ML12006A141

Enclosure 10 - Tn Calculation NUH32PHB-0401, Thermal Evaluation of Nuhoms 32PHB Transfer Cask for Normal, Off Normal, and Accident Conditions with Forced Cooling (Steady State)

ML12006A141
Person / Time
Site:	Calvert Cliffs
Issue date:	08/17/2011
From:	Venigalla V AREVA, Constellation Energy Group, Transnuclear, Calvert Cliffs
To:	Office of Nuclear Material Safety and Safeguards
References
NUHOMS32PHB, Rev. 1
Download: ML12006A141 (46)

Text

ENCLOSURE10 Non-Proprietary TN Calculation NUH32PHB-0401, Thermal Evaluation of NUHOMS 32PHB Transfer Cask for Normal, Off Normal, and Accident Conditions with Forced Cooling (Steady State)

NON-PROPRIETARY VERSION A Form 3.2-1 Calculation No.: NUH32PHB-0401 AR EVA Calculation Cover Sheet Revision No.: I TRANSNUCLEAR INC, TIP 3.2 (Revision 6) Page: 1 of 31 DCR NO (if applicable): NUH32PHB7010 PROJECT NAME: NUHOMS32PFIB System PROJECT NO: 10955 CLIENT: CENG - Calveit Cliff Nuclear Power Plant (CCNPP)

CALCULATION TITLE:

Thermal Evaluation of NUHOMS 32PHB Transfer Cask for Normal, Off Normal, and Accident Conditions with Forced Cooling (Steady State)

SUMMARY

DESCRIPTION:

1) Calculation Summary This calculation determines the maximum component temperatures of the Calvert Cliff Nuclear Power Plant Onsite Transfer Cask (CCNPP-FC TC) loaded with 32PHB DSC at 29.6 kW with forced cooling and also determines the peak fuel cladding temperatures in the 32PHB DSC.

2) Storage Media Description Secure network server initially, then redundant tape backup If original issue, is licensing review per TIP 3.5 required?

Yes D No Z (explain below) Licensing Review No.:

This calculation is prepared to support a Site Specific License Application by CCNPP that will be reviewed and approved by the NRC. Therefore, a 10CFR72.48 licensing review per TIP 3.5 is not applicable.

Software Utilized (subject to test requirements of TIP 3.3): Version:

ANSYS 10.0 Calculation is complete:

Originator Name and Signature: Venkata Venigalla Date: I /z/o*i Calculation has been checked for consistency, completeness and correctness:

Checker Name and Signature: Davy Qi Date: Ž3/ /

Calculation is approved for use:

Project Engineer Name and Signature: Kamran Tavassoli

• Date:

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 2 of 31 REVISION

SUMMARY

AFFECTED AFFECTED REV. DESCRIPTION PAGES Computational 1/0 0 Initial Issue All All 1 To update and clarify the loss of forced cooling 1-3, 6, 8, 17 None condition based on the maximum fuel cladding and 21 temperature limit used for this condition.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 3 of 31 TABLE OF CONTENTS Paqe 1.0 P u rp o s e ............................................................................................................................. 5 2 .0 R e fe re nce s ........................................................................................................................ 6 3.0 Assumptions and Conservatism .................................................. 7 3.1 CCNPP-FC TC Mass Flow Rate Model ............................................................... 7 3.2 CCNPP-FC TC Model ........................................................................................... 7 3.3 32PHB DSC Model ............................................................................................. 7 4 .0 De s ign Inp ut ...................................................................................................................... 8 4.1 Design Load Cases ............................................................................................ 8 4.2 Thermal Properties of Materials ........................................................................... 8 4.3 Surface Properties of Materials ........................................................................... 9 4.4 Design Criteria ................................................................................................... 9 5 .0 Me th o d o lo g y .................................................................................................................... 10 5.1 Flow Rate Model ............................................................................................... 11 5.2 CCNPP-FC TC Model ......................................................................................... 14 5.3 Loss of Forced Airflow during Transfer Operations ............................................. 17 5.4 32PHB DSC/Basket Analysis ............................................................................. 17 6.0 Results and Discussion ............................................................................................. 20 7 .0 C o nc lu s io n ...................................................................................................................... 27 8.0 Listing of Computer Files ........................................................................................... 28 APPENDIX A Forced Air Pressure Drop ............................................................................. 30

A

• Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 4 of 31 LIST OF TABLES Paqe Table 4-1 Design Load Cases for 32PHB DSC in CCNPP-FC TC with FC .................... 8 Table 4-2 List of Materials in the CCNPP-FC TC Model () .................................................. 9 Table 5-1 TC/DSC Annulus Hydraulic Diameter and Flow Area Calculation .................. 12 Table 5-2 List of the Friction Factors in the Mass Flow Model ...................................... 12 Table 5-3 Mass Flow Rates Along Each Annular Segment .......................................... 14 Table 5-4 Heat Transfer Coefficients in the DSCITC Annulus for Forced Air Flow ..... 16 Table 6-1 Maximum Temperatures of CCNPP-FC TC @ 29.6 kW, Forced Air C o o lin g ....................................................................................................... . . 21 Table 6-2 Maximum Temperatures of CCNPP-FC TC @ 29.6 kW, Loss of Forced A ir T ra nsie nt ............................................................................................... . . 22 Table 7-1 Maximum Temperatures of CCNPP-FC TC @ 29.6 kW, Forced Air C irc ula tio n .................................................................................................. . . 27 Table 8-1 Sum m ary of ANSYS Runs ........................................................................... 28 Table 8-2 Associated Files and Macros ......................................................................... 29 Table A-1 Forced A ir Pressure Drop ............................................................................. 31 LIST OF FIGURES Page Figure 5-1 Finite Element Mesh of Flow Rate Model with FLUID116 Elements .............. 18 Figure 5-2 Finite Element Model of CCNPP-FC TC O..........................

............................. 19 Figure 6-1 TC Temperature Distribution - Off-Normal Hot with Forced Convection, @

29.6 kW, 127 Btu/hr-ft 2 Insolation, 104 0 F Ambient (load case # 3) ............... 23 Figure 6-2 32PHB DSC Temperature Distribution - Off-Normal Hot with Forced Convection, @ 29.6 kW, 127 Btu/hr-ft 2 Insolation, 104 0 F Ambient (load c a s e # 3 ) ............................................................................................................ 24 Figure 6-3 TC Temperature Distribution - Loss of Forced Air Transient, t = 8 hr @

29.6 kW, 127 Btu/hr-ft 2 Insolation, 104 0 F Ambient (load case # 5) ............... 25 Figure 6-4 32PHB DSC Temperature Distribution - Loss of Forced Air Transient, t =

8 hr @ 29.6 kW, 127 Btu/hr-ft2 Insolation, 104 0 F Ambient (load case # 5) ....... 26

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: I TRANSNUCLEAR INC. Page: 5 of 31 1.0 PURPOSE The Calvert Cliff Nuclear Power Plant Onsite Transfer Cask (CCNPP-FC TC) loaded with 32PHB DSC at 29.6 kW utilizes forced cooling as a possible recovery mode to improve the thermal performance of the system if the transfer operations exceed the operational time limits (such as 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> for 29.6 kW heat load) determined for off-normal hot horizontal transfer conditions in Reference [6].

This calculation determines the maximum component temperatures of the CCNPP-FC TC loaded with 32PHB DSC at 29.6 kW with forced air cooling under steady-state conditions and also determines the peak fuel cladding temperature within the 32PHB DSC with the forced air cooling. There are no time limits associated for horizontal transfer operations once the forced air circulation is initiated.

It also establishes a time limit to restore the forced air circulation or to complete the transfer of the 32PHB DSC at 29.6 kW in CCNPP-FC TC to the HSM-HB in case of system failure to ensure that the peak fuel cladding temperature remains below the temperature limit of 752 0 F [8].

To determine the maximum component temperatures of the Calvert Cliff CCNPP-FC TC loaded with 32PHB DSC at 29.6 kW with forced air cooling under steady-state conditions, this calculation utilizes the methodology described in [7] and the ANSYS thermal model of CCNPP-FC TC described in [6]. The peak fuel cladding and the basket component temperatures for 32PHB DSC are determined using the ANSYS thermal model and methodology described in [5].

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 6 of 31

2.0 REFERENCES

1 Rohsenow, Hartnett, Cho, "Handbook of Heat Transfer", 3 rd Edition, 1998.

2 Rohsenow, Hartnett, Ganic, "Handbook of Heat Transfer Fundamentals", 2 rd Edition, 1985.

3 ANSYS computer code and On-Line User's Manuals, Version 10.0.

4 Design Criteria Document, "Design Criteria Document (DCD) for the NUHOMS 32PHB System for Storage", Transnuclear, Inc., NUH32PHB.0101 Rev. 2.

