ML14212A308

NUH32PHB-011, Rev 3, Design Report for 32PHB Dsc.

ML14212A308
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Site:	Calvert Cliffs
Issue date:	07/25/2014
From:	Tavassoli K AREVA, Transnuclear
To:	Office of Nuclear Material Safety and Safeguards
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ML14212A137	List: ML14212A307 ML14212A308
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10955 NUH32PHB-011, Rev. 3
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ENCLOSURE5 NUH32PHB-01 11 DESIGN REPORT FOR 32PHB DSC Calvert Cliffs Nuclear Power Plant July 25, 2014

6A0 7¶~C)fL7/ /Cec-'. oee&O1 NUH32PHB-011.1 A Report Number:

AR EVA Revision: 3 TRANSNUCLEAR INC. Page: 1 of 26 Design Report For The NUHOMS 32PHB DSC for Storage of Spent Nuclear Fuel Project Number 10955 Rev. Effective Prepared Checked Approved No. Date By By By Prakash Narayanan (Nuclear) 0 11110110 Raheel Haroon (Structural)

Slava Guzeyev (Thermal)

Kamran Tavassoli Davy Qi (Operation) Peter Shih 1 08119/11 Kamran Tavassoli Venkata Venigalla Peter Shih 2 1120/12 Kamran Tavassoli Slava Guzeyev Peter Shih GUZEYEV M"'"

1327:27 -04'00' e... .. -*h Kamran Tavassoli Slava Guzeyev Peter Shih

A Report Number: NUH32PHB-01 11 AR EVA Design Report Revision: 3 TRAINISNUCLEAR INC. Page .2 of 26 REVISION

SUMMARY

REV. DESCRIPTION AFFECTED PAGES 0 Initial Issue All 1 Update thermal calculation see DCR NUH32PHB-0401 1-3, 11, and 24 Update design drawings and calculation based on DCRs 1-2, 8,23-26 2 A *ad U"H 3,2 PoLl.,B..0-v11 "-nd .012,,A!s.

,111 -- d crit*ic

,. we-d fl,.w,, size

.,al calculation (Calculation NUH32PHB-0220, Rev. 0) to address requirements of ISG-15.

1-2. 11, 21,22 Editorial corrections and clarifications requested by CENG 3_ (CNG-CM-1.01-2003)

A Report Number: NUH32PHB-0111 AREVA Design Report Revision: 3 Page 3 of 26 TRANSNUCLEAR INC.

TABLE OF CONTENTS PAGE 1.0 Introduction ................ .................................. 4 2.0 Purpose ........................................................................................................ 5 3.0 NUHOMS32PHB System Physical Description ............................................. 6 3.1 NUHOMS32PHB DSC Description ....................................................... 6 3.2 HSM-HB Description ...................................................................................... 7 3.3 Transfer Cask Description ....................................................................... 8 4.0 Operation ...................................................................................................... 9 4.1 Time Limits for Vacuum Drying Operations ............................................... 9 4.2 Time Limits for Transfer Operations ........................................................ 11 5.0 Design Criteria ................................................................................................. 13 6.0 Structural Evaluation ........................................................................................ 14 7.0 Thermal Evaluation ................ I.... .......................... 16 8.0 Shielding Evaluation ....................................................................................... 18 9.0 Criticality Evaluation ...................................................................................... 19 10.0 Confinement Evaluation ................................................................................ 20 11.0 Acceptance Testing ............................................................................................ 21 12.0 Design Life..... ............................................... 21 13.0 Conclusion ..................................................................................................... 21 14 .0 R efe rences ......................................................................................................... 22 15.0 List of Structural Calculations ........................................................................ 23 16.0 List of Thermal Calculations .......................................................................... 24 17.0 List of Shielding Calculations .......................................................................... 24 18.0 List of Criticality Calculations .......................................................................... 25 19.0 List of Design Drawings ................................................................................. 25 LIST OF TABLES PAGE Table 1 NUHOMSe 32PHB Basket Types .......................................................... .... 7 Table 2 Time Limits for Transfer Operations .......................................................... 8 Table 3 Time Limits for Vacuum Drying Operations (Nitrogen Blow-Down) ...... 10 Table 4 Time Limits for Soaking (Nitrogen Blow Down) ....................................... 1 i0 Table 5 Time Limits for Vacuum Drying with no Soaking Time (Nitrogen B low D ow n) .......................................................................................... ... 11

A Report Number: NUH32PHB-0111 AREVA Design Report Revision: 3 Ti*ANSIUC__.AR Ijc. Page 4 of 26

1.0 INTRODUCTION

This design report is prepared in accordance with TIP 3.1, Revision 7, "Design Control" to document the design basis for the NUHOMS 32PHB Storage System.

The NUHOMS 32PHB Dry Shielded Canister (DSC) accommodates 32 Pressurized Water Reactor (PWR) spent fuel assemblies used in Calvert Cliffs Nuclear Power Plant (CCNPP) in accordance with 10CFR72 requirements. The spent fuel assemblies are intact CE 14x14 Standard, Value Added Pellet (VAP) and AREVA fuel assemblies (including fuel with stainless steel replacement rods) with and without axial blankets. Fuel assemblies with missing rods are not allowed for loading into NUHOMS 32PHB DSC.

The NUHOMS 32PHB system is a modular canister based spent fuel storage system, which consists of the following components:

• A Dry Shielded Canister (32PHB DSC) providing confinement, an inert environment, structural support, and criticality control for the 32 PWR fuel assemblies,

" A Horizontal Storage Module model HB, HSM-HB, providing environmental protection, shielding, and heat rejection during storage, and

" A Transfer Cask, CCNPP-FC TC, for onsite transfer of the 32PHB DSC from the spent fuel pool to the storage module.

