Revision 2 to Transnuclear, Inc. (TN) Application for Approval of the TN-LC ... · 2020. 8. 14. · A TRANSNUCLEAR AN AREVA COMPANY May 4, 2012 E-32623 U. S. Nuclear Regulatory Commission

ATRANSNUCLEAR

AN AREVA COMPANY

May 4, 2012E-32623

U. S. Nuclear Regulatory CommissionAttn: Document Control DeskOne White Flint North11555 Rockville PikeRockville, MD 20852

Subject: Revision 2 to Transnuclear, Inc. (TN) Application for Approval of the TN-LCTransportation Package, Response to Request for Additional Information (DocketNo. 71-9358; TAC No. L24543)

Reference: Letter from Pierre Saverot (NRC) to Jayant Bondre (TN), "Application forCertificate of Compliance No. 9358 for the Model No. TN-LC Package - Requestfor Additional Information," November 22, 2011 (Docket No. 71-9358; TAC No.L24543)

This submittal provides responses to the request for additional information (RAI) forwarded bythe letter referenced above, with the following enclosures.

* Enclosure 1 provides an affidavit, in accordance with 10 CFR 2.390, specificallyrequesting that you withhold proprietary information included in Enclosures 2, 7, 11, 12and 17 of this submittal from public disclosure. That information may not be used forany purpose other than to support NRC staff review of the application. Public versions ofcertain of these enclosures are discussed below. Because Enclosures 11, 12, and 17are entirely proprietary, no public versions are provided.

* Enclosure 2 provides each NRC RAI item, followed by a TN response.* Enclosure 3 provides a list of additional changes, not associated with the RAI." Enclosure 4 provides a list of each NRC RAI and each additional change item, with the

associated changed Safety Analysis Report (SAR) pages and drawings.* Enclosure 5 is not used.* Enclosure 6 provides a proposed Certificate of Compliance No. 9358.* Enclosure 7 provides a complete TN-LC SAR, Revision 2, proprietary version. The

latest changed areas are indicated by revision bars in the right margin and italics forinserted text, with "Revision 2, 05/12" in the page header.

" Enclosure 8 provides a complete TN-LC SAR, Revision 2, public version.* Enclosure 9 provides a public version of the RAI response enclosure." Enclosure 10 provides a list of files contained on the Enclosure 11 portable hard drive.* Enclosure 11 is a proprietary portable hard drive containing computer files associated

with certain RAI responses.* Additional enclosures 12, and 14 through 17 provide information associated with specific

RAI items.

7135 Minstrel Way, Suite 300, Columbia, MD 21045Phone: 410-910-6900 * Fax: 410-910-6902 D

Transnuclear E-32623 Page 2 of 2May 4, 2012

Should the NRC staff require additional information to support review of this application, pleasedo not hesitate to contact Mr. Kamran Tavassoli at 410-910-6944 or me at 410-910-6881.

Sincerely,

Jayant Bondre, PhDVice President - Engineering

cc: Pierre Saverot, Project Manager, NRC SFST, as follows:

* Two paper copies of this cover letter and Enclosures 1 through 4, 6, 7, 10, 12, and14 through 17

* Seven DVDs containing this cover letter and Enclosures 1 through 4, 6, 7, 10, 12,and 14 through 17

" One copy of the Enclosure 11 computer portable hard drive* One DVD containing this cover letter and Enclosures 1, 3, 4, 6, 8 through 10, and 14

through 16 for the publicly available information

Enclosures:

1. Affidavit Pursuant to 10 CFR 2.3902. Responses to Request for Additional Information (Proprietary)3. List of Additional Items, not Associated with the RAI4. List of RAIs and Additional Items, with Indication of the Associated Changed SAR

Pages and Drawings5. Not used6. Proposed Certificate of Compliance No. 93587. Proprietary Version of the TN-LC Safety Analysis Report, Revision 28. Public Version of the TN-LC Safety Analysis Report, Revision 29. Public Version of Enclosure 2 Responses to Request for Additional Information10. List of Files Contained on Enclosure 1111. Portable Hard Drive of Computer Files Associated with the RAI (Proprietary)12. Technical Report No. 35.01.424, "COMPRESSION TESTS OF REDWOOD SAMPLES,"

by B.W. Gammon and W.A. Dost, April 1985 (Proprietary) (associated with RAI 2.38)13. Not used14. TN-LC Impact Limiter Analysis Plots (associated with RAI 2.24)15. Parker Hannifin Corporation Technical Bulletin No. ORD5743, "Low Temperature FKM

V1289-75, (associated with RAI 2.31)16. CEETAK Test Report No. RC 19356A, "Low Temperature testing of Parker V1 289-75

O-rings," 2 nd September 09 (associated with RAI 2.31)17. Experience in Transportation of Nuclear Spent Fuel (Proprietary) (associated with RAI

1.1 and SAR Section 1.1.2)

Enclosure 1 to TN E-32623

AFFIDAVIT PURSUANTTO 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 authorizedto execute this affidavit, and have reviewed or caused to have reviewed the information which isidentified as proprietary and referenced in the paragraph immediately below. I am submitting thisaffidavit in conformance with the provisions of 10 CFR 2.390 of the Commission's regulations forwithholding this information.

The information for which proprietary treatment is sought is contained in Enclosures 2, 7, 11, 12,and 17 and is listed below:

* Enclosure 2 - Portions of the request for additional information (RAI) responses* Enclosure 7 - Portions of the Safety Analysis Report (SAR)* Enclosure 11 - Computer Hard Drive with Computer Files* Enclosure 12 - Report associated with RAI 2.38* Enclosure 17 - Report associated with RAI 1.1

These documents have been appropriately designated as proprietary.

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

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

1) The information sought to be withheld from public disclosure involves portions of responses torequests for additional information, portions of the Model TN-LC transportation packaging SAR,computer files associated with certain SAR analyses, and reports related to certain RAI responses,all related to the design of the TN-LC transportation packaging, which are owned and have beenheld in confidence by Transnuclear, Inc, or which are owned by others and have been provided inconfidence to Transnuclear, Inc.

2) The information is of a type customarily held in confidence by Transnuclear, Inc. and notcustomarily disclosed to the public. Transnuclear, Inc. has a rational basis for determining thetypes of information customarily held in confidence by it.

3) Public disclosure of the information is likely to cause substantial harm to the competitive positionof Transnuclear, Inc. because the information is related to the design of transportation packaging,the application of which provides a competitive economic advantage. The availability of suchinformation to competitors would enable them to modify their product to better compete withTransnuclear, Inc., take marketing or other actions to improve their product's position or impair

Page 1 of 2

Enclosure I to TN E-32623

the position of Transnuclear, Inc.'s product, and avoid developing similar data and analyses insupport of their processes, methods or apparatus.

Further the deponent sayeth not.

Jant BondreVice President, Transnuclear, Inc.

Subscribed and sworn to me before this 4 th

Page 2 of 2


List of Additional Changes, Not Associated with the RAI

Additional Changes Reason for the Change1 The following caution statement is added to SAR page 7-4: The change is based on TN

actions associated with NRCCAUTION: During vacuum pump system operation, Information Notice 2011-10,personnel should be in the area of loading operations, or in "THERMAL ISSUES

IDENTIFIED DURINGnearby low dose areas, in order to take proper action in the LD INGEO SPENT

even of maluncton.LOADING OF SPENTevent of a malfunction. FUEL STORAGE CASKS"

2 The sixth lettered-bullet on SAR Page 1-8 is changed from Bullets (a) through (e) on"(g)" to "(f)" this page were followed by

bullet (g). This editorial itemis corrected.

3 A few SAR changes were made involving editorial corrections Consistency and accuracy.for misspelled words, inconsistent terminology (such as 231U

replacing U-235), and incorrect cross-referencing.

