ML19178A145

HI-STAR 180 Proposed CoC 9325 R3

ML19178A145
Person / Time
Site:	07109325
Issue date:	06/21/2019
From:	Office of Nuclear Material Safety and Safeguards
To:	Holtec
References
1553041-NRC, EPID: L-2019-LLA-0122
Download: ML19178A145 (8)

Text

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9325 23 71-9325 USA/9325/B(U)F-96 1

OF 68

2. PREAMBLE

a. This certificate is issued to certify that the package (packaging and contents) described in Item 5 below meets the applicable safety standards set forth in Title 10, Code of Federal Regulations, Part 71, Packaging and Transportation of Radioactive Material.

b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION

a.

ISSUED TO (Name and Address)

b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Holtec International 1 Holtec Blvd.

Camden, NJ 08104One Holtec Drive Marlton, NJ 08053 Holtec International Report No. HI-2073681, Safety Analysis Report on the HI-STAR 180 Package, Revision No. 6TBD, dated April 21, 2014TBD.

4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a)

Packaging (1)

Model No.: HI-STAR 180 (2)

Description The HI-STAR 180 package is designed for transportation of undamaged irradiated Uranium Oxide (UO2) and Mixed Oxide (MOX) fuel assemblies. The fuel basket provides criticality control and the packaging body provides the containment boundary, helium retention boundary, moderator exclusion barrier, gamma and neutron radiation shielding, and heat rejection capability. The outer diameter of the HI-STAR 180 packaging is approximately 2700 mm without impact limiters and approximately 3250 mm with impact limiters. The maximum gross weight of the loaded HI-STAR 180 package is 140 Metric Tons.

Fuel Basket Metamic-HT, a metal matrix composite of aluminum and boron carbide, is the principal constituent material of the fuel basket, both as structural material and neutron absorber material. Two interchangeable fuel basket models, designated F-32 and F-37, contain either 32 or 37 Pressurized Water Reactor (PWR) fuel assemblies respectively, in regionalized and uniform loading patterns. The fuel basket features a honeycomb structure and flux traps between some but not all cells.

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9325 23 71-9325 USA/9325/B(U)F-96 2

OF 68 5.(a)(2) Description (continued)

Packaging Body The cylindrical steel shell containment system is welded to a bottom steel baseplate and a top steel forging machined to receive two independent steel closure lids, with each lid being individually designated as a containment boundary component. The outer surface of the the cask inner shell is buttressed with a monolithic shield cylinder for gamma and neutron shielding. Each closure lid features a dual metallic self-energizing seal system designed to ensure its containment and moderator exclusion functions. For this package, the inner closure lid inner seal and the inner closure lid vent/drain port cover inner seals are the containment boundary components on the inner lid; the outer closure lid inner seal and the outer closure lid access port plug seal are the containment boundary components on the outer lid.

Impact Limiters The HI-STAR 180 package is fitted with two impact limiters fabricated of aluminum honeycomb crush material completely enclosed by an all-welded austenitic stainless stainless-steel skin. Both impact limiters are attached to the cask with 16 bolts.

(3)

Drawings The packaging shall be constructed and assembled in accordance with the following Holtec International Drawings Numbers:

(a) HI-STAR 180 Cask Drawing No. 4845, Sheets 1-67, Rev. 1113 (b) F-37 Fuel Basket Drawing No. 4847, Sheets 1-4, Rev. 78 (c) F-32 Fuel Basket Drawing No. 4848, Sheets 1-4, Rev. 78 (d) HI-STAR 180 Impact Limiter Drawing No. 5062, Sheets 1-5, Rev. 67 5.(b)

Contents (1)

Type, Form, and Quantity of Material (a)

(a)

Only undamaged UO2 and MOX PWR fuel assemblies, with a Zr cladding type, or dummy fuel assemblies, meeting the specifications and requirements provided in Conditions 5.b(1)(b) through 5.b(1)(jk), and with the characteristics listed in Table 1a below, are authorized for transportation..