The NUHOMS 32PHB DSC basket is similar to the NUHOMS 32P DSC basket with the exception that solid aluminum rails are used in the NUHOMS32PHB DSC basket. The HSM-HB is similar in design to the storage module, HSM-H with flat stainless steel heat shields, utilized in the Standardized NUHOMS and the NUHOMS HD systems ([2] and [3]). The CCNPP-FC TC is a modified version of the original CCNPP TC with a new slotted top lid and a 0.5 inch thick spacer disc with wedge shaped protrusions installed at the bottom of the TC to enable air circulation through the TC/DSC annulus during transfer operations.

The-32PHB DSC is designed for a maximum heat load of 29.6 kW. The system is designed for high burnup fuel, up to 62 GWD/MTU, with a maximum assembly average initial enrichment of 5% wt U-235.

A Report Number: NUH32PHB-0111 AR EVA Design Report Revision: 3 TRANSNUCLEAR INC. Page 5 of 26 2.0 PURPOSE This design report summarizes the design basis and the qualification for the NUHOMSO 32PHB system for storage of 32 PWR fuel assemblies. The NUHOMS 32PHB system has been developed for submittal as an amendment to the CCNPP ISFSI Updated Safety Analysis Report (USAR) [1]. The NUHOMS32PHB design criteria for storage conditions are specified in [41. Design calculations are prepared for each key discipline area, as follows:

" Structural,

" Thermal,

" Shielding, and

" Criticality.

A summary of the design evaluations for each discipline area is provided in Sections 6.0 through 9.0 of this report. A summary of the confinement evaluation is included in Section 10.0. Acceptance testing of the NUHOMS32PHB system components is discussed in Section 11.0, followed by a discussion of the design life of the canister in Section 12.0. Conclusions with regard to the design are presented in Section 13.0.

Sections 15.0 through 19.0 provide lists of the documents that constitute the basis of the NUHOMS 32PHB system design.

A Report Number: NUH32PHB-0111 Revision: 3 AR EVA Design Report TRANSNUCLEAR INC. Page 6 of 26 3.0 NUHOMS 32PHB SYSTEM PHYSICAL DESCRIPTION 3.1 NUHOMS32PHB DSC Description The NUHOMS32PHB DSC consists of a DSC shell assembly (cylindrical shell, canister bottom and top cover plates and shield plugs or shield plug assemblies) and a basket assembly. The 32PHB DSC has a nominal outside diameter of 67.25 inches and a total length (including grapple ring) of 176.5 inches.

The 32PHB DSC top end closure assembly design is similar to the top end closure design of the 32P DSC described in the USAR [1] (a shield plug assembly with integrated vent and siphon block and lead shielding). The 32PHB DSC bottom end closure assembly design is similar to the bottom end closure design of the 32P DSC described in the USAR [1] (inner bottom cover plate, lead casing, and lead shielding).

The primary confinement boundary for the NUHOMS 32PHB DSC consists of the DSC shell, the top shield plug assembly and inner bottom cover plate, the siphon and vent port cover plates, and the associated welds. The outer top cover plate and associated welds form the redundant confinement boundary.

The cylindrical shell and the inner bottom cover plate boundary welds are fully compliant to Subsection NB of the ASME Code [5], and are made during fabrication.

The top closure confinement welds are multi-layer welds applied after fuel loading and comply with the guidance of ISG-1 5 [7]. The outer top cover plate is welded to the shell subsequent to the leak testing of the confinement boundary to the leak-tight criteria of ANSI N14.5-1997 [6].

The 32PHB DSC basket structure is similar to the 32P DSC basket structure described in USAR [1] and consists of 32 stainless steel guide sleeves. The guide sleeves are welded together at selected elevations along the axial length of the basket through stainless steel plates arranged in an egg crate configuration. The aluminum and neutron absorber plates are sandwiched between the guide sleeves and separated by the stainless steel plates.

Based on boron concentration in the spent fuel pool and initial enrichment of the fuel assemblies, two alternate options are considered for the 32PHB basket for criticality control. The 32PHB basket containing poison plates with minimum B10 areal density of 19.0 mg/cm 2 is assigned as "Basket A" and the 32PHB basket containing poison plates with minimum Blo areal density of 27.0 mg/cm2 is assigned as "Basket B".

Only 90% of the physically available Bl o in the poison plate is taken credit for in the criticality analysis. The applicability of these options for the NUHOMS 32PHB system is summarized in Table 1.

Report Number: NUH32PHB-01 11 A Design Report Revision: 3 AREVA Page 7 of 26 TRANSNUCLEAR INC.

Table I NUHOMS 32PHB Basket Types Minimum Physically Available BAeAreal Density of Poison Plate...

Maximum Allowable U-235 Enrichment Basket A Basket B 19.0 mg/cm 2 27.0 mg/cm 2 Boron 2450 PPM 4.75 wt% 5.00 wt%

Content in Borated 2550 PPM 4.85 wt% NA Water (1) The criticality analysis takescredit for only 90% of the minimum physically available BIo areal density in the poison plates.

The thermal evaluation of the 32PHB DSC (documented in calculation NUH32PHB-0403, Section 16, Item 16.4) considers a thickness of 0.125" and a conductivity of 6.26 Btu/hr-in-°F (130 W/m-K) for the poison plates. If poison plates with thicknesses other than 0.125" are to be used in the fabrication, the minimum required conductivity is the maximum value of Kp, resulting from the following equations.

kAlP=o*,, parallel = kAI x tA] + kpp x tpp =8.28 Btu/hr-in-OF (171.8 W/m-K),

tAl + tpp kpAlpoison, a=ss -

+ tpp /kpp =

tAl + tpp tAl/kAl 7.77 Btu/hr-in-°F (161.3 W/m-K)

Wherre kpp = minimum required thermal conductivity for poison plate, kAi = 10.375 Btu/hr-in-°F (215.3 W/m-K),

(thermal conductivity for All 100 plate at 4001F),

tAJ = nominal thickness of aluminum plate paired with poison plate, tpp = nominal thickness of poison plate.

Since the conductivity of applicable poison plates such as Metal Matrix Composite (MMC) or borated aluminum increases with temperature, the measurement for minimum required conductivity can be performed at room temperature.