Page I of 1


List of RAIs and Additional Items,with Indication of the Associated Changed SAR Pages and Drawings

RAI or Additional Change Number Changed SAR Page or Drawing

1.1 1-i

1.1 1-1

1.1 1-2

1.1 1-3

1.1 1-9

1.1 3-5

1.1 3-6

1.1 3-19

1.1 3-47

1.1 3-52

1.1 3-56a

1.1 3-79i

1.1 3-79j

1.1 3-79k

1.1 3-92b

1.1 3-126

1.1 3-127

1.1 5-2

1.1 6-2

1.1 7-7

1.15 2.13.13-3

2.1 2.13.12-7

2.1 2.13.12-8

2.10 2-2

2.10 2-23

2.10 2-32

2.10 2-39

2.10 2.13.14-i

2.10 2.13.14-1

2.10 2.13.14-2

2.10 2.13.14-3

2.10 2.13.14-4

2.10 2.13.14-5

Page 1 of 18




2.10 2.13.14-6

2.10 2.13.14-7

2.10 2.13.14-8

2.10 2.13.14-9

2.10 2.13.14-10

2.12 2.13.1-50

2.12 2.13.1-51

2.12 2.13.1-52

2.12 2.13.1-53

2.12 2.13.1-68

2.12 2.13.1-69

2.12 2.13.1-70

2.12 2.13.1-71

2.13 2.13.1-77

2.13 2.13.1-79

2.14 2.13.5-1

2.14 2.13.5-2

2.15 2.13.5-2

2.16 2-16

2.16 2.13.5-10

2.16 2.13.5-11

2.16 2.13.5-11a

2.16 2.13.5-21

2.16 2.13.5-22

2.16 2.13.5-23

2.16 2.13.5-24

2.16 2.13.5-8

2.16 2.13.5-9

2.17 2.13.7-27

2.17 2.13.7-28

2.17 2.13.7-30

2.18 dwg 65200-71-90 shl

2.18 dwg 65200-71-90 sh2

Page 2 of 18




2.18 2.13.8-5

2.18 2.13.8-7

2.18 2.13.8-13

2.18 2.13.8-14

2.18 2.13.8-15

2.18 2.13.8-15a

2.18 2.13.8-15b

2.18 2.13.8-16

2.18 2.13.8-57a

2.18 2.13.8-57b

2.18 2.13.8-57c

2.19 2.13.11-12

2.19 2.13.11-13

2.19 2.13.11-2

2.19 2.13.11-23

2.19 2.13.11-25

2.19 2.13.11-27

2.19 2.13.11-3

2.19 2.13.11-33

2.19 2.13.11-34

2.19 2.13.11-37

2.19 2.13.11-4

2.19 2.13.11-47

2.19 2.13.11-5

2.19 2.13.11-62

2.19 2.13.11-63

2.19 2.13.11-7

2.19 2.13.11-8

2.2 2-49

2.2 2-8

2.20 2.13.11-12

2.20 2.13.11-13

2.20 2.13.11-2

Page 3 of 18




2.20 2.13.11-23

2.20 2.13.11-25

2.20 2.13.11-27

2.20 2.13.11-3

2.20 2.13.11-33

2.20 2.13.11-34

2.20 2.13.11-37

2.20 2.13.11-4

2.20 2.13.11-47

2.20 2.13.11-5

2.20 2.13-11-62

2.20 2.13.11-63

2.20 2.13.11-7

2.20 2.13.11-8

2.21 2.13.11-12

2.21 2.13.11-13

2.21 2.13.11-2

2.21 2.13.11-21

2.21 2.13.11-23

2.21 2.13.11-25

2.21 2.13.11-27

2.21 2.13.11-3

2.21 2.13.11-33

2.21 2.13.11-34

2.21 2.13.11-37

2.21 2.13.11-4

2.21 2.13.11-47

2.21 2.13.11-5

2.21 2.13.11-62

2.21 2.13.11-63

2.21 2.13.11-7

2.21 2.13.11-8

2.24 2.13.12-12

Page 4 of 18




2.24 2.13.12-13

2.24 2.13.12-14

2.24 2.13.12-17

2.24 2.13.12-24c (new)

2.24 2.13.12-24d (new)

2.24 2.13.12-24e (new)

2.24 2.13.12-24f (new)

2.24 2.13.12-85

2.24 2.13.12-86 (new)

2.24 2.13.12-87 (new)

2.24 2.13.12-88 (new)

2.24 2.13.12-89 (new)

2.25 2.13.12-23

2.26 2.13.12-11

2.26 2.13.12-19

2.26 2.13.12-23

2.26 2.13.12-24

2.26 2.13.12-24a (new)

2.26 2.13.12-24b (new)

2.26 2.13.12-24c (new)

