View source for LR-N12-0194, and Independent Spent Fuel Storage Installation - HI-STORM 100 Cask Supplemental Cooling System Validation Testing Using Air Mass Flow Rate

{{Adams
| number = ML12187A230
| issue date = 06/25/2012
| title = and Independent Spent Fuel Storage Installation - HI-STORM 100 Cask Supplemental Cooling System Validation Testing Using Air Mass Flow Rate
| author name = Perry J
| author affiliation = PSEG Nuclear, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NMSS/SFST
| docket = 05000272, 05000311, 05000354, 07200048
| license number = DPR-070, DPR-075, NPF-057
| contact person = 
| case reference number = LR-N12-0194
| document type = Letter type:LR
| page count = 9
}}

=Text=
{{#Wiki_filter: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 Time after SCS            SCS     SCS initiated             T-inlet T-outlet Flow-rate Date/time                  (hours)             (deg-F)  (deg-F)    (gpm) 9/17/10 4:00                    0                 170      145      14.10 9/17/10 6:00                  2.0                 163      137      14.42 9/17/10 8:00                  4.0                 157      132      14.41 9/17/10 9:05                  5.1                 157      132      14.96 9/17/10 10:00                  6.0                 162      138      13.78 9/17/10 12:00                  8.0                 150      126      13.76 9/17/10 14:00                 10.0                 144      124      13.67 Note: SCS T-inlet or T-outlet measurements are taken from the inlet and outlet of the SCS heat-exchanger.
MPC helium backfill data Final              Helium Backfill Measured He               Pressure Pressure          Adjusted to 70 deg-F MPC                 (psig)                   (psig) 93                  52.8                    37.53 94                  63.5                    44.48 95                  52.2                    37.23 96                  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 Qtotal(1)    Qcoc(2)
(kW)
MPC                      (kW) 93         24.03        33.77 94         23.66        33.34 95         22.85        33.44 96         22.72        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 180 170 160 150 U-   140
: 0)   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.}}