ML19059A412
| ML19059A412 | |
| Person / Time | |
|---|---|
| Site: | 07103035 |
| Issue date: | 02/19/2019 |
| From: | Boyle R US Dept of Transportation (DOT) |
| To: | Garcia-Santos N Spent Fuel Licensing Branch |
| Garcia-Santos N | |
| References | |
| Download: ML19059A412 (6) | |
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0 U.S. Department of Transportation Pipeline and Hazardous Materials Safety Administration Norma Garcia Santos, Project Manager Spent Fuel Licensing Branch Division of Spent Fuel Management East Building, PHH-23 1200 New Jersey Avenue SE.
Washington, D.C. 20590 FEB 1 9 2019 Office of Nuclear Material Safety and Safeguards (NMSS)
U.S. Nuclear Regulatory Commission 11545 Rockville Pike Mail Stop T4B34 Rockville, MD 20852-2738
Dear Ms. Garcia Santos:
In accordance with the Memorandum of Understanding between our agencies, on August 8, 2018 I requested that you review the Japanese Certificate of Approval No. J/61/B(U)F-96, Revision 3, for the JRC-80Y-20T package and make a recommendation concerning our revalidation ofthe package for import and export use (Docket No. 71-3035 and EPID L-2018-LLA-0219). On December 21, 2018, you sent a Request for Additional Information (RAI) regarding this review.
Attached is the response to your RAI letter I have received from our applicant, Edlow International Company. Supporting files may be found in electronic form on the enclosed ed.
If you have any questions or need any additional safety information, please feel free to contact Michael Conroy of my staff at (202) 366-3597 or via email at Michael.Conroy@dot.gov.
Enclosures Richard W. Boyl,
Radioactive Materials/ Research & Development Division of Sciences, Engineering and Research Office of Hazardous Materials Safety
b b
b Edlow International Company 1666 Connecticut Ave., N.W., Suite 201 Washington, D.C. 20009, U.S.A.
Tel (202) 483-4959 Fax (202) 483-4840 Michael Conroy Pipeline and Hazardous Materials Safety Administration U.S. Department of Transportation 1200 New Jersey Avenue SE Washington, DC 20590 Edlow Ref: SUMI-3956 February 15, 2019
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR REVIEW OF THE REVALIDATION OF THE MODEL NO. JRC-80Y-20T PACKAGING (DOCKET NO. 71-3035)
Dear Mr. Conroy,
In reference to the U.S. Nuclear Regulatory Commission (USNRC) letter dated December 21,
2018, please find the responses to the "Request for Additional Information (RAI)" for the revalidation of the Japanese Certificate of Approval No. J/61/B(U)F-96, Revision 3, Model No.
JRC-80Y-20T.
The supporting files which are referenced in the answers below to the RAI will be sent to you on a CD via FedEx.
If you have any questions or concerns, you may contact me via email at arony@edlow.com or via telephone at (202) 483-4959.
Sincerely, Adrian Rony Edlow International Docket No. 71-3035 EPID L-2018-LLA-0219
Enclosure:
RAJ Response
REQUEST FOR ADDITIONAL INFORMATION (RAI)
U.S. DEPARTMENT OF TRANSPORTATION Docket No. 71 *3035 Japanese Certificate of Approval No. J/61/B(U)F*96 Revision 3 Model No. JRC*80Y*20T Regarding the request for additional information (RAI) which will be required by the NRC for a review of the Japanese Certificate of Approval No. 61/B(U)F-96, Revision 3, Model No. JCR-80Y-20T package, as described below, we will provide documents about evaluation of the package shield.
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.
Regarding the RAI-Sh-1 request, we will provide ORIGEN-JR input and output files for JRR-4HEU (RAI-Sh-1 JRR-4 HEU ORIGEN. inp, RAI-Sh-1 JRR-4 HEU ORIGEN. out). JRR-4 HEU data in II-Table D.2 is used in the input files.
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;
- 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.
Regarding the RAI-Sh-2 request, we will provide the ORIGEN-JR manual (RAI-Sh-2 Manual ORIGEN-JR). The ORIGEN-JR code was developed by JAEA, based on the ORIGEN code developed by ORNL, to evaluate radiation sources in spent-fuel shipping casks and spent fuel
RAI-Sh-3 reprocessing. The response to (a) is provided in Chapter 1, the response to (b) is provided in Chapter 2, and the response to (c) and (d) is provided in Chapter 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.
Regarding the RAI-Sh-3 request, we will provide representative input and output files and the QAD*CGGP2R code manual (RAI-Sh-3 Manual_QAD*CGGP2R).
- a.
JRR-3 Silicide Fuel (RAI*Sh-3 QAD) 1s used for gamma*ray evaluation. JRR*4LEU (RAI*Sh-3 DOT) is used for neutron evaluation. Evaluation was performed using the source with the highest intensity in II *Table D.3 and D.4.
- b.
The QAD*CGGP2R code is based on the QAD code developed by LANL. Modifications were made to QAD code by JAEA so that effective doses can be calculated. Geometric progression is used to interpolate the buildup factor for gamma rays.
Since DOT3.5 is a code developed by ORN, we will not provide the code manual. The ANISN code developed by ORL is used to generate cross sectional data.
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.
Regarding the RAI-Sh-4 request, we will provide the following information:
- a.
RAI*Sh*4*a Geometry of JRR*4HEU,
- b.
RAI*Sh*4*b Geometry of JRR*4HEU,
- c.
RAI*Sh*4*c Tolerances related to the dimensions of the plates
- d.
RAI*Sh*4 *d Table D.1,D.2.
We will provide other necessary information, if any.
Att: We send you total 16 files.
Sincerely yours, Jun Motohashi Research Reactor Technology Section Department of Reactors and Tandem Accelerator Nuclear Science Research Institute Japan Atomic Energy Agency File"RAI*Sh-3 DOT"stores the following 6 files.
- anisn.lst
- an1sn.mac
- dot*n.job
- dot*n.lst
- dot*n*lcm.out
- dot*n* lcm.ret File"RAI*Sh-3 QAD" stores the following 2 files.
- jrr3*si.dat
- jrr3*si.lst
- RAI*Sh*l JRR*4 HEU ORIGEN inp.inp
- RAI*Sh*l JRR-4 HEU ORIGEN out.out
- RAI*Sh-2 Manual_ORIGEN*JR.PDF
- RAI*Sh-3 Manual_QAD*CGGP2R.PDF
- RAI*Sh-4 a Geometry of the JRR-4 HEU.pdf
- RAI*Sh-4 b Geometry of the JRR-4 HEU.pdf
- Tolerances related to the dimensions of the plates.pdf
-RAI-Sh-4 d Table D.1, D.2.pdf