2.26 2.13.12-6

2.3 dwg 65200-71-01 shl

2.3 dwg 65200-71-01 sh2

2.3 dwg 65200-71-01 sh9

2.3 2.13.5-15

2.3 2.13.5-16

2.3 2.13.5-17

2.3 2.13.5-19

2.3 2.13.5-2

2.3 2.13.5-20

2.3 2.13.5-3

2.3 2.13.5-4

2.3 2.13.5-5

Page 5 of 18




2.3 2.13.5-6

2.3 2.13.5-7

2.3 1-5

2.3 2-2

2.3 2-16

2.3 7-2

2.3 7-7

2.31 4-3

2.31 4-7

2.32 8-15

2.35 2.13.10-11

2.35 2.13.10-12

2.35 2.13.10-15

2.35 2.13.10-3

2.35 2.13.10-4

2.35 2.13.10-5

2.39 dwg 65200-71-20

2.4 2-32

2.4 2-39

2.4 2-2

2.4 2-23

2.4 2.13.14-1

2.4 2.13.14-10

2.4 2.13.14-2

2.4 2.13.14-3

2.4 2.13.14-4

2.4 2.13.14-5

2.4 2.13.14-6

2.4 2.13.14-7

2.4 2.13.14-8

2.4 2.13.14-9

2.4 2.13.14-i

2.40 dwg 65200-71-102

Page 6 of 18




2.41 2.13.12-19

2.41 2.13.12-6

2.42 8-9

2.44 2.13.11-11

2.44 2.13.11-3

2.44 2.13.11-4

2.44 2.13.11-5

2.5 2-31

2.5 2-22

2.5 2-27

2.5 2-28

2.6 2-32

2.6 2-39

2.6 2.13.1-14

2.6 2.13.1-15

2.6 2-2

2.6 2-22

2.6 2-23

2.6 2.13.14-1

2.6 2.13.14-10

2.6 2.13.14-2

2.6 2.13.14-3

2.6 2.13.14-4

2.6 2.13.14-5

2.6 2.13.14-6

2.6 2.13.14-7

2.6 2.13.14-8

2.6 2.13.14-9

2.6 2.13.14-i

2.7 2-50

2.7 2-51

2.7 2.13.1-112

2.7 2.13.1-113

Page 7 of 18




2.7 2.13.1-114

2.7 2.13.1-115

2.7 2.13.1-19

2.7 2.13.1-20

2.7 2.13.1-22

2.7 2.13.1-28

2.7 2.13.1-30

2.7 2.13.1-30a

2.7 2.13.1-86a

2.7 2-28

2.8 2-36

2.9 2-40

2.9 2-41

2.9 2-42

2.9 2.13.1-26

2.9 2.13.4-10

2.9 2.13.7-5

2.9 2.13.7-6

2.9 2.13.8-4

2.9 2.13.8-45

2.9 2-6

2.9 2-7

3.4 3-50

3.5 3-11

3.6 3-122

3.6 3-123

3.6 3-124

3.6 3-125

3.6 3-56

3.6 3-76

3.6 3-79

3.6 3-79a

3.6 3-79b

Page 8 of 18




3.6 3-79c

3.6 3-79d

3.6 3-79e

3.6 3-79f

3.6 3-79g

3.6 3-79h

3.6 3-81

3.6 3-92a

3.6 3-14

3.6 3-15

5.1 5.6.4-101

5.1 5.6.4-102

5.1 5.6.4-19

5.1 5.6.4-84 to 92

5.1 5.6.4-9

5.1 5.6.4-9a

5.1 5.6.4-9b

5.1 5.6.4-9c

5.1 5.6.4-9d

5.4 5.6.4-19

5.4 5.6.4-9

5.4 5.6.4-9a

5.4 5.6.4-9b

5.4 5.6.4-9c

5.4 5.6.4-9d

5.5 5.6.4-11 to 18

5.5 5.6.4-18a

5.5 5.6.4-2 to 8

5.5 5.6.4-20

5.5 5.6.4-21

5.5 5.6.4-21a

5.5 5.6.4-31 to 35

5.5 5.6.4-41 to 48

Page 9 of 18




5.5 5.6.4-51 to 59

5.5 5.6.4-62 to 83

5.5 5.6.4-84 to 92

5.5 5.6.4-9

5.5 5.6.4-9a

5.5 5.6.4-9b

5.5 1.4.5-11 to 19

5.5 1.4.5-8

5.5 5-3

5.5 5-16

5.5 5-18

6.2 6.10.3-1

6.2 6.10.3-14

6.2 6.10.3-15

6.2 6.10.3-2

6.2 6.10.3-33

6.2 6.10.3-37

6.2 6.10.3-4

6.2 6.10.3-5

6.2 6.10.3-7

6.2 6.10.3-8

6.3 6.10.4-3

6.3 6.10.4-6

6.3 6.10.4-8

6.3 6.10.4-10

6.3 6.10.4-11

6.3 6.10.4-12

6.3 6.10.4-18

6.3 6.10.4-20

6.3 6.10.4-21

6.3 6.10.4-22

6.3 6.10.4-23

6.3 6.10.4-35

Page 10 of 18




6.3 6.10.4-38

6.3 6.10.4-4

6.3 6.10.4-42

6.3 6.10.4-44

6.3 6.10.4-48

6.3 6.10.4-49a

6.3 6.10.4-49b

6.3 6.10.4-49c

6.3 6.10.4-49d

6.3 6.10.4-49e

6.3 6.10.4-49f

6.3 6.10.4-49g

6.3 6.10.4-49h

6.4 6.10.4-10

6.4 6.10.4-11

6.4 6.10.4-12

6.4 6.10.4-18

6.4 6.10.4-20

6.4 6.10.4-21

6.4 6.10.4-22

6.4 6.10.4-23

6.4 6.10.4-35

6.4 6.10.4-38

6.4 6.10.4-4

6.4 6.10.4-42

6.4 6.10.4-44

6.4 6.10.4-48

6.4 6.10.4-49a

6.4 6.10.4-49b

6.4 6.10.4-49c

6.4 6.10.4-49d

6.4 6.10.4-49e

6.4 6.10.4-49f

Page 11 of 18




6.4 6.10.4-49g

6.4 6.10.4-49h

6.4 6.10.4-6

6.4 6.10.4-8

6.5 1.4.5-10

6.5 1.4.5-7

6.5, Additional Change 3 1.4.5-6

6.6 6.10.1-18

6.6 6.10.1-19

6.6 6.10.1-21

6.6 6.10.3-1

6.6 6.10.3-14

6.6 6.10.3-15

6.6 6.10.3-2

6.6 6.10.3-33

6.6 6.10.3-37

6.6 6.10.3-4

6.6 6.10.3-5

6.6 6.10.3-7

6.6 6.10.3-8

6.6 6.10.4-10

6.6 6.10.4-11

6.6 6.10.4-12

6.6 6.10.4-18

6.6 6.10.4-20

6.6 6.10.4-21

6.6 6.10.4-22

6.6 6.10.4-23

6.6 6.10.4-35

6.6 6.10.4-38

6.6 6.10.4-4

6.6 6.10.4-42

6.6 6.10.4-44

Page 12 of 18




6.6 6.10.4-48

6.6 6.10.4-49a

6.6 6.10.4-49b

6.6 6.10.4-49c

6.6 6.10.4-49d

6.6 6.10.4-49e

6.6 6.10.4-49f

6.6 6.10.4-49g

6.6 6.10.4-49h

6.6 6.10.4-6

6.6 6.10.4-8

6.6 6-9

6.6 6-9a

6.6 6-9b

6.6 6-10

6.6 6-12

6.7 6.10.1-18

6.7 6.10.1-19

6.7 6.10.1-21

6.7 6.10.2-14

6.7 6-9

6.7 6-9a

6.7 6-9b

6.7 6-10

6.7 6-12

6.8 6.10.3-1

6.8 6.10.3-2

6.8 6.10.3-4

6.8 6.10.3-5

6.8 6.10.3-7

6.8 6.10.3-8

6.8 6.10.3-14

6.8 6.10.3-15

Page 13 of 18




6.8 6.10.3-33

6.8 6.10.3-37

7.1 7.7.4-1

8.1 5-5

8.1 5-6

8.1 5-7

8.1 8-5

8.1 8-6

8.1 8-15

8.2 8-14

8.4 8-13

8.4 8-13a

Additional Change 1 7-i

Additional Change 1 7-4



Additional Change 3 1.4.1-1

















Page 14 of 18





































Page 15 of 18


List of RAts and Additional Items,with Indication of the Associated Changed SAR Pages and Drawings





shifted text 1-6

shifted text 1-7

shifted text 1-10

shifted text 1-11

shifted text 1-12

shifted text 1-13

shifted text 2.13.12-10


shifted text 2-23a

shifted text 2-28a

shifted text 3-16

shifted text 3-19a

shifted text 3-47a

shifted text 3-53

shifted text 3-54

shifted text 5.6.4-49 to 50



shifted text 6.10.4-10a




shifted text 7-5

shifted text 7-6

Update TOC 2-i

Update TOC 2-ii

Update TOC 3-i

Update TOC 3-ii

Update TOC 3-iii

Update TOC 3-iv

Page 16 of 18




Update TOC 5-i

Update TOC 8-i

Update TOC 2.13.1-i

Update TOC 2.13.1-ii

Update TOC 2.13.1-iii

Update TOC 2.13.1-iv

Update TOC 2.13.5-i

Update TOC 2.13.7-i

Update TOC 2.13.8-i


Update TOC 2.13.8-iii

Update TOC 2.13.8-iv

update TOC 2.13.11-i

update TOC 2.13.11-ii

update TOC 2.13.11-iii

Update TOC 2.13.12-i

Update TOC 5.6.4-i to iii

Update TOC 6.10.4-i


2.8, 2.19 to 2.23, and 2.44 2.13.11-1

2.8, 2.19 to 2.23, and 2.44 2.13.11-6

2.8, 2.19 to 2.23, and 2.44 2.13.11-9

2.8, 2.19 to 2.23, and 2.44 2.13.11-10

2.8, 2.19 to 2.23, and 2.44 2.13.11-14

2.8, 2.19 to 2.23, and 2.44 2.13.11-15

2.8, 2.19 to 2.23, and 2.44 2.13.11-16

2.8, 2.19 to 2.23, and 2.44 2.13.11-17

2.8, 2.19 to 2.23, and 2.44 2.13.11-18

2.8, 2.19 to 2.23, and 2.44 2.13.11-18a

2.8, 2.19 to 2.23, and 2.44 2.13.11-19

2.8, 2.19 to 2.23, and 2.44 2.13.11-20

2.8, 2.19 to 2.23, and 2.44 2.13.11-23a

2.8, 2.19 to 2.23, and 2.44 2.13.11-23b

Page 17 of 18




2.8, 2.19 to 2.23, and 2.44 2.13.11-23c

2.8, 2.19 to 2.23, and 2.44 2.13.11-37a

2.8, 2.19 to 2.23, and 2.44 2.13.11-38

2.8, 2.19 to 2.23, and 2.44 2.13.11-41

2.8, 2.19 to 2.23, and 2.44 2.13.11-42

2.8, 2.19 to 2.23, and 2.44 2.13.11-43

2.8, 2.19 to 2.23, and 2.44 2.13.11-44

2.8, 2.19 to 2.23, and 2.44 2.13.11-45

2.8, 2.19 to 2.23, and 2.44 2.13.11-64

2.8, 2.19 to 2.23, and 2.44 2.13.11-65

2.8, 2.19 to 2.23, and 2.44 2.13.11-66

2.8, 2.19 to 2.23, and 2.44 2.13.11-67

Page 18 of 18


Proposed Certificate of Compliance No. 9358

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSIOIN(8-2000)10 CFR 71

CERTIFICATE OF COMPLIANCEFOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATION NUMBER Tb. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES

9358 0 71-9358 USA/9358/B(U)F-96 1 OF 4

2. PREAMBLE

a. This certificate is issued to certify that the package (packaging and contents) described in Item 5 below meets the applicable safety standardsset 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.

c. ISSUED TO (Name and Address) d. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION

Transnuclear, Inc. Transnuclear Inc., application dated May, 2011, as7135 Minstrel Way, Suite 300 supplemented.Columbia, MD 21045

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: TN-LC

(2) Description:

The TN-LC transport packaging has been developed for exclusive-use transport of irradiatedtest, research, and commercial reactor fuel in a closed transport vehicle or an ISO container.The fuel is primarily of three basic types: highly enriched aluminum-uranium plate fuel, highlyenriched aluminum-uranium pin fuel, and commercial light water reactor fuel assemblies andfuel rods. Within the package, the fuel is contained in basket structures specifically designedfor each fuel type that provide for suitable heat rejection and criticality control. Weights anddimensions in the following discussion are approximate values, unless otherwise noted.

The TN-LC transport packaging can be used to transport several types of Boiling Water Reactor(BWR), Pressurized Water Reactor (PWR), Mixed Oxide Fuel (MOX), and EvolutionaryPressurized Reactor (EPR) fuel assemblies and/or fuel rods. Additional payloads includeNational Research Universal Reactor (NRU), National Research Experimental Reactor (NRX),Material Test Reactor (MTR), and Training, Research and Isotope, General Atomics Reactor(TRIGA) fuel assemblies and fuel elements. The fuel is contained in specific baskets which fitinto the TN-LC transport cask. The TN-LC transport package is limited to a maximum heat loadof 3.0 kW depending on the fuel types and basket being transported.

The TN-LC transport packaging consists of the following components:

A TN-LC transport cask consists of a containment boundary, structural shell, gammashielding material, and solid neutron shield.

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

* One set of removable trunnions are bolted to plates which are welded to the outer shell ofthe cask. There are also two pocket trunnions in the bottom flange that are used forrotating the cask and may be used for horizontal cask lifting.

* Impact limiters consisting of balsa and redwood blocks encased in stainless steel shells areattached to each end of the TN-LC transport cask during shipment. Each impact limiter isheld in place by eight attachment bolts.

" There are four TN-LC basket designs (TN-LC-NRUX, TN-LC-MTR, TN-LC-TRIGA, and TN-LC-1 FA) with multiple fuel types and configurations for use with the TN-LC transport cask.Details for each basket type are provided in Appendices A.1 through A.4. The baskets aredesigned to drain water readily when loading occurs in a fuel pool. The basket assemblylocates and supports the fuel assemblies/ elements, transfers heat to the cask inner shell,and provides neutron absorption (with or without poison plates) to satisfy nuclear criticalityrequirements.

(3) Drawings

The package shall be constructed and assembled in accordance with the followingTransnuclear, Inc., drawings:

65200-71-01 Revision 2

65200-71-02 Revision 0

65200-71-20 Revision 2

65200-71-21 Revision 0

65200-71-40 Revision 2

65200-71-50 Revision 2

65200-71-60 Revision 2

65200-71-70 Revision 2

65200-71-80 Revision 2

65200-71-90 Revision 2

65200-71-96 Revision 2

65200-71-102 Revision 2

TN-LC Cask Assembly (11 sheets)

TN-LC Transport CaskRegulatory Plate (1 sheet)

TN-LCImpact Limiter Assembly (3 sheets)

TN-LC Transport PackagingTransport Configuration (1 sheet)

TN-LC-NRUX BasketBasket Assembly (5 sheets)

TN-LC-NRUX BasketBasket Tube Assembly (5 sheets)

TN-LC-MTR BasketGeneral Assembly (4 sheets)

TN-LC-MTR BasketFuel Bucket (2 sheets)

TN-LC-TRIGA Basket (5 sheets)

TN-LC-1 FA Basket (5 sheets)

TN-LC-1 FA BWRSleeve and Hold-Down Ring (2 sheets)

TN-LC-1 FA25 Pin Can Basket (5 sheets)

5. (b) Contents of Packaging(1) Type and Form of Material

The TN-LC transport packaging is designed and evaluated to transport the following contents:

* 1 PWR Assembly

* 1 BWR Assembly

* Up to 25 PWR (including MOX and EPR) or BWR fuel rods in a 25 pin can basket

* Up to 26 NRU Fuel Assemblies

" Up to 26 NRX Fuel Assemblies

" Up to 54 MTR Fuel Assemblies

" Up to 180 TRIGA Fuel Elements

(2) Shipments in the TN-LC transport packaging shall not exceed the following limits:

* The fuel and content limits specified in Appendices A.1 through A.4.

* Only one package per conveyance is allowed.

* The maximum decay heat for any payload is 3.0 kW.

* Radiation standards shall meet the requirements of 10 CFR 71.47 and 10 CFR 71.51.

" Surface contamination shall meet the requirements of 10 CFR 71.87.

* The maximum number of fuel rods (pins) in the pin can basket is specified in Appendix A.4.

(3) Special Requirements for Plutonium

The TN-LC transport package may contain plutonium in excess of 0.74 Tbq (20 Ci) per package.As such, the plutonium is in solid form within the fuel matrix and must remain in the solid form.

(4) Criticality Safety Index "100"

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

(a) Each TN-LC transport package shall be both prepared for shipment and operated in accordancewith the Operating Procedures in Chapter 7 of the application.

(b) All fabrication acceptance tests and maintenance shall be performed for the TN-LC transportpackaging in accordance with Acceptance Tests and Maintenance Program in Chapter 8 of theapplication.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION(8-2000)10 CFR 71

CERTIFICATE OF COMPLIANCEFOR RADIOACTIVE MATERIAL PACKAGES

1. a CERTIFICATION NUMBER b. REVISION NUMBER c. DOCKET NUMBER I d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES

9358 0 71-9358 USA/9358/B(U)F-96 4 OF 4

7. Transport by air is not authorized.

8. The TN-LC transport package authorized by this certificate is hereby approved for use under thegeneral license provisions of 10 CFR 71.17.

9. Revision No. 0 of this certificate may be used until tbd.

10. Expiration Date: tbd.

REFERENCES

Transnuclear, Inc., Safety Analysis Report for the TN-LC Transport Packaging, Revision 0, dated May, 2011.

Supplement dated: August, 2011; May, 2012

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

Christine A. Lipa, ChiefLicensing BranchDivision of Spent Fuel Storage and TransportationOffice of Nuclear Material Safetyand Safeguards

Date:

Attachments to CoC 9358:

Appendix A. 1: TN-LC Transport Packaging Contents with TN-LC-NRUX Basket

Appendix A.2: TN-LC Transport Packaging Contents with TN-LC-MTR Basket

Appendix A.3: TN-LC Transport Packaging Contents with TN-LC-TRIGA Basket

Appendix A.4: TN-LC Transport Packaging Contents with TN-LC-1 FA Basket

CoC 9358, Appendix A. 1 Page 1 of 3

CoC 9358, Appendix A.1

TN-LC Transport Packaging Contents with TN-LC-NRUX Basket

(1) Type and Form of Material

Intact or damaged National Research Universal Reactor (NRU) and National ResearchExperimental Reactor (NRX) Mk I fuel assemblies which meet specifications listed inTables A.1-1 and A.1-2, respectively, are authorized for transportation in the TN-LC-NRUX basket. Intact fuel assemblies are fuel assemblies containing fuel rods with noknown or suspected cladding defects greater than hairline cracks or pinhole leaks.Damaged fuel assemblies with cladding damage in excess of pin hole leaks or hairlinecracks are authorized. The extent of the damage is limited such that the total surfacearea of the damaged cladding does not exceed 5% of the total surface area of each rod.

