Letter Sequence RAI |
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CAC:001794, (Approved, Closed) EPID:L-2023-DOT-0005, Enclosure 3-1, Summary of Changes to the Safety Analysis Report for the Japanese Certificate of Competent Authority Model No. JMS-87Y-18.5T, Revision 1 (J/2044/B(U)F) (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement
Results
Other: ML23058A279, ML23058A281, ML23058A284, ML23058A286, ML23058A287, ML23059A252, ML23067A441, ML23109A009, ML23115A080, ML23115A082, ML23115A086, ML23115A320, ML23160A084, ML23160A087, ML23310A163, ML23310A297, ML23310A299, ML23310A300, ML23310A301, ML23310A302, ML23310A303, ML23310A304, ML23310A305, ML23310A306, ML23331A675, ML23331A679, ML23331A681, ML23331A683, ML23331A684, ML23331A686, ML23331A688, ML23331A690, ML23331A692, ML23331A693, ML23331A695, ML23331A698, ML23331A700, ML23331A702, ML23331A897, ML23331A898, ML23331A899... further results
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MONTHYEARML23331A9071989-06-19019 June 1989 Decree No. 76/1989 Coll., Decree of the Czech Labour Safety Authority to Ensure the Safety of Technical Equipment in the Nuclear Power Industry (Cancelled: 7/27/2005) Project stage: Other ML23331A8971991-05-31031 May 1991 Decree No. 263/1991 Coll.Decree of the Czech Office of Labour Safety Amending and Supplementing Decree No. 76/1989 Coll. of the Czech Office of Labour Safety to Ensure the Safety of Technical Equipment in the Nuclear Power Industry (Cancell Project stage: Other ML23331A9041997-01-24024 January 1997 Act No. 18/1997 Coll., Peaceful Utilisation of Nuclear Energy and Ionising Radiation (the Atomic Act) and on Amendments and Alterations to Some Acts Project stage: Other ML23331A9011997-08-15015 August 1997 Regulation No. 214/1997 Sb., Quality Assurance in Activities Related to the Utilization of Nuclear Energy and in Radiation Practices and Laying Down Criteria for the Assignment and Categorization of Classified Equipment Into Safety Classes Project stage: Other ML23331A8991998-08-31031 August 1998 Regulation No. 106/1998 Sb., Nuclear Safety and Radiation Protection Assurance During Commissioning and Operation of Nuclear Facilities Project stage: Other ML23331A9001999-08-21021 August 1999 Regulation No. 195/1999 Sb., Requirements on Nuclear Installations for Assurance of Nuclear Safety, Radiation Protection and Emergency Preparedness Project stage: Other ML23310A3032002-06-13013 June 2002 Decree No. 317/2016, on type-approval of Packagings for Shipment, Storage and Disposal of Nuclear Materials and Radioactive Substances..., State Officer for Nuclear Safety, June 13, 2002, Czech Republic (Model No. SKODA Package Revalidation Project stage: Other ML23331A9022002-06-13013 June 2002 Regulation No. 307/2002 Coll., Radiation Protection Project stage: Other ML23331A8982002-06-13013 June 2002 Decree No. 317/2002, on type-approval of Packagings for Shipment, Storage and Disposal of Nuclear Materials and Radioactive Substances, on type-approval of Ionizing Radiation Sources and Shipment of Nuclear Materials and Specified Radioacti Project stage: Other ML23331A6922004-03-31031 March 2004 Appendix 4, Ujv Report Z-1172, MCP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, March 2004 Project stage: Other ML23331A6932004-05-0101 May 2004 Appendix 4, Ujv Report: Z-1172-Amendment 1, a SKODA MCNP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Amendment 1, May 2004 Project stage: Other ML23331A6792005-01-0808 January 2005 Appendix 2, Ae 11543/Dok, Rev. 2, Cover Page Only, SKODA Vpvr/M Safety Analysis Report, Cask Dynamic Behaviour SKODA Vpvr/M Project stage: Other ML23331A6752005-02-15015 February 2005 Appendix 1, Cover Page, Document No. Ae 11543/Dok, Rev. 2, Radiation Protection (Shielding Calculation), Safety Documentation of the Cask SKODA Vpvr/M Project stage: Other ML23331A7002005-02-15015 February 2005 Appendix 5, Cover Page Only, PZJ-02-04, Vision 2, Quality Plan, Vpvr Cask / SKODA Vpvr/M Cask Project stage: Other ML23331A6952005-08-0101 August 2005 Appendix 4, Ujv Report: Z-1172- Amendment 2, SKODA MCNP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Amendment 2 Project stage: Other ML23331A6812005-08-0101 August 2005 Appendix 2, Vz 04/01, Revision 3, Strength Analysis of SKODA Vpvr/M Cask