ML12187A230

Salem/Hope Creek Generating Station and Independent Spent Fuel Storage Installation - HI-STORM 100 Cask Supplemental Cooling System Validation Testing Using Air Mass Flow Rate

ML12187A230
Person / Time
Site:	Salem, Hope Creek
Issue date:	06/25/2012
From:	Perry J F Public Service Enterprise Group
To:	Document Control Desk, NRC/NMSS/SFST
References
LR-N12-0194
Download: ML12187A230 (9)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC JUN 2 5 2012 10 CFR 72.236(f)LR-N12-0194 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Materials and Safeguards Washington, DC 20555-0001 Salem Generating Station Units 1 and 2 Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos, 50-272 and 50-311 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354 Salem/Hope Creek Generating Station Independent Spent Fuel Storage Installation NRC Docket No. 72-0048

Subject:

HI-STORM 100 Cask Supplemental Cooling System Validation Testing Using Air Mass Flow Rate

References:

1) Entergy Letter to NRC 0CAN090902, HI-STORM-100 Cask System Supplemental Cooling System Validation Test, Arkansas Nuclear One, September 29, 2009 2) Entergy Letter to NRC, GNRO-2011/00086, HI-STORM-1 00 Cask System Supplemental Cooling System Validation Test, Grand Gulf Nuclear Station, Unit 1, October 14, 2011 3) Holtec Report HI-2002444, "HI-STORM 100 Cask System Final Safety Analysis Report", Revision 7 Condition 9, Special Requirements for First Systems in Place, of the Holtec HI-STORM 100 System Certificate of Compliance (CoC), requires a report of the Supplemental Cooling System (SCS) validation test and analysis for each first time user of a HI-STORM 100 Cask System SCS that uses components or a system that is not essentially identical to components or a system that has been previously tested. The SCS was first utilized during the initial Salem Unit 1 dry fuel storage loading campaigns that took place in September and October 2010. Each of the four systems loaded had heat loads that exceeded 28.74kW and/or included high burnup fuel assemblies, thus required the use of SCS.

Document Control Desk LR-N12-0194 Page 2 Prior SCS submittals (References 1 and 2) were reviewed to determine applicability for the use of SCS at Salem. These were deemed not to be applicable as neither had a configuration that could be considered essentially identical to the Salem SCS.A summary of the review performed of the SCS performance during its initial use at PSEG Nuclear is provided in the Attachment.

The results demonstrate that the SCS performance limits the coolant temperature to below 180 degrees Fahrenheit under steady-state conditions for the design basis heat load at an ambient air temperature of 100 degrees Fahrenheit as required by Reference

3. Therefore, the results for the MPCs loaded in 2010 validate the thermal methods described in the HI-STORM FSAR used to determine the SCS requirements.

There are no commitments contained in this letter.If you have any questions or require additional information, please contact Paul Bonnett at 856-339-1923.

Sincerely, John F. Perry Site Vice President

-Hope Creek Attachment

-Validation of PSEG Nuclear Supplemental Cooling System (SCS)Performance cc: Mr. W. Dean, Regional Administrator

-Region I U. S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 U. S. Nuclear Regulatory Commission Mr. J. Hughey, Project Manager -Hope Creek Mail Stop 08B3 Washington, DC 20555-0001 USNRC Senior Resident Inspector

-Hope Creek (X24)USNRC Senior Resident Inspector

-Salem (X24)

Document Control Desk LR-N12-0194 Page 3 Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 420 Trenton, New Jersey 08625 Hope Creek Commitment Coordinator (H02)Salem Commitment Coordinator (X25)Corporate Commitment Coordinator (N21)

Document Control Desk LR-N12-0194 Page 4 bcc: Vice-President

-Salem (S05)Director -Nuclear Fuels (N20)Regulatory Affairs Manager -Salem (x25)Regulatory Affairs manager -Hope Creek (H02)

Document Control Desk Attachment to LR-N 12-0194 Page 1 Attachment Validation of PSEG Nuclear Supplemental Cooling System (SCS) Performance Document Control Desk Attachment to LR-N12-0194 Page 2 The following tables provide the Supplemental Cooling System (SCS) temperature and water flow rate information as recorded during the initial use of the system for the Salem Unit 1 2010 dry fuel storage campaign: MPC-93 Time after SCS SCS SCS initiated T-inlet T-outlet Flow-rate Date/time (hours) (deg-F) (deg-F) (gpm)10/7/10 14:30 0 162 136 14.49 10/7/10 15:30 1.0 156 130 14.38 10/7/10 17:30 3.0 152 120 11.00 10/7/10 20:30 6.0 150 130 13.54 10/7/10 22:30 8.0 142 118 13.26 10/8/10 0:30 10.0 138 114 13.37 10/8/10 2:30 12.0 132 110 13.37 10/8/10 4:30 14.0 130 108 13.35 10/8/10 6:30 16.0 126 106 13.35 10/8/10 8:30 18.0 123 102 13.33 MPC-94 Time after SCS SCS SCS initiated T-inlet T-outlet Flow-rate Date/time (hours) (deg-F) (deg-F) (gpm)10/2/10 2:00 0 170 140 13.63 10/2/10 4:00 2.0 158 130 13.67 10/2/10 6:00 4.0 152 128 14.51 10/2/10 8:45 6.8 158 130 13.48 10/2/10 10:00 8.0 148 124 14.40 10/2/10 11:00 9.0 144 122 14.38 10/2/10 13:00 11.0 139 118 14.38 MPC-95 Time after SCS SCS SCS initiated T-inlet T-outlet Flow-rate Date/time (hours) (deg-F) (deg-F) (gpm)9/23/10 15:35 0 150 128 14.10 9/23110 17:30 1.9 154 132 14.42 9/23/10 19:30 3.9 158 131 14.41 9/23/10 21:30 5.9 160 135 14.96 9/23/10 23:30 7.9 158 124 13.78 9/24/10 1:30 9.9 144 122 13.76 9/24/10 3:30 11.9 140 120 13.67 9/24/10 5:30 13.9 136 116 13.54 9/24/10 7:30 15.9 134 114 13.71 Document Control Desk Attachment to LR-N12-0194 Page 3 MPC-96 Date/time 9/17/10 4:00 9/17/10 6:00 9/17/10 8:00 9/17/10 9:05 9/17/10 10:00 9/17/10 12:00 9/17/10 14:00 Time after SCS initiated (hours)0 2.0 4.0 5.1 6.0 8.0 10.0 SCS T-inlet (deg-F)170 163 157 157 162 150 144 SCS T-outlet (deg-F)145 137 132 132 138 126 124 Flow-rate (gpm)14.10 14.42 14.41 14.96 13.78 13.76 13.67 Note: SCS T-inlet or T-outlet measurements are taken from the inlet and SCS heat-exchanger.