5 Calculation, "Thermal Evaluation of NUHOMS 32PHB Canister for Storage and Transfer Conditions", Transnuclear, Inc., NUH32PHB-0403, Rev. 0.

6 Calculation, "Thermal Evaluation of NUHOMS 32PHB Transfer Cask for Normal, Off Normal, and Accident Conditions", Transnuclear, Inc., NUH32PHB-0402, Rev. 0.

7 Calculation, "Benchmarking of the ANSYS Model of the OS200FC Transfer Cask",

Transnuclear, Inc., NUH32PHB-0400, Rev. 1.

8 NRC Spent Fuel Project Office, Interim Staff Guidance, ISG-1 1, Rev 3, "Cladding Considerations for the Transportation and Storage of Spent Fuel".

9 GESC, NAC International, Atlanta Corporate Headquarters, 655 Engineering Drive, Norcross, Georgia (Engineering Report # NS3-020, Effects of 1300OF on Unfilled NS-3, while Bisco Products, Inc., 11/84).

10 Calvert Cliffs Independent Spent Fuel Storage Installation Updated Safety Analysis Report, Rev.17.

11 I.E. Idelchik, Handbook of Hydraulic Resistance, 3 rd Edition, 1994.

12 ASHRAE Handbook Fundamentals, 1997.

13 Perry & Chilton, Chemical Engineering Handbook, 5 th Edition,1973.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 7 of 31 3.0 ASSUMPTIONS AND CONSERVATISM The following assumptions and conservatism are considered in the calculation.

3.1 CCNPP-FC TC Mass Flow Rate Model All the assumption and conservatism considered in this calculation for the CCNPP-FC TC Mass Flow Rate Model are the same as those described in [7] and are summarized below.

The annulus between the DSC shell and the TC inner liner are divided into parallel, individual segments along the DSC axis. No circumferential air flow is considered between the parallel segments. Since the presence of circumferential flow will tend to exchange hotter air in the narrower segments of the annulus with cooler air in the wider segments of the annulus, ignoring the potential for circumferential flow will yield conservative temperature estimates for the peak temperatures on the DSC shell and TC inner liner An air flow rate of 450 cfm is considered for forced air cooling. To evaluate the air flow rate in each of the parallel segments, a constant pressure boundary condition is applied at the inlet such that the total mass flow rate at the outlet is equal to the total airflow rate of 450 cfm.

Since the pressure drop through the annulus between the DSC shell and TC inner shell is the major factor controlling the amount of air flow rate in each segment, the mass flow rate model considers only the annulus over the length of the DSC to determine the mass flow rate through each segment.

3.2 CCNPP-FC TC Model All the assumptions and conservatisms described in Section 3.1of [6] are applicable for this calculation.

The methodology to analyze the CCNPP-FC TC with forced cooling is presented in [7] and is used in this calculation.

3.3 32PHB DSC Model The assumptions and conservatism considered for 32PHB DSC model are the same as those described in [5], Section 3.0.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 8 of 31 4.0 DESIGN INPUT 4.1 Design Load Cases The following design cases in Table 4-1 are analyzed in this calculation to determine the thermal performance of CCNPP-FC TC with 32PHB DSC at 29.6 kW and with forced cooling (FC). The load cases are based on requirements in [4].

Table 4-1 Design Load Cases for 32PHB DSC in CCNPP-FC TC with FC nCondition Description Ambient Case Operation Notes Temperature(3 ) Insolation Airflow

[OF] . [Btu/hr-ft2] [cfm]

1 Normal Normal Hot, FC (1) 104 82 450 2 Normal Normal Cold, FC (1) -8 0 450 3 Off-Normal Off-Normal Hot, FC -- 104 127 450 4 Off-Normal Off-Normal Cold, FC 0 -8 0 450 5 Off-Normal1(4 Loss ofTransient Forced Airflow, (2) 104 127 0 (2)_ 104 _ 127 0 Notes:

1) Load cases # 1, 2 and 4 are bounded by the Load Case # 3 (See Section 6.0 for justification).

2) Initial temperatures taken from steady-state results of Load Case # 3. At time t=0, the forced air circulation is assumed to be lost.

3) Ambient air temperatures ranging from -8 to 104 0 F are conservative compared to the ambient air temperature range from -3 to 103OF in [10], Section 12.3.6.

4) The temperature limits of off-normal transfer conditions are considered to evaluate this load case.

4.2 Thermal Properties of Materials Materials used in CCNPP-FC TC ANSYS thermal model are listed in Table 4-3, Section 4.3 of

[6]. The material numbers associated with elements simulating the forced air cooling are listed in Table 4-2.

The heat transfer coefficients for the forced air flow over the DSC/TC annulus are calculated using the same correlations described in [7],Section 5.2 and are presented in MassFIowConvCoeff_32PHB_29.6kW.xls for the 29.6 kW heat load as noted in Table 8-2.

Thermal properties used in CCNPP-FC TC model are listed in Section 4.3 of [6].

Materials and Thermal properties used in the 32PHB DSC models are listed in Section 4.1 of

[5].

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 9 of 31 Table 4-2 List of Materials in the CCNPP-FC TC Model (1)

Component Mat # in ANSYS Model TC FLUID116 Flow Elements 90 TC LINK34 Convection Elements 451-466 TC LINK34 Convection Elements (At Entrance through spacer disc)

TC LINK34 Convection Elements 471 (At Exit thought Top Cask Lid)

(1) See Table 4-3, Section 4.3 of [6] for complete material listing of the CCNPP-FC TC components in addition to those listed above.

4.3 Surface Properties of Materials The emissivity value of 0.587 is considered for both the DSC shell (stainless steel) and the transfer cask inner shell (stainless steel) in calculation of thermal radiation exchange between these shells [1].

It is assumed that the absorptivity and the emissivity of stainless steel are equal. Solar absorptivity and emissivity of 0.587 are used for the TC outer surfaces [1].

4.4 Design Criteria The design criteria and evaluation of 32PHB DSC basket are presented in Reference [5] and design criteria for the TC are presented in Reference [6] and are listed below.

" Maximum fuel cladding temperature limits of 752 0 F (4000C) for normal/off-normal load cases listed in Table 4-1 and 1,0581F (5700C) for accident conditions listed in Table 4-1 are considered for the FAs with an inert cover gas as concluded in ISG-1 1 [8].

" The ASTM B29 lead used in the gamma shield has a melting point of approximately 620°F [13].

" For design purposes of this application, the long-term, bulk average temperature of the NS-3 material is set to 280 OF [10] or less, and short-term limits for accident conditions should be 1,300 OF or less [9].

A C Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 10 of 31 5.0 METHODOLOGY The CCNPP-FC TC contains design provisions for the use of forced air cooling to improve its thermal performance. The system will consist of redundant, industrial grade pressure blowers and power systems, ducting, etc. When operating, the fan system is expected to generate a flow rate of 450 cfm or greater, which will be ducted to the location of the ram access cover at the bottom of the cask.

The following are the steps to determine the maximum steady state temperatures of the DSCITC components with the forced convection using ANSYS:

1. Assume a ATair for initial runs, Calculate Texit and Tavg based on the initial guess and the air properties based on Tavg.

Where, Texit = Tamb + A Tair Tavg = (Tamb + Tex,, ) / 2 Tamb = 104'F

2. Run Flow Rate Model described in Section 5.1 iteratively based on average properties of air calculated in previous step to compute the air mass flow rate in each DSC/TC annulus segment. (Run ID: "FlowRate_32PHB_29kW" for 29.6 kW load case listed in Table 8-1)

3. Determine the heat transfer coefficients within the annulus based on the mass flow rates computed in Step 2 (see worksheet "Hcdata" for mass flow rate in Ibm/hr and Hccalc for convection coefficients in "MassFlowConvCoeff_32PHB_29.6kW.xls" for the 29.6 kW heat load as noted in Table 8-2)

4. Run Thermal Model (Run ID: "TR_32PHB_29kW' for 29.6 kW heat load as listed in Table 8-1) described in Section 5.2 based on mass flow rates and heat transfer coefficients calculated in Step 2 and Step 3.

5. Calculate Texit, Tavg, and ATair based on results from Thermal Model in Step 4.

6. If difference between assumed ATair in Step 1 and calculated ATair in Step 5 is less than 10F, stop iterations, otherwise proceed to Step 7.

