BSEP 10-0135, Independent Spent Fuel Storage Installation, Registration and Use of Casks to Store Spent Fuel and System Thermal Performance Assessment

Independent Spent Fuel Storage Installation, Registration and Use of Casks to Store Spent Fuel and System Thermal Performance Assessment

ML103330167
Person / Time
Site:	Brunswick, 07200006
Issue date:	11/18/2010
From:	Mentel P Progress Energy Carolinas
To:	Office of Nuclear Material Safety and Safeguards, Document Control Desk
References
BSEP 10-0135
Download: ML103330167 (6)

Text

Progress Energy NOV 1 8 2010 SERIAL: BSEP 10-0135 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 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, and 72-006 Independent Spent Fuel Storage Installation (ISFSI) Docket No.72-006 Registration and Use of Casks 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 providing information to register the use of two approved spent fuel storage casks at the Brunswick Steam Electric Plant (BSEP) ISFSI. The required cask registration information is provided in .

In addition, 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," require 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 dry shielded canister (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 (i.e., if using the Type 2 61BTH DSC).

Enclosure 2 provides a report and summary of heat loads for the two DSCs being registered through this letter. The calculation used to determine the limiting temperature differential between the HSM air inlet and air outlet for the heat loads being reported is consistent with the methodology in the Updated Final Safety Analysis Report for Amendment No. 10 to Certificate of Compliance No. 1004 for the NUHOMS-61BTH system.

Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant PO Box 10429 Southport, NC28461 1 ~jA50

I*

Document Control Desk BSEP 10-0135 / Page 2 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 WRM/wrm

Enclosures:

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

2. NUHOMS-61BTH System Thermal Performance Information

Document Control Desk BSEP 10-0135 / Page 3 cc (with enclosures):

U. S. Nuclear Regulatory Commission ATTN: Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, 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 10-0135 Page 1 of 1 Cask Registration Information Required by 10 CFR 72.2.12(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 Cask Model Number Type 2 NUHOMSO-61 BTH Horizontal Storage Module (HSM) Model HSM-H Number Cask Identification Numbers BNP-61 BTH-2-F- 1-HZ04 BNP-61BTH-2-F-1-HZ05 Service Dates October 28, 2010 (BNP-61BTH-2-F- 1-HZ04)

November 5, 2010 (BNP-61 BTH-2-F- 1-HZ05)

Enclosure 2 BSEP 10-0135 Page 1 of 2 NUHOMS-61BTH System Thermal Performance Information The following provides a 30-day notification of the results of the thermal performance assessment for the first system in place that is 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 dry shielded canister (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-61BTH-2-F- 1-HZ04 HSM Number 0-ISFSI-HSM-003 Loading Date October 28, 2010 Temperature Measurement Date (Equilibrium) November 1, 2010 Maximum Allowable Heat Load 31.2 kW Actual Loaded Heat Load 26.012 kW The calculated temperature differential limit is a function of both the DSC heat load and the ambient temperature. For the loaded DSC BNP-61BTH-2-F-1-HZ04, the heat load was 26.012 kW and the ambient temperature each day, at the time of the temperature measurements, was between 65°F and 74°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 65.5°F. The HSM for the DSC BNP-61BTH-2-F-1-HZ04 was closed on October 28, 2010, and the temperature rise reached equilibrium by November 1, 2010. On November 1, 2010, the air inlet temperature was 65.0°F (i.e., based on an average of three measurements) and the air outlet temperature was 88.9°F (i.e., based on an average of four measurements). This gives an actual temperature rise of 23.9°F, which is significantly less than the allowable limit of 65.5°F.

Enclosure 2 BSEP 10-0135 Page 2 of 2 DSC Number BNP-61BTH-2-F- 1-HZ05 HSM Number 0-ISFSI-HSM-004 Loading Date November 5, 2010 Temperature Measurement Date (Equilibrium) November 10, 2010 Maximum Allowable Heat Load 31.2 kW Actual Loaded Heat Load 27.974 kW For the loaded DSC BNP-61BTH-2-F-1-HZ05, the heat load was 27.974 kW and the ambient temperature each day, at the time of the temperature measurements, was between 57°F and 717F (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 70'F. The HSM for the DSC BNP-61BTH-2-F-1-HZ05 was closed on November 5, 2010, and the temperature rise reached equilibrium by November 10, 2010. On November 10, 2010, the air inlet temperature was 69.8°F (i.e., based on an average of three measurements) and the air outlet temperature was 94.2°F (i.e., based on an average of four measurements). This gives an actual temperature rise of 24.4°F, which is significantly less than the allowable limit of 70'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 NUHUMS-61BTH system, is conservative.

Reference:

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