(2) Maximum Quantity of Material per Package

(a) The quantity of material authorized for transport is 26 intact or damaged eitherNRU or NRX Mk I fuel assemblies.

(b) For materials described in A.1(1) above, the approximate maximum payload is122 kg for NRU fuel assemblies and 151 kg for NRX Mk I fuel assemblies.

CoC 9358, Appendix A.1 Page 2 of 3

Table A.1-1

NRU Fuel Specification and Fuel Design Characteristics of AssembliesPermitted in the TN-LC-NRUX Basket

Parameter ValuePhysical and Material Description

Number of Assemblies < 26Number of rods/assembly < 12Assembly length (inch) (1) < 116Nominal Assembly mass (g) 4660Fuel form U-Al235U per rod (g) < 45.4Enrichment (wt.% 235U) < 93Cladding and Spacer Material Al

Thermal and Radiological ParametersCooling Time (years) (2) > 10Depletion (wt.% 23 U) (3) < 80Decay Heat per Assembly (watts) (4) < 15

Notes:

1.2.3.4.

Maximum length of the fuel assembly (unirradiated) for shipmentThe cooling time of the fuel assembly rounded down to 0.5 yearsThe depletion (or burnup) of the fuel assembly rounded up to 0.5%The decay heat of the fuel assembly is less than 15 watts at the maximumburnup and minimum cooling time.


Table A.1-2

NRX Mk I Fuel Specification and Design Characteristics of Fuel AssembliesPermitted in the TN-LC-NRUX Basket

Parameter ValuePhysical and Material Description

Number of Assemblies < 26Number of rods/assembly 7Assembly length (inch) (1) <116Nominal Assembly mass (g) 5780Fuel form U-Al235U per rod (g) < 75.2Enrichment (wt.% 235U) < 93Cladding and Spacer Material Al

Thermal and Radiological ParametersCooling Time (years) (2) < 10Depletion (wt.% 235U) (3) < 80Decay Heat per Assembly (watts) (4) 5 15

Notes:

1. Maximum Length of the fuel assembly (unirradiated) for shipment2. The cooling time of the fuel assembly rounded down to 0.5 years3. The depletion (or burnup) of the fuel assembly rounded up to 0.5%4. The decay heat of the fuel assembly is less than 15 watts at the

maximum burnup and minimum cooling time.



TN-LC-MTR Basket

TN-LC Transport Packaging Contents with TN-LC-MTR Basket


(a) Intact or damaged MTR fuel elements which meet specifications listed inTable A.2-1 are authorized for transportation in the TN-LC-MTR basket.Intact fuel elements are fuel elements containing fuel plates with no knownor suspected cladding defects greater than hairline cracks or pinhole leaks.Damaged fuel elements with cladding damage in excess of pin hole leaks orhairline cracks are authorized. The extent of the damage is limited such thatthe total surface area of the damaged cladding does not exceed 5% of thetotal surface area of each element. The design characteristics of the MTRfuel elements are described in Table A.2-2.

(b) The fuel qualification table is shown in Table A.2-3, which specifies themaximum fuel element average burnup, minimum enrichment, and minimumcooling time. The fuel assemblies shall meet all the requirements inTable A.2-3.


(a) The quantity of material authorized for transport is 54 intact or damagedMTR fuel elements.

(b) For materials described in A.2(1) above, the approximate maximum payloadis 1,620 lbs.

CoC 9358, Appendix A.2 Page 2 of 4CoC 9358, Appendix A.2 Page 2 of 4

Table A.2-1

MTR Fuel Element Specification

PHYSICAL PARAMETERS: MTR fuel elements that are enveloped by the

fuel element design characteristics listed in

MTR Fuel Elements Table A.2-2. Fuel elements manufactured bythe same or other vendors but bounded bythe design characteristics listed in Table A.2-2 are also acceptable. Fuel elements arecategorized into eight classes based ondesign characteristics.

THERMAURADIOLOGICALPARAMETERS:

Fuel Element Average Burnup and Per Table A.2-3. Fuel elements areminimum Cooling Time categorized into four types based on

enrichment and 235U loading.

Decay Heat _ 25 watts per element


Table A.2-2

MTR Fuel Element Design Characteristics

Fuel Element Class M-01 M-02 M-03 M-04 M-05 M-06 M-07 M-08(1)

Number of Fuel Plates (2) 523 <21 <19 <17 <10 <18 <17 <23235U mass per Plate (g) <16 <16.5 <17.5 <19 <22 <20.5 511.5 522

Active Fuel Width (cm) <6.7 <6.7 <6.7 <6.7 <6.7 <5.9 <6.7 •<6.7

Active Fuel Length (cm) > 56 > 56 > 56 > 56 > 56 > 56 > 27.5 > 56

Enrichment (wt. % 235 U) < 94 • 94 < 94 • 94 • 94 • 94 • 94 • 94

Fuel Element Depth (cm) >7.5 >7.5 Ž7.5 >7.5 >7.5 >7.5 >7.5 >7.5

Notes:

1. The M-08 Element class requires that the central stack of fuel elements remain empty.Also, the total 235U mass is limited by the maximum value in Table A.2-3.

2. The plate thickness is greater than 0.12 cm and the clad thickness is greater than 0.02cm.


Table A.2-3

TN-LC-MTR Fuel Element Qualification

Burnup Cooling TimeEnrichment Type (MWD/MTU) (days)

66,000 740Type A 165,000 1120235U Enrichment -> 90% 330,000 1440235U Mass - 380 g 495,000 1680

660,000 195057,750 770

Type B 144,375 1150235U Enrichment > 90% 288,750 1470380 g < 235U Mass• 460 g 433,125 1710

577,500 195029,330 740

Type C 73,325 112040% < 235 U Enrichment < 90% 146,650 1440235U Mass < 380 g 219,975 1690

293,300 194013,930 830

Type D 34,825 122019% < 235U Enrichment < 40% 69,650 1560235U Mass < 470 g 104,475 1850

139,300 2150

Notes:

* Burnup = fuel element average burnup* Use burnup (MWD/MTU) and Enrichment Type (A, B, C or D with limits

on 235U Enrichment and 235U mass per element) to look-up minimumcooling time in years. Licensee is responsible for ensuring thatuncertainties in burnup, enrichment and mass are appliedconservatively.

" Fuel with burnup greater than those listed for each Enrichment Type isunacceptable for transport.

• Because only a limited number of burnup points are listed in this table,burnups may be either rounded up to the next higher burnup or linearinterpolation may be used to determine the minimum cooling time.However, for conservatism, an additional cooling time of 30 days mustbe added to any linearly interpolated value.

" Example: An M-06 class element with an enrichment of 45 wt. % 235Uand a 235U mass of 350 grams is classified as enrichment Type C. Aburnup of 100,000 MWD/MTU is acceptable for transport after 1440days cooling time as defined by 146,650 MWD/MTU from thequalification table (when linear interpolation is not employed). Whenlinear interpolation is employed the minimum required cooling time is1267 days (1237 days based on interpolation + 30 days additionalcooling time).



TN-LC Transport Packaging Contents with TN-LC-TRIGA Basket


(a) Intact TRIGA fuel assemblies/elements which meet specifications listed inTable A.3-1 are authorized for shipment in the TN-LC transport cask with TN-LC-TRIGA basket. Intact fuel assemblies/elements are fuelassemblies/elements containing fuel rods with no known or suspected claddingdefects greater than hairline cracks or pinhole leaks. The designcharacteristics of the TRIGA fuel assemblies/elements are described in TablesA.3-2 and A.3-3.