7. Rerun the Flow Rate Model described in Section 5.1 and Step 2 with air properties based on Tavg from Step 5.

8. If differences between air mass flow rates in each DSCITC annulus segment from Step 7 and Step 2 are less than 0.1 Ibm/hr, stop iterations, otherwise proceed to Step 9.

9. Repeat Steps 4 to 9 until the solution converges.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 11 of 31 The above methodology is validated versus a NRC accepted methodology using SINDA/FLUINT as documented in [7].

5.1 Flow Rate Model The forced air enters the TC from the ram access opening and the airflow turns and enters the ten (10) flow paths formed by the 0.25" thick cutouts in the spacer disc attached to the TC's bottom. After the forced air exits from the flow paths formed by the cutouts in the spacer disc, the airflow turns and flows in the annulus between the DSC and the TC's inner liner.

Given the gap between the DSC and TC varies with circumferential position, plus variances in the heating of the air, the airflow will distribute itself around the circumference of the DSC/TC inner liner, until an equal pressure drop is achieved everywhere.

For the purposes of this calculation, each half of the annulus is divided into 19 angular segments as shown in Table 5-1 with 00 at the top of the normally horizontal TC and 1800 at the bottom. The mass flow rate along each of the 19 angular segments is calculated using the Flow Rate Model. The mass flow rates obtained from this model are used as input to the thermal model of the DSC/TC described in Section 5.2.

The 19 annular segments for forced air flow are modeled using FLUID116 elements with their length equal to the length of the DSC. The potential for circumferential airflow is conservatively ignored as discussed in Section 3.1. The flow area and hydraulic diameter for each annular segment are calculated based on the position of the DSC within the TC cavity.

The determination of the gap between the DSC and the TC inner liner as a function of circumferential position was made considering a DSC shell outer diameter of 67.25 inches, a TC inner liner inner diameter of 68 inches, and a 0.120-inches thick slide rail that is located 18.50 from the centerline of the TC. Table 5-1 presents the calculation basis for the gap between the TC and DSC and the associated hydraulic diameter and air flow area.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 12 of 31 Table 5-1 TC/DSC Annulus Hydraulic Diameter and Flow Area Calculation Cask "X" Cask "Y" DSC "X" DSC "Y" Hydraulic Angle Location Location Location Location Diameter Flow Area Section Angle Segment (degrees) (in) (in) (in) (in) (m) (m2) 1 -5 5 0 0.000 34.000 0.000 33.355 0.0328 2.423E-03 2 5 15 10 5.904 33.483 5.793 32.852 0.0326 2.407E-03 3 15 25 20 11.629 31.950 11.414 31.359 0.0319 2.363E-03 4 25 35 30 17.000 29.445 16.696 28.918 0.0309 2.289E-03 5 35 45 40 21.855 26.046 21.481 25.600 0.0296 2.189E-03 6 45 55 50 26.046 21.855 25.625 21.502 0.0279 2.066E-03 7 55 65 60 29.445 17.000 29.003 16.745 0.0259 1.923E-03 8 65 75 70 31.950 11.629 31.510 11.469 0.0237 1.765E-03 9 75 85 80 33.483 5.904 33.068 5.831 0.0214 1.595E-03 10 85 95 90 34.000 0.000 33.625 0.000 0.0191 1.420E-03 11 95 105 100 33.483 -5.904 33.160 -5.847 0.0167 1.244E-03 12 105 115 110 31.950 -11.629 31.684 -11.532 0.0144 1.073E-03 13 115 125 120 29.445 -17.000 29.237 -16.880 0.0122 9.123E-04 14 125 135 130 26.046 -21.855 25.891 -21.725 0.0102 7.667E-04 15 135 145 140 21.855 -26.046 21.747 -25.917 0.0085 6.406E-04 16 145 155 150 17.000 -29.445 16.929 -29.323 0.0072 5.382E-04 17 155 165 160 11.629 -31.950 11.587 -31.836 0.0062 4.627E-04 18 165 175 170 5.904 -33.483 5.885 -33.376 0.0055 4.164E-04 19 175 185 180 0.000 -34.000 0.000 -33.895 0.0053 4.007E-04 The friction factor along the length of the DSC/cask annulus is calculated as:

f=(1.58

• In Re- 3.28)- 2 [Eq. 7 of Reference 2 / Section 5.1 of 7]

Table 5-2 lists the friction factors as a function of Reynolds numbers.

Table 5-2 List of the Friction Factors in the Mass Flow Model Re f 4*f Re f 4*f 1 0.093 0.372 1500 0.015 0.058 100 0.063 0.250 1750 0.014 0.055 200 0.039 0.154 2000 0.013 0.052 300 0.030 0.122 3000 0.011 0.046 400 0.026 0.105 4000 0.010 0.041 500 0.023 0.094 5000 0.010 0.039 600 0.021 0.086 6000 0.009 0.037 800 0.019 0.075 8000 0.008 0.034 1000 0.017 0.069 12500 0.007 0.030 1250 0.016 0.063 22500 0.006 0.025 The areas, hydraulic diameters, and friction factors calculated for the 19 annular segments are applied as real constants to the FLUID116 elements. The friction factors are applied using the TB,FCON command as function of temperature and Reynolds number.

A, Calculation No.: NUH32PHB-0401 AR EVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 13 of 31 The total mass flow rate based on 450 cfm discharge from the fan for the 29.6 kW load case is calculated as follows:

m = 450 cfm

• Parraveragetemp

=450* (0.3048)3

• 0.973 kg 60 S

=0.2067 kg / s

Where, m = Total Mass Flow Rate, (kg/s)

= Density of air based on Average Air Temperature = 0.973 kg/mi3 Pair,averag,,emp The air density in the above equation is calculated based on a pressure drop of 6 inches water gauge based on the calculations presented in Appendix A and an initial air exit temperature of 292 0 F for the 29.6 kW heat load case. The final air exit temperature is determined iteratively through the steps shown in Section 5.0.

The forced air introduced in the annular gap between the DSC and the cask distributes itself based upon the flow area and hydraulic diameter. The Flow Rate Model computes the air flow rate in each annular segment based on achieving an equal pressure drop over any segments of the annulus. The Flow Rate Model for determining the mass flow rates is shown in Figure 5-1.

A constant volumetric airflow rate of 450 cfm is assumed to evaluate the air mass flow rate in each of the parallel segments. A constant pressure is applied at the inlet of the air flow into the DSCITC annulus and the mass flow at the outlet is computed for the flow along the 19 annular segments. The pressure at the inlet is iteratively changed until the total mass flow rate at outlet of the 19 annular segments is equal to total mass flow rate of 0.2067kg/s for the 29.6 kW heat load.

The mass flow rates obtained for each of the 19 angular segments for use in the CCNPP-FC TC thermal model along with the hydraulic diameters and flow areas are presented in the Table 5-3 29.6 kW heat load cases.

A Calculation No.: NUH32PHB-0401 AR EVA Calculation Revision No.: 1 TRANSNUCLEAR INC.I Page: 14 of 31 Table 5-3 Mass Flow Rates Along Each Annular Segment 29.6 kW Hydraulic Flow Massflow Diameter Area Section (Ibm/hr) (in) (in2) 1 100.53 1.29 3.75 2 99.46 1.28 3.73 3 96.26 1.26 3.66 4 91.33 1.22 3.55 5 84.26 1.16 3.39 6 75.78 1.10 3.20 7 66.59 1.02 2.98 8 57.09 0.93 2.74 9 47.89 0.84 2.47 10 39.32 0.75 2.20 11 30.98 0.66 1.93 12 23.67 0.57 1.66 13 17.61 0.48 1.41 14 12.81 0.40 1.19 15 9.17 0.34 0.99 16 6.66 0.28 0.83 17 5.01 0.24 0.72 18 4.07 0.22 0.65 19 3.77 0.21 0.62 5.2 CCNPP-FC TC Model ANSYS model and the thermal analysis methodology for the CCNPP-FC TC are described in Section 5.0 of reference [6]. This calculation utilizes the thermal model of CCNPP-FC TC from reference [6] by adding the FLUID1 16 and LINK34 elements to simulate the forced convection. Figure 5-2 shows the CCNPP-FC TC finite element model with the LINK34 and FLUID1 16 elements added.

Forced air circulation through the annulus of the DSC/TC is modeled using the FLUID1 16 and LINK34 elements. The FLUID1 16 element models the forced air flow along the axial length of the DSC/cask annulus by conducting heat and transmitting the fluid between its nodes, whereas the LINK34 elements model the convection from the DSCOIC surfaces due to the forced air flow. The FLUID1 16 elements are modeled such that they are connected to the LINK34 convection elements.

