ML17061A614
| ML17061A614 | |
| Person / Time | |
|---|---|
| Issue date: | 03/02/2017 |
| From: | Michael Layton Division of Spent Fuel Management |
| To: | Mccullum R Nuclear Energy Institute |
| CHUNG D | |
| References | |
| Download: ML17061A614 (2) | |
Text
R. McCullu UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 2, 2017 Rodney J. McCullum Senior Director, Used Fuel and Decommissioning Programs Nuclear Energy Institute 1201 F Street, N.W., Suite 1100 Washington, D.C. 20004
SUBJECT:
RESPONSE TO NUCLEAR ENERGY INSTITUTE LETTER REGARDING PROPOSED REGULATORY ISSUE RESOLUTION PROTOCOL FOR IMPROVING THE EFFICIENCY OF THE REGULATORY FRAMEWORK FOR DRY STORAGE OF SPENT NUCLEAR FUEL
Dear Mr. McCullum:
In response to your letter (RIRP-I-16-01) dated January 12, 2017 (Agencywide Document Access Management System Accession No. ML17013A155), NRC staff from the Office of Nuclear Material Safety and Safeguards, Division of Spent Fuel Management (DSFM) reviewed the Used Fuel and Transportation Issue Screening Form, the Resolution Plan, and independent spent fuel storage installation (ISFSI) License and Cask Certificate of Compliance Format, Content, and Selection Criteria. While the proposed approach is generally in alignment with our discussions during the November 21, 2016, meeting, there are a few details that still need to be addressed in the approach to determine the selection criteria used for evaluation within the graded-approach framework. As you are aware, the staff has planned a public meeting for March 24, 2017, to further discuss the approach proposed in your letter.
Through the public meetings and workshops held during 2016, significant progress has been made for building a graded-approach regulatory framework to advance clarity in the selection criteria for deciding what information should be included in the certificate of compliance (CoC) and technical specification (TS), and what information can be relocated to other documents such as the final safety analysis report (FSAR). The staff plans to continue making progress on this effort during the upcoming public meeting to support a pilot CoC application implementing the proposed approach. The staff will also continue to provide comments during the development of industry guidance to offer clarity as to the appropriate details to be included in the CoC.
R. McCullum 2 If you have questions, please contact Donald Chung. Dr. Chung can be reach at (301) 415-8738. We look forward to continuing cooperation on this effort.
Sincerely,
/RA/
Michael Layton, Director Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards cc: Mark Richter, NEI
ML17061A614 Office DSFM/CSRAB DSFM/SFLB/LA DSFM/CSRAB DSFM DSFM Name DChung WWheatley TTate AHsia MLayton Date 2/24/17 2/22/17 2/24/17 2/47/17 3/2/17