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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, ML23331A693, ML23331A695, ML23331A698, ML23331A700, ML23331A702, ML23331A897, ML23331A898, ML23331A899, ML23331A900, ML23331A901, ML23331A902, ML23331A903, ML23331A904, ML23331A907, ML24022A254, ML24023A003, ML24023A321, ML24046A245... 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 ML23331A9022002-06-13013 June 2002 Regulation No. 307/2002 Coll., Radiation Protection 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML23160A0852023-01-27027 January 2023 Email Dated 1/27/23 from Rwboyle (DOT) to Arony (Edlow)-Incomplete Application, Teleconference Questions for Discussion, Japanese Certificate of Competent Authority No. J/2043/B(U)F, Model No. JRF-90Y-950K Project stage: Meeting ML23038A0352023-02-0101 February 2023 NRC-699, Telephone Call Summary, 11:00AM - Conference Call to Discuss Questions Regarding the Application for Revalidation of the Japanese Certificate of Competent Authority No. J/2043/B(U)F, Model No. Jrf 90Y-950K (Docket No. 71-3036) 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 ML23038A0342023-02-0606 February 2023 Email Dated February 6, 2023, from R. Boyle (DOT) to N. Garcia Santos (Nrc), Comment or Edits on the JRF-90Y-950K Telephone Call Summary on February 1, 2023 Project stage: Other ML23160A0862023-02-14014 February 2023 Email Dated 2/14/23 from Rneely (Edlow) to Rboyle (DOT)-Initial Need Dates (Clarification), Japanese Certificate of Competent Authority No. J/2043/B(U)F, Model No. JRF-90Y-950K Project stage: Other ML23115A0812023-02-15015 February 2023 Enclosure 5, Revision 0, Japan Atomic Energy Agency, Statement of Proprietary Information, Revalidation Application for the Japanese Mode No. JRC-80Y-20T Package (J/2045/B(U)F) Project stage: Request ML23058A2552023-02-20020 February 2023, 23 February 2023, 27 February 2023, 2 March 2023 Response to Request for Supplemental Information - Revalidation of the Japanese Certificate of Competent Authority No. J/2043/B(U)F, Model No. Jrf 90Y-950K (Docket No. 71-3036) Project stage: Request ML23058A2842023-02-20020 February 2023 Part 1-Response Acceptance Review, 2-23-23, Document No. 5, Affidavit on the Proprietary Documents of the Application of the Model No. JRF-90Y-950K Project stage: Other ML23310A1632023-02-22022 February 2023 Czech Language and English Translation of the Certificate of the Competent Authority for the Model No. S?Koda MTR Triga Package, CZ/100/B(U)F-6, Revision 0 Project stage: Other ML23058A2792023-02-23023 February 2023 Part 1-Response, Acceptance Review, 2/23/23, Document No. 2-1 (Non-Proprietary) Safety Analysis Report, Application of Design Approval for the Model No. JRF-90Y-950K (J/2043/B(U)F) Project stage: Other ML23058A2852023-02-23023 February 2023 Part 1 - Transmittal Letter Dated 2/23/23 from Russell Neely (Edlow International) to Rick Boyle (Dot), Responses of Request for Supplemental Information from NRC on Completeness of the Application for the Model No. JRF-90Y-950K (J/2043/B(U Project stage: Supplement ML23058A2812023-02-23023 February 2023 Part 1-Response Acceptance Review, 2-23-23, Document No. No. 3-1 (Non-proprietary), Summary of Change of SAR for JRF-90Y-950K Project stage: Other ML23090A0022023-02-23023 February 2023 Part 2 - Request Response, Corrected Page 47 in Correction Table of Document No. 4-1 Project stage: Other 2016-12-14
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U.S. Department East Building, PHH-23 of Transportation 1200 New Jersey Avenue SE Washington, D.C. 20590 Pipeline and Hazardous Materials Safety Administration May 11, 2023 Norma Garcia Santos, Project Manager Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards (NMSS)
U.S. Nuclear Regulatory Commission 11545 Rockville Pike Rockville, MD 20852-2738
Dear Ms. Garcia Santos:
In accordance with the Memorandum of Understanding between our agencies, on January 5, 2023 I requested that you review the Japanese Certificate of Approval No. J/2043/B(U)F for the JRF-90Y-950K transport package and make a recommendation concerning our revalidation of the package for import and export use. On May 1, 2023, you sent a Request for Additional Information (RAI) regarding this review.
Our applicants response to your RAI was received and has been electronically transmitted to you and your staff and is attached to this correspondence.
If you have any questions or need any additional safety information, please feel free to contact me at (202) 697-1301 or via email at rick.boyle@dot.gov.
Sincerely, Richard W. Boyle, Radioactive Materials Division of Sciences and Engineering Office of Hazardous Materials Safety Enclosure RICHARD BOYLE Digitally signed by RICHARD BOYLE Date: 2023.05.11 14:14:55
-04'00'
Request for Additional Information U.S. Department of Transportation Japanese Approval Certificate No. J/2043/B(U)F, Revision 2 Docket No. 71-3036 Certificate of Compliance No. 3036 Model No. JRF-90Y-950K By letter dated January 5, 2023 (Agencywide Documents Access and Management System
[ADAMS] Accession Number ML23006A104) and supplemented on March 2, 2023 (ML23061A186),
you submitted an application to the U.S. Nuclear Regulatory Commission (NRC) for the review of the Certificate of Competent Authority No. J/2043/B(U), Model No. JRF-90Y-950K. In your application you requested that the NRC provides a recommendation to revalidate the Model No.