3.2 HSM-HB Description The 32PHB DSC is stored. in HSM-HB, which a modified version of the Horizontal Storage Module (HSM-H) described in the UFSAR for the Standardized NUHOMSO and the NUHOMSO HD systems ([2] and [3]). The door and the spacer are modified

A Report Number: NUH32PHB-01 11 AR EVA Design Report Revision: 3 TRANSNUCLEAR INC. Page 8 of 26 to accommodate the diameter and length of the 32PHB DSC. In addition, attenuation pipes are added, as an option, to the inlet vent screens to improve the shielding capabilities of the module. All other key design features of the HSM-HB, which provide enhanced shielding and heat rejection capabilities remain unchanged from those described in the UFSARs (121 and [31).

3.3 Transfer Cask Description The CCNPP-FC TC used to transfer the 32PHB DSC is a modified version of the original CCNPP TC described in the iSFSi USAR [i]. The cavity length and cavity diameter of the modified cask are 173.5" and 68.0", respectively. These dimensions are identical to the dimension of the original CCNPP TC. The CCNPP-FC TC is equipped with a slotted top lid, a spacer disc installed at the bottom of the cask cavity, and an airflow adaptor to allow air circulation through the TC/DSC annulus during transfer operations when time limits for transfer operations cannot be satisfied.

The time limits considered for the transfer operation depend on the heat load and are listed in Table 2.

Table 2 Time Limits for Transfer Operations

>25.6 kW >23.04 kW Heat Load _521.12 kW to to :23.04 kW

__29.6 kW <_25.6 kW Transfer Time Limit No time 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (Maximum) limit

A -~ Report Number: NUH32PHB-0111 AR EVA Design Report Revision: 3 TRANSNUCLEAR INC. Page 9 of 26 4.0 OPERATION The major operations considered in the design of the NUHOMSO 32PHB system are as follows.

~~ D S n o t e Tn .... ...

• ~ti. ~ ......

.od . ....

" Loading the DSC into the TC,

" Filling the DSC and TC with water,

" Placing the TC/DSC with water in the fuel pool,

• Loading spent fuel into the DSC,

• Moving the loaded TC to the decontamination area,

" Welding the top shield plug assembly to the DSC shell,

" Draining and drying the DSC,

" Leak testing the top shield plug assembly and vent and siphon port covers for leak tightness,

• Welding the DSC outer top cover plate to the DSC shell,

• Loading the loaded TC/DSC on the transfer trailer,

" Transferring the loaded TC/DSC/Trailer to the ISFSI,

• Inserting the DSC into the HSM-HB from the TC,

• Storage of the DSC in the HSM-HB, and

• Retrieving the DSC from the HSM-HB.

Operational procedures for NUHOMS 32PHB DSC are similar to the procedures for NUHOMS 24P and NUHOMS 32P DSCs except for the vacuum drying and transfer operations. Several time limits are imposed on the operations for NUHOMS 32PHB DSC due to its high heat load. These time limits are described below.

4.1 Time Limits for Vacuum Drying Operations The vacuum drying operations for 32PHB DSC start from the initiation of water drainage (blow down) from the DSC cavity after the top shield. plug of the DSC is seal welded and a nondestructive examination (NDE) is performed. It is assumed that active fuel length remains covered with water during welding and NDE. The vacuum drying operations for 32PHB DSC end with the completion of first backfilling of DSC cavity with helium to 22 psia (7.3 psig). Note that the procedures for 24P and 32P DSCs require to evacuate the DSC cavity after the first helium pressurization and to backfill the DSC cavity to the final pressure of 2.5+/-1 psig in the consequent steps. A similar operation is considered for 32PHB DSC. The water level in the TC/DSC annulus shall be maintained at approximately 12 inches below the upper edge of the DSC shell during the vacuum drying operations.

The time limits imposed on vacuum drying operations are to maintain the fuel cladding temperature below the allowable limit of 752 0 F. Nitrogen or helium can be used to the blow down the water out of the 32PHB DSC cavity. If helium is used for blow down, no time limit exists for any heat load for the vacuum drying operations.

Report Number: N UH32PH B-0111 A 3 ARE VA Design Report Revision:

TRANSNUCLEAR INC. Page 10 of 26 If nitrogen is used for the blow down, the following time limits shall be considered for vacuum drying operations.

, For decay heat loads less than or equal to 23.04 kW, the vacuum drying time shall be limited to 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br />.

- For decay heat loads greater than 23.04 kW and less than or equal to 25.6 kW, the vacuum drying time shall be limited to 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

• For decay heat loads greater than 25.6 kW and less than or equal to 29.6 kW, the vacuum drying time shall be limited to 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.

These time limits are presented in Table 3 for reference.

Table 3 Time Limits for Vacuum Drying Operations (Nitrogen Blow-Down)

>25.6 kW >23,04 kW Heat Load to to Q23.04 kW

_*29.6 kW <525.6 kW Vacuum Drying Time 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> Limit (Maximum)

In addition to the above time limits for the vacuum drying operations, if nitrogen is used for the blow down, the 32PHB DSC shall remain soaked in the water present in the annulus between the DSC and transfer cask for the following minimum times after completion of the first helium backfilling. This minimum time limit is required to ensure that the fuel assemblies and DSC components cool down sufficiently to the initial conditions used in the transfer cask thermal analysis.

• For decay heat loads less than or equal to 23.04 kW, the minimum soaking time is 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

• For decay heat loads greater than 23.04 kW and less than or equal to 29.6 kW, the minimum soaking time is 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.

These time limits are presented in Table 4 for reference.

Table 4 Time Limits for Soaking (Nitrogen Blow Down)

>23.04 kW Heat Load to _<23.04 kW

<_29.6 kW Soaking Time Limit 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> (Minimum)

Report Number: NUH32PHB-01-11 A Design Report Revision: 3 AREVA Page 11 of 26 TRANSNUCLEAR INC.

In the case that the vacuum drying operations conclude within the following time limits, the soaking time limits listed in Table 4 are not applicable for the consequent operations.

