ML18360A236
| ML18360A236 | |
| Person / Time | |
|---|---|
| Site: | 07103035 |
| Issue date: | 12/21/2018 |
| From: | Garcia-Santos N Spent Fuel Licensing Branch |
| To: | Boyle R US Dept of Transportation (DOT) |
| References | |
| EPID L-2018-LLA-0219 | |
| Download: ML18360A236 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 21, 2018 Mr. Richard W. Boyle Radioactive Materials\Research and Development Division of Sciences, Engineering, and Research Office of Hazardous Materials Safety U.S. Department of Transportation 1200 New Jersey Ave., S.E.
Washington, D.C. 20590
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR REVIEW OF THE REVALIDATION OF THE MODEL NO. JCR-80Y-2OT PACKAGING (DOCKET NO. 71-3035)
Dear Mr. Boyle:
By application dated August 8, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18270A163), the U.S. Department of Transportation, requested the staff to provide a revalidation recommendation for the Japanese Certificate of Approval No.
J/61/B(U)F-96, Revision 3, Model No. JCR-80Y-2OT package. The certificate holder proposes to add JRR-4 high enriched uranium fuel as authorized content of the Model No. JCR-80Y-2OT.
In connection with our review, we need the information identified in the enclosure to this letter.
To assist us in scheduling staff review of your response, we request that you provide this information by January 11, 2019. Inform us at your earliest convenience, but no later than January 4, 2019, if you are not able to provide the information by that date. If you are unable to provide a response by January 11, 2019, our review may be delayed.
R. Boyle Please reference Docket No. 71-3035 and EPID L-2018-LLA-0219 in future correspondence related to this request. The staff is available to meet to discuss your proposed responses. If you have any questions regarding this matter, you can contact me at (301) 415-6999.
Sincerely,
/RA/
Norma Garcia Santos, Project Manager Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-3035 EPID L-2018-LLA-0219
Enclosure:
Request for Additional Information
R. Boyle
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR REVIEW OF THE REVALIDATION OF THE MODEL NO. JCR-80Y-20T PACKAGING (DOCKET NO. 71-3035), DOCUMENT DATE: December 21, 2018 DISTRIBUTION: SFST r/f NGarcia-Santos DMarcano http://fusion.nrc.gov/nmss/team/sfst/sfst-licensing/10_cfr_71/jcr-reval/Shared Documents/JCR_RAIs_Ltr.docx ADAMS Accession Number: ML18360A236 OFFICE DSFM DSFM DSFM DSFM DSFM NAME NGarcia Santos SFigueroa ASotomayor Rivera DChung by email JMcKirgan by email by email for TTate DATE 12/20/18 12/20/18 12/20/18 12/20/18 12/21/18 OFFICIAL RECORD COPY
Request for Additional Information U.S. Department of Transportation Docket No. 71-3035 Japanese Certificate of Approval No. J/61/B(U)F-96 Revision 3 Model No. JCR-80Y-2OT By application dated August 8, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18270A163), the U.S. Department of Transportation, requested the staff to provide a revalidation recommendation for the Japanese Certificate of Approval No.
J/61/B(U)F-96, Revision 3, Model No. JCR-80Y-2OT package.
This request for additional information (RAI) identifies information needed by the U.S. Nuclear Regulatory Commission staff (the staff) in connection with its review of the application. The International Atomic Energy Agency, Specific Safety Requirement No. 6 (SSR-6), Regulations for the Safe Transport of Radioactive Material, 2012 Edition, was used by the staff in its review of the application.
This RAI describes information needed by the staff for it to complete its review of the application and to determine whether the applicant has demonstrated compliance with the regulatory requirements of 10 CFR Part 71.
SHIELDING EVALUATION RAI-Sh-1 Provide representative ORIGEN or ORIGEN-JR input files for the Model No.
JCR-80Y-20T package including the fuels used to determine the bounding gamma and neutron source terms for the JRR-4 as well as the input file for the JRR-4.
In Section D.2.1, Gamma Source, of the application, the applicant states the following:
The gamma source intensity is calculated by using ORIGEN code or ORIGEN-JR code together with the data such as irradiation, cooling condition, etc. shown in (II)-Table D.2 The staff needs to verify that the key parameters shown in (II)-Table D.2 of the application are properly included and used in the input file to calculate the transport index (TI).
This information is required to determine compliance with paragraphs 523, 526, and 648(b) of IAEA SSR-6, 2012 Edition.
RAI-Sh-2 Provide the following information about the ORIGEN-JR code:
- a. Similarities and differences between this code and the ORIGEN code developed by ORNL;
- b. Modifications to the ORIGEN code developed by ORNL; Enclosure
- c. How the applicant used the reactor data, power histories, and assembly data in the code; and
- d. The portion of the manual that describes the input/output files with enough detail to understand the input/output files requested in RAI-Sh-1.
In Section D.2.1, Gamma Source, of the application, the applicant notes that it also uses the ORIGEN-JR code to calculate gamma and neutron source terms.
The applicant also noted that the ORIGEN-JR code was based on the ORIGEN code and developed by the Japan Atomic Energy Research Institute. The applicant did not provide details about the ORIGEN-JR code in its application and how the ORIGEN-JR code compares to the ORIGEN code.
This information is required to determine compliance with paragraphs 523, 526, and 648(b) of IAEA SSR-6, 2012 Edition.
RAI-Sh-3 Provide the following information related to the QAD-CGGP2R code and DOT3.5 code for the fuels used to determine bounding dose rates for the JRR-4:
- a. A representative input and output file used to calculate radiation levels;
- b. Portions of the code manual relevant to understanding the input and output submitted by the applicant.
In Section D.4 of the application, the applicant states that it used the QAD-CGGP2R code for calculating the radiation level from gamma emission.
For calculating the radiation level from neutron emission, the applicant used the DOT3.5 code.
The staff needs to evaluate the input files to ensure that the proper parameters were used to calculate dose rates from the output files and that the dose rates are in agreement with the values reported in the shielding evaluation.
This information is required to determine compliance with paragraphs 523, 526, and 648(b) of IAEA SSR-6, 2012 Edition.
RAI-Sh-4 Provide information on the geometry of the fuel plates for the JRR-4 high enriched uranium fuel including:
- a. Thickness of the plates,
- b. Length and width of the plates,
- c. Tolerances related to the dimensions of the plates, and
- d. Fuel composition of each plate.
In Section D, Contents of the Package, of the application, the applicant submitted information such as specific power, and fuel parameters (I-Table D.1, Specification of Contents) such as enrichment, burnup and cooling time, but there is no information about the geometry of the fuel plates such as thickness of the plates, dimensions, tolerances, and fuel composition. The staff needs this information in order to perform confirmatory analyses and confirm that the fuel was appropriately represented by the applicant within the dose rate analyses and in the certificate.
This information is required by the staff to determine compliance with paragraphs 523, 526, and 648(b) of IAEA SSR-6, 2012 Edition.