The mass flow rates obtained from the Flow Rate Model described in Section 5.1 for each of the annular segments from 0 ' to 1500 are applied to the FLUID116 elements using the "SFE,,,hflux" command.

Based on the mass flow rates obtained for each of the annular segments from 00 to 1500, the convection heat transfer coefficients for the DSC/TC annulus are computed using the correlations for flow within ducts and pipes. The convection heat transfer coefficients are

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 15 of 31 computed as a function of the local hydraulic diameter, the Reynolds number, and the thermophysical properties of air. These convection heat transfer coefficients are applied to the LINK34 elements using the mpdata,hf / mp,hf commands.

The correlations for the convection coefficients are identical to those in [7] and are taken from equations 7, 43, 44, 45, 57, and 57a from Chapter 7 of [2] as follows:

For 0.5 < Pr < 2000 and 104 < Re < 5x106:

N hCDh Re x Pr x f/2 k 1.07 + 12.7(Pr213 - 1)(f/2) 05 Re- VxpxDh P

f = (1.58 x In Re - 3.28)-2 For 0.5 < Pr < 2000 and 3000 < Re < 104:

Nu- hCDh (Re- 1000) x Pr x f/2 k 1.0 + 12.7(Pr 213 - 1)(f/2)0 5 For 0.5 < Pr < 2000 and 0 < Re < 3000:

Nu- hCDh = 2.035x(x')-11/3) -0.7, for x*< 0.01 k

Nu = 2.035 x (x)-( 1 /3)-0.2, for 0.01 < x*< 0.06 Nu = 3.657 + 0.0998/x , for x* > 0.06 Where:

Nu = Nusselt number hc= convection coefficient Dh = hydraulic diameter k = thermal conductivity of fluid at film temperature V = flow velocity p = density of fluid at the film temperature

= dynamic viscosity Pr = Prandtl number f = friction factor Re = Reynolds number x* = entry length factor = x/Re/Dh /Pr x = length of duct/pipe

A I Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 16 of 31 Forced convection is omitted conservatively and conduction is assumed in the region between the canister support rails (i.e., approximately 1500 to 1800) due to the narrowness of the gap between the DSC and the TC inner liner. Based on the above correlations and the mass flow rates from Section 5.1 the heat transfer coefficients for the annular segments from 00 to 1500 are calculated and are presented in Table 5-4 for the DSC/TC annulus with a 29.6 kW heat load.

The material properties used in the CCNPP-FC TC model are listed in Section 4.3 of [6] as noted in Section 4.0.

The geometry of the CCNPP-FC TC Model is shown in Figure 5-1 to Figure 5-5 of Reference

[6] and in Figure 5-2 with the LINK34 and FLUID1 16 elements.

Typical boundary conditions for the Thermal Model of CCNPP-FC TC are shown in Figure 5-6 through Figure 5-7 of Reference [6].

Steady state calculations were performed to determine the maximum component temperatures for the CCNPP-FC TC with 32PHB DSC at 29.6 kW and forced convection.

Table 5-4 Heat Transfer Coefficients in the DSC/TC Annulus for Forced Air Flow Heat Transfer Coefficients (Btu/hr-in - F)

Temp Entry at Section Section Section Section Section Section Section Section (OF) Spacer(1 ) 1 2 3 4 5 6 7 8 110 0.028 0.028 0.028 0.027 0.027 0.026 0.025 0.024 210 0.029 0.029 0.028 0.028 0.027 0.026 0.025 0.024 310 0.015 0.029 0.029 0.029 0.029 0.028 0.027 0.026 0.024 410 0.030 0.030 0.030 0.029 0.029 0.028 0.026 0.025 510 0.031 0.031 0.030 0.030 0.029 0.028 0.027 0.025 Heat Transfer Coefficients (Btu/hr-in 2- F)

Exit at Temp Section Section Section Section Section Section Section Section Top

(`F) 9 10 11 12 13 14 15 16 Lid"1' 110 0.022 0.020 0.009 0.010 0.011 0.012 0.015 0.017 210 0.022 0.020 0.010 0.011 0.012 0.014 0.017 0.020 310 0.023 0.010 0.011 0.012 0.014 0.016 0.019 0.022 0.016 410 0.023 0.011 0.012 0.013 0.015 0.017 0.021 0.024 510 0.011 0.012 0.013 0.014 0.016 0.019 0.022 0.026 Notes:

(1) The lowest heat transfer coefficient is used for the Entry at spacer disc and Exit at Top lid for conservatism

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 17 of 31 5.3 Loss of Forced Airflow during Transfer Operations The postulated loss of forced airflow condition considers an evaluation of the system performance for the case wherein steady-state conditions are established with the fan in operation and, subsequently the fan airflow is lost. To minimize the occurrence of this postulated condition, the CCNPP-FC TC skid is equipped with redundant industrial grade blowers, each one of these blowers capable of supplying the required minimum air flow rate.

These blowers are also powered with a redundant power supply. The analysis assumes that the transient begins with DSC/TC at steady-state conditions from load case# 3. At time = 0, the fan airflow is lost and the system starts to heat up.

This analysis presents a time limit to restore the forced airflow or to complete the transfer of the 32PHB DSC with 29.6 kW heat load to the HSM-HB concrete module. The time limit is selected such that the peak fuel cladding temperature will remain below the normal/off-normal cladding temperature limit of 752 0 F for transfer operations as recommended in [8]. The selected time limit is bounding for NUHOMS 32PHB system with heat loads at or less than 29.6 kW. The results of the calculated thermal response of the DSC and TC for this transient analysis are presented in Section 6.0.

It should be noted that this condition also covers the normal/off-normal conditions in the transfer operations when the fans are removed and the ram is prepared to insert the DSC into the HSM-HB.

5.4 32PHB DSC/Basket Analysis The DSC shell temperature profiles from steady state analysis in Section 5.2 for load case #

3 and from the transient analysis described in Section 5.3 for load case # 5 are used to determine the maximum basket component temperatures including the maximum fuel cladding temperature based on the 32PHB DSC/basket model described in Reference [5]. No changes are considered to the thermal model of the 32PHB DSC and the methodology presented in Reference [5].

Calculation No.: NUH32PHB-0401 Revision No.: 1 Page: 18 of 31 The mass flow rate along each of the 19 annular A constant segments is pressure is obtained at the applied at the outlet for use in inlet, such that the CCNPP-FC total mass flow TC thermal rate is 0.2067 model.

kg/s for 29.6 kW load cases.

Figure 5-1 Finite Element Mesh of Flow Rate Model with FLUID116 Elements

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 19 of 31 Exit Nodes Coupled to FLUIDI16 Elements Air Flow Inlet Nodes, Fixed at 1040 F

/

Fluid116 and Link34 TC Rail

/

Elements Figure 5-2 Finite Element Model of CCNPP-FC TC

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 20 of 31 6.0 RESULTS AND DISCUSSION Based on the ambient conditions for normal/off-normal operations presented in Table 4-1, off-normal hot ambient conditions (load case # 3) presents the bounding case for the thermal analysis due to the higher ambient temperature/insolation. Therefore, the maximum temperatures of the CCNPP-FC TC with 32PHB DSC at 29.6 kW and forced convection for off-normal hot ambient conditions (load case # 3) bounds the maximum temperatures for normal hot/cold and off-normal cold conditions (load cases # 1, 2 and 4).

Steady state thermal analysis is performed for the CCNPP-FC TC with 32PHB DSC at 29.6 kW and forced convection for off-normal hot ambient conditions listed in Table 4-1 to determine the DSC shell temperature profile and the maximum TC component temperatures.

The DSC shell temperature profiles is used to determine the peak fuel cladding and basket component temperatures based on the 32PHB DSC/Basket thermal model steady state analysis.

Table 6-1 summarizes the maximum temperatures for the CCNPP-FC TC components /

32PHB DSC components and shows that the maximum component temperatures are below the allowable limits. Figure 6-1 and Figure 6-2 present the temperature profiles for the off-normal hot condition with forced convection for the CCNPP-FC TC and 32PHB DSC.

In addition, the maximum difference between the exit air temperature of 2920 F assumed in Section 5.1 and exit air temperature of 291.6 obtained from the thermal model as presented in Table 6-1 for the 29.6 kW heat load is -0.40 F. Therefore, no further iterations are required.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 21 of 31 Table 6-1 Maximum Temperatures of CCNPP-FC TC @ 29.6 kW, Forced Air Cooling Temperature [OF]

Component______Max.