outlet of the MPC 93 94 95 96 MPC helium backfill data Final Helium Backfill Measured He Pressure Pressure Adjusted to 70 deg-F (psig) (psig)52.8 37.53 63.5 44.48 52.2 37.23 64.1 44.63 Fuel Handling Building temperature during the time of the 2010 dry storage campaign ranged from 67 to 81 degrees Fahrenheit.

The MPC heat generation was calculated initially as part of the fuel selection for cask loading effort.MPC Heat Loads MPC 93 94 95 96 Qtotal(1)(kW)24.03 23.66 22.85 22.72 Qcoc(2)(kW)33.77 33.34 33.44 33.44 Notes: (1) Qtotal is the summation of the decay heat loads in each of the MPC 32 cells. This includes the individual assembly and contained component decay heat values at the time the MPC was loaded.

Document Control Desk Attachment to LR-N12-0194 Page 4 (2) Qcoc is the MPC heat generation used to demonstrate CoC compliance per HI-STORM 100 FSAR Revision 7 Section 2.1.9.1.2.

It is determined by taking the highest loaded fuel assembly heat generation (includes fuel and inserted component) multiplied by the total number of MPC cells.The combined SCS performance results for the initial system use are shown below: Salem Unit 1 2010 Dry Storage -SCS Measurements U-0)180 170 160 150 140 130 120 110 100 90 0 2 4 6 8 10 12 14 16 18 20 Time from SCS initiation (hours)s MPC-93 inlet --o- -MPC-93 outlet & MPC-94 inlet ---MPC-94 outlet-m-- MPC-95 inlet -.o- -MPC-95 outlet -- MPC-96 inlet --o- -MPC-96 outlet During the 2010 Salem dry fuel storage campaign, the SCS maintained the coolant water temperate below 180 degrees Fahrenheit at all times the system was running for all four canisters.

As previously noted, the ambient air temperature in the fuel handling building remained below 100 degrees Fahrenheit during these evolutions.

An additional assessment was performed to determine the system capability over a range of ambient conditions for a number of SCS water temperatures.

This provides an additional validation for this aspect of the CoC Condition 9 SCS requirement.

The heat exchanger utilized in the Salem SCS is sized to remove 110,000 BTU/hour from the cooling water to an ambient air temperature of 100 degrees Fahrenheit.

Per Holtec SCS specification, the heat exchanger was sized to remove sufficient heat to maintain fuel cladding temperatures below 400 degrees Celsius at an ambient air Document Control Desk Attachment to LR-N12-0194 Page 5 temperature of 100 degrees Fahrenheit (assuming maximum fouling factors for the process liquids).To maintain a lower outlet water temperature, the heat exchanger needs to transfer more heat to ambient. Also, as the difference between the water temperature (inside the annulus between the HI-TRAC (transfer cask) and MPC) and ambient air temperature increases, more of the MPC heat is rejected through the HI-TRAC, thus reducing the required heat exchanger capability.

Heat exchanger required capacity is shown below over a given range of ambient air and SCS water temperatures:

Required heat transfer rate (BTU/hour)

T-ambient

-> 80 90 100 110 T-scs I V 140 93,210 97,020 100,820 104,620 150 88,930 92,740 96,540 100,340 160 84,360 88,460 92,260 96,060 170 80,090 84,180 87,980 91,780 180 75,610 79,420 83,320 87,500 Note, both T-ambient and T-SCS are in degrees Fahrenheit All the above cases consider a total MPC heat generation of 34 kW. In all cases, the heat exchanger capacity exceeds the system requirements over the expected range of ambient conditions and required SCS water temperature.

This is consistent with the SCS recorded data that that shows a reduction in water temperature while the system was in operation.

Thus, the SCS in use at PSEG Nuclear, as demonstrated during the initial Salem DCS campaign, meets the necessary HI-STORM FSAR Revision 7 Appendix 2.C design criteria.