(b) The fuel qualification tables are shown in Tables A.3-4 and A.3-5, which specifythe maximum assembly/element average burnup and minimum cooling time.The fuel elements/assemblies shall meet all the requirements in Tables A.3-4and A.3-5.

(c) The poison plates in TN-LC-TRIGA basket are constructed from boronaluminum alloy, or metal matrix composite (MMC), or Borale. The minimumareal Boron-10 (10B) concentrations for the either boron enriched aluminumalloy or metal matrix composite is 5.56 mg/cm 2 and for Boral® is 6.67 mg/cm 2.


(a) The quantity of material authorized for transport is 180 intact TRIGA fuelelements/assemblies.

(b) For materials described in A.3(1) above, the approximate maximum payload is2,380 lbs.


Table A.3-1

TRIGA Fuel Assembly/Element Specification

PHYSICAL PARAMETERS:

Fuel Assemblies/Elements andFuel Follower Control Rods

Intact TRIGA assemblies/elements that areenveloped by the fuel assemblies/elementdesign characteristics listed in Table A.3-2.Fuel assemblies/elements manufactured bythe same or other vendors but bounded bythe design characteristics listed in Table A.3-2 are also acceptable.

Intact TRIGA fuel follower control rods thatare enveloped by the fuel assembly/elementdesign characteristics listed in Table A.3-3.Fuel follower control rods manufactured bythe same or other vendors but bounded bythe design characteristics listed in Table A.3-3 are also acceptable.

THERMAL/RADIOLOGICALPARAMETERS:

Fuel Assemblies/Element Average Burnup Per Table A.3-4 for fuel assemblies/ elementsand minimum Cooling Time

Per Table A.3-5 for follower control rodsDecay Heat (maximum) 8 watts per assembly/element


Table A.3-2

TRIGA Fuel Assembly/Element Design Characteristics

Assembly/Element Al ACPR(1) Standard FLIP (2) FLIP (2) FLIP(2)Type Clad _ ___ LEU-I (3) LEU-11 (3)

Element ID T-01 T-02 T-03 T-04 T-05 T-06

Fuel Material U-ZrH U-ZrH U-ZrH U-ZrH U-ZrH U-ZrH

Enrichment (wt. % 235U) < 20 5 20 5 20 < 70 < 20 < 202 5U-Mass (g) < 41 < 56 < 41 < 137 < 101 5169Active Fuel Length < 15 < 15 < 15 < 15 < 15 • 15(inch)Pellet Diameter (inch) < 1.41 < 1.41 < 1.44 < 1.44 < 1.44 < 1.44Clad Material Al SS304 SS304 SS304 SS304 SS304

Notes:1. ACPR - Annular Core Pulse Reactor2. FLIP - Fuel Life Improvement Program3. LEU - Low Enriched Uranium

CoC 9358, Appendix A.3 Page 4 of 6CoG 9358, Appendix A.3 Page 4 of 6

Table A.3-3

TRIGA Fuel Follower Control Rods Design Characteristics

Assembly/Element Standard FLIP (2) ACPRType LEU-I (3)

Element ID T-07 T-08 T-09

Fuel Material U-ZrH U-ZrH U-ZrHEnrichment (wt. %

2 3 5U) -- 20 5 20 5 20

235U-Mass (g) 5 38 5 97 5 56Active Fuel Length (inch) 5 15 5 15 5 15Pellet Diameter (inch) < 1.32 5 1.32 5 1.32Clad Material SS304 SS304 SS304

Notes:1. ACPR - Annular Core Pulse Reactor2. FLIP - Fuel Life Improvement Program3. LEU - Low Enriched Uranium

CoC 9358, Appendix A.3 Page 5 of 6CoG 9358, Appendix A.3 PageS of 6

Table A.3-4

TRIGA Fuel Qualification for Fuel Assembly/Elements

Burnup Cooling TimeElement ID (MWD/MTU) (days)

T-01 35,750 40071,500 560107,250 640143,000 710

T-02 35,750 65071,500 970107,250 1310143,000 1870

T-03 35,750 52071,500 840107,250 1170143,000 1730

T-04 112,500 1000225,000 1380337,500 1820450,000 2520

T-05 35,750 920

71,500 1290107,250 1710143,000 2360

T-06 36,500 119073,000 1690109,500 2320146,000 3170

Note: The explanatory notes and limitations regarding the use ofthis table follow Table A.3-5.


Table A.3-5

TRIGA Fuel Qualification for Fuel Follower Control Rods

Burnup Cooling TimeElement ID (MWD/MTU) (days)

T-07 35,750 54071,500 890107,250 1280143,000 1960

T-08 35,750 94071,500 1350107,250 1840143,000 2580

T-09 35,750 67071,500 1020107,250 1420143,000 2100

Notes: Table A.3-4 and Table A.3-5:" Burnup = fuel element / assembly I follower control rod

average burnup* Use burnup (MWD/MTU) and Element ID to look-up

minimum cooling time in years. Licensee is responsiblefor ensuring that uncertainties in burnup are appliedconservatively.

* Fuel with a burnup greater than that listed for eachelement type in Table A.3-4 and A.3-5 is unacceptablefor transport.

* Because only a limited number of burnup points arelisted in Table A.3-4 and Table A.3-5, burnups may beeither rounded up to the next higher burnup or linearinterpolation may be used to determine the minimumcooling time. However, for conservatism, an additionalcooling time of 30 days must be added to any linearlyinterpolated value.

" Example: A T-03 element with a burnup of 100,000MWD/MTU is acceptable for transport after 1170 dayscooling time as defined by 107,250 MWD/MTU (TableA.3-4, rounding up) on the qualification table (whenlinear interpolation is not employed). When linearinterpolation is employed the minimum required coolingtime is 1133 days (1103 days based on interpolation +30 days additional cooling time).



TN-LC Transport Packaging Contents with TN-LC-1FA Basket


(a) Intact PWR fuel assembly, as specified in Table A.4-1, or intact BWR fuelassembly, as specified in Table A.4-6, or fuel rods in a pin can. The fuel rodsinclude irradiated PWR, BWR, MOX, and EPR fuel rods. PWR intact and BWRintact fuel rods may be from any of the fuel assemblies listed in Table A.4-1 orTable A.4-6, respectively. MOX rods have the same geometry as PWR or BWRrods, as defined in Table A.4-1 and Table A.4-6, although with a different fuelcomposition. The composition of MOX fuel is specified in Table A.4-5. The EPRfuel rods are specified in Table A.4-3. Intact fuel assemblies are fuel assembliescontaining fuel rods with no known or suspected cladding defects greater thanhairline cracks or pinhole leaks.

(b) The poison plates in TN-LC-1FA basket are constructed from boron aluminumalloy, or metal matrix composite (MMC), or Boral®. The minimum B-10 aerialdensity of the poison plate is 16.7 mg/cm 2 if boron aluminum alloy or metal matrixcomposite (MMC) is used. The minimum B-10 aerial density of the poison plate is20.0 mg/cm 2 if Boral® is used.

(c) In addition to the poison plates provided in the basket, Poison Rod Assemblies(PRAs) are required while transporting PWR fuel assemblies. The minimumrequired B4C content of the absorber rods in the PRA is 40 percent TheoreticalDensity (TD). A summary of the number of absorber rods required in the PRA foreach PWR fuel class is shown in Table A.4-4. PRA loading configurations are alsoillustrated in Figure A.4-1 through Figure A.4-4.

(d) The PWR fuel assemblies fuel qualification table (FQT) is provided in Table A.4-8.

The BWR fuel assemblies FQT is provided in Table A.4-9.

PWR rod FQTs are shown in Table A.4-10 and Table A.4-11 for the 25 and 9 rodconfigurations, respectively.

BWR rod FQTs are shown in Table A.4-12 and Table A.4-13 for the 25 and 9 rodconfigurations, respectively.