Component Off-Normal Hot (Load Case # 3) Allowable Fuel Cladding 689 752 [4, 8]

Basket (Guide Sleeve) 667 Al/Poison Plate 666 Basket Rails 451 Top Shield Plug 366 Bottom Shield Plug 247 Max. DSC Shell (1) 410 ---

Inner Shell 362 ---

Gamma Shield 356 620 Structural Shell 310 ---

Bulk Avg. Temp of Radial Neutron Shield Bulk Avg. Temp of Top Neutron Shield Bulk Avg. Temp of 151 280 [101 Bottom Neutron Shield Cask Lid 256 ---

Cask Outer Shell 279 ---

Forced Air, Inlet/ Exit 104/291.6 (1) The maximum DSC shell temperature is the temperature along the "DSC Shell" as shown in Figure 5-3 of [6] and does not include the top and bottom end plates.

Transient thermal analysis is performed for the CCNPP-FC TC with 32PHB DSC at 29.6 kW and without forced convection to analyze the loss of forced air circulation condition listed in Table 4-1 to determine the DSC shell temperature profile and the maximum TC component temperatures. This analysis assumes that the transient begins with DSC/TC at steady-state conditions from load case# 3. At time = 0, the fan airflow is lost and the system starts to heat up.

Based on the transient thermal analysis a maximum duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is available to complete the transfer to the HSM-HB or re-establish the fan airflow. The DSC shell temperature profiles at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time the fan airflow is lost is used to determine the peak fuel cladding and basket component temperatures based on the 32PHB DSC/Basket thermal model steady state analysis. Table 6-2 summarizes the maximum temperatures for the CCNPP-FC TC components / 32PHB DSC components and shows that the maximum component temperatures are below the allowable limits.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 22 of 31 Table 6-2 Maximum Temperatures of CCNPP-FC TC @ 29.6 kW, Loss of Forced Air Transient Temperature [°F]

Component Loss of Forced Air Flow Max.

(Load Case # 5) Allowable Time = 8 hrs Fuel Cladding 734 752 [4, 8]

Basket (Guide Sleeve) 716 Al/Poison Plate 715 Basket Rails 478 Top Shield Plug 377 Bottom Shield Plug 316 Max. DSC Shell 422 ---

Inner Shell 364 ---

Gamma Shield 358 620 Structural Shell 310 ---

Bulk Avg. Temp of Radial Neutron Shield Bulk Avg. Temp of Top Neutron Shield Bulk Avg. Temp of Bottom Neutron Shield Cask Lid 253 ---

Cask Outer Shell 276 ---

(1) The maximum DSC shell temperature is the temperature along the "DSC Shell" as shown in Figure 5-3 of [6] and does not include the top and bottom end plates.

Figure 6-3 and Figure 6-4 present the temperature profiles for the loss of forced air flow transient analysis at 8 hrs for the CCNPP-FC TC and 32PHB DSC.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 23 of 31 AN NOV 25 2009 11:21:48 PLOT NO. 5 NODAL SOLUTION STEP=I SUB =4 TEhIE=1 SMN =104 SY =361.724

- 104

__132.636 El161.272

__189.908

_ 218.544 247.18 275.816 304.452 333.088 361. 724 AN NOV 25 2009 11:21:49 P1F0 NO. 6 NODAL SOLUTION STEP=-I SUB =4 TIlvE=1 TEMP SMN =104 SMX =361.724 104

__132.E636

_ 161.272 189.908 218.544 247.18 r-n 275.816 304.452 333.088 361.724 Figure 6-1 TC Temperature Distribution - Off-Normal Hot with Forced Convection,

@ 29.6 kW, 127 Btu/hr-ft 2 Insolation, 104 0 F Ambient (load case # 3)

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 24 of 31 ANSYS 10lOAI ANSYS i0.lAI NOV 25 2009 NOV25 2009 13:39:19 13:39:26 PLOT NO. 2 PLOT NO. 3 NODALSOLUTION NODALSOLUTION STEP=1 STEP=-1 SUB =1 500 =1 TRCA=1 SM =258.12 81 =247. 426 SM{ =689.126 *,{ =667. 038 258.12 S247.426 306.01 ,, 294.049 353.899 S340. 673 401.789 S387. 297 449.679 S433.92 497.568 __ 480.544 545.458 m- 527.167 593.347 620. 415 641.237 689.126 667.038 Fuel Cladding Guide Sleeve ANSYS 10.OA1 ANSYS i0.OAI NOV25 2009 NOV 25 2009 13:39: 43 13:39:47 PLr NO. 5 PLOT NO. 6 NODALSOI3TION NODALSOLUTION STEP=-1 STEP=1 SUB =1 SUBN=1 TnIE=1 TDE=1 SM =250.226 SM =104 S =450.662 SM7 =407.957 250.226 104 272.497 137.773 294.768 171.546 317.038 205.319 S339.309 239.092 r-n361.579 272.865 383.85 306. 638 406.121 340.411 428.391 374.184 450.662 407. 957 Basket Rail DSC Shell Figure 6-2 32PHB DSC Temperature Distribution - Off-Normal Hot with Forced Convection, @ 29.6 kW, 127 Btu/hr-ft 2 Insolation, 1040 F Ambient (load case # 3)

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 25 of 31 AN NOV 25 2009 11:43:17 PLOT NO. 3 NODAL SOILUIION TIDE=8 TE*P SM1=151.096 SMX =363.79 151.096 174.728 198.361 221.994 F-q245.626 F-q269.259 F-q292.892 316.524 340,157 363.79 CXNPP-FC-TC with 32PHB, 29.6 kW- Off-Normal Loss of FC Transient AN NOV 25 2009 11:43:18 PLOT NO. 4 NODAL SOLUTION TI1ME=8 Tue smN =151.096 SMX =363.79 151.096 174.728 198.361 221.994 245.626 269.259 V-q292.892 316.524 i 340.157 363.79 OCNPP-FC-TC with 32PHB, 29.6 kW Off-Normal Loss of FC Transient Figure 6-3 TC Temperature Distribution - Loss of Forced Air Transient, t = 8 hr

@ 29.6 kW, 127 Btu/hr-ft 2 Insolation, 104 0 F Ambient (load case # 5)

A Calculation No.: NUH32PHB-0401 AREVA Calculation RevisionNo.: 1 TRANSNUCLEAR INC. Page: 26 of 31 ANSYS 10.OAI ANSYS 10.0Al NOV25 2009 NOV25 2009 13:41:01 13:41:09 PLOr NO. 12 PLOT NO. 13 NODALSOLUTION NODALSOUJTION STEP=2 STEP=-2 SUB =1 SUB =1 TIME=2 TDvE=2 TEM SM -=373.651 SFM =364.024 SM =734.416 SNM =715.816

= 373.651 M1413.736

- 364.024 M- 453.821 ___ 403.112

_-- 442.2 7 493.906 481.288 533.991 520.376 574.076 - 559.464

_-- 614.161 598.552

___ 654.246 637.64 694.331 PM676.728 734.416 715. 816 Fuel Claddincq Guide Sleeve ANSYS 10.OAI ANSYS 10.0A1 NOV 25 2009 NOV 25 2009 13:41:26 13:41:30 PLOT NO. 15 PLOT NO. 16 NODALSOUJ3TION NODALSOLUION STEP=2 STEP=2 SUB =1 SUB =1 TIME=2 TIME=2 7EMP SM6 =366.165 SMI =258.341 SM =478.169 SW =422.84 366.165 258.341 378.61 276.618 391.054 294.896 403.499 313.174

_-- 415.944 331.451

- 428.389 - 349.729 440.834 _-- 368.007 453.279 386.285 465.724 404.562 478.169 422.84 Basket Rail DSC Shell Figure 6-4 32PHB DSC Temperature Distribution - Loss of Forced Air Transient, t = 8 hr

@ 29.6 kW, 127 Btu/hr-ft 2 Insolation, 104 0 F Ambient (load case # 5)

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 27 of 31

7.0 CONCLUSION

Table 7-1 summarizes the maximum temperatures of the TC components and the 32PHB DSC for the off-normal hot horizontal transfer condition with forced cooling and at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> transient after the loss of forced cooling.

Table 7-1 Maximum Temperatures of CCNPP-FC TC @ 29.6 kW, Forced Air Circulation Temperature [OF]

CompnentMax.

Component Off-Normal Hot Loss of Forced Cooling AIowabl (Load Case # 3) time = 8 hrs (Load Case # 5) e Fuel Cladding 689 734 752 [4, 8]

Basket (Guide Sleeve) 667 716 Al/Poison Plate 666 715 Basket Rails 451 478 Top Shield Plug 366 377 Bottom Shield Plug 247 316 Max. DSC Shell 410 422 ---

Inner Shell 362 364 ---

Gamma Shield 356 358 620 Structural Shell 310 310 Bulk Avg. Temp of 203 216 280 [10]

Radial Neutron Shield Bulk Avg. Temp of Top Neutron Shield Bulk Avg. Temp of Bottom Neutron Shield Cask Lid 256 253 ---

Cask Outer Shell 279 276 ---

Forced Air, Inlet / Exit 104/291.6 ....

