ML26048A388
| ML26048A388 | |
| Person / Time | |
|---|---|
| Site: | 07109979 |
| Issue date: | 02/22/2026 |
| From: | Nishka Devaser Storage and Transportation Licensing Branch |
| To: | Eberl K Savannah River National Lab |
| References | |
| EPID L-2025-LLA-0073 | |
| Download: ML26048A388 (0) | |
Text
Kurt R. Eberl Program Manager Battelle Savannah River Alliance, LLC Savannah River National Laboratory Aiken, SC 29808
SUBJECT:
CERTIFICATE OF COMPLIANCE NO. 9979 FOR THE MODEL NO. 9979 -
REQUEST FOR ADDITIONAL INFORMATION
Dear Kurt R. Eberl:
By letter dated November 21, 2025 (Agencywide Documents Access and Management System
[ADAMS] Accession No. ML25325A178), you submitted an application to the U.S. Nuclear Regulatory Commission (NRC) for a revision to the certificate of compliance (CoC) for the 9979 transportation package.
In connection with our review, the NRC needs 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 30 days from the date of this letter.
In accordance with Title 10 of the Code of Federal Regulations Part 2, Agency Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room (PDR) or from the Publicly Available Records component of the NRCs ADAMS. ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. The PDR is open by appointment. To make an appointment to visit the PDR, please send an email to PDR.Resource@nrc.gov or call 1-800-397-4209 or 301-415-4737, between 8 a.m. and 4 p.m. eastern time (ET), Monday through Friday, except Federal holidays.
February 22, 2026
K. Eberl 2
Please reference Docket No. 71-9979 and Enterprise Project Identifier No. L-2025-LLA-0073 in future correspondence related to this request. The staff are available to meet to discuss your proposed responses. If you have any questions, I may be contacted at (301) 415-5196.
Sincerely, Nishka Devaser, Project Manager Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-9979 EPID L-2025-LLA-0073
Enclosure:
Request for Additional Information Signed by Devaser, Nishka on 02/22/26
ML26048A388 OFFICE NMSS/DFM NMSS/DFM NMSS/DFM NAME NDevaser WWheatley JSmith DATE 2/17/26 2/18/26 2/18/26 OFFICE NMSS/DFM NMSS/DFM NMSS/DFM NAME CSydnor LRegner YDiazSanabria DATE 2/18/26 2/20/26 2/22/26 OFFICE NMSS/DFM NAME NDevaser DATE 2/22/26
Enclosure Request for Additional Information Docket No. 71-9979 Model No. 9979 Package Certificate of Compliance No. 9979 Revision No. 3 By letter dated November 21, 2025 (Agencywide Documents Access and Management System Accession No. ML25325A178), Battelle Savannah River Alliance (BSRA or the applicant) submitted an application to the U.S. Nuclear Regulatory Commission (NRC) for a revision to the certificate of compliance (CoC) for the 9979 transportation package.
This request for additional information identifies information needed by the NRC staff (NRC or the staff) in connection with its review of the application. The staff used guidance provided in NUREG-2216, "Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material, in its review of the application.
The questions below describe 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.
Chapter 2:
Structural Analysis RAI 2-1.
The applicant is asked to specifically cite which codes and/or standards are employed to evaluate the package for the effects of external pressures, vibration and shock, and the fire event in SAR section 2.1.4, Identification of Codes and Standards for Package Design.
SAR section 2.1.2 states that the pressure and vibration effects are evaluated with criteria equivalent to American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (B&PVC), Section III-NB level A service conditions, and that the fire event is evaluated by analysis. In SAR section 2.1.4, the applicant refers to the drawings for the code and standards applicable to fabrication, examination and testing but does not specifically cite the codes and/or standards employed for structural design evaluation.
This information is required to satisfy the requirements of 10 CFR 71.31(c).
Chapter 7:
Materials Analysis RAI 7-1.
For packages that rely on the compact augmented permeation system (CAPS) to protect against the accumulation of a flammable concentration of hydrogen gas in the 30-gallon drum for normal conditions of transport (NCT), please provide additional information to address the following criteria:
a) Construction of the CAPS, including drawings, dimensions, listing of parts, and associated material specifications; b) Describe the compatibility of the CAPS subcomponents and materials with package service environments (NCT temperatures, interior atmosphere, and exterior environment of the 30-gallon drum), and NCT and HAC loadings, such that the functionality of the CAPS is assured for NCT, and containment integrity is assured for both NCT and HAC;
2 c)
Describe CAPS design features for preventing significant transfer of radioactive particulates and radionuclides from volatile species and noble gases outside of the 30-gallon drum during NCT to ensure compliance with 10 CFR 71.43(h);
d) Describe CAPS design qualification testing, acceptance testing for placement of a newly manufactured CAPS into service, and periodic maintenance requirements to ensure CAPS functionality for NCT throughout its service life; e) Describe potential failure modes of the CAPS (e.g., blockages or material failures), method of detecting a CAPS failure during NCT, and contingencies and/or corrective actions if CAPS fails to function properly during NCT.
f)
Address whether the hydrophobic porous PTFE adhesive-backed disk (item 13 on Drawing No. R-R2-G-00057, Rev. 13) covering the new diffusion hole under the 55-gallon drum curl will allow for the passage of hydrogen gas that permeates through the CAPS, and describe the compatibility of the hydrophobic adhesive-backed disk with package service environments (NCT temperatures, interior, and exterior environments of the 55-gallon drum).
The Model 9979 package application describes the CAPS as an optional device that may be installed in the 30-gallon drum lid to prevent a flammable concentration of hydrogen gas from collecting within the 30-gallon drum during NCT. The application includes several references to technical requirements documents for the CAPS, including M-DS-G-00124 (cited in Table 2.4 and Drawing No. R-R1-G-00028, Rev. 9) and M-DS-A-00124 (cited in section 8.1.5 of the application for CAPS acceptance tests). The staff needs to review the above requested information from these documents and/or other sources to ensure that the CAPS is adequately designed, constructed, tested, and maintained to prevent a flammable concentration of hydrogen gas from collecting in the 30-gallon drum during NCT, and to ensure that CAPS structural integrity is adequately maintained for NCT and HAC loading to protect against a loss of containment for the 30-gallon drum.
The staff is requesting this information in order to determine whether the package meets the requirements of 10 CFR 71.33(a), 71.35(a), and 71.43(d, e, f, and h).
Editorial Comments:
E-1.
The applicant should note that NUREG-2216 Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material superseded NUREG-1609, which is cited in SAR section 2.1.2.