal of Registration for Independent Spent Fuel Storage Installation Casks #45, #46 and #47 ML0913902972009-05-15015 May 2009 Submittal of Registration for Independent Spent Fuel Storage Installation (ISFSI) Casks #42, #43 and #44 ML0716902242007-07-0505 July 2007 Co. and Amergen Energy Company'S Plants Closure Letters - Approval to Use Delta Protection Mururoa Model Blu Single - Use Self-Fed Respiratory Protection Equipment RS-06-179, Cover Letter for Additional Information - Application to Use Weighting Factors for External Exposure2006-12-13013 December 2006 Cover Letter for Additional Information - Application to Use Weighting Factors for External Exposure RS-06-130, Amergen and Exelon Nuclear - Response to Request for Additional Information - Application to Use Weighting Factors for External Exposure2006-09-0606 September 2006 Amergen and Exelon Nuclear - Response to Request for Additional Information - Application to Use Weighting Factors for External Exposure RS-06-051, Amergen, Response to Request for Additional Information - Application to Use Weighting Factors for External Exposure2006-04-18018 April 2006 Amergen, Response to Request for Additional Information - Application to Use Weighting Factors for External Exposure RS-05-165, Application to Use Weighting Factors for External Exposure2005-12-14014 December 2005 Application to Use Weighting Factors for External Exposure ML0518900652005-06-24024 June 2005 Submittal of Registration for Independent Spent Fuel Storage Installation (ISFSI) Casks #27 and #28 ML0517304342005-06-14014 June 2005 Submittal of Registration for Independent Spent Fuel Storage Installation (ISFSI) Casks #25 and #26 RS-04-177, Response to Request for Additional Information - Exemption from 10CFR20.1703 and 10CFR20 Appendix a Use of Delta Protection French Designed Respiratory Protection Equipment2004-12-0707 December 2004 Response to Request for Additional Information - Exemption from 10CFR20.1703 and 10CFR20 Appendix a Use of Delta Protection French Designed Respiratory Protection Equipment ML0416900922004-06-11011 June 2004 Submittal of Registration for Independent Spent Fuel Storage Installation (ISFSI) Casks #21 and #22 ML0317401732003-06-13013 June 2003 Submittal of Registration for Independent Spent Fuel Storage Installation (ISFSI) Casks #19 and #20 ML0220405822002-07-11011 July 2002 Submittal of Registration for Independent Spent Fuel Storage Installation (ISFSI) Casks #14 & #15 2022-01-12
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML21083A0292021-03-24024 March 2021 Supplemental Response to Request for Additional Information for the Tn Americas LLC Application for Renewal of TN-68 Dry Storage Cask, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014) ML21040A4062021-02-0909 February 2021 Tn Americas LLC, Response to Request for Additional Information for the Application for Renewal of TN-68 Dry Storage Cask ML20211L7072020-07-29029 July 2020 Response to Request for Supplemental Information - Tn Americas LLC, Renewal Application for the TN-68 Dry Storage Cask System, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014) 2021-03-24
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Text
Orano TN 7160 Riverwood Drive Suite 200 Columbia, MD 21046 USA Tel: 410-910-6900 Fax: 434-260-8480 July 29, 2020 E-57065 U. S. Nuclear Regulatory Commission Attn: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852
Subject:
Response to Request for Supplemental Information - TN Americas LLC Renewal Application for the TN-68 Dry Storage Cask System, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014)
Reference:
Letter from Christian Jacobs (NRC) to Prakash Narayanan (TN Americas LLC), Request for Supplemental Information - TN Americas LLC Renewal Application for the TN-68 Dry Storage Cask System, Certificate of Compliance No. 1027 (Docket No. 72-1027, CAC No. 001028, EPID: L-2020-RNW-0014), dated June 30, 2020 TN Americas LLC (TN) hereby submits our response to the Request for Supplemental Information (RSI) forwarded by the letter referenced above. Enclosure 1, herein, provides the response to the RSI. The RSI response did not require changes to the Application for Renewal of Certificate of Compliance (CoC) No. 1027 for the TN-68 Dry Storage Cask.
Should you have any questions regarding this submittal, please do not hesitate to contact Mr. Douglas Yates at 434-832-3101, or by email at Douglas.Yates@orano.group.
