ML22339A250
| ML22339A250 | |
| Person / Time | |
|---|---|
| Site: | 07103102 |
| Issue date: | 12/15/2022 |
| From: | Nishka Devaser Storage and Transportation Licensing Branch |
| To: | Boyle R US Dept of Transportation, Radioactive Materials Branch |
| References | |
| EPID L-2022-DOT-0003 | |
| Download: ML22339A250 (3) | |
Text
December 15, 2022 Richard W. Boyle Radioactive Materials Branch U.S. Department of Transportation 1200 New Jersey Avenue SE Washington, D.C. 20590
SUBJECT:
REQUEST FOR REVALIDATION OF UNITED KINGDOM CERTIFICATE OF APPROVAL GB/4120/B(U) FOR THE DPR 200 PACKAGE - REQUEST FOR ADDITIONAL INFORMATION, DOCKET 71-3102
Dear Richard Boyle:
By letter dated May 4, 2022 (Agencywide Documents Access and Management System
[ADAMS] Accession No. ML22203A081), the U.S. Department of Transportation requested that the U.S. Nuclear Regulatory Commission staff perform a review of the United Kingdom Certificate of Approval GB/4120/B(U), for the Model No. DPR 200 transport package and make a recommendation concerning the revalidation of the package for import and export use.
In connection with our review, this letter is to advise you that the information needed to continue our review, described as a request for additional information, is in the enclosure to this letter.
Addressing the request for additional information does not preclude the staff from issuing further requests for additional information during the detailed technical review of this application.
In order to complete our technical review on schedule, your response should be provided within 30 days of the date of this letter. If you have any questions regarding this matter, I may be contacted at (301) 415-5196 or via email at Nishka.Devaser@nrc.gov.
Sincerely, Signed by Devaser, Nishka on 12/15/22 Nishka Devaser, Project Manager Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-3102 EPID L-2022-DOT-0003
Enclosure:
Request for Additional Information
ML22339A250 OFFICE NMSS/DFM NMSS/DFM NMSS/DFM NMSS/DFM NMSS/DFM NAME NDevaser SFigueroa CBajwa DMarcano YDiazSanabria DATE 12/06/22 12/06/22 12/06/22 12/07/22 12/08/22 Request for Additional Information Docket No. 71-3102 Model No. DPR 200 Package United Kingdom Certificate GB/4120/B(U)
By letter dated May 4, 2022 (Agencywide Documents Access and Management System
[ADAMS] Accession No. ML22203A081), the U.S. Department of Transportation requested that the U.S. Nuclear Regulatory Commission (NRC) staff perform a review of the United Kingdom Certificate of Approval GB/4120/B(U), for the Model No. DPR 200 transport package and make a recommendation concerning the revalidation of the package for import and export use.
This request for additional information identifies information needed by the NRC staff (the staff) in connection with its technical review of the Model No. DPR 200 package application.
Containment Evaluation 4-1 Clarify the leakage criteria for the DPR 200 package and whether the DPR 200 package is considered leaktight under the American National Standards Institute (ANSI) N14.5 or International Organization for Standardization (ISO) 12807 definition of the term. For non-spent fuel contents, describe how the package user demonstrates that the package meets the criteria in International Atomic Energy Agency SSR-6, Paragraph 671(a).
Section 6.7 of Report SR-030: DPR 200 Containment Safety Assessment is entitled:
Leaktightness. In this section the applicant states:
The containment system must be capable of retaining solid radioactive material which, in the worst case, could mean a fine powder. Para[graph] 659.13, SSG-26, quotes a helium leak rate of 10-6 Pa*m3/s as being sufficient to retain even the smallest particle size powder. This is therefore the criteria used in testing the containment boundary and the seals.
The staff notes that the helium leak rate cited above is greater than the leaktight criteria defined in ANSI N14.5-2014 (or the corresponding ISO 12807 standard) which defines leaktight as demonstration of a leakage rate less than or equal to 1E10-7 ref*cm3/s, which is equivalent to 1E10-8 Pa*m3/s. If the package is not leaktight a demonstration that the package meets the radioactive release limits in SSR-6 Paragraph 671(a) will need to be provided.
This information is needed to determine compliance with SSR-6 Paragraphs 659 and 671(a).
Enclosure