ML16273A275

Susquehanna, Units 1 and 2 - Registration for the Use of Dry Fuel Storage Module D-16 and Thermal Performance Assessment

ML16273A275
Person / Time
Site:	Susquehanna, 07201004
Issue date:	09/29/2016
From:	Franke J A Susquehanna, Talen Energy
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
PLA-7521
Download: ML16273A275 (2)

Text

Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 jon.franke@talenenergy.com ENERGY SEP 2 9 2018 ATTN: Document Control Desk 10 CFR 72.212 Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION REGISTRATION FOR THE USE OF DRY FUEL STORAGE MODULE D-16 AND THERMAL PERFORMANCE ASSESSMENT PLA-7521 Docket No. 72-28 Pursuant to 10 CFR 72.212(b)(2), this letter is being submitted to register Susquehanna Nuclear, LLC's use of Dry Fuel Storage Module D-16 at the Susquehanna Steam Electric Station. The required information follows: Licensee Name: Licensee Address: Reactor License Numbers: Reactor Docket Numbers: Dry Fuel Storage Docket Number: Person Responsible for Providing Additional Information:

Cask Certificate Number: Cask Model Number: Susquehanna Nuclear, LLC and Allegheny Electric Cooperative, Inc. Susquehanna Steam Electric Station 7 69 Sa l em Boulevard Berwick, P A 18603 Unit 1 NPF-14 Unit2 NPF-22 Unit 1 50-387 Unit2 50-388 72-28 Melisa Krick, Nuclear Regulatory Affairs 72-1004, Amendment 10 NUHOMS -61BTH Horizontal Storage Module (HSM) Model: Cask Identification (Serial Number): HSM Identification:

Load Date: NUHOMS Model 102 SSE-61BTH-1-C-2-066 D-16 September 9, 2016. Document Control Desk PLA-7521 In addition, this letter provides information for the Dry Shielded Canister (DSC) required by Technical Specification (TS) for Certificate of Compliance (CoC) No. 1004, Amendment No. 10, Section 1.1.7, "Special Requirements for First System in Place." Technical Specification 1.1. 7 requires the submittal of a thermal performance assessment for all DSCs that are loaded with higher heat loads than previously reported.

The following is the thermal performance assessment data for the identified DSC: HSM Identification Number: Dry Shielded Canister:

Calculated Heat Load: Calculated Temperature Rise: Measured Temperature Rise (Note 1): D-16 SSE-61BTH-1-C-2-066 17.237 kW 71.0°F 48.4°F Note 1: The measured temperature rise represents the measured change in temperature during equilibrium conditions.

There are no new or revised regulatory commitments contained in this letter. Should you have any questions regarding this submittal, please contact Mr. Jason Jennings, Manager-Nuclear Regulatory Affairs at (570) 542-3155.

J 1\. Franke Copy: NRC Region I, Regional Administrator Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, PA DEP/BRP