Notes:

(1) The maximum DSC shell temperature is the temperature along the "DSC Shell" as shown in Figure 5-3 of [6] and does not include the top and bottom end plates.

Also based on the discussion presented in Section 6.0, in the event of loss of forced air flow a maximum duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is available to complete the transfer to the HSM-HB or re-establish the fan airflow.

As seen the above table, all design criteria specified in Section 4.4 are herein satisfied.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 28 of 31 8.0 LISTING OF COMPUTER FILES All the runs are performed using ANSYS version 10.0 [3] with operating system "Linux RedHat ES 5.1", and CPU "Opteron 275 DC 2.2 GHz" / "Xeon 5160 DC 3.0 GHz".

A summary of ANSYS runs is shown in Table 8-1.

Table 8-1 Summary of ANSYS Runs Date / Time for Run Name Description Output File Flow Rate Model to determine the mass flow rates 11/25/2009 FlowRate_32PHB_29kW for 29.6 kW Heat Load. 11:04 AM CCNPP-FC TC with 32PHB DSC and 11/25/2009 TR_32PHB_29kW Forced Convection- 29.6 kW 11:21 AM TR_32PHB_29kW-Map Run for Mapping the 32PHB DSC Shell 11/25/2009 TR____32H_29kW-MapTemperature Profiles for off-normal hot load case 11:33 AM Run for Mapping the CCNPP-FC TC Temperature 11/25/2009 TR_32PHB_29kW-TO-Map Profiles for Loss of Forced Airflow load case 11:33 AM 32PHBLOSSECOFNTRANS CCNPP-FC TC with 32PHB DSC and 11/25/2009 32PHB_______L _O_ TRANS__Loss of Forced Airflow- 29.6 kW 11:43 AM Run for Mapping the 32PHB DSC Shell 11/25/2009 32PHBLOSSFCOFNTRANSMap Temperature Profiles for Loss of Forced Airflow 11:48 AM load case at 8 hrs Load 1: 32PHB DSC Basket for Off-Normal Hot 11/25/2009 32PHBTC4M Transfer with Forced Convection Load 2: 32PHB DSC Basket for Loss of Forced 1:42 PM airflow @ 8 hrs I

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 29 of 31 ANSYS macros, and associated files used in this calculation are shown in Table 8-2.

Table 8-2 Associated Files and Macros File Name Description Date / Time Total heat transfer coefficients for horizontal 2/19/2009 HTOT_HCL.MAC [6] cylindrical surface 12:37 PM Total heat transfer coefficients for vertical flat 2/19/2009 HTOT_VPL.MAC [6] surface 12:37 PM 10/21/2009 6071 PM 32PHBTC _Mat.inp [6] Material properties for CCNPP-FC Cask 6:07 PM 32PHBTCRADHorizontal.inp [6] Macro for Creating Radiation Exchange between the 10/21/2009 DSC/TC when the TC is in Horizontal Orientation 4:46 PM 32PHB Matl.inp [5] Material properties for 32PHB DSC with Helium 09/09/09 09:54 AM 32PHBHLZC2.MAC [5] Heat generation for 32PHB DSC, 29.6 kW 09/03/09 08:56 AM Macro [5] Macro to get Maximum/Minimum temperatures 05/20/05 12:03 PM Results.mac [5] Macro to list maximum and average 32PHB DSC 07/22/09 component temperatures 11:52 AM CCNPP-FC-TC.db [6] ANSYS thermal model for CCNPP-FC TC 08/28/09 2:41 PM 32PHBModel.db [5] ANSYS thermal model for 32PHB DSC 07/10/09

- 7:49 PM 11/11/2009 32PHB TC PPLFC.inp Macros for Post-Processing Transient Runs 5:07P 5:07 PM Spreadsheet for calculating the hydraulic diameters, 11/25/2009 MassFIowConvCoeff_32PHB_29.6kW.xls friction factors, mass flow rates and heat transfer 4:01 PM coefficients 4:01_PM 11/25/2009 Pressure Drop-CCNPP-FC-TC.xls Spreadsheet for Pressure Drop Calculation 4:00P 4:00 PM

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 30 of 31 APPENDIX A FORCED AIR PRESSURE DROP The pressure drop experienced by the forced air from the fan discharge, through the DSC and cask annulus, and its subsequent exhausting back into the ambient is computed assuming 1-D flow pipe flow relationships. Table A-1 presents the build up of the 'fittings' assumed along the flow path, the effective hydraulic diameter, the assumed loss coefficients from [11] and [12], and the resultant pressure drop. A pressure drop of approximately 5.64 inches water gauge is expected. For conservatism and to account for operational modifications, a design fan rating of 8 inches water gauge is recommended.

A Calculation No.: NUH32PHB-0401 AREVA Calculation Revision No.: 1 TRANSNUCLEAR INC. Page: 31 of 31 Table A-1 Forced Air Pressure Drop Proprietary Information Withheld Pursuant to 10 CFR 2.390

ATTACHMENT (2)

MARKED UP TECHNICAL SPECIFICATION PAGES Calvert Cliffs Nuclear Power Plant, LLC December 8, 2011

Insert A for the NUHOMS-24P and NUHOMS-32P DSCs. The double closure seal welds at the bottom of the DSC shall satisfy the Liquid Penetrant Acceptance Standards of ASME B&PV Code Section III, Division 1, Subsection NB-5350 (1998 with addenda up to and including 1999) for the NUHOMS 32-PHB DSCs.

Insert 3.1.1(2)

(a) 4.5 weight percent U-235 for the NUHOMS-24P DSC and NUHOMS-32P DSC (b) 4.75 weight percent U-235 for NUHOMS-32PHB DSC for basket type A (c) 5.0 weight percent U-235 for NUHOMS-32PHB DSC for basket type B Insert 3.1.1(3)

(a) 47,000 MWd!MTU for NUHOMS-24P DSCs (b) 52,000 MWd/MTU for NUHOMS-32P DSCs (c) 62,000 MWd/MTU for NUHOMS-32PHB DSCs Insert 3.1.1(5)

(a) 0.66 kilowatts per fuel assembly for the NUTHOMS-24P DSC and NUHOMS-32P DSCs (b) 0.8 kilowatts per fuel assembly for the NUHOMS-32PHB DSC basket zones 1 and 4 (c) 1.0 kilowatts per fuel assembly for the NUHOMS-32PHB DSC basket zones 2 and 3 Insert 3.1.1(7)

(a) 1450 lbs (658 kg) for the NUHOMS-24P and NUHOMS-32P DSCs (b) 1375 lbs (625 kg) for the NUHOMS-32PHB DSCs Insert 3.2.2.1 for the NUHOMS-24P and NUHOMS-32P DSCs. The top shield plug closure weld, the siphon and vent port cover welds, and the top cover plate weld shall satisfy the Liquid Penetrant Acceptance Standards of ASME B&PV Code Section III, Division 1, Subsection NB-5350 (1998 with addenda up to and including 1999) for the NUHOMS 32-PHB DSCs.

NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION 110-2000) 10 CFR 72 PAGE 1 OF 4 PAGES LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter 1, Part 72, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, and possess the power reactor spent fuel and other radioactive materials associated with spent fuel storage designated below; to use such material for the purpose(s) and at the place(s) designated below; and to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified herein.

Licensee

1. Calvert Cliffs Nuclear Power Plant, LLC 3. License No. SNM-2505

2. 100 Constellation Way Amendment No. 9 I Baltimore, MD 21202 ti*.*..

-EX*pirp.tibrn-D~te. November 30, November 30,,2012 2012

5. Docket or *7 .8 Reference No.

6. Byproduct, Source, and/or 7. Chemical or Physical Form 8. Mximum Amount That Licensee Special Nuclear Material '4*`My Possess at Any One Time t'inder This License Spent fuel assemblies frqm A. `A U0 2 clad with zirc-nrn A eU of spent fuel Calvert Cliffs Nuclear Station ,,zir.onuays*.', aseiMblies.

