ML19259A233

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Letter to T. Tate Revision No. 12 of Certificate of Compliance No. 9319, for the Model Nos. MAP-12 and MAP-13 Transportation Packages (W/Enclosure 2)
ML19259A233
Person / Time
Site: 07109319
Issue date: 09/17/2019
From: John Mckirgan
Spent Fuel Licensing Branch
To: Travis Tate
Framatome
Saverot P
References
EPID L-2019-LLA-0056
Download: ML19259A233 (5)


Text

OFFICIAL USE ONLY - SECURITY RELATED INFORMATION September 17, 2019 Framatome Inc.

Mr. Timothy J. Tate 2101 Horn Rapids Road Richland, WA 99354

SUBJECT:

REVISION NO. 12 OF CERTIFICATE OF COMPLIANCE NO. 9319, FOR THE MODEL NOS. MAP-12 AND MAP-13 TRANSPORTATION PACKAGES

Dear Mr. Tate:

As requested by your amendment request dated May 24, 2019, supplemented August 6, 2019, enclosed is Certificate of Compliance No. 9319, Revision No. 12, for the Model Nos. MAP-12 and MAP-13 packages. Changes made to the enclosed certificate are indicated by vertical lines in the margin. The staff's safety evaluation report is also enclosed.

The approval constitutes authority to use the package for shipment of radioactive material and for the package to be shipped in accordance with the provisions of Title 49 of the Code of Federal Regulations (49 CFR) 173.471. Those on the attached list have been registered as users of the package under the general license provisions of 10 CFR 71.17 or 49 CFR 173.471.

If you have any questions regarding this certificate, please contact me or Pierre Saverot of my staff at (301) 415-7505.

Sincerely,

/RA Bernie White Acting for/

John McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-9319 EPID No. L-2019-LLA-0056 Enclosure 3 transmitted herewith

Enclosures:

contains Official Use Only -

1. CoC No. 9319, Rev. No. 12 Security-Related Information.
2. Safety Evaluation Report When separated from Enclosure 3,
3. Registered Users this document is uncontrolled.

cc w/encls 1 & 2: R. Boyle, DOT J. Shuler, DOE c/o L.F. Gelder Registered Users OFFICIAL USE ONLY - SECURITY RELATED INFORMATION

OFFICIAL USE ONLY - SECURITY RELATED INFORMATION T. Tate

SUBJECT:

REVISION NO. 12 OF CERTIFICATE OF COMPLIANCE NO. 9319, FOR THE MODEL NOS. MAP-12 AND MAP-13 TRANSPORTATION PACKAGES, DOCUMENT DATE: September 17, 2019 DISTRIBUTION: SFST r/f ADimitriadis RI B. Bonser, RII M. Kunowski, RIII GWarnick, RIV G:\SFST\PART 71 CASEWORK\Model MAP-12 and MAP-13 Docket 71-9319\71-9319.R12.LTR&SER.docx; 71-9319.R12.doc EPID : Closes L-2019-LLA-0056 ADAMS Package No.: ML19259A236 LTR AND SER Accession No.: ML19259A233 CoC Accession No.: ML19259A232 OFC: DSFM DSFM DSFM DSFM DSFM NAME: PSaverot SFigueroa RRodriguez DDunn YDiaz-Sanabria DATE: 08/13/2019 09/12/2019 08/21/2019 09/06/2019 09/09/2019 OFC: DSFM DSFM BWhite NAME: MRahimi for JMcKirgan DATE: 09/09/2019 09/17/2019 OFFICIAL RECORD COPY OFFICIAL USE ONLY - SECURITY RELATED INFORMATION

SAFETY EVALUATION REPORT Docket No. 71-9319 Model Nos. MAP-12 and MAP-13 Certificate of Compliance No. 9319 Revision No. 12

SUMMARY

By letter dated May 24, 2019, Framatome Inc., (or the applicant) requested an amendment to Certificate of Compliance (CoC) No. 9319 for the MAP packaging to include a weight difference between the MAP-12 and MAP-13 packages, update packaging licensing drawings, include additional information on the ball lock pins and discuss ball lock pin brittle fracture, and provide regulatory consistency with the definition of the slightly contaminated uranium contents similarly to what was approved for the Model No. TN-B1 package.

The application was revised on August 6, 2019 in response to staffs requests for clarification regarding an apparent discrepancy with respect to the description of the performance of the MAP package closure pins during drop testing and the proposed weight margins associated with fabrication tolerances.

The staff reviewed the revised application dated August 6, 2019, and determined that the changes do not affect the ability of the package to meet the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 71. The certificate has been updated to Revision No. 12.

EVALUATION The scope of the structural review was limited to the evaluation of weight margins associated with fabrication tolerances. The staff reviewed enclosures, additions and edits to the application, including licensing drawings for completeness and technical sufficiency. In Section 2.12.4 of the application, the applicant justified the addition of 300 lbs. to the gross package weight of the MAP-13, from 8630 lbs. to 8930 lbs., by (i) the additional center cover plates (150 lbs.) that were accounted for during the drop test campaign (container CTU3), and (ii) 150 lbs.

estimated for fabrication tolerances. The applicant discussed how the gross package weight was calculated for the MAP-13 package: weights for individual components were generated by multiplying the volume of each component by their respective density while weight information from the supplier was used for components, such as fasteners and rivets, purchased commercially. The applicant further discussed that variations in material sizes, particularly sheet/plate thickness, during fabrication could represent a significant variation in weight; therefore, an additional 150 lbs. (above the 150 lbs. previously accounted for the center cover plates) to the MAP-13 gross package weight should provide sufficient margin to account for any discrepancy. The staff finds that the applicant properly characterized how additional weights were considered and calculated in the analysis. As such, the resulting gross weight of the package provides a reasonable margin to account for unexpected fabrication tolerances.