Table 5 Time Limits fr Vacuum Dring with no Soaking Time (Nitrogen Blow Down)

>25.6 kW >23.04 kW Heat Load to to *23.04 kW

<_29.6 kW :_25.6 kW Vacuum Drying Time Limit (Maximum) 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with no Soaking Time limit If the vacuum drying operations cannot be concluded within the time limits listed in Table 5, the time limits for the vacuum drying and soaking are applicable as noted in Table 3 and Table 4, respectively.

4.2 Time Limits for Transfer Operations The transfer operation starts with the initiation of the water drainage from the annulus between the DSC and transfer cask and ends with the loading of the DSC into the HSM-HB. The time limits considered for the transfer operation are to maintain the fuel cladding temperature below the allowable limit of 752 0 F.

Depending on the heat load, the following time limits apply for the transfer operation.

• For decay heat loads less than or equal to 23.04 kW, the transfer operation time shall be limited to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• For decay heat loads greater than 23.04 kW and less than or equal to 25.6 kW, the transfer operation time shall be limited to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

° For decay heat loads greater than 25.6 kW and less than or equal to 29.6 kW, the transfer operation time shall be limited to 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

• For decay heat loads less than or equal to 21.12 kW, the transfer operation has no time limit.

These time limits are presented in Table 2 for reference.

If the transfer operation cannot be concluded within the specified time limits, corrective action such as initiation of forced cooling or refilling the TC/DSC annulus with clean demineralized water shall be followed immediately.

If the forced cooling is interrupted due to any reason (an accident, a system failure, or initiation of DSC loading into the HSM-HB), a time limit of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> applies to either re-establish the forced cooling or to complete the loading of the DSC into the HSM-HB.

In addition, a time limit of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> is considered for the operations when the transfer cask contains a loaded 32PHB DSC in vertical orientation. This time limit applies for

A Report Number: NUH32PHB-0111 Revision: 3 AREVA Design Report TRANSNUCL.AR INC. Page 12 of 26 any heat load after the initiation of water drainage from the TC/DSC annulus. The annulus shall be filled back with clean demineralized water to a level approximately 12 inches below the DSC shell upper edge if the determined time limit of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> exceeds or is anticipated to exceed. This time limit is applicable to all allowable heat loads as noted, but is coincidently equal to the time limit set for transfer operation with heat loads greater than 25.6 kW and less than or equal to 29.6 kW.

A Report Number: NUH32PHB-01 11 AR EVA Design Report Revision: 3 Page 13 of 26 TRANSNUCLEAR INC.

5.0 DESIGN CRITERIA The NUHOMS 32PHB system provides structural integrity, confinement, shielding, criticality control and passive heat removal independent of any other facility structures or components. The NUHOMSO 32PHB design criteria for storage conditions are specified in the Design Criteria Document (DCD) [4]. The environmental and loading conditions associated with the operations and design of the NUHOMS 32PHB system are also provided in [4].

The version of the ASME Boiler and Pressure Vessel Code used in the design is the 1998 edition, including 1999 addenda for the DSC design and the 1998 edition for the cask design. Alternatives to the code for the NUHOMS 32PHB DSC and basket are provided in Drawing NUH32PHB-30-30 listed in Section 19.0.

A Report Number: N UH32PHB-01 11 AR EVA Design Report Revision. 3 TRANSNUCLEAR INC. Page 14 of 26 6.0 STRUCTURAL EVALUATION The components evaluated in the structural analyses are:

o 32PHB DSC shell and basket assemblies,

• HSM-HB reinforced concrete and DSC support steel, including the 32PHB DSC,

° CCNPP-FC transfer cask (loaded by the DSC).

The structural performance for each component is determined for the normal, off-normal and postulated accident conditions described in the DCD [4]. The loading conditions for operations inside of the TC, loading and unloading the DSC to the HSM-H, and storage of the DSC in the HSM-H are considered as specified in the DCD [4].

An actual drop event is not considered credible. However, it is postulated that the transfer cask with the DSC inside will be subjected to an end, side, or oblique drop with a maximum height of 80 inches onto a thick concrete slab. Based on USAR [1],

a design basis load of 75g is considered for accident drops.

The structural evaluation of the intact fuel assembly design basis drops is performed to demonstrate that sub-criticality is maintained and fuel cladding remains intact following the design basis drops.

An equivalent static finite element analysis was performed for side drop evaluation. It was assumed that the cladding is subjected to lateral loads comprised of both the fuel and cladding weights but no credit is taken for stiffness of the fuel pellets. A maximum normal operating temperature of 750=F was conservatively used. A side drop acceleration of 75g was considered for the fuel assemblies. It was demonstrated that the maximum calculated bending stress plus rod internal pressure stress is ,

significantly lower than the yield strength of the fuel cladding material. Therefore, it was concluded that the fuel cladding will not fail under hypothetical side drop accident condition.

It is concluded that the analyses for NUHOMS 32P+ DSC in [10] bound all the fuel assemblies in the 32PHB DSC except for the AREVA fuel assemblies. Since the geometry for the AREVA fuel assembly is the same as the one used in the 32P+ DSC analysis, the results were scaled due to the differences in the M5 and Zircaloy-4 materials. The evaluation concluded that the fuel cladding deforms elastically with very small amount of maximum principal strain. Therefore, the fuel cladding maintains its structural integrity during the hypothetical end drop condition.

The 32PHB DSC shell assembly is a Class 1 vessel that is designed and fabricated to the requirements of the ASME Code Subsection NB to the maximum possible extent. The DSC shell assembly provides a confinement boundary that meets the leak tight criteria of [6].

A Report Number: NUH32PHB-0111 AR EVA Design Report Revision: 3 TRANSNUCLEAR INC. Page 15 of 26 The 32PHB DSC is evaluated for pressures of 15 psig, 20 psig, and 100 psig, corresponding to normal, off-normal, and accident conditions. Vertical end drops are not credible for the NUHOMS 32PHB system. However, analyses for 75g side and end drops are performed as a means of conservatively bounding the design for the postulated corner drop.