for Spent Fuel Assemblies from Research Reactors Drop from the Height of 9 Meters Project stage: Other ML23331A6832005-08-0101 August 2005 Appendix 3, Ujv Report: Z-1336, Revision 2, Decontamination Effect on Structural Materials of the SKODA Vpvr/M Cask Project stage: Other ML23331A6842005-08-0101 August 2005 Appendix 3, Cover Page Only, Ae 11543/Dok, Rev. 2, Safety Analysis Report of SKODA Vpvr/M Cask, Decontamination Effect on Structural Materials Project stage: Other ML23331A6902005-08-0101 August 2005 Appendix 4, Cover Page Only, Ae 11543/Dok, Revision 2, Nuclear Safety Subcriticality Evaluation Project stage: Other ML23331A6972005-08-0101 August 2005 Appendix 4A, Cover Page, Ae 11543/Dok, Revision 2, Safety Documentation of the Cask SKODA Vpvr/M, Nuclear Safety (Subcriticality Calculation), Supplements 1 and 2) Project stage: Supplement ML23331A6982005-08-0101 August 2005 Appendix 5, Ae 11543/Dok, Rev. 2, Cover Page Only, Safety Documentation of the Cask SKODA Vpvr/M, Q.A. - 1 Project stage: Other ML23331A6862006-07-0101 July 2006 Appendix 3, Újv Report: Z-1336, Revision 2, Decontamination Effect on Structural Materials of SKODA Vpvr/M Cask, July 2005 Project stage: Other ML23331A6882006-08-0101 August 2006 Appendix 4, Ujv Report Z-1296, SKODA MCP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Nuclear Research Institute, Division of Reactor Services, August 2005 Project stage: Other ML23310A3022016-07-14014 July 2016 Act No. 263/201, Atomic Act, July 14, 2016, Czech Republic (Model No. SKODA Revalidation) Project stage: Other ML23310A3042016-10-17017 October 2016 Decree No. 358/2016, Requirements for Assurance of Quality and Technical Safety and Assessment and Verification of Conformity of Selected Equipment, October 17, 2016, Czech Republic (Model No. SKODA Revalidation) Project stage: Other ML23310A3052016-11-0707 November 2016 Decree No. 376/2016, Requirements for a Declaration Concerning the end-use of a dual-use Item in the Nuclear Area, November 7, 2016, Czech Republic (Model No. SKODA Revalidation) Project stage: Other ML23310A3062016-11-0707 November 2016 Decree 379/2016, Approval of Some Products in the Field of Peaceful Use of Nuclear Energy and Ionising Radiation and the Carriage of Radioactive or Fissile Material, November 7, 2016, Czech Republic (Model No. SKODA Revalidation) Project stage: Other ML23310A3002016-12-0606 December 2016 Decree No. 408/2016, Management System Requirements, December 6, 2016, Czech Republic (Model No. SKODA Package Revalidation) Project stage: Other ML23310A3012016-12-14014 December 2016 Decree No. 422/2016, Implementing Decree, Radiation Protection and Security of a Radioactive Source, December 14, 2016, Czech Republic (Model No. SKODA Revalidation) Project stage: Other ML23310A2992017-07-11011 July 2017 Resolution No. SUBJ/ORNV/12586/2017, Certificate No. CZ/048/B(U)F–96, State Office for Nuclear Safety, July 11, 2017, Czech Republic (Model No. SKODA Package Revalidation) Project stage: Other ML23331A7022017-07-11011 July 2017 Appendix 5, Pzj 02-04, Revision 2, Vpvr Cask, SKODA Vpvr/M Cask Project stage: Other ML23331A9032017-07-11011 July 2017 Czech Republic Certificate of Competent Authority Identification No. CZ/048/B(U)-96, Revision 2, SKODA Vpvr/M Project stage: Other ML23310A2972017-09-26026 September 2017 Decree No. 329/2017, Implementing Decree, September 26, 2017, Czech Republic (Model No. SKODA Package Revalidation) Project stage: Other ML23115A0802019-08-16016 August 2019 U.S. Certificate of Competent Authority USA/0208/B(U)F-96, Revision 13 (Japanese Certificate J/61/B(U)F-96), Expired May 28.2022 Project stage: Other ML23058A2862022-07-29029 July 2022 Part 1-Response, Acceptance Review, 2/23/23, Document No. 1 Japanese Certificate of the Competent Authority No. J/2043/B(U)F, Model No. JRF-90Y-950K (English Version) Issued on May 23, 2022 Project stage: Other ML23006A1042023-01-0505 January 2023 Cover Letter from Richard Boyle (DOT) Requesting the Review and Revalidation of the Model No. JRF-90Y-950K Project stage: Request ML23006A0982023-01-0505 January 2023 Document No. 5 - Summary of Changes of the Safety Evaluation Report for the Model No. JRF-90Y-950K Nuclear Fuel Transport Package Project stage: Request ML23160A0842023-01-0505 January 2023 Email Dated 1/5/23 from Rwboyle (DOT) to Arony (Edlow)-Incomplete Application, Information Request, Japanese Certificate of Competent Authority No. J/2043/B(U)F, Model No. JRF-90Y-950K Project stage: Other ML23046A0402023-02-0202 February 2023 Revised Affidavit Dated 2/3/23, Revalidation Request for the Japanese Certificate of the Competent Authority No. J/2043/B(U)F, Model No. JRF-90Y-950K Project stage: Request 2006-07-01