JRF-90Y-950K package.
This request for additional information (RAI) identifies information needed by the NRC staff (the staff) in connection with its review of the application. The staff used International Atomic Energy Agency (IAEA) Specific Safety Requirements No. 6 (SSR-6), Regulations for the Safe Transport of Radioactive Material, 2018 Edition, in its review of the application.
The RAI describes information needed by the staff to complete its review of the application and to determine whether the applicant has demonstrated compliance with the regulatory requirements of the IAEA SSR-6, 2018 Edition.
Materials Evaluation RAI 7-1. Provide details on how the heat insulator (hard polyurethane foam) and shock absorber (balsa wood) are considered to be in a sealed state (e.g., encased in welded stainless steel), such that the materials are adequately protected from damage due to moisture or water intrusion. If the polyurethane foam and wood are not permanently sealed, please address how these materials are inspected for water damage and repaired/replaced, as needed, since both are susceptible to degradation over time when exposed to moisture or water intrusion. Also, Revise the SAR with additional details to remove the ambiguity.
JAEA Official Response The heat insulator (hard polyurethane foam) and shock absorber (balsa wood) are encased in the outer shell body and lid (welded stainless steel plate) as shown below. In addition, fusible(melting) plugs (solder, stainless steel) are attached to the outer shell body and lid. The fusible(melting) plugs are for venting gas in case of fire and are not to be removed during normal operation, so that moisture and water cannot enter the container.
The main body, outer shell lid, and fusible(melting) plugs are inspected prior to shipping (prior to transportation) as described in (III)-A-1 to 4 to check for any abnormalities. The scope of the visual inspection includes the main body, inner shell lid, and outer lid, and the appearance of the balsa wood and the component (stainless steel) that contains the polyurethane foam inside is inspected.
<()-C-6>
2.1 Main body (Refer to ()-Fig. C.6)
The main body is cylindrical in shape with 1,559mm in height and 840mm in outer diameter and consists of the outer shell and inner shell.
The outer shell consists of 3mm thick stainless steel and 6mm thick stainless steel at the bottom.
The inner shell consists of 10mm thick stainless steel and 35mm thick stainless steel at the bottom.
The shell and bottom plate are welded completely. The space between the outer and inner shells, heat insulators and shock absorbers are applied to reduce the heat gain caused by fire and to absorb impact energy caused by drop. At the upper side of the main body, the eye-plates are welded at 4 places to lift the packaging.
Eight fusible(melting) plugs are provided on the outer shell. These plugs are provided to avoid the pressure raise by steam or gas generated from the heat insulator and shock absorber due to heat during fire.
<()-C.8>
2.4 Outer lid (Refer to ()-Fig. C.9)
The outer lid is cylindrical in shape with 398mm in height and 840mm in outer diameter.
The outer cover plate consists of 3mm thick stainless steel shell and 6mm thick stainless steel upper plate. The inner cover plate consists of 3mm thick stainless steels.
The space between the outer and inner cover plates, the heat insulators and shock absorbers are applied to reduce the heat gain caused by fire and to absorb impact energy caused by drop.
4 eye-bolt bosses for lifting are welded to the outer lid. 4 fusible(melting) plugs are provided on the outer cover plate. These plugs are used to avoid the pressure raise by steam or gas generated from the heat insulator and shock absorber due to heat during fire.
The staff is unclear if the polyurethane foam and wood materials are sealed in the main body and the outer lid only when the package is sealed closed for transportation, or if both the main body and the outer lid provide independent sealed compartments even when the outer lid is not installed on the main body.
JAEA Official Response Both the body and the outer lid provide independent sealed compartments even when the outer lid is not attached to the body. In the drawings below, all outside lines indicate stainless steel; polyurethane foam and wood materials are inside this.
()-C-10: Main Body (Refer to ()-Fig. C. 6.)
()-C-13: Outer shell lid (Refer to ()-Fig. C. 9.)
If both these materials are only considered to be in a sealed state when the outer lid is installed on the main body, how are the polyurethane foam and wood materials visually inspected and repaired/replaced if damage is found? Visual inspection requirements in Section III-Table A.1 for pre-shipment inspection, and Section (III) B for maintenance requirements only mention visual inspection of inner and outer surfaces of the main body, fuel basket, inner lid and outer lid.
JAEA Official Response From the above response, both the body and the outer lid provide independent hermetic compartments even when the outer lid is not attached to the body. Therefore, the visual inspection requirement in (III)-
B-1 inspects the inner stainless steel (and some solder).
Revise the SAR with additional details to remove the ambiguity. This information is needed to determine compliance with SSR-6 2018 Edition, paragraphs 613A and 809(f).
Enclosure Observations Observation 7-1 In SAR Section (III)-A package handling methods, on Page (III)-A-1 and Page (III)-A-2, the pre-shipment content inspection is referenced to be in section (IV)-A.2 and (IV)-Table A.1.
However, the pre-shipment inspection of the package is found on Page (III)-A-3 under (III) Table A.1.
JAEA Official Response This appropriate advice is correct, and the sentences on the SAR was incorrect.
Therefore, we amended them as below; Page 596 :
Incorrect : (IV)-A.2 Correct : ()-A. 2.
Page 597 :
Incorrect : (IV)-Table A. 1 Correct : ()-Table A. 1