Acceptance criteria for the shell assembly are based primarily on the ASME Code Section III, Division 1, Subsection NB, and Appendix F for Service Level D conditions. The inner and outer top cover plates to the canister shell welds are evaluated in accordance with ISG-15 [7]. The minimum inspection requirement for the end closure welds is liquid penetrant examination of the root and final weld layers. The lifting lug and associated welds are evaluated as an ASME Code Subsection NF component using Level B stress allowables.

In the structural evaluation of the basket, no credit is taken for the structural capacity of the aluminum heat transfer plates or poison plate material except for through-thickness bearing (compression) loads. The connections between the transition rails and the fuel compartment tubes are not required to maintain structural capacity of the basket assembly. These connections are provided primarily to simplify basket assembly insertion into the canister during fabrication, and are designed to allow free thermal expansion of the connected parts.

The end and side drops are used to envelop the corner drop. A basket assembly stability analysis is performed to evaluate the buckling stability of the fuel compartments. Acceptance criteria for the basket assembly are primarily based on the ASME Code Section III, Division 1 NG, and Appendix F allowables.

The HSM-HB reinforced concrete and support structure evaluations are based on analysis performed for HSM-H considering bounding environmental, heat, and seismic loads. The calculated forces, moments and shears in the reinforced concrete sections are translated into required reinforcing and structural steel in accordance with the rules of ACI 349-97 and AISC Manual of Steel Construction for the DSC support steel, respectively.

The structural evaluation of CCNPP-FC TC demonstrated that the stresses computed for the original CCNPP TC loaded with 32P DSC are bounding for the 32PHB DSC with the exceptions of some localized component. Localized stresses due to higher 32PHB DSC localized component weights are shown to be acceptable.

It is also demonstrated that the modified design of CCNPP-FC TC satisfies the ASME code criteria for drop accident conditions.

A list of structural calculations is provided in Section 15.0.

A Report Number: NUH32PHB-0111 ARE VA Design Report Revision: 3 TRANSNUCLEAR INC. Page 16 of 26 7.0 THERMAL EVALUATION The maximum decay heat load considered for the NUHOMS 32PHB DSC is 29.6 kW with a heat load zone configuration shown in the DCD [4], Figure 4-1. The maximum allowable heat load per assembly is 1.0 kW. Ambient temperature range is between -8°F and 104 0 F as specified in the DCD [4]. The ambient temperatures are considered as steady state conditions for the thermal evaluations.

Thermal evaluation of the HSM-HB is based on the thermal analysis of HSM-H with 61 BTH DSC and 31.2 kW heat load. This analysis determines the bounding DSC shell temperatures for the 32PHB DSC for the normal and off-normal conditions. The methodology used to evaluate the thermal performance of the HSM-H has been validated by thermal tests performed on a 1:1 scale of a HSM-H mockup structure for heat loads varying from 32 to 44 kW. The thermal evaluation methodology for the HSM-H has been reviewed and accepted by the NRC for the NUHOMS 24PTH system [2] and the NUHOMS HD system [3].

Thermal evaluation of the CCNPP-FC TC is conducted using ANSYS computer code.

The methodology of using ANSYS to evaluate the forced cooling performance is benchmarked against a SINDA/FLUINT model of OS200FC transfer cask loaded with 32PTH1 DSC. The SINDA/FLUINT model has been reviewed and accepted by the NRC for the NUHOMS 61BTH system and the NUHOMS 32PTH1 system [2].

The DSC thermal performance is evaluated based on a three-dimensional ANSYS model of the 32PHB DSC. The DSC shell temperatures from the HSM-HB (HSM-H) or transfer cask analysis models are applied to the DSC model to determine the maximum fuel cladding temperature and basket component temperatures for the normal, off-normal, and accident conditions.

The fuel assemblies are considered as a homogenized material in the DSC model.

The effective thermal conductivity of the homogenized fuel assemblies used in the 32PHB DSC model is based on the conservative assumption of radiation and conduction heat transfer only, where any convection heat transfer is neglected.

The DSC model included the effects of the fuel axial decay heat profile. To simplify the model and expedite the computational time, the paired poison and aluminum plates and the gaps between them are homogenized in the DSC model. Orthotropic effective conductivities are calculated for the homogenized poison and aluminum plates to maintain the accuracy of the modeling.

The evaluation of vacuum drying conditions are conducted assuming a pool temperature of 140 0 F. Transient analyses are performed to determine the maximum vacuum drying time and minimum soaking times when nitrogen is used as blow-down gas. Steady state runs are performed to determine the maximum temperatures when helium is used as blow-down gas. Since no repeated cycling occurs for vacuum drying of 32PHB DSC, the limit of 66 0C (11 80F).on thermal cycling is not applicable to NUI-IOMS 32PHB system.

A Design Report Report Number: NUH32PHB-0111 Revision: 3 AREVA TRANSNUCLEAR INC. Page 17 of 26 The applicable allowable fuel cladding temperatures are compared against calculated temperatures as the basis for the acceptance of thermal evaluations.

Maximum DSC internal pressures are calculated based on the variation of the DSC initial backfill gas (heliurm) prssure With the variation in temperature for the specified normal, off-normal and accident conditions. Additional fuel rod fill gas and fission gases are assumed to be released based on an assumed percentage of failed fuel rods (1% for normal conditions, 10% for off-normal conditions, and 100% for accident conditions). The total amount of filled and fission gases released per fuel rod is 97.9186 in3 at STP (68°F and 1 atm) as provided by CCNPP in [9] and is reflected in DCD [4]. It is demonstrated that the maximum DSC pressures remain below the design pressures considered for structural evaluations.

Thermal expansion of the components is evaluated to demonstrate that adequate gaps among basket, DSC, cask and irradiated fuel assemblies are provided to allow free thermal expansion growths during transfer and storage conditions.

A list of thermal calculations is provided in Section 16.0.