Units 1 and 2 reactor using . s*:

natural water for coolinrg..a enriched not greater tha.,

percent U-235 and associated radioactive materials related to receipt, storage, and trarnsfer . . .- .. ., .

of fuel assemblies. ,.-

9. Authorized Use: For use inry'accordance with thee 'codfitions inrithis lic~ense and the attached Technical Specifications. The basis fori~sijsicense was subdmitted in the Saftý`,,Analysis Report (SAR) application dated December 21, 1989, andsý pplemented April 26, June 29, h*vlember 1, and December 20, 1990; February 1, February 12, September,ý6pO.qtjober , 18, Decei dver 19,'and December 27, 1991; August 18 and September 4, 1992; July 29 and O 31, 1995; November 22, 1999; May 19, June 20, October 4, November 10 and 16, 2000; May 18, and July 26, 2001; December 12, 2003, May 12, .2004 and June 7, 2005; May 16, September 29, October 28, 2005, January 22, February 26, April 8, June 25, July 27, October 15, October 19, October 25 (2 letters), October 26, October 28, 2009; June 15, 2009, February 18, March 31, May 6, and September 1, 2010.

The material identified in 6.A and 7.A above is authorized for receipt, possession, storage, and transfer.

10. Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored at the Calvert Cliffs ISFSI located on the Calvert Cliffs Nuclear Power Plant site in Calvert County, Maryland. This site is described in Chapter 2 of the licensee's SAR for the Calvert Cliffs ISFSl.

11. The Technical Specifications contained in Appendix A attached hereto are incorporated into, the license.

The licensee shall operate the installation in accordance with the Technical Specifications in Appendix A.

NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 3 OF 4 PAGES 10 CFR 72 License No. Amendment No.

LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2505 9 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-8 SUPPLEMENTARY SHEET B The Calvert Cliffs Nuclear Power Plant Emergency Plan shall be reviewed and modified as required to include the ISFSI.

C A training module shall be developed for the Calvert Cliffs Nuclear Power Plant Training Program establishing an ISFSI Training and Certification Program which will include the following:

1. DSC, TC, and HSM Design (overview)

2. ISFSI Facility Design (ovyiew)

3. ISFSI Safety ,Aalys'is (overview)

4. Fuel loading, and DSC and TC handling procedureI and abnormal procedures

5. ISFS, Licen'se (overview).

D The Calvert X Cliffs Nuclear-.Pwer, Plant health physis p5ocedures be reviewed and IJtll modified asrequired to inolUde the ISFS9-,,N E The Calvert Cliffs Nuclear, P.,ovWtPla.rt :Admýinistrative Procedures sIll be reviewed and modified as eSFI.

SFSquiredtn , ,

M' eh o6cumerotation tM procedure shall berEIep pipfdfr of the characterizations perf o si$ct se t? be stre in theanisters and modules.

Such procedurpeshall inil*.).d.e . rlf'Trof fuel assbly selection by an individual otheithan the ongiina 1ný I[m~knrý s selectior,..'-

G A procedure shall bedeveloped and, imrhmIented for two ,independent determinations (two samples analyzed by;di,ferent individuals) of the boron 6doicentration in the water used to fill the DSC cavity for fuel loadiag andunloading:acti\,ies.

H Written procedures shall be implemented'to describe actions to be taken during operation and abnormal/emergency conditions.

15. The design, construction, and operation of the ISFSI shall be accomplished in accordance with the NRC regulations specified in Title 10 of the U.S. Code of Federal Regulations. All commitments to the applicable NRC Regulatory Guides and to engineering and construction codes shall be carried out.

16. The double closure seal welds at the bottom end of the DSC shall satisfy the Liquid Penetrant Acceptance Standards of ASME B&PV Code Section III, Division 1, Subsection NB-5350 (19839 Additionally, these seal welds at the bottom of the DSC shall be leak tested in accordance with ANSI N14.5 (1987).

Fuel and TC movement and handling activities which are to be performed in the Calvert Cliffs Nuclear Power Plant Auxiliary Building will be governed by the requirements of the Calvert Cliffs Nuclear Power Plant Facility Operating Licenses (DRP-53 and -69) and associated Technical Specifications.

18. Pursuant to 10 CFR 72.7, the licensee is hereby exempted from the provisions of 10 CFR 72.122(i) with respect to providing instrumentation and control systems for the DSC and HSM during storage

2.0 FUNCTIONAL AND OPERATING LIMITS 2.1 FUEL TO BE STORED AT ISFSI SPECIFICATION: Any fuel not specifically filling the requirements of Section 3.1 for maximum burnup and post irradiation time may be stored if it meets the minimum cooling time listed in the Calvert Cliffs ISFSI SAR Table 9.4.1 and all the following requirements are met:

Neutron Source Per Assembly < 2.23 x 108 n/sec/assembly, with spectrum bounded by (NUHOMS-24P) Table 3.1-4 of the Calvert Cliffs ISFSI SAR Neutron Source Per Assembly < 4.175 x 108 n/sec/assembly, with spectrum bounded by (NUHOMS-32P) Table 3.1-4 of the Calvert Cliffs ISFSI SAR Gamma Source Per Assembly

• 1.53 x 1015 MeV/sec/assembly with spectrum bounded by (NUHOMS-24P) that shown in Table 3.1-4 of the Calvert Cliffs ISFSI SAR Gamma Source Per Assembly *1.61 x 1015 MeV/sec/assembly with spectrum bounded by (NUHOMS-32P) that shown in Table 3.1-4 of the Calvert Cliffs ISFSI SAR APPLICABILITY: This specification is applicable to all spent fuel to be stored in the Calvert Cliffs ISFSI.

ACTION: If the requirements of the above specification are not met, do not load the fuel assembly into a DSC for storage.

All-u-r 5,ot-cLg- 2 Q POrce\o\.j Z. toW )( 10 r\/ -clav e~cki, A-~.spe-aor, 0-14s i:SFSk :S-SootTC- 4Z, S& X. '10- ~vA,\b 0*4 Vd~r LO Page 2 of 13 Amendment 9

3/4.1 FUEL TO BE STORED AT ISFSI LIMITING CONDITION FOR OPERATION 3.1.1 The spent nuclear fuel to be received and stored at the Calvert Cliffs ISFSI shall meet the following requirements:

(1) Only fuel irradiated at the Calvert Cliffs Units 1 or 2 may be used. (14 x 14 CE type PWR Fuel)

(2)~~ jlhment shall not exc35.

(3) Maximum assembly avera e burnut shall not excee 400mgattdype (4) Minimum burnup shall exceed the minimum specified in SAR Figure 3.3-1.

(Applicable only to NUHOMS-24P.)

(5) en *on rate shall not excee. aa (6) Fuel shall-havecooled as specified in ISFSI SAR Table 9.4.1.

(7) Maximum assembly mass including control components shall not exceec(-"

(8) Fuel shall be undamaged.

(9) Fuel shall be intact (NUHOMS-32P), only if air is the blowdown medium for DSC drying.

APPLICABILITY: This specification is applicable to all spent fuel to be stored in Calvert Cliffs ISFSI.

ACTION: If any fuel does not specifically meet the requirements for maximum burnup and post irradiation time (items 3 & 6 above), confirm to see if the requirements of Section 2.1 are satisfied. If any other requirements of the above specification are not satisfied, do not load the fuel assembly into a DSC for storage.

Page 5 of 13 Amendment 9

3/4.2 DRY SHIELDED CANISTER (DSC) 3/4.2.2 DSC CLOSURE WELDS LIMITING CONDITION FOR OPERATION 3.2.2.1 The top shield plug closure weld, the siphon and vent port cover welds, and the top cover plate weld shall satisfy the Liquid Penetrant AccepnceStan-dards of ASME B&PV Code Section III, Division 1, Subsection NB-5350 (1983)3 3.2.2.2 The standard helium leak rate for the top shield plug closure weld, and the siphon and vent port cover welds shall not exceed 10 4atm-cc/s. (AJ,,-k. L,,c t'JUH,.,*$ I2.) .-

APPLICABILITY: Applicable to all DSCs. IL-)7 - cc.i (tjiUj . 2*. -

ACTION: With the requirements of the above specifications not satisfied, the weld shall be repaired in accordance with approved procedures and re-examined in accordance with these specifications.

SURVEILLANCE REQUIREMENT 4.2.2.1 During DSC loading operations, the top shield plug closure and the siphon and vent port cover welds shall be tested using a helium leak detector to ensure that, for each weld, leak tightness is less than or equal to 10-4 atm-cc/ These welds and the DSC top cover plate weld shall be dye penetrant tested.