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Category:Request for Additional Information (RAI)
MONTHYEARML24046A2452024-02-14014 February 2024 Email Dated 2/14/24 from Rboyle (DOT) to Rneely (Edlow), Revalidation of Model Nos. JMS-87Y-18.5T and JRC-80Y-20T Packages, Response to Letter Jaea, Delay Responses to Fall 2024 ML24046A2432024-02-13013 February 2024 Letter Dated February 13, 2024, from H Nagadomi (Jaea) to R Boyle (Dot), Jaea Offical Letter Revalidation of Model Nos. JMS-87Y-18.5T and JRC-80Y-20T Packages Delaying the Responses to RAIs to the Fall of 2024 ML24023A0492023-08-24024 August 2023 Letter Dated 8/24/23 from R. Neely (Edlow) to R. Boyle (Dot), Official Final Responses to RAIs Discussed at the Conference Call on 7/12/23 Regarding the Revalidation Requests of the Model Nos. JMS-87Y-18-5T and JRC-80Y-20T Japanese Packages ML24043A2232023-06-27027 June 2023 Letter Dated 6/27/23 from Rboyle (DOT) to Ngarcia Santos (NRC) Responses to Requests for Additional Information for the Revalidation Recommendation for the Model No. JMS-87Y-18.5T, Japanese Certificate of Competent Authority No. J/2044/B(U) ML24043A2222023-06-27027 June 2023 Enclosure 1 - Responses to Requests for Additional Information (Rais) for the Revalidation Recommendation for the Model No. JMS-87Y-18.5T, Japanese Certificate of Competent Authority No. J/2044/B(U)F, Docket No. 71-3004, June 27, 2023 ML24043A2202023-06-26026 June 2023 Affidavit 6/26/23 - Responses to Requests for Additional Information (Rais) for the Revalidation Recommendation for the Model No. JMS-87Y-18.5T, Japanese Certificate of Competent Authority No. J/2044/B(U)F, Docket No. 71-3004 ML24043A2242023-06-20020 June 2023 Letter Dated 6/20/23 from K Tsuchiya (Jaea) to R W Boyle (Dot), Responses to Requests for Additional Information for the Revalidation Recommendation for the Model No. JMS-87Y-18.5T, Japanese Certificate of Competent Authority No. J/2044/B(U ML23158A2442023-06-14014 June 2023 Transmittal Letter - Request for Additional Information for Japanese Certificate of Competent Authority No. J/2044/B(U)F, Model No. JMS-87Y-18.5T Package, Revalidation Request (Docket No. 71-3004) ML23158A2462023-06-14014 June 2023 Enclosure 1 (Non-Proprietary) - Request for Additional Information for the Japanese Certificate of Competent Authority No. J/2044/B(U)F, Model No. JMS-87Y-18.5T Package, Revalidation Request (Docket No. 71-3004) ML23257A0052023-06-0202 June 2023 Attachment-Email Dated 6-2-23 from Ngarcia Santos (NRC) to Rboyle (DOT) Staggered Request for Additional Information for the Revalidation Recommendation of the Model No. JMS-87Y-18.5T, Materials Evaluation and General Information ML24046A2162023-06-0202 June 2023 Redacted, Attachment-Email Dated 6-2-23 from Ngarcia Santos (NRC) to Rboyle (DOT) Staggered Request for Additional Information for the Revalidation Recommendation of the Model No. JMS-87Y-18.5T, Materials Evaluation and General Information ML23257A0022023-05-30030 May 2023 Attachment-Email Dated 5-30-23 from Ngarcia Santos (NRC) to Rboyle (DOT) Staggered Request for Additional Information for the Revalidation Recommendation of the Model No. JMS-87Y-18.5T, Structural Evaluation ML24046A2172023-05-30030 May 2023 Redacted, Attachment-Email Dated 5-30-23 from Ngarcia Santos (NRC) to Rboyle (DOT) Staggered Request for Additional Information for the Revalidation Recommendation of the Model No. JMS-87Y-18.5T, Structural Evaluation 2024-02-14
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Request for Additional Information Docket No. 71-3004 Model No. JMS -87Y-18.5T Japanese Certificate of Competent Authority J/2044/B(U)F
The questions below describe information needed by the staff for it to complete its review of the application and to determine whether the applicant has demonstrated compliance with regulatory requirements.