OR

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9325 23 71-9325 USA/9325/B(U)F-96 3

OF 68 5.(b)(1)(a) continued Only undamaged UO2 and MOX PWR fuel assemblies, with a Zr cladding type, or dummy fuel assemblies, meeting the specifications and requirements provided in Conditions 5.b(1)(b) through 5.b(1)(j), and with the characteristics listed in Table 1a below of which up to 2 basket cell locations may contain quivers with the characteristics in Table 1b below meeting the additional specifications and requirements provided in Condition 5.b(1)(k) through 5.b(1)(m).

Table 1a - PWR Fuel Assembly Characteristics Fuel Assembly Type 14x14 Design Initial Heavy Metal Mass (kg/assembly) 341 Maximum Maximum Fuel Assembly Mass (kg) 500 No. of Fuel Rod Locations 179 Fuel Rod Clad O.D. (mm) 10.72 Nominal Fuel Rod Clad I.D. (mm) 9.61 Nominal Fuel Pellet Diameter (mm) 9.31 Nominal Fuel Rod Pitch (mm) 14.224 Nominal Active Fuel Length (mm) 3070 Nominal Maximum Fuel Assembly Length (mm) 3524 Nominal Fuel Assembly Width (mm) 199.3 Nominal No. of Guide and/or Instrument Tubes 17 Guide/Instrument Tube Thickness (mm) 0.285 Nominal Minimum Cooling Time for Assemblies with Zr Guide/Instrument Tubes (years) 3 2 Minimum Cooling Time for Assemblies with Stainless Steel Guide/Instrument Tubes (years) 15 Minimum Cooling Time for Assemblies with NFH insertion more than 38 cm into the active region during full power operation (years) 20 Table 1b - Quiver and Quiver Content Characteristics Source of separated fuel rods See Table 1a Maximum number of separated fuel rods per quiver 48 Maximum Loaded Quiver Mass (kg) 500 Maximum Quiver Length (mm) 3496 Nominal

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9325 23 71-9325 USA/9325/B(U)F-96 4

OF 68 5.(b)(1) continued (b)

Damaged fuel assemblies, i.e., assemblies with known or suspected cladding defects greater than pinhole leaks or hairline cracks and which cannot be handled by normal means, as well as fuel debris, non-fuel hardware and neutron sources are not authorized contents.

(c)

The maximum initial enrichment of any UO2 assembly is 5.0 percent by weight of uranium-235.

(d)

Each loaded MOX fuel assembly must meet one of the criteria sets (1-4) from Table 2 and one of the criteria sets (1-3) from Table 3. MOX fuel isotopic compositions in Table 2 are bounding for dose and decay heat and used to establish the loading patterns. MOX fuel isotopic characteristics in Table 3 are bounding for criticality purposes.

Table 2 Isotopic Characteristics of MOX Fuel Isotopic Composition (gram/assembly)

Criteria Isotope 1

2 3

4 Pu238 700 202 202 202 Pu239 1280813000 11000 74387524 8000 Pu240 57265800 3800 1700 1700 Pu241 2300 1600 1250 1600 Pu242 1900 751 700 751 U235 724730 720 2100 720 U238 298007297000 320200 326000 326000

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9325 23 71-9325 USA/9325/B(U)F-96 5

OF 68 5.(b)(1)(d) continued Table 3 Isotopic Characteristics of MOX Fuel Criteria Composition 1

2 3

Pu-239 (g/kg-HM) 39.5 49 26 Pu-238/Pu-239 (g/g) 0.0 0.015 0.0 Pu-240/Pu-239 (g/g) 0.27 0.38 0.21 Pu-241/Pu-239 (g/g) 0.15 0.20 0.16 Pu-242/Pu-239 (g/g) 0.012 0.06 0.012 Am-241(g/kg-HM) 0.0 0.0 0.0 U-235 (g/kg-HM) 7.1 7.1 7.1 (e)

The post-irradiation minimum cooling time, maximum burnup, maximum decay heat load, and minimum initial enrichment per assembly are listed in Tables 1.2.8 and 1.2.9 of the application. The F-32 and F-37 fuel basket cell numbering and quadrant identification are depicted in Figures 1.2.3 and 1.2.4 of the application, respectively.