Prakash Narayanan Chief Technical Officer cc: Christopher Markley, NRC DFM Doug Yates, TN
Enclosure:
- 1. RSI and Response
RSI and Response to E-57065 Page 1 of 5 Materials RSI:
RSI-M1:
Provide supplemental information that addresses the differences between the cladding alloys to demonstrate how the M5 cladding included in the Department of Energy (DOE) High Burnup Dry Storage Cask Research and Development Project can be used as a surrogate for the high burnup Zircaloy-2 clad fuel in the TN-68 Dry Storage Cask.
The supplemental information should address the differences between the high burnup Zircaloy-2 cladding and the M5 in the following areas: (1) the potentially higher hydrogen content in the cladding, (2) the higher fuel burnup, and (3) the lower threshold stress for reorientation. In addition, the supplemental information should address the maximum cladding temperatures for the TN-68 dry storage cask and the temperatures measured in the DOE High Burnup Dry Storage Cask Research and Development Project to show how it can be used as a surrogate.
Additional information is provided below.
As background, the CoC No. 1027 Renewal Application High Burnup Fuel Aging Management Program Section 4.5.1 states:
The parameters of the surrogate demonstration program are applicable to the Design bases HBU fuel, as:
maximum allowed burnup of the design-bases HBU fuel (i.e., 60.0 GWd/MTU) is on the order of the nominal burnup of the fuel in the surrogate demonstration program (i.e., 58 GWd/MTU),
the similar cladding texture between Zircaloy-2 and M5 of recrystallized annealed (RXA) and higher hoop stresses in the M5 PWR fuel cladding when compared to Zircaloy-2 BWR fuel cladding, M5 PWR fuel cladding can be considered an enveloping surrogate for Zircaloy-2 BWR fuel cladding, and the cladding temperature of the HBU fuel is limited to the values in ISG-11 and the cladding temperature in the surrogate demonstration program is as close to the ISG-11 limits as practicable.
The staff notes that, in addition to cladding texture and hoop stress, cladding hydrogen content as a result of fuel burnup, threshold stress, and temperature are important factors for hydride reorientation in spent fuel cladding. The staff is seeking information regarding the differences between the high burnup Zircaloy-2 cladding and the M5 in the following areas:
- 1. A comparison of Zircaloy-2 and M5 cladding alloys in NUREG-2214 Section 3.6.1 shows that above 45 gigawatt-days per metric ton of uranium (GWd/MTU), the hydrogen uptake in Zircaloy-2 cladding is greater than the hydrogen uptake for M5 cladding (NRC, 2019),
which leads to greater hydrogen content. In addition, the Zircaloy-2 cladding appears to have more variability in hydrogen uptake cladding when the fuel burnup exceeds 50 GWd/MTU (Geelhood and Beyer 2011) compared to M5 with a similar burnup (Hanson et al. 2016, Figure 3-11).
RSI and Response to E-57065 Page 2 of 5
- 2. The actual maximum burnup for the M5 cladding in the DOE High Burnup Dry Storage Cask Research and Development Project is 53.5 GWd/MTU (Hanson et al. 2016 FCRD-UFD-2016-000063, Figure 6-1), whereas the maximum allowed burnup for the Zircaloy-2 cladding in the TN-68 Dry Storage Cask is 60 GWd/MTU as stated in the CoC No. 1027 Amendment 1 Technical Specifications (ML073050262).
- 3. A review of data in NUREG-2214 Section 3.6.1 indicates that the threshold stress for Zircaloy-2 is reported to be as low as 70 megapascals (MPa) which is substantially lower than the value of 90 MPa reported for the other Zirconium alloys used in fuel cladding (NRC 2019).
- 4. The DOE High Burnup Dry Storage Cask Research and Development Project uses a TN-32 Dry Storage Cask. The maximum measured temperature during loading and cask placement for the DOE High Burnup Dry Storage Cask Research and Development Project was 237°C [459°F] (Hanson 2018). The maximum fuel cladding temperature for the TN-68 dry storage cask is 343°C [649°F] as stated in Table 3-3 of the TN-68 renewal application (ML20100F295).
This information is needed to determined compliance with 10 CFR 72.240(c)(3).
References Geelhood, K., and C. Beyer, Hydrogen Pickup Models for Zircaloy-2, Zircaloy-4, M5' And ZIRLO', Paper T2-011, 2011 Water Reactor Fuel Performance Meeting, Chengdu, China, Sept. 11-14, 2011 (ML12093A469).
Hanson, B.D., S.C. Marschman, M.C Billone, J. Scaglione, K.B. Sorenson, S.J. Saltzstein, High Burnup Spent Fuel Data Project Sister Rod Test Plan Overview, FCRD-UFD-2016-0000632016, PNNL-25374, April 29, 2016.
