ML18179A428
| ML18179A428 | |
| Person / Time | |
|---|---|
| Site: | 07109341 |
| Issue date: | 06/26/2018 |
| From: | Nishka Devaser Spent Fuel Licensing Branch |
| To: | Noss P AREVA Federal Services |
| Devaser N | |
| References | |
| EPID L-2018-LLA-0028 | |
| Download: ML18179A428 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 26, 2018 Mr. Philip Noss Licensing Manager AREVA Federal Services LLC 505 S. 336th Street, Suite 400 Federal Way, WA 98003
SUBJECT:
APPLICATION FOR THE AMENDMENT REQUEST OF CERTIFICATE OF COMPLIANCE NO. 9341 FOR THE BRR PACKAGE - REQUEST FOR ADDITIONAL INFORMATION
Dear Mr. Noss:
By letter dated January 30, 2018, AREVA Federal Services LLC (AFS) submitted an application in accordance with Title 10 of the Code of Federal Regulations Part 71 to amend Certificate of Compliance No. 9341 for the Model No. BRR package per the details of the submitted revision of the safety analysis report for the BRR package, Revision 11. The cover letter to this request and a publicly available version of the report can be found in our agencys document database, the Agencywide Documents Access and Management System (ADAMS) at Accession Numbers ML18044A148 and ML18044A164, respectively.
In connection with the U.S. Nuclear Regulatory Commission (NRC) staff review, we need the information identified in the enclosure to this letter. Additional information requested by this letter should be submitted in the form of revised pages. Please provide your response within 2 months from the date of this letter.
Please reference Docket No. 71-9341 and Enterprise Project Identifier No. L-2018-LLA-0028 in future correspondence related to this request. The staff is available to meet to discuss your proposed responses. If you have any questions, I may be contacted at (301) 415-5196.
Sincerely,
/RA/
Nishka Devaser, Project Manager Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-9341 EPID No. L-2018-LLA-0028
Enclosure:
Request for Additional Information
APPLICATION FOR THE AMENDMENT REQUEST OF CERTIFICATE OF COMPLIANCE NO.
9341 FOR THE BRR PACKAGE - REQUEST FOR ADDITIONAL INFORMATION, DOCUMENT DATE: June 26, 2018 Distribution: DSFM r/f, G:\\SFST\\Devaser\\Casework\\AFS-BRR Amd 6 RAI 1 Letter.docx ADAMS Package No.: ML18179A428
- via e-mail OFC DSFM DSFM DSFM DSFM DSFM NAME NDevaser*
WWheatley*
ASotomayor-Rivera*
TTate*
JMcKirgan DATE 06/21/18 06/21/18 06/21/18 06/26/18 06/26/18 OFFICIAL RECORD COPY
Enclosure Request for Additional Information AREVA Federal Services LLC Docket No. 71-9341 Certificate of Compliance No. 9341 Model No. BEA Research Reactor Transportation Package Regarding Safety Analysis Report: Cobalt-60 Production Targets Submitted: January 2018 By application dated January 30, 2018, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18044A148), AREVA Federal Services LLC (AFS) submitted an application in accordance with Title 10 of the Code of Federal Regulations Part 71 (10 CFR Part 71) to amend Certificate of Compliance No. 9341 for the Model No. BRR package per the details of the submitted revision of the safety analysis report for the BRR package, Revision 11. This request for additional information identifies information needed by the U.S.
Nuclear Regulatory Commission staff (the staff) in connection with its review of the application.
The staff used guidance provided in NUREG-1617, "Standard Review Plan for Transportation Packages for Spent Nuclear Fuel, in its review of the application.
The question 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 regulatory requirements.
Shielding Evaluation
- 1. Demonstrate how the calculated dose rates for the package containing the 1 kCi source at discrete locations can be scaled up to represent a package configuration that contains different sources with varying strengths.
The applicant stated in Section 5.6.2.1 of the SAR (ADAMS Accession No. ML18044A164) that a 1 kCi Co-60 source is modeled and scaled as needed to match the Co-60 payload of the different package configurations. Source intensity, gamma energy release rate, and total source decay heat for the 1 kCi modeled Co-60 source are shown in Table 5.6-2 alongside scaled values for Type 1 and Type 2 payloads. However, the configurations are not uniform. Therefore, it is not clear to the staff how the scaling is performed for the non-uniform source configuration.
The staff requests that the applicant provide an explanation, with justification, on how the model using a 1 kCi source can be scaled up when the source is not uniform.
This information is needed to verify compliance with the external dose rate regulations in 10 CFR 71.47 and 10 CFR 71.51(a)(2).