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 Revalidation of Japanese Competent Authority Certificate of Approval No.
J/2044/B(U)F, Model No. JMS-87Y-18.5T Materials Review -
Request for Additional Information (RAI)
EPID: L-2023-DOT-0005
RAI-Ma-1:
Please describe any national or international codes, standards, and/or other methods, programs, or procedures that are implemented to ensure that package maintenance activities (including visual inspections, screening and evaluation of visual indications, and corrective actions such as component repairs and replacements) are adequate to manage the effects of aging in metallic package components that would see long-term use, such that the package components are capable of performing their requisite safety functions throughout the period of use.
Per IAEA SSG-26, Paragraph 613A.3, the package should be evaluated during the design phase in the demonstration of compliance with the Transport Regulations. Based on this evaluation, an inspection and maintenance program me should be developed. The programme should be structure so that the assumptions (e.g. thickness of containment wall, leaktightness, neutron absorber effectiveness) used in the demonstration of compliance of the package are confirmed to be valid through the lifetime of the packaging.
The staff requests that this description address the following criteria:
- 1. Inspection methods (e.g., bare metal visual exams and/or other types of nondestructive exams such as liquid penetrant exams or ultrasonic exams) for detection, characterization, and sizing of localized aging effects such as cracks, pits, and crevice corrosion.
- 2. Inspection equipment and personnel qualification requirements (e.g., lighting and visual acuity requirements for performing visual exams) to ensure reliable inspections that can adequately detect and characterize indications of localized aging effects prior to component failure or loss of safety function.
- 3. Acceptance criteria for aging effects such as early stage fatigue cracks and localized corrosion of stainless steel components, such as chloride induced stress corrosion cracking (SCC), pitting, and crevice corrosion. Examples of visual indications that may indicate potential localized corrosion of stainless steel components include the accumulation of atmospheric deposits such as salts, buildup of corrosion products, rust-colored stains or deposits, and surface discontinuities or flaws associated with pitting, crevice corrosion, and/or SCC.
- 4. Describe any surface cleaning requirements that are implemented to ensure that bare metal visual inspections of component surfaces are capable of detecting surface flaws, and for ensuring adequate removal of atmospheric deposits such as salts or other chemical compounds that may contribute to localized corrosion of stainless steel components.
- 5. Describe any flaw evaluation methods (such as flaw sizing and flaw analysis methods) and associated flaw acceptance criteria that may be used to determine whether components containing flaws are acceptable for continued service.
This information is requested in order to verify compliance with requirements of the 2018 Edition of IAEA SSR-6, Paragraphs 503(e), 613A, and 809(f).
RAI-Ma-2:
Per IAEA SSG-26, Paragraph 613A.1, The designer of a package should evaluate the potential degradation phenomena over time, such as corrosion, abrasion, fatigue, crack propagation, changes of material compositions or mechanical properties due to thermal loadings or radiation, generation of decomposition gases and the impact of these phenomena on performance of safety functions. As t he staff was not able to locate a discussion on abrasion being evaluated as an aging mechanism, the staff requests the applicant to provide an evaluation of abrasion as an aging mechanism.
This information is requested in order to verify compliance with requirements of the 2018 Edition of IAEA SSR-6, Paragraph 613A.
RAI-Ma-3:
Per IAEA SSG-26, Paragraph 613A.5, For designs of Type B(U), B(M) and Type C packages these programmes are required to be included in the application for approval of packages for shipment after storage (see paras 809(f) and (k) of the Transport Regulations). The results of the ageing management programme and the gap analysis programme should be taken into account when preparing an inspection plan prior to transport. The staff was not able to locate an aging management program or gap analysis program as required by IAEA SSR -6, Paragraphs 809(f) and (k). The staff requests the applicant to provide the aging management program (per the structure and procedure in IAEA SSG -26, Paragraph 613A.3) and gap analysis program.
This information is requested in order to verify compliance with requirements of the 2018 Edition of IAEA SSR-6, Paragraphs 809(f) and (k).
RAI-Ma-4: The staff requests the applicant to address two inconsistencies identified between the maximum temperatures identified for the wood impact limiter (Fir-Plywood) in SAR Section B.4.2 and SAR Section F.2, and provide the basis for the evaluation of the wood in the impact limiter in the ana lyzed range of temperatures. In SAR Section F.2, the applicant states that the maximum temperature identified at the surface of the package is 111°C during transportation.
However, in SAR Section B.4.2, Table (II) -B.15 and B.16, the highest temperature listed is 82° C. Secondly, the applicant states that based on the results of analysis, the temperature inside the shock absorber during actual transportation is estimated to be below about 40° C. The applicant later states that the average temperature data of the shock absorber of another package with a track record of transportation of spent fuel was evaluated and shown to be around 40° C to 70°C, which contradicts the previous temperature estimate.
This information is requested in order to verify compliance with requirements of the 2018 Edition of IAEA SSR-6, Paragraphs 613A, 616, and 639.
RAI-Ma-5: In SAR Section F.2, the applicant described the corrosion that could affect the shock absorber (Wood - Fir-Plywood). The staff requests the applicant to clarify how they are addressing potential water absorption by the shock absorber. In SAR Table III -B.1, a visual inspection is described but does not include any mention of inspection of the welds or areas adjacent to the welds, nor is any specific acceptance criteria described.
This information is requested in order to verify compliance with requirements of the 2018 Edition of IAEA SSR-6, Paragraph 613A.
RAI-Ma-6: In SAR Section F.2, the applicant describes heat related aging mechanisms that can affect the Boron Carbide-Aluminum Alloy, stating that thermal analysis indicated a substantial temperature difference between the maximum temperature expected during transport and the melting temperature of the Boron Carbide-Aluminum Alloy. The A1100- H14 cladding material, however, has a much lower melting temperature and the staff requests that the applicant provide a comparison between the maximum temperature expected during transport to the qualified temperature limit for the A1100-H14 cladding material.
This information is requested in order to verify compliance with requirements of the 2018 Edition of IAEA SSR-6, Paragraph 613A.
General RAI
Replace all references to the IAEA transport safety regulations in the JMS SAR to appropriately reflect Rev. 1 of SSR-6, (2018).
In the JMS SAR, Rev. 1, on page (II)-A-410 (for example), reference (29) is listed as IAEA/ Radio active material safety transportation regulations (1985 transaction) safety series No. 6; however, since the SAR has been revised to meet the requirements of SSR-6, Rev. 1 (2018), the correct reference should be to SSR-6, Rev. 1 (2018).
This information is needed to establish alignment with the requirements in SSR -6, Rev. 1 (2018 Edition) Paragraph 102.