Hanson, B., High Burnup Spent Fuel Data Project & Thermal Modeling and Analysis, Presentation at the NWTRB Meeting, Albuquerque, NM October 24, 2018.
U.S. Nuclear Regulatory Commission, NUREG-2214, Managing Aging Processes in Storage (MAPS) Report, July 2019 (ML19214A111).
RSI and Response to E-57065 Page 3 of 5 Response to RSI-M1:
The High Burnup Spent Fuel Data Project and the testing of sister rods are focused on bridging the technical data gaps associated with the cladding for high burnup (HBU) pressurized water reactor (PWR) and boiling water reactor (BWR) fuel assemblies. This project aims to be representative of all HBU PWR and BWR fuel assemblies above 45 GWd/MTU. For this reason, the HBU spent nuclear fuel (SNF) in the Research Project Cask has been chosen to be representative of typical HBU fuel assemblies, with M5 cladding alloy expected to cover all recrystallized cladding such as Zy-2. Meanwhile, the sister rods testing has not only been defined to provide an initial picture of the fuel assemblies studied in the Research Cask project but also to study individual specific rods with peak conditions such as peak burnup rods and/or high peak cladding temperature. Nevertheless, according to the High Burnup Spent Fuel Data Project Sister Rod Test Plan Overview [1], the burnups in this High Burnup Spent Fuel Data Project are fully representative of fuel not only discharged to date, but of expected future discharges as well. Moreover, the peak cladding temperature, as well as the assembly-average burnup mentioned in the TN-68 CoC, are conservatively higher than those actually expected or measured in the HBU demonstration program.
Item 1:
Hydride reorientation embrittlement threshold: The Electric Power Research Institute (EPRI) report [2], based on studies such as [3] and [4], shows that the 70 MPa threshold mentioned by Kamimura [5] is not applicable for Zy-2 with liner when a low cooling rate is applied. Indeed in that case, hydrogen in solution has more time to diffuse into the pure Zr inner liner (due to the terminal solid solubility precipitation (TSSp) difference between Zr and Zy-2), leading to large hydride depleted zones and little radial hydride reorientation. This statement is consistent with the SPAR II report from IAEA [6]. Moreover, the burnups of some irradiated fuel claddings under investigation can exceed the 55.5 or even 60 GWd/MTU considered in the application. In the study from the CEA [3], Westinghouse Sweden supplied the LK3 cladding material, which was irradiated in the Leibstadt BWR for seven cycles up to 68 GWd/tU (local burn-up). Thus, Zy-2 cladding with liner would be immune to hydride reorientation embrittlement during dry storage and is expected to retain, or even increase ductility (due to irradiation defects annealing).
Most of BWR HBU fuel claddings are expected to have an inner liner, since according to [7], this technology was introduced in the 1980s and most of HBU fuel assemblies have been generated after this date. The ORNL report [8] does discuss the introduction of liners or barrier fuel into the GE design. The report also states that barrier fuel was offered commercially by GE beginning in 1983. By 1986, GE expected that 100% of the fuel produced at their Wilmington facility would be barrier fuel (See page 27 of 165 in [8]). The general licensee also confirmed that all HBU fuel assemblies have a liner in the fuel cladding.
Item 2:
High burnup range: The maximum allowed burnup for the Zy-2 cladding as reported in the Technical Specifications for Certificate of Compliance (CoC) No. 1027 is 60 GWd/MTU.
However, according to the DOE test plan overview [1], no HBU BWR fuel assembly from the United States would be expected to see an assembly-average burnup above the range of 55 GWd/MTU.
RSI and Response to E-57065 Page 4 of 5 Moreover, as stated in the sister rod testing plan, peak rod-average burnups are typically 5 to 9 percent higher than the assembly-average burnup (Geelhood and Beyer 2013). Where possible, a sister rod representing the peak burnup of its donor assembly was chosen for this testing program, so it is expected that individual rod-average burnups as high as 59 GWd/MTU will be tested. Thus, other than for lead test assemblies (LTA), the burnups in this High Burnup Spent Fuel Data Project are fully representative of fuel not only discharged to date but of expected future discharges as well.