(f)

Regions, cells and quadrants for regionalized loading of the F-32 and F-37 baskets are identified in Tables 1.2.6.a and 1.2.6.b of the application. Table 1.2.7a of the application provides the minimum burnup requirements for the F-37 basket, based on initial enrichment for various configurations. Table 1.2.7b of the application provides maximum initial enrichment limits for fresh UO2 Fuel Assemblies for certain configurations.

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9325 23 71-9325 USA/9325/B(U)F-96 6

OF 68 5.(b)(1) continued (g)

In-core operating limits for those assemblies that need to meet the burnup requirements in Table 1.2.7a of the application are as follows:

Parameter Requirement Assembly Average Specific Power 39.4 MW/MTU Assembly Average Moderator Temperature 597º K Maximum Assembly Average Fuel Temperature 1127ºK Core Average Soluble Boron Concentration 700 ppmb (h)

For those spent fuel assemblies that need to meet the burnup requirements specified in Table 1.2.7a of the application, a burnup verification shall be performed either in accordance with Section 6.F.3.1 or 6.F.3.2 of the application.

(i)

Allowable loading patterns and fuel specifications for each basket region are referenced in Tables 1.2.8 and 1.2.9 of the application. Alternative fuel specifications for each regional loading pattern are presented in Table 1.2.10 of the application.

(j)

The maximum decay heat for either the F-32 or F-37 basket model is 32 kW per basket, with 8 kW maximum decay heat per basket quadrant.

(k)

Partially loaded casks must not have more than 12 empty storage locations (i.e. the equivalent mass of 12 fuel assemblies) with contents evenly spread to the extent practical. Dummy fuel assemblies may be used to achieve the required mass.

(l)

Quiver is a hermitically sealed container for individual fuel rods which have been removed from their assembly. The fuel rods may be leaking, broken or fragmented (i.e. fuel debris) or purposely punctured to relieve internal pressure.

(m)

Up to two quivers are allowed in F-32 in cells 1 and 32 or 10 and 23 (See Figure 1.2.3 of the application). Up to two quivers are allowed in F-37 in cells 4 and 34 or 8 and 30 (See Figure 1.2.4 of the application).

(j)(n)

The maximum decay heat per quiver in either F-32 or F-37 basket model is in accordance with basket cell heat loads corresponding to allowable quiver locations in Tables 1.2.8 and 1.2.9 of the application.

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9325 23 71-9325 USA/9325/B(U)F-96 7

OF 68 5.b.(2) Maximum Quantity of Material Per Package (a) 32 or 37 PWR fuel assemblies, as described in 5(b)(1), in the F-32 or F-37 basket respectively.

(b) 32 or 37 PWR fuel assemblies, as described in 5(b)(1), in the F-32 or F-37 basket respectively of which up to 2 fuel assemblies may be replaced by up to 96 separated fuel rods.

5.(c)

Criticality Safety Index (CSI) is=

0.0

6.

In addition to the requirements of Subpart G of 10 CFR Part 71:

(a)

The package shall be prepared for shipment and operated in accordance with Chapter 7 of the application.

(b)

The package shall meet the acceptance tests and be maintained in accordance with Chapter 8 of the application. For the bend test qualification of a representative friction stir weld sample, the sample must meet the visual acceptance criteria of ASME Section III, Subsection NG 5362.

7.

The personnel barrier shall be installed and remain installed while transporting the package if necessary to meet package surface temperature and/or package dose rates requirements.

8.

The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.

9.

Transport by air of fissile material is not authorized.

10.

The package may be used in the U.S. for shipment of UO2 fuel meeting the above specifications.

11.

Expiration Date: October 31, 2019TBD

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9325 23 71-9325 USA/9325/B(U)F-96 8

OF 68

REFERENCES:

Holtec International application Safety Analysis Report on the HI-STAR 180 Package, Revision No. 6TBD, dated April 21, 2014TBD.

Supplement dated: August 14, 2014.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

/RA/

Michele SampsonTBD, Chief Spent Fuel Licensing Branch Division of Spent Fuel Storage and TransportationDivision of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Date: October 3, 2014TBD