L-MT-13-103, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
| ML13283A101 | |
| Person / Time | |
|---|---|
| Site: | Monticello, 07201004  |
| Issue date: | 10/07/2013 |
| From: | Fili K Northern States Power Co, Xcel Energy |
| To: | Document Control Desk, NRC/NMSS/SFPO |
| References | |
| L-MT-13-103 | |
| Download: ML13283A101 (8) | |
Text
Monticello Nuclear Generating Plant XceIEnergy~
2807 W County Road 75 Monticello, MN 55362 October 7, 2013 L-MT-13-103 10 CFR 72.212(b)(2)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001 Monticello Nuclear Generating Plant Renewed Facility Operating License No. DPR-22 Reactor Docket Number: 50-263 Independent Spent Fuel Storage Installation Docket Number: 72-1004 Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel In accordance with 10 CFR 72.212(b)(2), Northern States Power Company - Minnesota (NSPM), doing business as Xcel Energy, Inc., is registering the use of three U. S.
Nuclear Regulatory Commission (NRC) approved spent fuel storage casks at the Monticello Nuclear Generating Plant (MNGP) Independent Spent Fuel Storage Installation (ISFSI). Registration of a cask is required no later than 30 days after using that spent fuel storage cask to store spent fuel in accordance with 10 CFR 72.212(b)(2).
Cask-specific registration information is provided for each NUHOMS-61 BTH dry shielded canister (DSC) in Enclosure 1. of this letter provides a summary of the results of the thermal performance assessment for the highest heat load 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." provides the results of the thermal performance assessment for DSC MNP-61BTH-1-B-2-011, which has the highest heat load to date.
If you have any questions or require additional information, please contact Mr. Richard Loeffler, Senior Regulatory Affairs Engineer, at (763) 295-1247.
Document Control Desk L-MT-13-103 Page 2 of 2 Summary of Commitments This letter proposes no new commitments and does not revise any existing commitments.
Karen D. Fili Site Vice President Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (2) cc:
Regional Administrator, Region III, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC
ENCLOSURE1 MONTICELLO NUCLEAR GENERATING PLANT
SUMMARY
OF REGISTRATION INFORMATION FOR THE FIRST THREE DRY SHIELDED CANISTERS LOADED DURING THE 2013 LOADING CAMPAIGN (1 Page Follows)
L-MT-1 3-103 Page 1 of 1
SUMMARY
OF REGISTRATION INFORMATION FOR THE FIRST THREE DRY SHIELDED CANISTERS LOADED DURING THE 2013 LOADING CAMPAIGN HSM Model Number HSM Serial Date Placed Number into Service Cask Certificate of No. 1004 Compliance:
Cask Amendment Amendment 10 Number:
DSC Model Number:
NUHOMS-61BTH DSC Serial Number:
MNP-61BTH-1-B-2-011 NUHOMS HSM-H HSM-6A 09/09/2013 MNP-61BTH-1-B-2-012 NUHOMS HSM-H HSM-6B 09/17/2013
[MNP-61BTH-1-B-2-013 INUHOMS HSM-H HSM-7A 09/26/2013
ENCLOSURE2 MONTICELLO NUCLEAR GENERATING PLANT
SUMMARY
OF THE THERMAL PERFORMANCE OF THE MNP-61BTH-1-B-2-011 DRY SHIELDED CANISTER (3 Pages Follow)
L-MT-1 3-103 Page 1 of 3
SUMMARY
OF THE THERMAL PERFORMANCE OF THE MNP-61BTH-1-B-2-011 DRY SHIELDED CANISTER On September 9, 2013 the Monticello Nuclear Generating Plant (MNGP) placed its initial NUHOMS-61BTH Dry Shielded Canister (DSC) for the 2013 loading campaign into storage. Technical Specification 1.1.7 of Certificate of Compliance 1004, Amendment 10 requires that the heat transfer characteristics of the system be recorded by taking temperature measurements of the first DSC placed in service (MNP-61BTH B-2-011 on 09/09/2013) and any subsequent DSCs containing higher decay heat loads.
The thermal performance of the system will be assessed by measuring the air inlet and outlet temperature for normal airflow through the HSM in accordance with Technical Specification 1.2.8b.
Technical Specification 1.1.7 requires that a letter report be submitted to the NRC for the evaluation and assessment of the heat removal characteristics of the loaded DSC in the HSM within 30 days of placing the DSC in service, in accordance with 10 CFR 72.4.
This report is being submitted to meet this requirement.
System Information DSC Serial Number:
MNP-61BTH-1-B-2-011 DSC Model:
NUHOMS-61BTH Total Decay Heat Load for DSC:
10.96 kW HSM Serial Number:
HSM-6A HSM Model:
HSM-H Certificate of Compliance:
No. 1004, Amendment 10
L-MT-l 3-103 Page 2 of 3 As required by Technical Specification 1.2.8b, inlet and outlet vent temperatures for HSM-6A were taken daily. These readings are shown in Figure Number 1 below.
Figure 1 - HSM-6A Inlet and Outlet Vent Temperatures 100.0 90.0 60.0 50.0-
~40ý0
-I
-ft ft
+
30.0 2D0.0 10.0 09/10/11 09/11/13 09/12/13 09113/13 Date 09/14/13 09/15/13 09/16/13 HSM-H Inkt
-113
"- OulkI Technical Specification 1.2.8b requires that, if a 61 BTH DSC is placed in the HSM-H with a heat load less than 31.2 kW, the limiting difference between outlet and ambient temperatures shall be determined by a calculation performed by the user using the same methodology and inputs documents in Appendix T of the Standardized NUHOMS FSAR. Transnuclear calculation NUH61 BTH-0425, NUHOMS HSM-H Air Temperature Rise vs. Decay Heat Calculation establishes acceptance criteria for the temperature rise across the HSM-H vents for varying ambient temperatures and decay heat loads.
L-MT-1 3-103 Page 3 of 3 Data on the Temperature Rise across the inlet and outlet vents of HSM-6A are shown in Figure Number 2 below along with the associated allowable temperature difference from Transnuclear calculation NUH61 BTH-0425.
Figure 2 - HSM-6A Vent Temperature Difference 40.0 35.0 30.0
~25.0 120.0 10.0 10 I
0.0 1-...
09/1 0113 09/11113 09112/
W13/13 09114/13 09/15/13 Date 09/16/13 Tompa'tu Dafftre=ct AWlobte The system reached thermal equilibrium on or before September 16, 2013. At that time the temperature difference across the inlet and outlet vents was 28.30F. This is below the acceptance criteria of 35.0°F. MNGP has determined the system is functioning as designed.