BSEP 11-0025, Registration and Use of Cask to Store Spent Fuel and System Thermal Performance Assessment

Registration and Use of Cask to Store Spent Fuel and System Thermal Performance Assessment

ML110670429
Person / Time
Site:	Brunswick, 07200006, 07201004
Issue date:	02/24/2011
From:	Mentel P Progress Energy Carolinas
To:	Document Control Desk, NRC/NMSS/SFST
References
BSEP 11-0025
Download: ML110670429 (4)

Text

jProgress Energy FEB 2.4-2011 SERIAL: BSEP 11-0025 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Material Safety and Safeguards Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Independent Spent Fuel Storage Installation (ISFSI) Docket No.72-006 Registration and Use of Cask to Store Spent Fuel and System Thermal Performance Assessment Ladies and Gentlemen:

In accordance with 10 CFR 72.212(b)(1)(ii), Carolina Power & Light Company (CP&L),

now doing business as Progress Energy Carolinas, Inc., is registering the use of an approved spent fuel storage cask at the Brunswick Steam Electric Plant (BSEP) ISFSI.

Registration of the cask is required no later than 30 days after using that cask to store spent fuel. The required cask registration information is provided in Enclosure 1.

This letter is also providing a summary of the results of the thermal performance assessment for the highest heat load dry storage canister (DSC) as required by the General Requirements and Conditions of the Technical Specifications for Amendment No. 10 to Certificate of Compliance No. 1004, Section 1.1.7, "Special Requirements for First System in Place." Enclosure 2 provides the results of the thermal performance assessment for DSC BNP-61BTH-2-F-1-HZ08, which has the highest heat load to date.

No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Acting Supervisor - Licensing/Regulatory Programs, at (910) 457-2487.

Sincerely, Phyllis N. Mentel Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant POBus 10429 Southport, NC28461

Document Control Desk BSEP 11-0025 / Page 2 WRM/wrm

Enclosures:

1. Cask Registration Information Required by 10 CFR 72.212(b)(1)(ii)

2. NUHOMS-61BTH System Thermal Performance Information cc (with enclosures):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Mr. W. Lee Cox, III, Section Chief Radiation Protection Section North Carolina Department of Environment and Natural Resources 1645 Mail Service Center Raleigh, NC 27699-1645

Enclosure 1 BSEP 11-0025 Page 1 of 1 Cask Registration Information Required by 10 CFR 72.212(b)(1)(ii)

The following information is required by 10 CFR 72.212(b)(1)(ii), which states that the general licensee shall "Register use of each cask with the Nuclear Regulatory Commission no later than 30 days after using that cask to store spent fuel."

Licensee Name Carolina Power & Light Company (dba Progress Energy Carolinas, Inc.)

Licensee Address Progress Energy Brunswick Steam Electric Plant P.O. Box 10429 Southport, NC 28461-0429 Reactor License Numbers DPR-71 (Unit 1)

DPR-62 (Unit 2)

Reactor Docket Numbers 50-325 (Unit 1) 50-324 (Unit 2)

Independent Spent Fuel Storage Installation 72-006 (ISFSI) Docket Number Person Responsible for Providing Additional Lee Grzeck Information Acting Supervisor - Licensing/Regulatory Programs (910) 457-2487 Cask Certificate of Compliance Number 1004, Amendment 10 Cask Model Number Type 2 NUHOMSw-61BTH Horizontal Storage Module (HSM) Model HSM-H / 0-ISFSI-HSM-008 Number / HSM Number Cask Identification Number BNP-61BTH-2-F-1 -HZ08 Service Date February 9, 2011

Enclosure 2 BSEP 11-0025 Page 1 of I NUHOMS-61 BTH System Thermal Performance Information The following provides a 30-day notification of the results of the thermal performance assessment for the highest heat load dry storage canister (DSC) as required by the General Requirements and Conditions of the Technical Specifications for Certificate of Compliance No. 1004, Amendment No. 10, Section 1.1.7, "Special Requirements for First System in Place."

Section 1.1.7, "Special Requirements for First System in Place," requires a summary of the results of thermal measurements for the first cask system in place. Specifically, Section 1.1.7 requires the heat transfer characteristics of the cask system to be recorded by temperature measurements with a DSC loaded with fuel assemblies producing approximately 24 kW heat load in a horizontal storage module (HSM). Section 1.1.7 also requires that if the system does not include fuel capable of producing a 24 kW heat load, then the user may use the lesser heat load and provide a calculation and comparison of the thermal performance, and that this process should continue to be performed and reported for any higher heat loads until a 31.2 kW heat load is achieved for the Type 2 61 BTH DSC being used for the Brunswick Independent Spent Fuel Storage Installation (ISFSI).

DSC Number BNP-61 BTH-2-F- 1-HZ08 HSM Number 0-ISFSI-HSM-008 Loading Date February 9, 2011 Temperature Measurement Date (Equilibrium) February 12, 2011 Maximum Allowable Heat Load 31.2 kW Actual Loaded Heat Load 29.771 kW The calculated temperature differential limit is a function of both the DSC heat load and the ambient temperature. For the loaded DSC BNP-61 BTH-2-F- I-HZ08, the heat load was 29.771 kW and the ambient temperature each day, at the time of the temperature measurements, was between 42°F and 57°F (i.e., based on an average of three measurements). Based on these conditions and methodology consistent with the Transnuclear Updated Final Safety Analysis Report, the maximum allowable temperature rise is approximately 71.3°F. The HSM for the DSC BNP-61BTH-2-F-1-HZ08 was closed on February 9, 2011, and the temperature rise reached equilibrium by February 12, 2011. On February 12, 2011, the air inlet temperature was 57.4°F (i.e., based on an average of three measurements) and the air outlet temperature was 87.4°F (i.e., based on an average of four measurements). This gives an actual temperature rise of 30.0°F, which is significantly less than the allowable limit of 71.3°F.

Based on these measurements, it can be concluded that the thermal analysis, as described in Amendment No. 10 to Certificate of Compliance No. 1004 for the NUHOMS-61BTH system, is conservative.

Reference:

Transnuclear, Inc. Calculation No. NUH61BTH-0425, Revision 0.