A Report Number: NUH32PH B-01 11 AR EVA Design Report Revision: 3 TRANSNUCLEAR INC. Page 18 of 26 8.0 SHIELDING EVALUATION The shielding performance of the NUHOMS 32PHB system is determined for conditions of transfer and storage based on the appropriate design basis source terms. The design basis fuel source terms are provided by CCNPP as documented in the DCD [4].

The radiation shielding analyses are performed for 32PHB DSC in the HSM-HB and in the CCNPP-FC TC using the 3-Dimensional Monte-Carlo Code, MCNP5 with the continuous energy cross-section library. These analyses determine surface dose rates on the transfer cask and HSM-HB under all conditions of ioading, transfer, and storage. The occupational exposure during loading and transfer operations are also calculated. Site dose rate is calculated for an ISFSI containing 132 HSM-HBs loaded with 32PHB DSCs in two rows of 2x6 back-to-back arrays of HSM-HBs in five phases (120 HSM-HBs) and two rows of 1x6 arrays of HSM-HBs (12 HSM-HBs). The shielding calculations demonstrate that the design of NUHOMS 32PHB system satisfies the design criteria in [4]. A list of shielding calculations is provided in Section 17.0.

A Report Number: NUH32PHB-01 11 AR EVA Design Report Revision: 3 TRANSNUCLEAR INC. Page 19 of 26

9.0 CRITICALITY EVALUATION

Criticality performance of the NUHOMS 32PHB system is determined for conditions of storage, and transfer. The criticality evaluation is based on the NUHOMS32PHB DSC being stored in the HSM-HBJ and trainsferred in the CCNPP-FC TC, which are identical for criticality purposes. Intact and reconstituted fuel assemblies are considered for criticality evaluations.

An Upper Safety Limit (USL) is determined from a statistical analysis of benchmark criticality experiments documented. The criticality analyses are performed with the CSAS5 module of the SCALE system. A series of sensitivity analyses are performed to determine the most reactive configuration for the NUHOMS 32PHB DSC. These analyses also evaluate a variety of fuel assembly types, initial enrichments, and poison loadings to determine the maximum allowed initial enrichment as a function of soluble boron concentration in the pool and fixed poison.

The postulated fuel assembly drops which can potentially lead to fuel rod repositioning are addressed in the criticality evaluations. The results of the criticality evaluation demonstrate that the effect of these drops on the reactivity of the 32PHB DSC is insignificant. The criticality analyses show that the 32PHB DSC/TC configuration is subcritical under normal, off-normal, and accident conditions of loading, transfer and storage. A list of shielding calculations is provided in Section 18.0.

A Report Number: NUH32PHB-01 11 AR EVA Design Report Revision: 3 "RANSNUCLEAR INC. Page 20 of 26 10.0 CONFINEMENT EVALUATION Confinement within the NUHOMS 32PHB DSC is provided for intact and reconstituted fuel assemblies. The fuel pellets are confined first within the fuel cladding that is protected from degradation by an inert helium atmosphere. The second confinement barrier is the DSC shell and multiple barriers formed by the inner and outer top and bottom cover plates. The DSC shell, the inner bottom cover plate, and the top shield plug assembly are fabricated and inspected to ASME Code requirements and leak tested in accordance with ANSI N14.5-1997 to a "leak tight" condi*t. The pressure calculaton dscribd in Sctin -7.0 demonstrtes that fth maximum DSC internal pressures do not exceed the design pressure. Furthermore, the structural calculations described in Section 6.0 show that confinement boundary is not breached under all normal, off-normal, and accident conditions considered bounding design pressures. Therefore, the NUHOMS 32PHB DSC does not require a detailed confinement evaluation.

A Report Number: NUH32PHB-0111 ARE VA Design Report Revision: 3 TRANSNUCLEAR INC. Page 21 of 26 11.0 ACCEPTANCE TESTING Testing for the NUHOMS 32PHB DSC and CCNPP-FC TC includes that required by the ASME Code for the qualification of materials, welded joints, and canister leakage per ANSI N 14.5-1997. Additionally, specific operational type fit-up testing is required.

Specific required tests are specified in the appropriate drawings provided in Section 19.0.

The following minimum testing shall be performed:

• ASME Code required testing (materials and welding),

• Helium leak testing of the final pressure boundary to a "leak tight" condition as defined by ANSI N14.5 -1997,

" Dummy fuel assembly insertion and withdrawal for each basket fuel guide sleeve, and

" Testing of the poison material.

The minimum inspection requirement for the end closure welds is liquid penetrant or magnetic particle examination of the root and final weld layers to achieve this efficiency.

12.0 DESIGN LIFE The NUHOMS" 32PHB DSC and the CCNPP-FC TC are fabricated primarily from high quality stainless steel. The main DSC and TC components materials are fabricated using ASME code materials and are used consistent with code-approved applications. The DSC and TC materials are resistant to corrosion and are not susceptible to other galvanic reactions. The NUHOMS 32PHB DSC (basket and shell) design life is the same as the existing design of NUHOMS 32P system because the material of construction and all the other conditions are the same. The NUHOMS 32PHB DSC internals are enveloped in a dry, inert helium environment and are designed for all postulated environmental conditions. The HSM-HB is a reinforced concrete component with an internal steel support structure that is fabricated to the ACI and AISC Code requirements, respectively; both have durability well beyond their design life. Therefore, the NUHOMS 32PHB DSC, CCNPP-FC TC, and HSM-HB will meet the specified design criteria for a design life in excess of 50 years.

13.0 CONCLUSION

The NUHOMS 32PHB system design presented in the documents listed in Section 15.0 through Section 19.0 and summarized in this design report satisfies the criteria specified in the applicable Design Criteria Document [4].

A Report Number: NUH32PHB-0111 Revision: 3 AR EVA Design Report TRANSNUCL.AR INC. Page 22 of 26

14.0 REFERENCES

1 Calvert Cliffs Nuclear Power Plant ISFSI, "Updated Safety Analysis Report," NRC Docket Numbers 50-317 and 50-318, Revision 21.

2 Transnuclear, Inc., "Updated Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel," NRC Docket No. 72-1004, Transnuclear Document No.