Structural Review
RAI St-1 Provide clarification on how stress concentration effects (higher stresses in the surrounding region of local geometric discontinuities of the component parts) have been accounted for in the fatigue evaluations for the reusable package components. Justify omission of or consider stress concentration effects, where it is applicable.
The application evaluates fatigue for the lifting devices, containment device and tie-down attachments in sections (II) -A.4.4.3.3, (II)-A.10.5, (II)-A.10.6.3(11) and (II)-A.10.6.4(3) of the safety analysis report ( SAR). However, the staff could not locate any discussion on consideration of stress concentration fac tor to account for the effect of any irregularities or discontinuities of the component parts or justification thereof for not considering in the components fatigue evaluations.
The stress concentration factor is typically used to account for the effect of discontinuities such as holes, grooves or notches, bolt threads and head fillets that are not represented in detail in the finite element analysis (FEA) model.
This information is requested to determine compliance with the requirements in paragraphs 613A and 809(f) of the IAEA SSR-6, 2018 Edition.
RAI St-2 Clarify values of the maximum repetitive stress for the cask body lifting lugs considered in section (II) -A.4.4.3.3 of the SAR.
Based on the stress intensity (s) calculation at the hole of the lifting lug in section (II)-A.4.4.3.1, the staff finds that the maximum repetitive stress should be 59 N/mm2 instead of 37.3 N/mm2 considered by the applicant in the evaluation of the cask body lifting lug
This information is requested to determine compliance with the requirements in paragraphs 613A and 809(f) of the IAEA SSR-6, 2018 Edition.
RAI St-3 Verify and confirm that the stress amplitudes corresponding to the n umber of stress cycles from the design fatigue curves are properly adjusted for differences between the moduli of elasticity on the design fatigue curves and that used in the analysis of the component parts to determine allowable repeated peak stress intensity in section (II)-A.10.5 and possibly other sections of the SAR.
Section (II)-A.10.5 of the SAR, evaluates containment devices for the combined repeated peak stress intensity. In this evaluation, the allowable repeated peak stress intensity is determined by multiplying the stress amplitude corresponding to the number of stress cycles from the design fatigue curves by the ratio of modulus of elasticity on the fatigue curves to the modulus of elasticity used in the analysis. Instead, it appears to the staff that the allowable peak stress intensity
Page 1 of 4 Request for Additional Information Docket No. 71-3004 Model No. JMS -87Y-18.5T Japanese Certificate of Competent Authority J/2044/B(U)F
should be det ermined by multiplying the stress amplitude by the ratio of modulus of elasticity used in the analysis to the modulus of elasticity on the fatigue curves.
This information is needed to determine compliance with the requirements of the paragraphs 613A of the IAEA SSR-6, 2018 Edition.
RAI St-4 Verify the values in the Repeated Peak Allowable Stress Intensity column of the Table (II)-A.31 and confirm if they are values of the allowable stress intensity range or values of the alternating component, which is half of the allowable stress intensity range. Update this table as necessary, which needs to be worked in conjunction with resolution of other RAIs as applicable.
Section (II)-A.10.5 of the SAR, evaluates containment device and basket components for the combined repeated peak stress intensity. Although conservative, it appears to the staff that the values in the R epeated Peak Allowable Stress Intensity column of the Table (II)-A.31 are values for the alternating component, which is half of the allowable stress intensity range from the applicable design fatigue curves. The values in this column are compared against the combined repeated peak stress intensity values per the analysis and used to derive margin of safety in the design of the components.
This information is needed to determine compliance with the requirements of the paragraphs 613A of the IAEA SSR-6, 2018 Edition.
