ML18283A323
| ML18283A323 | |
| Person / Time | |
|---|---|
| Site: | 07201004, Nine Mile Point  (DPR-063, NPF-069) |
| Issue date: | 09/27/2018 |
| From: | Moore D Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| NMP1L 3242 | |
| Download: ML18283A323 (2) | |
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Exelon Generation NMP1L 3242 September 27, 2018 10 CFR 72.212(b)(2)
U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 Docket Nos. 50-220 and 50-41 O Nine Mile Point Nuclear Station Independent Spent Fuel Storage Installation General License Docket No. 72-1036, 7 *z_- /DD lf
SUBJECT:
General License 30-day Cask Registration Notification and Thermal Performance Assessment Pursuant to the requirements of 1 O CFR 72.212(b)(2), this letter provides the information to register the use of three approved spent fuel storage casks at the Nine Mile Point Nuclear Station (NMPNS) Independent Spent Fuel Storage Installation (ISFSI).
Licensee's Name:
Address:
Reactor License Numbers:
Docket Numbers:
Person Responsible for Providing additional information:
Cask Certificate Number:
Certificate Amendment Number:
Cask Model Number:
Cask Identification Numbers:
Nine Mile Point Nuclear Station, LLC PO Box 63 Lycoming, NY 13093 DPR-63 and NPF-69 50-220, 50-410 and 72-1036 Mr. Kenneth J. Kristensen 315-349-2069 1004 10, Revision 1 NUHOMS-61 BTH NMP-61 BTH-1-A-2-030, loaded August 30, 2018 NMP-61 BTH-1-A-2-031, loaded September 6, 2018 NMP-61 BTH-1-A-2-032, loaded September 13, 2018 The Technical Specifications (TS) for Certificate of Compliance (CoC) No. 1004, Amendment No. 10, Revision 1, § 1.1.7 "Special Requirements for First System in Place", requires the results of the temperature measurements of the first Dry Shielded Canister (DSC) placed in service be submitted to the NRC for evaluation and assessment. Additionally, this section of TS requires subsequent users of the system to report heat loads higher than the first user. The first user of the NU HOMS CoC No. 1004, Duke Energy, submitted the heat transfer characteristics for an 18.95 kilowatt (kW) Dry Shielded Canister (DSC) in a letter to the NRC, from Duke Energy, "Cask Certificate of Compliance, Docket No.: 72-1004, 30-day Report for Higher Canister Heat Loading per General Requirement Section 1.1.7," dated August 8, 2007
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30 Day Cask Registration September 27, 2018 Page2 (ML072340622). The first DSC loaded at NMPNS had a heat load of 7.30 kW, as reported in our letter dated October 17, 2012.
A summary of the thermal performance of DSCs 30, 31 and 32 in place at the NMPNS ISFSI is submitted for your information.
Horizontal Storage Module (HSM) Model:
NUHOMS Model HSM-H HSM Identification Number:
Cask:
Calculated Heat Load:
Calculated I::. T:
Actual t::.T (Note 1):
HSM Identification Number:
Cask:
Calculated Heat Load:
Calculated I::. T:
Actual I::. T (Note 1):
HSM Identification Number:
Cask:
Calculated Heat Load:
Calculated I::. T:
Actual I::. T (Note 1 ):
7DFS-HSM008C NMP-61 BTH-1-A-2-030 8.565 kW 46 degrees F 20.4 degrees F 7DFS-HSM008D NMP-61 BTH-1-A-2-031 8.405 kW 46 degrees F 20.5 degrees F 7DFS-HSM008E NMP-61 BTH-1-A-2-032 8.251 kW 46 degrees F 17.9 degrees F Note 1: The actual I::. T represents the measured I::. T obtained during equilibrium conditions.
Equilibrium conditions were achieved when the daily temperature change observed was less than 6 degrees F over three consecutive days.
This letter contains no NRC commitments.
Should you have any questions regarding the information in this submittal, please contact Ken Kristensen at (315) 349-2069.
Sincerely, Dennis M. Moore Regulatory Assurance Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC DMM/KJK cc:
NRC Regional Administrator, Region I NRC Resident Inspector NRR Project Manager