ML18190A400

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Letter to P. Noss Request for Additional Information for Review of the Letter Authorization for the Model No. Bea Research Reactor (Brr) Package (EPID No. L-2018-LLA-0117) (W/Enclosure)
ML18190A400
Person / Time
Site: 07109341
Issue date: 07/06/2018
From: Garcia-Santos N
Spent Fuel Licensing Branch
To: Noss P
Orano Federal Services
Garcia-Santos N
References
EPID L-2018-LLA-0117
Download: ML18190A400 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 6, 2018 Mr. Philip Noss Licensing Manager Orano Federal Services LLC 505 S. 336th St., Suite 400 Federal Way, WA 98003

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR REVIEW OF THE LETTER AUTHORIZATION FOR THE MODEL NO. BEA RESEARCH REACTOR (BRR)

PACKAGE (EPID NO. L-2018-LLA-0117)

Dear Mr. Noss:

By application dated April 19, 2018 [Agencywide Documents Access and Management System Accession (ADAMS) No. ML18122A065], Orano Federal Services LLC (Orano or the applicant),

requested authorization for a one time shipment of tests assemblies using the Model No. BEA Research Reactor (BRR) transport package, Certificate of Compliance (CoC) No. 9341. These test assemblies are not authorized contents of the Model No. BRR.

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 August 20, 2018. Inform us at your earliest convenience, but no later than July 27, 2018, if you are not able to provide the information by that date. If you are unable to provide a response by August 20, 2018, our review may be delayed.

Please reference Docket No. 71-9341 and EPID No. L-2018-LLA-0117 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, I may be contacted 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. 71-9341 EPID No. L-2018-LLA-0117

Enclosure:

Request for Additional Information

ML18190A400 G:\\SFST\\Garcia\\Casework_NGS\\Spent Fuel Packages\\BRR-NGS\\BRR_Rev_5_Letter_Authorization_2018\\BRR-RAIs_Ltr_Letter_Autorization.docx OFFICE DSFM DSFM DSFM NAME NGarcía Santos SFigueroa ASotomayor Rivera DATE 07/03/2018 07/03/2018 07/05/2018 OFFICE DSFM DSFM DSFM NAME Zhian Li for TTate JMcKirgan DATE 07/05/2018 07/06/2018 C = COVER E = COVER & ENCLOSURE N = NO COPY

Enclosure Request for Additional Information Orano Federal Services LLC Docket No. 71-9341 Certificate of Compliance No. 71-9341 Model No. BEA Research Reactor (BRR) Package By application dated April 19, 2018 [Agencywide Documents Access and Management System Accession (ADAMS) No. ML18122A065], Orano Federal Service LLC (Orano or the applicant),

requested authorization for a one time shipment of tests assemblies using the Model No. BEA Research Reactor (BRR) transport package, Certificate of Compliance (CoC) No. 9341. These test assemblies are not authorized contents of the Model No. BRR under the current CoC.

This request for additional information (RAI) identifies information needed by the NRC staff in connection with its review of the application. NUREG-1617, Standard Review Plan for Transportation Packages for Spent Fuel, were used by the staff in its review of the application.

Each RAI describes information needed by the staff 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 Sh-1. 1 Provide the parameters used to calculate the gamma and neutron source terms.

In Section 4.2 of the BRR application, the applicant stated that the spent fuel payload source term is generated in two steps using the ORIGEN module of SCALE 6.2.1 code package. However, the applicant did not provide a description on how the parameters (i.e., burnup, enrichment) were used to calculate the gamma and neutron sources.

This information is needed to determine compliance with the regulations in 10 CFR 71.47.

1 In general, the nomenclature used for identifying the RAIs is as follows: Topic-Applications Chapter-Counter. (Topics: G -

General; Cr - Criticality; M - Materials; and Sh - Shielding.)