Letter Sequence Supplement |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: L-23-005, Independent Spent Fuel Storage Installation License Renewal Application, Revision 1 (Cac/Epid No. 001028/L-2022-RNW-0007), ML19150A559, ML19182A107, ML20002A442, ML20009D008, ML20010D564, ML20015A450, ML20015A451, ML20015A454, ML20028E845, ML20028E846, ML20049A082, ML20052E146, ML20052E154, ML20065N281, ML20071F156, ML20076D696, ML20099A180, ML20104C015, ML20104C018, ML20104C019, ML20105A135, ML20105A136, ML20105A137, ML20105A138, ML20105A139, ML20105A173, ML20111A240, ML20136A050, ML20136A051, ML20150A335, ML20150A421, ML20155K741, ML20155K743, ML20155K744, ML20161A088, ML20163A702, ML20163A703, ML20163A704, ML20181A211, ML20181A212, ML20192A328, ML20192A329, ML20212L768, ML20212L769, ML20261H420, ML20269A259, ML20279A577, ML20279A586, ML20289A493... further results
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MONTHYEARML20052D9362018-07-0303 July 2018 Response to Nrg Request for Additional Information (RAI) Regarding NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density Project stage: Request ML18267A2142018-08-29029 August 2018, 25 September 2018 Package: Summary of August 29, 2018, Public Meeting with Interim Storage Partners to Discuss Consolidated Emergency Response Plan for Its Proposed WCS Consolidated Interim Storage Facility (W/Enclosure 1 and 2) Project stage: Request ML18267A2112018-09-25025 September 2018 Memorandum to A. Rivera-Varona Summary of August 29, 2018, Public Meeting with Interim Storage Partners to Discuss Consolidated Emergency Response Plan for Its Proposed WCS Consolidated Interim Storage Facility (W/Enclosure 1 and 2) Project stage: Meeting ML18320A1842018-11-16016 November 2018 Letter to J. Isakson Interim Storage Partners' License Application to Construct and Operate the Waste Control Specialists Consolidated Interim Storage Facility, Andrews County, Texas, Dkt No. 72-1050 - First RAI, Part 1 (W/Enclosure 1) Project stage: RAI ML19032A2302019-02-0404 February 2019 Summary of Closed Public Meeting to Discuss RAI Issued in Connection with Nrc'S Review of the Interim Storage Partner Consolidated Isfs Application for a Facility at Andrews County, Texas (W/Encl. 1&2) Project stage: RAI ML19065A0192019-03-0606 March 2019 Letter to J. Isakson Interim Storage Partners Llc'S License Application to Construct and Operate the WCS Consolidated Interim Storage Facility, Andrews County, Texas, Docket No. 72.1050 - First Request for RAI Part 2 (W/Enclosure 1) Project stage: RAI ML19072A1562019-03-14014 March 2019 Summary of Partially Closed Public Meeting to Discuss Request for Additional Information Issued in Connection with Nrc'S Review of the ISP Cisf Application for a Facility at Andrew'S County, Tx (W/Encl. 1&2) Project stage: RAI ML19126A0682019-04-0303 April 2019, 6 May 2019 Summary of April 16, 2019, Partially Closed Public Meeting to Discuss RAI Issued in Connection with Nrc'S Review of the ISP Consolidated Isf Application for a Facility at Andrews County, Texas Project stage: Request ML19105B2172019-04-19019 April 2019 Memorandum to C. Regan Summary of March 20, 2019, Public Meeting to Discuss Request for Additional Information Issued in Connection with Nrc'S Review of the Interim Storage Partners Consolidated Isf Application (W/Enclosures 1 and 2) Project stage: RAI ML19120A4282019-04-23023 April 2019 Letter to J. Isakson Interim Storage Partners Llc'S License Application to Construct and Operate the Waste Control Specialists Consolidated Interim Storage Facility, Andrews County, Texas, Dkt No. 72-1050 - First RAI (W/Enclosure) Project stage: RAI ML19126A0662019-05-0606 May 2019 Memorandum to C. Regan Summary of April 16, 2019, Partially Closed Public Meeting to Discuss RAI Issued in Connection with Nrc'S Review of the ISP Consolidated Isf Application for a Facility at Andrews County, Texas (W/Enclosure 1 & 2) Project stage: RAI ML20015A4502019-05-31031 May 2019 Sprint Andrews County Disposal Facility, Andrews County, Texas- Railroad Commission of Texas Commercial Processing and Disposal Facility Permit Application Project stage: Other ML19150A5592019-06-0303 June 2019 Letter to J. Isakson Site Audit Plan for Interim Storage Partners Proposed Application for a Site-Specific License of an Away-from-Reactor Independent Spent Fuel Storage Installation Project stage: Other ML19182A1072019-07-0101 July 2019 Letter to J. Isakson Interim Storage Partners Llc'S Application for a Specific ISFSI for the Waste Control Specialists Consolidated Interim Storage Facility for Spent Nuclear Fuel - Revised Review Schedule Project stage: Other ML20015A4512019-08-22022 August 2019 Report No. R1432-01, Acoustical Analysis of ISP Cisf Project stage: Other ML20015A4542019-11-30030 November 2019 Socioeconomic Impacts of the Proposed Spent Nuclear Fuel Consolidated Interim Storage Facility, Andrews County, Texas, Revision 5 Project stage: Other ML19357A1762019-12-18018 December 2019 NAC International - Submission of a Request to Renew the U.S. Nuclear Regulatory Commission Certificate of Compliance No. 1025 for the NAC-MPC Cask System Project stage: Request ML20002A4422019-12-20020 December 2019 International _Affidavit Project stage: Other ML19354A7142019-12-20020 December 2019 Approval of Tn America Request for Withholding Information from Public Disclosure for Coc 1029 Renewal Request for Supplemental Information