ML042660158

Summary Report of Cask System Heat Removal Characteristics

ML042660158
Person / Time
Site:	Palisades, 07201004
Issue date:	09/10/2004
From:	Domonique Malone Nuclear Management Co
To:	Document Control Desk, NRC/NMSS/SFPO
References
+sispmjr200504, -RFPFR
Download: ML042660158 (4)

Text

NM C Committed to Nuclear Excellce Palisades Nuclear Plant Operated by Nuclear Management Company, LLC September 10, 2004 10 CFR 72.4 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 Palisades Nuclear Plant Dockets 50-255 and 72-7 License No. DPR-20 Summary Report of Cask System Heat Removal Characteristics By letter dated August 19, 2004, Nuclear Management Company, LLC (NMC) submitted a summary report of the heat removal characteristics of the first NUHOMSO 32PT cask system placed in service at the Palisades Nuclear Plant. NMC is now submitting a summary report of the heat removal characteristics of the fourth NUHOMS 32PT cask system placed in service at the Palisades Nuclear Plant. This fourth cask exceeds the heat load of the first cask placed in service. This report is provided in accordance with Certificate of Compliance 72-1004, Technical Specification 1.1.7, "Special Requirements for First System in Place." Dry shielded canister, serial number PNP-32PT-K01-S125, was placed in horizontal storage module (HSM), serial number HSM-004, and then placed in service at the Palisades Nuclear Plant on August 13, 2004 at 1602 hours0.0185 days <br />0.445 hours <br />0.00265 weeks <br />6.09561e-4 months <br />. The decay heat load is approximately 16.879 kW. Enclosure 1 contains the summary report of the heat removal characteristics for HSM-004.

For further information, please contact Bob Rice, Project Manager of Dry Fuel Storage, at (269) 764-2242.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

Daniel J. Malone Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosure (1)

CC Administrator, Region ll, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 27780 Blue Star Memorial Highway

• Covert, Michigan 49043-9530 Telephone: 269.764.2000

ENCLOSURE 1

SUMMARY

REPORT OF CASK SYSTEM HEAT REMOVAL CHARACTERISTICS Purpose This report summarizes the results of the initial thermal performance testing per Certificate of Compliance 72-1004, Technical Specification 1.2.8, 'HSM Maximum Air Exit Temperature." The testing was conducted on dry shielded canister (DSC), serial number PNP-32PT-K01-S125, which was placed in horizontal storage module (HSM), serial number HSM-004. The DSC was placed in service on August 13, 2004 at 1602 hours0.0185 days <br />0.445 hours <br />0.00265 weeks <br />6.09561e-4 months <br />. The decay heat load of this DSC is approximately 16.879 kW.

HSM-004 has a heat load that exceeds the heat load of the first NUHOMSO 32PT system placed in service at the Palisades Nuclear Plant. Therefore, Certificate of Compliance 72-1004, Technical Specification 1.1.7, "Special Requirements for the First System in Place," applies. Technical Specification 1.1.7 requires a summary report, due 30 days from placing the DSC in service, which summarizes the heat removal characteristics of the cask.

Test Methodoloqv Palisades does not have candidate fuel assemblies capable of producing a 24 kW heat load, while meeting Certificate of Compliance 72-1004, Technical Specification 1.2.1, "Fuel Specifications." Therefore, Reference 1 was used to establish maximum DSC temperature rise (AT) as a function of heat load and ambient temperature using the same methodology documented in the Final Safety Analysis Report.

The thermal performance test conducted on the DSC involved recording daily inlet air temperature (ambient) and outlet air temperature measurements from August 14, 2004, through August 20, 2004, when equilibrium was reached.

Test Results The results obtained during the initial thermal performance testing for DSC, serial number PNP-32PT-K01-S125, are provided in Table 1 below and shown in Figure 1.

The test data obtained was within established acceptance criteria. Nuclear Management Company, LLC has determined that the storage system is performing as designed, since the equilibrium temperature rises measured do not exceed the calculated values. This ensures the fuel clad and concrete temperatures are maintained at or below acceptable long-term storage limits.

Table 1 Ambient Avg. Exhaust Temperature Calculated Date/Time Temperature (OF) Temperature (fF) Rise (fF) 8/14/2004 12:00 70.8 114.7 43.9 72 8/15/2004 10:09 72.0 111.0 39.0 72 8/16/2004 10:40 72.8 111.3 38.5 72 8/17/2004 12:30 73.0 108.5 35.5 72 8/18/2004 10:39 74.9 114.8 39.9 72 8/19/2004 11:19 69.1 113.8 44.7 72 8/20/2004 11:10 67.8 110.2 42.4 71 Page 1 of 3

Figure 1: HSM-004 Temperature Data I--- Delta Temperature --- Ambient Temperature - Limit I 90.0 I - ________ - ________ ________ - - - ________

80.0

- - __ --A -6 - -- £ a-.-

70.0 60.0 L 50.0 a.

40.0 30.0 20.0 10.0 0.0 08/14/04 08/15/04 08/16/04 08/17/04 08/18/04 08/19/04 08/20/04 08/21/04 Date Page 2 of 3 ccO

Reference

1. Transnuclear Calculation Package NUH004.0420, 'Standardized NUHOMS HSM Air Temperature Rise vs. Decay Heat Calculation," Revision 5 Page 3 of 3