In Section 2.5.1, the applicant included the new gross package weight of 8930 lbs. into the calculation for lifting devices and compression and demonstrated sufficient safety margins in all Enclosure 2

2 cases considered with the additional weight. The staff reviewed the calculations and finds that margins of safety are maintained. In Section 2.5.4, the applicant stated that the additional weight will not influence the packages center of gravity calculation since the increased weight, related to fabrication tolerances, would be uniformly distributed.

The staff reviewed the applicants assessment and concludes that (i) the additional weight of 300 lbs. -from 8630 lbs. to 8930 lbs.- is minimal in relation to the overall gross weight of the MAP-13 package, (ii) it is reasonable to consider it to be uniformly distributed, and thus would not have any adverse effect on the package center of gravity calculation. In Section 2.12.4, the applicant stated that the results of previous drop tests, although performed at 8630 lbs., have enough margin to encompass the 300 lbs. added weight. In the physical drop tests, the impact limiter only deformed about half of its full capacity.

The staff reviewed the performance of the impact limiters and finds that there is reasonable assurance that the additional 300 lbs., i.e., about 3% of the MAP-13 gross weight, would not challenge the impact limiters. Based on review of the statements and representations in the application, the NRC staff concludes that the structural design has been adequately described and evaluated and that the package has adequate structural integrity and continues to meet the requirements of 10 CFR Part 71.

The staff also reviewed the list of drawing changes and the updated drawings for the MAP-12/13 package. The staff determined that the drawing changes were limited to minor corrections, clarifications and updates to material specifications. The staff determined that the revised drawings were consistent with the guidance in NUREG/CR-5502 and contain material specifications, dimensions and tolerances, welding specifications and nondestructive examination requirements.

The staff reviewed the updated information on the ball lock pins used to secure the upper and lower sections of the MAP-12/13 package. The staff reviewed the results of hypothetical accident condition tests and determined that the MAP-12/13 package specifies an adequate number of ball lock pins to secure the upper and lower package sections. The staff reviewed the material specifications for the ball lock pins and determined that the combination of material used, which include a precipitation hardened stainless steel and an austenitic stainless steel, would not be susceptible to brittle fracture under low temperature conditions.

The staff determined that the evaluation of the performance of the ball lock pins is acceptable based on the material specifications, package testing results, and the package design which does not rely on the ball lock pins to maintain containment function during normal conditions of transport or under accident conditions.

The staff reviewed the change in the allowable normal operational temperature for the aluminum alloy fuel cavity doors. The staff determined that the revised maximum allowable normal temperature for the fuel cavity doors was acceptable because the maximum temperature is consistent with the allowable temperatures for the aluminum alloy in the ASME B&PV Code Section II Part D.

The staff reviewed the applicants justifications for allowing a trace amount of material as defined in Table 1 of this CoC in the UO2 fuel and finds the justifications presented to be acceptable. Although the pregnancy of some of the isotopes, e.g. U-232, in the slightly contaminated uranium will elevate the A2 value and the radiation sources, the limits in Table 1 are to be applied at the time of shipment, thus not allowing a significant amount of time for the

3 build up of high gamma emitting daughter products. It is unrealistic to specify radionuclide values exactly at the time of shipment because radioactive daughters are constantly building up; therefore, a trace amount of contaminants is accounted for within the allowable gamma source and this amount will not cause a significant increase in the A2 value and radiation sources.

Based on this reason, the staff determines that the trace amount of material, as defined in Table 1 of the CoC, will not impose significant additional impacts on the safety of the package with respect to the containment and shielding design, and the package will continue to meet the respective parts of the regulatory requirements of 10 CFR Part 71. The trace amount of fissile isotopes, as specified in Table 1, will not also cause significant changes to the neutron multiplication factor, keff, because their quantities are negligible with respect to the criticality safety of the package.

Based on the discussion above, the staff found the applicants proposed changes to the CoC would not affect the ability of the Model No. MAP package to meet the criticality safety requirements of 10 CFR Part 71.

CONDITIONS The following changes were made to the certificate of compliance:

Item No. 3(b) identifies the revised application dated August 6, 2019.

Condition No. 5(a)(2) is revised to update the maximum gross weight of the MAP-13 package to 8,930 lbs.

Condition No. 5(a)(3) is modified to include new revisions of the licensing drawings.

Condition No. 5(b)(1) revises the description of the contents as slightly contaminated uranium with trace quantities limits.

Condition No. 9 has been modified to extend the previous revision of the certificate for approximately one year.

The expiration date of the certificate (Condition No. 10) was not modified.

The References section of the certificate was updated to include the application MAP PWR Fuel Shipping Package, FS1-0038397, Revision 4, dated August 6, 2019.

CONCLUSION Based on the statements and representations in the application, the staff finds that these changes do not affect the ability of the package to meet the requirements of 10 CFR Part 71.

Issued with Certificate of Compliance No. 9319, Revision No. 12, On September 17, 2019.