Responses (CAC No. 001028) Project stage: Withholding Request Acceptance ML19360A0472019-12-26026 December 2019 Internationals Application for Specific Independent Spent Fuel Storage Installation License for the Hi-Store Consolidated Interim Storage Facility for Spent Nuclear Fuel - Request for Clarification of Responses Related to Emergency Response Project stage: Approval ML20009D0512020-01-0606 January 2020 Notification of NRC Acceptance of the Standardized Advanced NUHOMS CoC 1029 Renewal Application for Review Project stage: Acceptance Review ML20009D0082020-01-0606 January 2020 Acknowledgement of NRC Receipt of CoC 1025 (NAC-MPC) Renewal Application Project stage: Other ML20015A4522020-01-0606 January 2020 Interim Storage Partners LLC - Submittal of Supplemental Information in Support of RAI, Part 3 - Clarification Related to the Response to RAI AQ-6 Project stage: Supplement ML19354B6372020-01-0707 January 2020 Exemption Request for NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density Request for Additional Information Project stage: RAI ML20010D5642020-01-10010 January 2020 Proprietary Determination Letter for HI-STAR 100 CoC Renewal Submittals Project stage: Other ML20028E8462020-01-17017 January 2020 Enclosure 3 - RAIs and Responses Project stage: Other ML20028E8452020-01-17017 January 2020 Enclosure 1 - Affidavits Project stage: Other ML20031D0562020-01-29029 January 2020 Interim Storage Partners, LLC - Submittal of ISP Updated Draft Responses for Rals NP-8-1, NP-8-2 and Associated SAR Markups from First Request for Additional Information, Part 2, Docket 72-1050 Cac/Epid 001028/L-2017-NEW-0002 Project stage: Draft Request ML20049A0822020-01-31031 January 2020 International - HI-STORM 100 Storage CoC Renewal Application Project stage: Other ML20049A0812020-01-31031 January 2020 Holtec International - HI-STORM 100 Storage CoC Renewal Application Project stage: Request ML20034E8352020-02-0303 February 2020 Letter-Materials Request for Additional Information Clarification with Enclosure Project stage: RAI ML20034E9872020-02-11011 February 2020 Meeting Summary - Meeting with Westinghouse Electric Company, LLC, Pre-Application Amendment No. 5 of Storage CoC No. 1026 for the Fuelsolutions Spent Fuel Management System, November 21, 2019 Project stage: Meeting ML20052D9962020-02-14014 February 2020 Interim Storage Partners, LLC - Submission of ISP Responses for RAIs and Associated Document Markups from First Request for Additional Information, Part 2, Docket 72-1050 Cac/Epid 001028/L-2017-NEW-0002 Project stage: Request ML20052E1462020-02-17017 February 2020 Interim Storage Partners, LLC - Submittal of Revision 3 of the Environmental Report for the WCS CISF, Docket 72-1050 Cac/Epid 001028/L-2017-NEW-0002 Project stage: Other ML20052E1542020-02-17017 February 2020 WCS Consolidated Interim Spent Fuel Storage Facility Environmental Report, Revision 3 - Part 2 of 3 Project stage: Other ML20064F6162020-02-29029 February 2020 January 15, 2020, Summary of Meeting with Holtec International, Inc., to Discuss the Upcoming Submittal of the Application for Renewal of the Storage Certificate of Compliance No. 1014 for the HI-Storm 100 Cask System Project stage: Meeting ML20063M0152020-03-0303 March 2020 HI-STORM 100 Renewal Presubmittal Meeting (Holtec Slides, 1-15-20) Project stage: Meeting 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 ML20071J0552020-03-0505 March 2020 Notice of Cancelled Meeting with the U.S. Department of Energy, Idaho Operations Office to Discuss the Upcoming Submittal of the Application for Renewal of the Idaho Spent Fuel Facility License (SNM-2512) Project stage: Meeting ML20065J4272020-03-0505 March 2020 Submittal of Renewal Application for the TN-32 Dry Storage Cask - CoC 1021 Project stage: Request ML20071F1562020-03-0505 March 2020 Interim Storage Partners, LLC - Affidavit Project stage: Other ML20071F1532020-03-0505 March 2020 Interim Storage Partners, LLC - Supplemental Information in Support of NRCs Environmental Review Project stage: Supplement ML20065L3442020-03-0606 March 2020 Amendment No. 15 to Certificate of Compliance No. 1014 for the Hi-Storm 100 Multipurpose Canister Storage System - Request for Additional Information Project stage: RAI ML20066K5782020-03-0606 March 2020 Acceptance Review of Request for Amendment No. 7 to Certificate of Compliance No. 1032 for the HI-STORM Flood/Wind Multipurpose Canister Storage System Project stage: Acceptance Review ML20065N2812020-03-0909 March 2020 ISFSI Preamble-License Renewal Order Project stage: Other ML20076D6962020-03-11011 March 2020 Interim Storage Partners, LLC - Submittal of Clarifications to Support NRCs Continued Review of the Safety Case for the WCS CISF Project stage: Other ML20104C0152020-03-30030 March 2020 International - Amendment No. 4 to the HI-STORM Umax Canister Storage System Project stage: Other ML20104C0182020-03-30030 March 2020 International - HI-STORM Umax Amendment 4 FSAR - Changed Pages Project stage: Other ML20104C0202020-03-30030 March 2020 International - HI-STORM Umax Amendment 4 Responses to Requests for Additional Information - Supplemental Information Project stage: Supplement ML20104C0192020-03-30030 March 2020 International - Affidavit for Kimberly Manzione Project stage: Other 2019-07-01
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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.