NUH-003, Revision 11.

3 Transnuclear, Inc., "Updated Final Safety Analysis Report for the NUHOMS HD Horizontal Modular Storage System for Irradiated Nuclear Fuel", NRC Docket No. 72-1030, Revision 2.

4 Transnuclear, Inc., "Design Criteria Document (DCD) for the NUHOMS 32PHB System for Storage", Document No. NUH32PHB-0101, Rev. 2.

5 ASME Boiler and Pressure Vessel Code, 1998 edition with all addenda up to and including 1999 Addenda for DSC/ Basket design and 1992 edition for the transfer cask design.

6 ANSIN 14.5, "Radioactive Materials - Leakage Tests on Packages for Shipment of," 1997.

7 USNRC, Spent Fuel Project Office Interim Staff Guidance, ISG-15, "Materials Evaluation", 2001.

8 Not used.

9 Calculation, "Calvert Cliffs Unit 2 Cycle 16 Bounding Fuel Performance Analysis for ZrB2 Implementation at 2746 MWt Core Power", CCNPP Fuel Operations Support Unit, Calculation No. CA06525, Revision 0.

10 Calculation, "Fuel End Drop Analysis for NUH32P+ Using LS-DYNA",

Transnuclear, Inc. Calculation No. NUH32PT+.0204, Rev. 1.

A Design Report Report Number: NUH32PHB-0111 Revision: 3 AR EVA TRANSNUCLEAR INC. Page 23 of 26 15.0 LIST OF STRUCTURAL CALCULATIONS 15.1 Calculation, "NUHOMS 32PHB Weight Calculation of DSC/TC System",

Transnuclear Calculation No. NUH32PHB-0201, Rev. 0.

15.2 Calculation, "Evaluation of the 32PHB SysteM for Hydr ogen Gereration Effects", Transnuclear Calculation No. NUH32PHB-0202, Rev. 0.

15.3 Calculation, "PWR Fuel Rod Accident Side Drop Loading Stress Analysis for NUHOMS 32PHB System", Transnuclear Calculation No. NUH32PHB-0203, Rev. 1.

15.4 Calculation, "NUHOMS 32PHB Canister Structural Evaluation for Storage and Onsite Transfer Loads", Transnuclear Calculation No. NUH32PHB-0204, Rev. 0.

15.5 Calculation, "NUHOMS32PHB Basket Evaluation for Storage and Transfer Loads", Transnuclear Calculation No. NUH32PHB-0205, Rev. 1.

15.6 Calculation, "NUHOMS32PHB Transfer Cask - Local Shell Stresses at Trunnion Locations", Transnuclear Calculation No. NUH32PHB-0206, Rev.

0.

15.7 Calculation, "Fuel End Drop Analysis for NUH32PHB Using LS-DYNA",

Transnuclear Calculation No. NUH32PHB-0207, Rev. 1.

15.8 Calculation, "HSM-HB Structural Analysis for NUHOMS 32PHB System",

Transnuclear Calculation No. NUH32PHB-0208, Rev. 0.

15.9 Calculation, "Reconciliation for Transfer Cask CCNPP-FC Structural Evaluation", Transnuclear Calculation No. NUH32PHB-021 1, Rev. 1.

15.10 Calculation, "CCNPP-FC Transfer Cask Structural Evaluation - Accident Conditions, 75G Side Drop and 75G Top End Drop Cases", Transnuclear Calculation No. NUH32PHB-0212, Rev. 1.

15.11 Calculation, "NUHOMS 32PHB Canister Lifting Lug Analysis", Transnuclear Calculation No. NUH32PHB-0213, Rev. 0.

15.12 Calculation, "NUHOMS 32PHB Reconciliation for Civil Structures",

Transnuclear Calculation No. NUH32PHB-0214, Rev. 0.

15.13 Calculation, "NUHOMS 32PHB Reconciliation for Lift Beam", Transnuclear Calculation No. NUH32PHB-0216, Rev. 0.

15.14 Calculation, "NUH32PHB DSC Stress Analysis Due to Blow Down and Test Pressure", Transnuclear Calculation No. NUH32PHB-0217, Rev. 0.

15.15 Calculation, "NUH32PHB Cask Spacer Disc Friction Screw Attachment Evaluation", Transnuclear Calculation No. NUH32PHB-0218, Rev. 0.

15.16 Calculation, "NUH32PHB DSC Shell Assembly Outer Top Cover Plate Critical Flaw Size of Welds", Transnuclear Calculation No. NUH32PHB-0220, Rev. 0.

A Report Number: N UH32PHB-01 11 ARE VA Design Report Revision: 3 TRANSNUCLEAi INIC. Page 24 of 26 16.0 LIST OF THERMAL CALCULATIONS 16.1 Calculation, "Benchmarking of the ANSYS Model of the OS200FC Transfer Cask", Transnuclear Calculation No. NUH32PHB-0400, Rev. 1.

16.2 Calculation, "Thermal Evaluation of NUHOMS 32PHB Transfer Cask for Normal, Off Normal, and Accident Conditions with Forced Cooling (Steady State)", Transnuclear Calculation No. NUH32PHB-0401, Rev. 1.

16.3 Calculation, "Thermal Evaluation of NUHOMS 32PHB Transfer Cask for Normal, Off Normal, and Accident Conditions", Transnuclear Calculation No.

NUH32PHB-0402, Rev. U.

16.4 Calculation, "Thermal Evaluation of NUHOMS 32PHB DSC for Storage and Transfer Conditions", Transnuclear Calculation No. NUH32PHB-0403, Rev.

0. "

16.5 Calculation, "Internal Pressure for NUHOMS 32PHB DSC for Storage and Transfer Conditions", Transnuclear Calculation No. NUH32PHB-0404, Rev.

0.

16.6 Calculation, "Thermal Expansion of NUHOMS 32PHB System for Transfer and Storage Conditions", Transnuclear Calculation No. NUH32PHB-0405, Rev. 0.

