ML082320884

Site, Independent Spent Fuel Storage Instillation (ISFSI) General License Cask Certificate of Compliance, 30-Day Report Due to Higher Canister Heat Loading

ML082320884
Person / Time
Site:	Oconee, 07201004
Issue date:	08/13/2008
From:	Baxter D Duke Energy Carolinas, Duke Energy Corp
To:	Document Control Desk, NRC/NMSS/SFPO
References
Download: ML082320884 (5)

Text

S Duke DAVE BAXTER r negyVice President SEnergy. Oconee Nuclear Station Duke Energy Corporation ONO1 VP/7800 Rochester Highway Seneca, SC 29672 864-885-4460 864-885-4208 fax dabaxter@dukeenergy.com August 13, 2008 ATTN: Document Control Desk, Director, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Site, Units 1, 2, and 3 Independent Spent Fuel Storage Installation (ISFSI)

General License Cask Certificate of Compliance, Docket No.: 72-1004 30-day Report Due to Higher Canister Heat Loading In accordance with the subject Certificate of Compliance (CofC) sections, Duke Energy Carolinas, LLC (Duke), hereby submits the subject report to the Commission. NUHOMS Model 102 Horizontal Storage Module (HSM) E-43 was placed in service at the Oconee Nuclear Site on August 1, 2008. The total spent fuel decay heat load of the NUHOMS 24PHBL Dry Shielded Canister (DSC) was 21.51 kilowatts (kW), which exceeded the maximum heat load of previously loaded canisters and, pursuant to General Requirement 1.1.7, a 30-day report is required whenever this situation occurs (up to 24 kW).

The heat transfer characteristics were determined for the loaded HSM as required by Technical Specification 1.2.8 of the subject CofC. The difference between the average HSM inlet and outlet temperatures was used to calculate a temperature rise. This value was compared to a predicted maximum temperature rise (as a function of average inlet temperature and DSC heat load). The methodology for this predicted temperature rise is documented in the General License Certified Safety Analysis Report for the HSM,.and in Trans-Nuclear West calculation NUH004.0420.

The calculated temperature rise for the HSM is plotted with the predicted temperature difference rise for a 21.51 kW DSC in Attachment 1. Temperature measurements and the calculated temperature rise for the HSM are shown in Attachment 2. Since the equilibrium temperature rises measured do not exceed the calculated values, the HSM and DSC have been verified to be performing as designed.

www. duke-energy,com

U. S. Nuclear Regulatory Commission Page 2 August 13, 2008 If there are any questions regarding this registration, please contact Stephen C.

Newman, Oconee Regulatory Compliance Lead Engineer, at (864) 885-4388.

Very truly yours, Dave axter Vice President, Oconee Nuclear Site Attachments:

1. HSM E-43 Temperature Rise (calculated vs. predicted)

2. Heat Transfer Characteristics for HSM E-43 at ONS

U. S. Nuclear Regulatory Commission Page 3 August 13, 2008 cc:

Mr. Luis Reyes, Regional Administrator Region II Mr. Andy Hutto, Senior Resident Inspector Oconee Nuclear Site Mr. Lenny Olshan, Project Manager Office of Nuclear Reactor Regulation Senior Fuel Facility Inspector, Region II

U. S. Nuclear Regulatory Commission Page 5 August 13, 2007 / Attachment 1 ATTACHMENT 1 HSM E-43 Temperature Rise (calculated vs. predicted) 95 90 85 o 80 75 60 55 50 0 20 40 60 80 100 120 HSM Inlet Temperature (Deg. F)

U. S. Nuclear Regulatory Commission Page 6 August 13, 2008 / Attachment 2 ATTACHMENT 2 HeatTransfer Characteristics for HSM E-43 at ONS Avg. Inlet Avg. Outlet Temperature Calculated Temperature Temperature Rise Rise Date ('F) (OF) (OF) (OF) 8/1/08 84.6 161.55 76.92 86.72 8/2/08 76 153.75 77.75 85.32 8/3/08 73.25 151.25 78 84.87 8/4/08 78.75 152.5 73.75 85.77 8/5/08 76.75 153.75 77 85.47 8/6/08 75.5 149 73.5 85.27