Item 3:
Hoop stress threshold: End of Life rod internal pressures in BWR fuel cladding (Zy-2) are expected to be lower than for PWR (M5) leading to hoop stresses in the range of 40 MPa as reported in NUREG 2214 [9] (based on Raynauds work [10]). This hoop stress is lower than the 70 MPa threshold mentioned above where a loss of ductility is induced, especially when combined with peak clad temperature around 300 °C. Note that in the study from Kamimura [5],
a threshold stress of 40 MPa is mentioned but deals only with initiation of hydride reorientation on lined Zy-2 without inducing loss of ductility and it becomes not applicable for slow cooling rates associated with dry storage (as explained above).
Moreover, some margin can be added to the demonstration, since the hoop stress value reported at 40 MPa in [9] and [10] has been evaluated with a cladding temperature of 400 °C.
With a more realistic peak cladding temperature (PCT) combined with the lower temperature of the gas in the plenum, a lower hoop stress value could be derived using the ideal gas ratio between the pressure and the temperature.
Consequently, even for Zy-2 cladding without liner, it is expected that the fuel assemblies are not affected by hydride reorientation embrittlement. The HBU demonstration program is aimed to provide further arguments and demonstration of this statement.
Item 4:
PCT range: Regarding the PCT, the maximum measured thermocouple temperature on the HBU project was 237 °C, which corresponds to a PCT of about 240 °C as provided in Section 6.2.1.3 of [11]. The temperature limit on the radial neutron shield of the TN-32 cask limited the High Burnup Demonstration Cask Project from being able to further increase the heat load and cladding temperatures for the Research Cask. It must be noted as a fact, however, that for the High Burnup Research Project Cask, the calculated PCT for the license application was originally 348 °C as provided in Section 6.2.1.3 of [11]. So for the TN-68 license renewal application, the calculated PCT of 343 °C is comparable to the original design basis calculation for the HBU demonstration of 348 °C and the actual PCT (if measured) in the TN-68 would be expected to be on the order of 240 °C, similar to the HBU demonstration. Note also that the sister rods testing will simulate higher peak cladding temperatures reached by some fuel claddings, to force hydride reorientation and demonstrate the fuel cladding performance.
In conclusion, the BWR Zy-2 cladding is not expected to be sensitive to hydride reorientation embrittlement, either through the inner liner immunity or due to the low hoop stress on BWR. As a final demonstration of this statement, the DOE High Burnup Dry Storage Cask Research and Development Project (including the sister rods testing) can be used as a surrogate for the HBU Zy-2 clad fuel in the TN-68 Dry Storage Cask.
RSI and Response to E-57065 Page 5 of 5
References:
- 1. HighBurnup Spent Fuel Data Project Sister Rod Test Plan Overview-Hanson, B.D-FCRD-UFD-2016-000063, PNNL-25374, April 29, 2016
- 2. EPRI TR 3002016033, Effect of Hydride Reorientation in Spent Fuel CladdingStatus from Twenty Years of Research, Final Report, June 2020
- 3. Hydride Reorientation and its Impact on Ambient Temperature Mechanical Properties of High Burn-Up Irradiated and Unirradiated Recrystallized Zircaloy-2 Nuclear Fuel Cladding with an Inner Liner-Q. Auzoux-Journal of Nuclear Materials 494 (2017) 114e126
- 4. Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage-Masaki Aomi-Journal of ASTM International, Vol. 5, No. 9
- 5. K. Kamimura (2010 November), Integrity Criteria of Spent Fuel for Dry Storage in Japan at International Seminar on Spent Fuel Storage - ISSF 2010
- 6. IAEA-TECDOC-1680, Spent Fuel Performance Assessment and Research: Final Report of a Coordinated-Research Project (SPAR-II)
- 7. C.D. Williams, M.O. Marlowe, R.B Adamson, S.B., Wisner, R.A. Band, J.S. Armijo (1996),
Zircoloy-2 Lined Zirconium Barrier Fuel Cladding in Zirconium in the Nuclear Industry-11th International Symposium
- 8. ORNL / TM-10902, Physical Characteristics of GE BWR Fuel Assemblies - R. S. Moore, June 1989
- 9. NUREG-2214 Managing Aging Processes in Storage (MAPS) Report, U.S. Nuclear Regulatory Commission, July 2019, ADAMS No. ML19214A111
- 10. Cladding Stress During Extended Storage of High Burnup Spent Nuclear Fuel-Patrick A.C.
Raynaud-Journal of Nuclear Materials 464 (2015) 304-312, ADAMS No. ML15180A411
- 11. EPRI TR 3002015076, High Burnup Dry Storage Research Project Cask Loading and Initial Results, Final Report, October 2019 Impact:
No change as a result of this RSI.