16.7 Calculation, "Thermal Evaluation of NUHOMS 32PHB Transfer Cask for Normal, Off Normal, and Accident Conditions (Heat Loads of <29.6 kW)",

Transnuclear Calculation No. NUH32PHB-0406, Rev. 2.

16.8 Calculation, "Effective Thermal Properties of Bounding CE 14x14 Fuel Assembly for 32PHB DSC", Transnuclear Calculation No. NUH32PHB-0407, Rev. 0.

16.9 Calculation, "Thermal Analysis of NUHOMS 32PHB DSC for Vacuum Drying Operations", Transnuclear Calculation No. NUH32PHB-0408, Rev. 1.

16.10 Calculation, "Forest Fire Thermal Evaluation for CCNPP ISFSI",

Transnuclear Calculation No. NUH32PHB-0409, Rev. 0.

16.11 Calculation, "Reconciliation of Thermal Analyses Results for 32PHB DSC Storage in HSM-HB Module", Transnuclear Calculation No. NUH32PHB-0410, Rev. 1.

17.0 LIST OF SHIELDING CALCULATIONS 17.1 Calculation, "Source Terms and Material Densities for Shielding Evaluation of NUHOMS 32PHB System", Transnuclear Calculation No. NUH32PHB-0501, Rev. 1.

17.2 Calculation, "Calvert Cliffs NUHOMS -32PHB Radiation Dose Rates for Loading and Transfer", Transnuclear Calculation No. NUH32PHB-0502, Rev. 2.

A Design Report Report Number: NUH32PHB-0111 Revision: 3 AR EVA TRANSNUCLEAR INC. Page 25 of 26 17.3 Calculation, "HSM-HB Shielding Analysis for NUHOMS 32PHB System",

Transnuclear Calculation No. NUH32PHB-0503, Rev. 1.

17.4 Calculation, "Site Dose Analysis for NUHOMS 32PHB System",

Transnuclear Calculation No. NUH32PHB-0505, Rev. 1 . ................................

18.0. LIST OF CRITICALITY CALCULATIONS 18.1 Calculation, "Criticality Evaluation for NUHOMS 32PHB System",

Transnuclear Calculation No. NUH32PHB-0600, Rev. 0.

18.2 Calculation, "USL Evaluation for NUHOMS 32PHB System", Transnuclear Calculation No. NUH32PHB-0603, Rev. 0.

19.0 LIST OF DESIGN DRAWINGS 19.1 Drawing, "NUHOMS 32PHB Canister for PWR Fuel, Shell & Bottom Plug Assembly", Transnuclear Drawing No. NUH32PHB-30-1, Rev- 11 19.2 Drawing, "NUHOMS 32PHB Canister for PWR Fuel, Shell & Siphon Pipe Assembly Details", Transnuclear Drawing No. NUH32PHB-30-2, Rev. 1.

19.3 Drawing, "NUHOMS 32PHB Canister for PWR Fuel, Siphon Pipe / Adaptor

& Lifting Block Details", Transnuclear Drawing No. NUH32PHB-30-3, Rev. 1.

19.4 Drawing, "NUHOMS 32PHB Canister for PWR Fuel, Top Shield Plug Details", Transnuclear Drawing No. NUUH32PHB-30-4, Rev. 1.

19.5 Drawing, "NUHOMSO 32PHB Canister for PWR Fuel, Top Cover Plate and Siphon/Vent Port Covers", Transnuclear Drawing No. NUH32PHB-30-5, Rev.

1.

19.6 Drawing, "NUHOMS 32PHB Basket Assembly", Transnuclear Drawing No.

NUH32PHB-30-6, Rev. 2.

19.7 Drawing, "NUHOMS 32PHB Basket Details", Transnuclear Drawing No.

NUH32PHB-30-7, Rev. 1.

19.8 Drawing, "NUHOMS 32PHB Basket Assembly, Rails and Stud Details",

Transnuclear Drawing No. NUH32PHB-30-8, Rev. 1.

19.9 Drawing, "NUHOMS 32PHB Basket Plates Details", Transnuclear Drawing No. NUH32PHB-30-9, Rev. 2.

19.10 Drawing, 'NUHOMS 32PHB Parts List", Transnuclear Drawing No.

NUH32PHB-30-10, Rev. 3.

19.11 Drawing, "General License NUHOMS ISFSI Onsite Transfer Cask Overview", Transnuclear Drawing No. NUH32PHB-30-11, Rev. 0.

19.12 Drawing, "NUHOMS 32PHB ISFSI, Onsite Transfer Cask, Spacer Option for Forced Cooling", Transnuclear Drawing No. NUH32PHB-30-12, Rev. 0.

A Report Number: NUH32PHB-01 11 AREVA Design Report Revision: 3 TRANSNUCLEAR INC. Page 26 of 26 19.13 Drawing, "NUHOMS 32PHB ISFSI, Onsite Transfer Cask, Forced Air Cooling Lid Modifications", Transnuclear Drawing No. NUH32PHB-30-13, Rev. 0.

19.14 Drawing, "NUHOMSP System HSM-HB Door", Transnuclear Drawing No.

NUH32PHB-30-14, Rev. 1.

19.15 Drawing, "NUHOMS System HSM-HB, Support Structure - Welded Spacers", Transnuclear Drawing No. NUH32PHB-30-15, Rev. 1.

19.16 Drawing, "NUHOMS System HSM-HB, Alternate Birdscreen", Transnuclear Drawing No. NUH32PHB-30-16, Rev. 0.

19.17 Drawing, "NUHOMS 32PHB Canister for PWR Fuel, Final Assembly, Field Welding & Testing", Transnuclear Drawing No. NUH32PHB-30-20, Rev. 1.

19.18 Drawing. "NUHOMS 32PHB Canister for PWR Fuel, ASME Code Exceptions", Transnuclear Drawing No. NUH32PHB-30-30, Rev. 1.

19.19 Drawing, "NUHOMSO System HSM-HB, Configuration Drawing",

Transnuclear Drawinig No. NUH32PHB-7100, Rev. 0.