ML18262A127
| ML18262A127 | |
| Person / Time | |
|---|---|
| Site: | 07109372 |
| Issue date: | 09/06/2018 |
| From: | Framatome |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| TJT:18:031 FS1-0039661, Rev 2 | |
| Download: ML18262A127 (24) | |
Text
CW01L Rev. 5.2 - 24/08/18 This text shall no be visible - Adjust frames over to ensure signature block will completely cover this text This text shall no be visible - Adjust frames over to ensure signature block will completely cover this text IDENTIFICATION REVISION Framatome Fuel FS1-0039661 2.0 TOTAL NUMBER OF PAGES: 24 TN-B1 Shielding Evaluation ADDITIONAL INFORMATION:
TN-B1; Docket No. 71-9372; FS1-0015020 PROJECT DISTRIBUTION TO PURPOSE OF DISTRIBUTION HANDLING None CATEGORY DAD - Design Analysis Documentation STATUS ROLES NAMES DATES ORGANIZATIONS SIGNATURES AUTHOR REVIEWER APPROVER ROYCE Christopher L.
SAKACH Vonna TATE Tim RELEASE DATA:
Classification Export AL: 0E001 ECCN: 0E001 Les marchandises portant la désignation "AL inégal N" sont soumises la réglementation européenne ou allemande en matire de contrle des exportations au sein ou hors de l'UE. Les marchandises portant la désignation "ECCN inégal N" sont soumises la réglementation américaine. Les marchandises portant les désignations "AL:N" ou "ECCN:N" peuvent, selon la destination ou l'utilisation finales du produit, également tre soumises autorisation.
Export classification AL: 0E001 ECCN: 0E001 Goods labeled with AL not equal to N are subject to European or German export authorization when being exported within or out of the EU. Goods labeled with ECCN not equal to N are subject to US reexport authorization. Even without a label, or with label AL: N or ECCN: N, authorization may be required due to the final whereabouts and purpose for which the goods are to be used.
SAFETY RELATED DOCUMENT:
1
CHANGE CONTROL RECORDS:
This document, when revised, must be reviewed or approved by following regions:
France:
USA:
Germany:
N Y
N
Exportkennzeichnung AL: 0E001 ECCN: 0E001 Die mit "AL ungleich N" gekennzeichneten Güter unterliegen bei der Ausfuhr aus der EU bzw.
innergemeinschaftlichen Verbringung der europischen bzw. deutschen Ausfuhrgenehmigungspflicht. Die mit "ECCN ungleich N" gekennzeichneten Güter unterliegen der US-Reexportgenehmigungspflicht. Auch ohne Kennzeichen, bzw. bei Kennzeichen "AL: N" oder "ECCN: N", kann sich eine Genehmigungspflicht, unter anderem durch den Endverbleib und Verwendungszweck der Güter, ergeben.
This document is electronically approved. Records regarding the signatures are stored in the Fuel BU Document Database. Any attempt to modify this file may subject employees to civil and criminal penalties. EDM Object Id:
- Release date (YYYY/MM/DD) :
[Western European Time]
Role Name Date (YYYY/MM/DD) Organization
FDD
- ULWHU 52<&(&KULVWRSKHU
)UDPDWRPH,QF
5HYLHZHU 6$.$&+9RQQD
)UDPDWRPH,QF
$SSURYHU 7$7(7LPRWK\\
)UDPDWRPH,QF
N° FS1-0039661 Rev. 2.0 TN-B1 Shielding Evaluation Handling:
None Page 2/24 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page REVISIONS REVISION DATE EXPLANATORY NOTES 2.0 See 1st page release date Corrected typographic error in the table is Section 2.
1.0 9/4/2018 New document
N° FS1-0039661 Rev. 2.0 TN-B1 Shielding Evaluation Handling:
None Page 3/24 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page TABLE OF CONTENTS
- 1.
PURPOSE...................................................................................................................................... 4
- 2.
