ML15149A385
| ML15149A385 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/25/2015 |
| From: | Blake Purnell Division of Operating Reactor Licensing |
| To: | Bryan Hanson Exelon Generation Co |
| Pulvirenti A | |
| References | |
| TAC MF5734, TAC MF5735 | |
| Download: ML15149A385 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 June 25, 2015
SUBJECT:
DRESDEN UNITS 2 AND 3-ACCEPTANCE OF LICENSE AMENDMENT REQUEST REGARDING SPENT FUEL STORAGE POOL CRITICALITY METHODOLOGY AND PROPOSED CHANGE TO TECHNICAL SPECIFICATION 4.3.1, "CRITICALITY" (TAC NO(S). MF5734 AND MF5735)
Dear Mr. Hanson:
By application dated December 30, 2014 (RS-14-310) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14364A100), as supplemented by licensee letter dated May 8, 2015 (RS-15-119) (ADAMS Accession No. ML15128A305), Exelon Generation Company, LLC (EGC, the licensee) submitted a license amendment request for Dresden Nuclear Power Station (DNPS), Units 2 and 3. The proposed license amendment would change the criticality safety analysis methodology for the DNPS, Unit 2 and 3, spent fuel pools and the DNPS Technical Specification (TS) 4.3.1, "Criticality."
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR Part 50 addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
If you have any questions, please contact Russell Haskell at (301) 415-1129, or email Russell.Haskell@nrc.gov.
Docket No(s). 50-237 and 50-249 cc: Distribution via Listserv Sincerely, (jj_~
Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML15149A385 OFFICE NRR/DORL/LPL4-2 NRR/DORL/LPL3-2 NRR/DORL/LPL3-2 NRR/DORL/LPL3-2 LA NAME APulvirenti RHaskell BPurnell SRohrer DATE 6/9/15 6/9/15 6/10/15 6/11 /15 OFFICE NRR/DORL/LPL3-2 NRR/DORL/LPL4-2 NRR/DORL/LPL3-2 NAME BBeasley APulvirenti BPurnell DATE 6/22/15 6/24/15 6/25/15