RAI St-5 Provide a complete evaluation of fatigue for the reusable package components for the 4 0-year period of use that considers the combined effects of all applicable types of accumulated stress cycles in components during normal service conditions, including the following cycle types (as described in this question):
- a. Lifting cycles
- b. Pressurization cycles
- c. Thermal stress cycles
- d. Vibration cycles
The staff needs a complete fatigue evaluation that considers the combined effects of all applicable types of stress cycles during normal service, including consideration of the cycle types listed above. Also, the appropriate number of cycles need to be considered in fatigue evaluation depending upon the type of cycle being evaluated. If certain types of stress cycles are not applicable or negligible for certain components, explain why these are not applicable or are negligible.
If such a complete fatigue evaluation cannot be performed, or if the fatigue evaluation cannot show adequate protection against fatigue failure considering the combined effects of all applicable types of accumulated stress cycles in components, provide the following information:
a.1 a description about how periodic maintenance inspections will be used to identify and address fatigue cracks in components of the package.
Page 2 of 4 Request for Additional Information Docket No. 71-3004 Model No. JMS -87Y-18.5T Japanese Certificate of Competent Authority J/2044/B(U)F
b.1 A description of the corrective actions that will be taken for any detected fatigue cracks, such as analytical flaw evaluation with follow-up inspections, repair/replacement of components with cracks, etc.
The following provide additional descriptions about accumulated stress cycles as provided in the application:
- 1. Lifting cycles - The staff recognizes that these cycles are already evaluated in section (II)-A.4.4.3.3 for the cask body and lid lifting device, section (II)-A.10.6.4(3) for the skid lifting device and table (II)-F.2 of the SAR. However, the staff noted that the lifting cycles are evaluated without considering the other types of stress cycles that may also be accumulated by the lifting devices for the cask body and the lid. To perform an adequate analytical evaluation that demonstrates sufficient safety margin against fatigue failure of these components, the combined effects of accumulated lifting cycles along with other applicable types of accumulated stress cycles in these components (including consideration of cycle types listed herein) on the potential for fatigue of lifting devices should be considered.
- 2. Pressurization and thermal stress cycles - The staff recognize that pressure and thermal cycles are already evaluated in sections (II) -A.10.5 and table II-F.2 for the containment device (i.e., cask body, lid and connecting bolts). However, the staff noted that the containment device pressurization & thermal cycles are evaluated for 1000 cycles over 30 years, which is contrary to the 40- year service life considered for the components fatigue evaluations elsewhere. Also, the staff noted that thermal stress cycles may occur in components due to cyclical fluctuation of spatial temperature gradients within components, which could exceed 1000 cycles over 40- year service life. In addition, the staff noted that this evaluation does not address the potential for fatigue of package components due to the combined effects of other types of stress cycles that may also be accumulated by the containment device components. To perform an adequate analytical evaluation that demonstrates sufficient safety margin against fatigue failure of these components, the combined effects of accumulated pressurization & thermal cycles along with other applicable types of accumulated stress cycles in these components (including consideration of cycle types listed herein) on the potential for fatigue of containment device components should be considered.
- 3. Vibration cycles - The staff noted that section (II)-A.4.7 provide an evaluation that demonstrates that package resonance is a not a concern considering package vibration caused by vehicle transport. The staff also recognizes that the tie-down attachments are already evaluated in section (II)-A.10.6.3(11) of the SAR for fatigue cycles. However, the staff noted that the tie -down attachment components are evaluated for 4 000 cycles, which the applicant has inappropriately considered as lifting cycles, and not as vibratory cycles. The package components could experience
Page 3 of 4 Request for Additional Information Docket No. 71-3004 Model No. JMS -87Y-18.5T Japanese Certificate of Competent Authority J/2044/B(U)F
many vibration cycles from numerous vehicle transports by road during the 40-year service life, which may exceed 4000 lifting cycles considered in the fatigue evaluation. In addition, the staff noted that this evaluation does not address the potential for fatigue of package components due to the combined effects of the accumulation of many vibration cycles resulting from the allowed transports of the package over 40- year service life, along with the accumulation of other applicable types of stress cycles, including consideration of the cycle types listed herein.
To determine that fatigue as not an aging concern, as indicated in section ( II)-F of the application, the staff needs a complete fatigue evaluation that considers the combined effects of all applicable types of stress cycles during normal service, including consideration of the cycle types listed above. Also, the appropriate number of cycles need to be considered in fatigue evaluation depending upon the type of cycle being evaluated.
This information is requested to determine compliance with the requirements in paragraphs 503(e), 613, 613A, and 809(f) of the IAEA SSR-6, 2018 Edition.
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