SUMMARY
OF RESULTS.............................................................................................................. 4
- 3.
BACKGROUND............................................................................................................................. 4
- 4.
ASSUMPTIONS AND MODEL SIMPLIFICATIONS....................................................................... 5
- 5.
SOFTWARE................................................................................................................................... 6
- 6.
CALCULATIONS........................................................................................................................... 6 6.1.
INPUTS................................................................................................................................................... 6 6.2.
OUTPUTS............................................................................................................................................... 6
- 7.
RESULTS....................................................................................................................................... 6 APPENDIX A: MECHANICAL DESIGN INPUTS.................................................................................. 7 APPENDIX B: URANIUM DESIGN INPUT............................................................................................ 8 APPENDIX C: CONCEPTUAL INPUT............................................................................................... 10 APPENDIX D: MICROSHIELD INPUTS AND OUTPUTS................................................................... 13 REFERENCES 1 FS1-0015020 Revision 1.0, TN-B1 Shipment of ATRIUM 11 Assemblies 2 TJT 16:08 ltr Docket No. 71-9372, AREVA TN-B1 Shipping Container, Application For Approval For Incorporation Of ATRIUM 11 Fuel Assemblies. Dated 18 November 2016 3 TJT 17:007 ltr Docket No. 71-9372, AREVA TN-B1 Shipping Container, Application For Approval For Incorporation Of ATRIUM 11 Fuel Assemblies. Dated 17 February 2017 4 FS1-0014159 Revision 8.0, Framatome TN-B1 Docket No. 71-9372 Safety Analysis Report 5 FS1-0025122 Revision 1.0, AREVA TN-B1 ATRIUM-11 Fuel Assembly Shipping Container Drop Analyses
N° FS1-0039661 Rev. 2.0 TN-B1 Shielding Evaluation Handling:
None Page 4/24 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page
- 1.
PURPOSE Reference (1) TN-B1 Shipment of ATRIUM 11 Assemblies was a shielding evaluation done to demonstrate that the ATRIUM 11 Lead Test Assembly (LTA) shipments would meet the dose rate limits of 10 CFR 71.47(a),
10 CFR 71.51(a)(2), and 49 CFR 173.441(a). This evaluation, because of the assumptions made in the evaluation, was initially considered adequate to meet the requirements when an application to modify TN-B1 CoC 9372 (USA/9372/B(U)F-96 to incorporate the ATRIUM 11 (see references (2) and (3)) was submitted.
Upon further review it was determined that the correlation in reference (1) and the allowed package content of the TN-B1 shown in reference (4) FS1-0014159 AREVA TN-B1 Docket No. 71-9372 Safety Analysis Report could be more specific. It was then decided to repeat the analysis of reference (1) to provide an improved analysis with a direct correlation to the defined package limits content of the TN-B1.
- 2.
SUMMARY
OF RESULTS The results of these analyses show shipments of ATRIUM 11 will meet the dose rate limits of 10 CFR 71.47(a),
10 CFR 71.51(a)(2), and 49 CFR 173.441(a) for both the normal conditions of transport (NCT) and the hypothetical accident conditions (HAC).
Normal Conditions of Transport Package surface mSv/h (mrem/h) 1 Meter from Package Surface mSv/h (mrem/h)
Radiation Top Side Bottom Top Side Bottom Gamma
.4591 (45.9)
.405 (40.5)
.245 (24.6)
.036 (3.51)
.02 (2.02)
.003 (.27) 10 CFR 71.47(a) limit 2 (200) 2 (200) 2 (200)
These results are consistent with the results of reference (1).
- 3.
BACKGROUND The allowed contents of the TN-B1 are found in section 1.2.3 Contents of reference (4). The content is generally described as having a maximum of two fuel assemblies which are placed in each package. The assemblies are configured either in 8x8, 9x9,10x10 or 11x11 arrays or as loose rods contained in a cylinder, The nuclear fuel pellets are located in fuel rods and contained in the fuel assembly. The fuel pellets are either UO2 or UO2-Gd2O3.