N L~uH-orvw ?L/P atA pjNUrnHMASc 10 -7v-; -rCc/s (NJu~omvs 3ZP14B)

Page 8 of 13 Amendment 7

3/4.3 TRANSFER CASK 3/4.3.2 TIME LIMIT FOR COMPLETION OF NUHOMS 32 PHB DSC TRANSFER OPERATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The time limit for completion of transfer of a loaded and welded NUHOMS 32 PHB DSC from the cask handling area to the HSM is as follows:

a. No time limit for a DSC with a total heat load of < 21.12 kW

b. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for a DSC with a total heat load > 21.12 kW and < 23.04 kW

c. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for a DSC with a total heat load > 23.04 kW and < 25.6 kW

d. 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> for a DSC with a total heat load > 25.6 kW and < 29.6 kW APPLICABILITY: This specification is applicable to NUHOMS 32 PHB DSCs only. The time limit is defined as the time elapsed after the initiation of draining the transfer cask/DSC annulus water until completion of insertion of the DSC into the HSM.

ACTION: Initiate one of the following actions within eight hours if the specified time limit is exceeded. The chosen action may be temporarily suspended under administrative controls to change from one action to another.

1. Complete the transfer of the DSC to the HSM or,

2. If the transfer cask is in the cask handling area in a vertical orientation fill the transfer cask/DSC annulus with clean water or,

3. If the transfer cask is in a horizontal orientation, initiate air circulation by starting one of the blowers provided on the transfer skid or,

4. Return the transfer cask to the cask handling area and fill the transfer cask/DSC annulus with clean water, or initiate appropriate external cooling of the transfer cask outer surface by other means to limit the surface temperature increase.

SURVEILLANCE REQUIREMENTS 4.3.2.1 Monitor the time duration following initiation of draining of the transfer cask/DSC annulus until completion of the insertion of the NUHOMS 32 PHB DSC into the HSM.

Page 1 of 2 Amendment X

3/4.3.3 TIME LIMIT FOR COMPLETION OF NUHOMS 32 PHB DSC VACUUM DRYING OPERATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The time limit for completion of vacuum drying of a loaded NUHOMS 32 PHB DSC following blow down with nitrogen is as follows:

a. 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> for a DSC with a total heat load < 23.04 kW

b. 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> for a DSC with a total heat load > 23.04 kW and < 25.6 kW

c. 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> for a DSC with a total heat load > 25.6 kW and < 29.6 kW APPLICABILITY: This specification is only applicable to vacuum drying of a NUHOMS 32 PHB DSC following blow down with nitrogen. The time limit is defined as the time elapsed after the initiation of the DSC blow down operation with the intent to uncover the active fuel region until the initiation of helium backfill. This specification is not applicable, and there are no time limits imposed on vacuum drying, when helium is used for blow down of the NUHOMS 32 PHB DSC.

ACTION: If vacuum drying cannot be completed within the specified time limit, backfill the DSC with helium and continue with the vacuum drying operation.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Monitor the time duration following initiation of DSC blow down using nitrogen until the initiation of helium backfill.

Page 2 of 2 Amendment X

3/4.4 HORIZONTAL STORAGE MODULE (HSM) 3/4.4.1' MAXIMUM AIR TEMPERATURE RISE LIMITING CONDITION FOR OPERATION 3.4.1.1 The air temperature rise from the HSM inlet to the HSM outlets shall not exceed 64 0 F APPLICABILITY: Applicable to all HSMs. o ?o OF, (

ACTION: If the temperature ris is greater than 64F0 he air inlet and outlets should be checked for block e. If any blockage is c e*red and the temperature rise is still greater than 64 0 F the DSC and HSM cavity shall be inspected, using video equipment or other suita le means. Analysis of the existing conditions shall be performed to confirm that conditions adversely affecting the fuel cladding integrity do not exist. Subsequent actions to return to acceptable conditions such as, providing temporary forced ventilation and/or retrieval of the DSC and verification that an assembly fuel with no more than 0.66 kW was loaded shall be performed.

SURVEILLANCE REQUIREMENTS 4.4.1.1. The maximum air temperature rise from the HSM inlet to outlets shall be checked at the time the DSC is stored in the HSM, again 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> later, and again after 7 days.

4.4.1.2 The HSM shall be visually inspected to verify that the air inlet and outlets are free from obstructions when there is fuel in the HSM. The visual inspection frequency shall be every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

118"-'e \AStY\ - HB 4L IZý, Oe'>

0OL4 I A' s V-k (-o- e,,c-t qo'F.a Page 11 of 13 Amendment 9

5.0 DESIGN FEATURES 5.1 GENERAL The Calvert Cliffs ISFSI design approval was based upon review of specific design drawings, some of which have been deemed appropriate for inclusion in the Calvert Cliffs ISFSI Safety

-Evaluation Report (SER). Drawings listed in Section 1.5 of the Calvert Cliffs ISFSI SER have been reviewed and approved by the NRC. These drawings may be revised under the provisions of 10 CFR 72.48 as appropriate. A - , OS -

5.2 NUHOMS-32P DRY SHIELDED CANISTER (DSC)

The NUHOMS-32P DSC poison plates shall have a minimum B10 areal density of 0.0100g/cm 2 .

5.3 COMBUSTIBLE GAS MONITORING DURING TOP SHIELD PLUG LID WELDING AND CUTTING During top shield plug lid-to-shell welding and cutting operations, combustible gas monitoring of the space under the top shield plug lid is re uired to ensure that there is no combustible mixture present. te-S 3-Z V 4B posos-N P S 6.0 ADMINISTRATIVE CONTROLS Om O.O' c_.rz -PO *-nt cs- "_1 o 6.1 GENERAL 0Ji The Calvert Cliffs ISFSI is located on the Calvert Cliffs Nuclear Power Plant site and will be managed and operated by the Calvert Cliffs Nuclear Power Plant, LLC, staff. The administrative controls shall be in accordance with the requirements of the Calvert Cliffs Nuclear Power Plant Facility Operating Licenses (DPR-53, and -69) and associated Technical Specifications as appropriate.

6.2 ENVIRONMENTAL MONITORING PROGRAM The licensee shall include the Calvert Cliffs ISFSI in the environmental monitoring for Calvert Cliffs Nuclear Power Plant. An environmental monitoring program is required pursuant to 10 CFR 72.44(d)(2).

6.3 ANNUAL ENVIRONMENTAL REPORT The annual radioactive effluent release reports under 10 CFR 50.36(a)(2) license requirements for the Calvert Cliffs Nuclear Power Plant shall also specify the quantity, if any, of each of the principal radionuclides released to the environment in liquid and gaseous effluents during the ISFSI operation and such other information as may be required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent releases.

Copies of these reports shall be submitted to the NRC Region I office and to the Director, Office of Nuclear Material Safety and Safeguards. The report under this specification is required pursuant to 10 CFR 72.44(d)(3).

Page 13 of 13 Amendment 9

ATTACHMENT (3)

TRANSNUCLEAR, INC. PROPRIETARY AFFIDAVIT Calvert Cliffs Nuclear Power Plant, LLC December 8, 2011

AFFIDAVIT PURSUANT TO 10 CFR 2.390 Transnuclear, Inc. )

State of Maryland ) SS.

County of Howard )

I, Jayant Bondre, depose and say that I am a Vice President of Transnuclear, Inc., duly authorized to execute this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conformance with the provisions of 10 CFR 2.390 of the Commission's regulations for withholding this information.

The information for which proprietary treatment is sought is contained in following documents as listed below:

1. TN Calculation NUH32P1IB-0401, "Thermal Evaluation of NUHOMS 32P1B Transfer Cask for Normal, Off Normal, and Accident Conditions with Forced Cooling (Steady State)," Revision 1.

2. TN Calculation NUH32PHB-0503, "HSM-HB Shielding Analysis for NUHOMS 32PHB System," Revision 1.

These documents have been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Transnuclear, Inc. in designating information as a trade secret, privileged or as confidential commercial or financial information.

Pursuant to the provisions ofparagraph (b) (4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.

1) The information sought to be withheld from public disclosure are certain portions of thermal evaluation and radiation dose rate analyses for NUHOMS 32PH13 dry storage system which are owned and have been held in confidence by Transnuclear, Inc.

2) The information is of a type customarily held in confidence by Transnuclear, Inc. and not customarily disclosed to the public. Transnuclear, Inc. has a rational basis for determining the types of information customarily held in confidence by it.

3) Public disclosure of the information is likely to cause substantial harm to the competitive position of Transnuclear, Inc, because the information consists of descriptions of the design and analysis of dry spent fuel storage systems, the application of which provide a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Transnuclear, Inc., take marketing or other actions to improve their product's position or impair the position of Transnuclear, Inc.'s product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.

Page 1 of 2

Further the deponent sayeth not.

Jayant Bondre Vice President, Transnuclear, Inc.

of November. 2011.

My Commission Expires Page 2 of 2