The MOX rod FQT is provided in Table A.4-14 for both 25 and 9 rods. The MOXrod FQT is applicable to both BWR and PWR MOX rods.

The U0 2 Standard EPR rods are governed by the PWR rod FQTs (Table A.4-10and Table A.4-1 1), while MOX EPR rods are governed by the MOX rod FQTs(Table A.4-14).


(a) The quantity of material authorized for transport is one intact PWR fuel assemblyor one intact BWR fuel assembly, or up to 25 intact light water reactor fuel rods in apin can. When transporting 9 or fewer rods, the rods shall be placed in the center3x3 region of the pin can.

(b) For materials described in A.4(1) above, the approximate maximum payload is1650 lbs per PWR assembly, 710 lbs per BWR assembly, and 15 lbs per fuel rod.


Table A.4-1PWR Fuel Specification for the Fuel to be Transported in the TN-LC-1FA Basket

PHYSICAL PARAMETERS:

Fuel Class (1) (2) Intact unconsolidated B&W 17x17, WE 17x17,CE 16x16, B&W 15x15, WE 15x15, CE 15x15,WE 14x14, and CE 14x14 class PWRassemblies (without control components) thatare enveloped by the fuel assembly designcharacteristics listed in Table A.4-2. Reload fuelmanufactured by the same or other vendors butenveloped by the design characteristics listed inTable A.4-2 is also acceptable.

Maximum Assembly + PRA Weight 1850 lbs

Fissile Material U0 2

Maximum Initial Uranium Content(4) 490 kg/assembly

Maximum Unirradiated Assembly Length 178.3 inches

THERMAL/RADIOLOGICAL PARAMETERS:

Fuel Assembly Average Burnup, Enrichment and Per Table A.4-8Minimum Cooling Time

Maximum Planar Average Initial Enrichment 5.0(31 wt.% 235U

Maximum Decay Heat(5) 3.0 kW per Assembly

* 16.7 mg/cm 2 (Natural or Enriched BoronAluminum Alloy / Metal Matrix Composite

Minimum B10 content in poison plates loading (MMC))

* 20.0 mg/cm 2 (Boral®)

Minimum number of absorber rods per PRA as a Per Table A.4-4function of assembly class

Notes:1. Up to 25 PWR fuel rods from any of the PWR fuel assemblies listed in Table A.4-2 may also be transported in

the TN-LC-1FA basket in a 25 pin can. The fuel rods are loaded in a 25 pin can with a cavity length of 168.5inches (Option 3) which is placed within the TN-LC-1 FA basket. The maximum peak burnup for the fuel rods is90 GWd/MTU. The required cooling time as a function of a PWR fuel rod burnup and enrichment are providedin Table A.4-10 for 25 rods and Table A.4-1 1 for 9 rods, respectively.

2. Up to 25 EPR fuel rods from any of the fuel class listed in Table A.4-2 and meeting EPR rod parametersspecified in Table A.4-3 may also be loaded in the TN-LC-1FA basket. The fuel rods are loaded in a 25 pin canwith a cavity length of 179.5 inches (Option 1 and Option 2) which is placed within the TN-LC-1FA basket. Themaximum peak burnup for the fuel rods is 90 GWd/MTU. The required cooling time as a function of an EPRfuel rod burnup and enrichment are provided in Table A.4-1 0 for 25 rods and Table A.4-11 for 9 rods,respectively.

3. For CE 15x1 5, the maximum planar average initial enrichment is 3.70 wt. % 235U.4. The maximum initial uranium content is based on the shielding analysis. The listed value is higher than the

actual.5. The maximum decay heat per rod is 220 watts when loading up to 9 rods. The maximum decay heat per rod is

120 watts when loading 10 or more (up to 25) rods.


Table A.4-2PWR Fuel Assembly Design Characteristics for Transportation in the TN-LC-1 FA

Basket

B&W B&W WE CE WE CE WE CEAssembly Class 15x15 17x17 17x17 15x15 15x15 14x14 14x14 16x16

Maximum Number ofFuel Rods 208 264 264 216 204 176 179 236

Maximum Number of

Guide/Instrument Tubes 17 25 25 9 21 5 17 5

Rod Pitch(1) (inch) < 0.568 1 0.502 5 0.496 5 0.550 5 0.563 5 0.580 < 0.556 5 0.506

Pellet Diameter(1) (inch) 5 0.374 5 0.323 5 0.323 5 0.360 5 0.367 5 0.382 5 0.368 5 0.326

Clad Outer Diameter" 0.416 >-0.379 > 0.360 >0.417 >0.422 > 0.440 > 0.400 > 0.382(inch) I I I

Clad Thickness() (inch) > 0.024 > 0.024 > 0.022 >0.026 >0.024 > 0.026 >0.022 > 0.023

Notes:

1. The fuel assembly fabrication documentation may be used to demonstrate compliance with these fuelassembly parameters. The fuel assembly parameters are design nominal values. The maximum andminimum dimensions are specified to bound variations in design nominal values among fuelassemblies within a fuel assembly class (or an array type).

Table A.4-3Irradiated EPR Fuel Rod Parameters

Parameter Value

Maximum Unirradiated Length 179.5 inches

Cladding Thickness Nominal 0.022 inch

Maximum Initial Uranium Content 2.05 kgU/rod


Table A.4-4Summary of PRA Requirements for PWR Fuel Assembly Classes

Diameter of MinimumNumber of Absorber B4 C B 4C

Assembly Rods in PRAs and Absorber ContentClass Locations (cm) (g/cm)

WE 17x17 8, Per Figure A.4-4 0.88 0.613CE 16x16 5, All Guide Tubes 1.02 0.824BW 15xl 5 8, Per Figure A.4-3 0.88 0.613CE 15x15 1, Center Guide Tube 0.76 0.475WE 15x15 8, Per Figure A.4-2 0.88 0.613CE 14x14 5, All Guide Tubes 1.02 0.824WE 14x14 8, Per Figure A.4-1 0.88 0.613BW 17x17 8, Per Figure A.4-4 0.76 0.475


Table A.4-5Specification for the MOX Fuel Rods to be Transported in the TN-LC-1 FA Basket

PHYSICAL PARAMETERS:" Up to 25 PWR MOX fuel rods with physical

parameters as those listed in Table A.4-1.* Up to 25 BWR MOX fuel rods with physical

parameters as those listed in Table A.4-6." Up to 25 EPR MOX fuel rods with physical

parameters as those listed in Table A.4-3.

Fissile Material U0 2, PuO 2 (Mixed Oxide or MOX)

Heavy Metal (HM) Content _ 2.5 kgU/rod

CRITICALITY PARAMETERS* U-235 Content in U0 2 : 0.5 5 U-235 5 0.7 wt. %* Plutonium Content: Pu / (U + Pu) - 7.0 wt. %

Initial MOX composition: * Initial Pu-239 Content in PuO 2 5 60.0 wt. %* Initial Pu-241 Content in PuO 2 -5 7.5 wt. %

THERMAL/RADIOLOGICAL PARAMETERS:* Pu-238 / Pu-239 5 4.0 wt. %

Initial MOX Composition for Fuel Qualification a Pu-239/ PuO 2 - 50 wt. %* Am-241 / PuO 2 5 70 ppm* U-235/U Ž- 0.5 wt. %

Burnup and Minimum cooling time for MOX Per Table A.4-14rods

M 3.0 kW for the 25 pin can with up to 25 rodsMaximum Decay heat per 25 pin cana 1.98 kW for the 25 pin can with up to 9 rods

* 16.7 mg/cm2 Boron Aluminum Alloy / Metal Matrix

Minimum B10 content in poison plates loading Composite (MMC)

* 20.0 mg/cm2 (Boral®)


Table A.4-6Fuel Specification for the BWR Fuel to be Transported in the in the TN-LC-1FA

Basket

PHYSICAL PARAMETERS: Intact 7x7, 8x8, 9x9 or 10x10 BWR

Fuel Class(1 ) assemblies manufactured by GeneralElectric or Exxon/ANF or FANP or ABB orreload fuel manufactured by same orother vendors that are enveloped by thefuel assembly design characteristics listedin Table A.4-7.

