ML051010283

Submittal of Registration for Independent Spent Fuel Storage Installation Casks and Notification of Thermal Performance for First System in Place

ML051010283
Person / Time
Site:	Millstone, 07201004
Issue date:	03/11/2005
From:	Price J Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
+sispmjr200504, 05-117, MPS 32PT-S100-A-R002, MPS 32PT-S100-A-R003
Download: ML051010283 (3)

Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station Dominion-Rope Ferry Road Waterford, CT 06385

" R I1a U.S. Nuclear Regulatory Commission Serial No.05-117 Attention: Document Control Desk MPS Lic/MAE RO Washington, DC 20555 Docket Nos. 50-336 72-47 License No. DPR-65

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DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 SUBMITTAL OF REGISTRATION FOR INDEPENDENT SPENT FUEL STORAGE INSTALLATION CASKS AND NOTIFICATION OF THERMAL PERFORMANCE FOR FIRST SYSTEM IN PLACE Pursuant to 10 CFR 72.212, 'Conditions of general license issued under §72.210,"

paragraph (b)(1)(ii), Dominion Nuclear Connecticut, Inc. (DNC) hereby provides the Nuclear Regulatory Commission (NRC) notification regarding the initial use and registration of spent fuel storage casks approved under NRC Certificate of Compliance No. 1004. The cask information required per 10 CFR 72.212(b)(1)(ii) is provided as follows:

Licensee Name: Dominion Nuclear Connecticut, Inc.

Licensee Address: Rope Ferry Road Waterford, CT 06385 Reactor License No.: DPR-65 Reactor Docket No.: 50-336 Cask Certificate No.: 1004 Cask Model No.: Standardized NUHOMS-32PT Cask Identification No.: MPS 32PT-S100-A-R002, Initial Use: February 15, 2005 MPS 32PT-S100-A-R003, Initial Use: February 22, 2005 In addition, pursuant to the General Requirements and Conditions of the Technical Specifications for Certificate of Compliance 1004, §1.1.7 'Special Requirements for First System in Place," a summary of the thermal performance of the first Dry Shielded Canister (DSC) loaded at the Millstone ISFSI is provided. DSC MPS 32PT-SlOO-A-R002 was loaded with Unit 2 spent fuel in a Horizontal Storage Module (HSM) Model 152. The calculated heat load for the DSC is approximately 13.5 kW, constituting the Mrnssol

Serial No.05-117 30-Day Notification in accordance with 10 CFR 72.212(b)(1)(ii)

Page 2of3 highest heat load for the current spent fuel loading campaign. The inlet and outlet air temperatures for the HSM were measured consistent with the method provided in Technical Specification 1.2.8. Upon obtaining equilibrium conditions, the measured inlet air temperature was 290 F and outlet air temperature was 780F, corresponding to a temperature difference of 49 0F. This temperature differential is well within that calculated for the specific heat load and ambient temperature. The calculation utilizes the same methodology and inputs as those described in the NUHOMS FSAR, and provides an appropriate adjustment for the actual heat load and ambient temperature.

For the conditions reported, the calculated temperature differential is 560F. Therefore, it is concluded the thermal performance for the initial loaded DSC/HSM at the Millstone ISFSI is satisfactory.

If you have any questions or require additional information, please contact Mr. David W.

Dodson, Licensing Supervisor, at (860) 447-1791, extension 2346.

Very truly yours, J. Price Siice President- Millstone

Serial No.05-117 30-Day Notification in accordance with 10 CFR 72.212(b)(1)(ii)

Page 3 of 3 Attachments:

Commitments made in this letter: None.

cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. R. Prince, NRC Inspector U.S. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. J. Wray, NRC Inspector U.S. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ms. M. J. Ross-Lee Spent Fuel Project Office, NMSS U.S. Nuclear Regulatory Commission 11555 Rockville Pike, M/S 0-6-F-18 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station