The fuel may be of either Type A or Type B content. When the contents of the packaging is commercial grade uranium or other uranium materials and the A2 value is not exceeded, the packaging may be considered Type A. When the contents of the packaging includes enriched reprocessed uranium or other origin uranium not exceeding the values in Table 1-3 Type B Quantity of Radioactive Material of reference (4), the packaging is considered Type B. Table 1-3 Type B Quantity of Radioactive Material is reproduced as Appendix B of this document.
For the Hypothetical Accident Condition (HAC), reference (5) FS1-0025122 AREVA TN-B1 ATRIUM-11 Fuel Assembly Shipping Container Drop Analyses was reviewed. It was noted that this evaluation concluded that
N° FS1-0039661 Rev. 2.0 TN-B1 Shielding Evaluation Handling:
None Page 5/24 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page the ATRIUM 11 Fuel Assemblies shipped within the AREVA TN-B1 shipping container deform but still maintain cladding integrity and structural stability while complying with the 10 CFR and ASME structural code requirements. The deformation noted would not cause any significant variation that would result in a lack of conservatism as compared to the analysis.
- 4.
ASSUMPTIONS AND MODEL SIMPLIFICATIONS MicroShield can only handle very simple geometries. Hence, it was necessary to assume a rectangular volume that would envelop the uranium portions of the assembly. These dimensions were provided in Appendix A. The uranium mass was smeared throughout this volume, i.e. had a constant density.
It was assumed that all of the uranium in the assemblies was entirely BLEU. BLEU material is the most restrictive mixture of material processed at Framatome. This includes slightly irradiated fuel. All fuels at Framatome, other than BLEU meet ASTM C-996 standards for isotopic makeups. The isotopic make-up of BLEU varies, but was assumed to be at the limits for U-232, U-234, U-235, and U-236 shown in Table 1 of Appendix B.
Both UF6 and BLEU may contain gamma radiation from fission products and alpha activity from neptunium and plutonium (see ASTM C-996 section 4.5). For gamma emitters the limiting content is shown in Table 1 of Appendix B. The dose rate from BLEU varies with time due to the build-in and decay of daughters. The principal nuclide of concern is Tl-208, a constituent of the U-232 decay chain, which emits a number of gamma rays, including a 2.614 MeV gamma with a 100% yield. The peak dose rate occurs roughly 10.25 years after uranium purification. MicroShield was used to calculate the activities of the daughters at 10.25 years of age, and these were subsequently used in the calculations.
Additional radionuclides were added based on the ASTM C-996, C-787, C-1295 standards for irradiated UF6 and their subsequent analysis. These radionuclides are reflected in Table 2 of Appendix B. Feed and product fuel at Framatome meet this requirement. Calculations were performed at the limits of the feed material.
The model conservatively assumed no spacing or shielding from the TN-B1 shipping container.
Only one set of calculations were made for each dose point. Only credit was taken for shielding from Uranium, one thickness of the Zirconium Cladding. Additionally, distances between the fuel and the outer layer of the container were ignored. The calculations represent two unshielded fuel assemblies. This is extremely conservative and displays the lack of a need of additional shielding or additional accident scenario calculations.
No credit was taken for any other materials present including the top and bottom nozzles. Distances were taken from RAJ-11 DWG NO. 105E3737 REV 6 and distances and densities are shown in Appendix C.
MicroShield calculates both exposure rates and dose rates. The exposure rates are higher than the dose rates. In the comparison with DOT limits, the exposure rates were used as dose rates.
Manufacturing tolerances of both the TN-B1 and the ATRIUM 11 fuel affect the actual dose rates. However, given the conservatisms employed in the analysis and the comparison of results with regulatory limits, variations within tolerances are not a concern.
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- 5.
SOFTWARE MicroShield Version 8.03 was used to calculate the activities of the uraniums, uranium daughters, potential transuranics and daughters and mixed fission products and daughters and the associated dose rates.
MicroShield is a comprehensive photon/gamma ray shielding and dose assessment program that is widely used for designing shields and estimating source strength from radiation measurements.
MicroShield is fully interactive and utilizes extensive input error checking. Integrated tools provide graphing of results, material and source file creation, source inference with decay (dose-to-Ci calculations accounting for decay and daughter buildup), and projection of exposure rate versus time as a result of decay, access to material and nuclide data.
- 6.
CALCULATIONS MicroShield Version 8.03 was used to estimate the dose rates at midpoints of the ends, top, and side surfaces and at a distance of 1 meter from the fuel assemblies. (Midpoints should be where the dose rates are the highest.) The dose rates calculated using MicroShield were then compared to NRC and DOT limits. If the dose rates were less than NRC and DOT dose limits, no additional shielding would be needed.
6.1.
INPUTS The inputs for MicroShield are shown in Appendices A, B, C and D.
6.2.
OUTPUTS The outputs from each run from MicroShield are contained in Appendix D.
- 7.
RESULTS The results of these analyses show shipments of ATRIUM 11 will meet the dose rate limits of 10 CFR 71.47(a),
10 CFR 71.51(a)(2), and 49 CFR 173.441(a) for both the normal conditions of transport (NCT) and the Hypothetical Accident Condition (HAC).
Normal Conditions of Transport Package surface mSv/h (mrem/h) 1 Meter from Package Surface mSv/h (mrem/h)
Radiation Top Side Bottom Top Side Bottom Gamma
.459 (45.9)
.405 (40.5)
.246 (24.6)
.36 (3.61)
.02 (2.02)
.003 (.27) 10 CFR 71.47(a) limit 2 (200) 2 (200) 2 (200) 49 CFR 173.441 (a) Limit 2 (200) 2 (200) 2 (200) 10 CFR 71.51(a)(2) Limit 10 (1000) 10 (1000) 10 (1000)
Note: Since the packaging is not modelled, the NCT radiation results presented above do not result in a lack of conservatism when compared against the HAC limits.
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None Page 7/24 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page APPENDIX A: Mechanical Design Inputs TN-B1 specifications came from GNF drawings (see Reference 1) x RAJ-11 Outer/inner Container Assembly Licensing Drawing 105E3737, dated 03-26-04 x
RAJ-11 Outer Container Main Body Assembly Licensing Drawing 105E3738, dated 03-26-04 x
RAJ-11 Outer Container Lid Assembly Licensing Drawing 105E3743, dated 03-26-04 x
RAJ-11 Inner Container Lid Assembly Licensing Drawing 105E3745, dated 03-26-04 x
RAJ-11 Inner Container Parts Assembly Licensing Drawing 105E3746, dated 03-26-04 x
RAJ-11 Inner Container Lid Assembly Licensing Drawing 105E3747, dated 03-26-04
N° FS1-0039661 Rev. 2.0 TN-B1 Shielding Evaluation Handling:
None Page 8/24 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page APPENDIX B: Uranium Design Input Table 1 Type B Quality of Radioactive Material (Based in 11x11 Fuel Assembly)
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None Page 9/24 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page Table 2 Type B Quantity of Target non fuel Radioactive Material (Based in 11x11 Fuel Assembly)
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None Page 10/24 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page APPENDIX C: Conceptual Input Misc Data Atrium 11 Value Units Uranium Weight (excluding Gd) 248 kg Assembly Length 12.761 cm Assembly Width 12.761 cm Assembly Height 381 cm Zirc Clad Shielding Lengtth 0.57 cm Zirc Clad Shielding Density 6.49 g/cm3 Steel Wall Shielding 0.2 cm Density of Steel Wall 7.874 g/cm3
N° FS1-0039661 Rev. 2.0 TN-B1 Shielding Evaluation Handling:
None Page 11/24 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page From RAJ-11 DWG NO. 105E3737 REV 6 All units in mm
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