Fuel may be transported with or withoutChannels channels, channel fasteners, or finger

springs.

Fissile Material U02

Maximum Assembly Weight with Channels 710 lbs

Maximum Unirradiated Assembly Length 176.6 inches

THERMAL/RADIOLOGICAL PARAMETERS:

Maximum Lattice Average Initial Enrichment 5.0 wt. % 235U

Fuel Assembly Average Burnup, Enrichment and Minimum Per Table A.4-9

Cooling Time

Maximum Decay Heat(2) 2.0 kW per Assembly

* 16.7 mg/cm 2 Boron Aluminum Alloy /

Minimum B10 Content in Poison Plates Metal Matrix Composite (MMC)

* 20.0 mg/cm 2 (Boral®)

Notes:

1. Up to 25 fuel rods from any of the BWR fuel assemblies listed in Table A.4-7 may also be transportedin the TN-LC-IFA basket in the 25 pin can. The fuel rods are loaded in a 25 pin can with a cavitylength of 168.5 inches which is placed within the TN-LC-1FA basket. The required cooling time as afunction of BWR fuel rod burnup and enrichment are provided in Table A.4-12 for 25 rods and TableA.4-13 for 9 rods respectively.

2. The maximum decay heat per rod is 220 watts when loading up to 9 rods. The maximum decay heatper rod is 120 watts when loading 10 or more (up to 25) rods.


Table A.4-7BWR Fuel Assembly Design Characteristics(1 ) for Transportation in the TN-LC-1FA

Basket

(Part 1 of 3)

Transnuclear ID 7x7-4910 8x8-6311 8x8-6212 8x8-6014 8x8-6011 9x9-7412

GEl GE4 GE-5 GE8 Type II GE9 GEl1Initial Design or Reload GE2 GE-Pres GE10 GE13Fuel Designation

GE3 GE-Barrier

GE8 Type IFANP 8x8-

2

Maximum Number of 49 63 62 60 60 74Fuel RodsMaximum InitialUanium Intitl 198 192 192 192 192 192Uranium Content (kg)

Rod Pitch(5) (inch) < 0.738 < 0.640 < 0.640 < 0.640 < 0.640 < 0.566

Pellet Diameter ~ < 0.487 < 0.416 < 0.411 < 0.411 < 0.411 < 0.376(inch)Clad Outer Diameter >Ž 0.563 > 0.493 > 0.483 > 0.483 > 0.483 > 0.440(inch)Clad Thickness > 0.032 > 0.034 > 0.032 > 0.032 > 0.032 > 0.028(inch) I I I

Table A.4-7BWR Fuel Assembly Design Characteristics(') for Transportation in the TN-LC-1FA

Basket

(Part 2 of 3)

Transnuclear ID 10x10-9212 7x7-49/0Z 7x7-48/1Z 8x8-60/4Z FANP 9x9 Siemens QFAInitial Design or Reload GE12 ENC-IIIA ENC-1II(2) ENC Va FANP9 9x9

9x9 3 9)Fuel Designation GE14 ENC Vb

Maximum Number of 92 49 48 60 81 72Fuel RodsMaximum InitialUaxium Intial 192 198 198 192 192 192Uranium Content (kg)

Rod Pitchn5 ) (inch) < 0.510 < 0.738 < 0.738 5 0.642 < 0.572 < 0.570

Pellet Diameter"5 ) (inch) < 0.345 < 0.488 < 0.491 5 0.420 5 0.357 -< 0.374

Clad Outer Dianeter~) Ž> 0.404 > 0.570 > 0.570 a 0.501 a 0.424 > 0.433(inch) I

Clad Thickness"5 ) (inch) > 0.026 > 0.035 > 0.035 > 0.036 > 0.030 > 0.026


Table A.4-7BWR Fuel Assembly Design Characteristics(1 ) for Transportation in the TN-LC-IFA

Basket

(Part 3 of 3)

Transnuclear ID 1Ox1O-9111 ABB-8x8 ABB-10xl0 LaCrosse

ATRIUM 10 SVEA-64 SVEA-100(4) Allis Chalmers - 10x10Initial Design or Reload ATRIUM 1OXM Exxon/ANF 10x10Fuel Designation

Maximum Number of 91 64 100 100Fuel RodsMaximum Initial Uranium 192 192 192 125Content (kg)Rod Pitch(5) (inch) _s 0.510 5 0.622 - 0.512 _< 0.565

Pellet Diameter(5) (inch) -< 0.350 < 0.411 • 0.346 5 0.350Clad Outer Diameter) >- 0.405 >- 0.378 0.378 - 0.394(inch) ->_._5___037___.38_-_039

Clad Thickness(5) (inch) a 0.023 Ž 0.024 - 0.022 _ 0.020

Notes:1. Any fuel channel average thickness up to 0.120 inch is acceptable on any of the fuel designs.2. Includes ENC-IIIE and ENC-IIIF.3. Includes FANP 9x9-72, 9x9-79, 9x9-80, and 9x9-81.4. Includes SVEA-92, SVEA-96, SVEA-96+, SVEA-96 OPTIMA, SVEA-96 OPTIMA2, SVEA-96+/L.

5. The fuel assembly fabrication documentation may be used to demonstrate compliance with these fuelassembly parameters. The fuel assembly parameters are design nominal values. The maximum andminimum dimensions are specified to bound variations in design nominal values among fuelassemblies within a fuel assembly class (or an array type).

CoC 9358 Appendix A.4 Page 9 of 20

Table A.4-8Fuel Qualification Table for a PWR Fuel Assembly

(Minimum required years of cooling time after reactor core discharge)Burnup, Enrichment (wt. % 2 35 U)GWd/MTU 0.7 0.8 0.9 1.2 1.5 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0

10 2.25 2.25 2.20 2.10 2.05 2.05 2.05 2.00 2.00 2.00 2.00 2.00 2.00 1.95 1.95 1.95 1.95 1.95 1.95 1.95 1.95 1.95 1.95 1.90 1.90 1.90 1.90 1.90 1.90 1.90 1.90 1.90 1.90 1.90 1.90 1.90

20 3.37 3.35 3.30 3.20 3.05 2.90 2.90 2.85 2.85 2.80 2.80 2.80 2.75 2.75 2.75 2.75 2.75 2.75 2.70 2.70 2.70 2.70 2.65 2.65 2.65 2.65 2.65 2.65 2.60 2.60 2.60 2.60 2.60 2.60 2.60 2.55

30 4.70 4.35 4.10 3.80 3.70 3.65 3.60 3.60 3.55 3.50 3.45 3.45 3.40 3.35 3.35 3.35 3.30 3.30 3.25 3.25 3.20 3.20 3.15 3.15 3.15 3.15 3.15 3.15 3.10 3.10 3.10 3.05 3.05 3.05

39 4.95 4.85 4.75 4.65 4.55 4.45 4.40 4.35 4.25 4.20 4.15 4.10 4.00 3.95 3.95 3.90 3.85 3.80 3.75 3.70 3.70 3.70 3.65 3.65 3.60 3.55 3.55 3.50 3.50 3.50 3.50

40 4.55 4.45 4.35 4.30 4.25 4.15 4.15 4.10 4.05 4.00 3.90 3.90 3.90 3.85 3.80 3.75 3.70 3.70 3.65 3.65 3.65 3.60 3.55 3.55 3.5045 • 5.40 5.25 5.15 5.05 4.95 4.85 4.80 4.70 4.60 4.55 4.50 4.45 4.35 4.35 4.30 4.20 4.15 4.10 4.10 4.05 4.00 3.95 3.95 3.90 3.85

50 """ - 6.80 6.60 6.50 6.25 6.15 6.00 5.85 5.75 5.60 5.50 5.40 5.30 5.20 5.10 5.05 4.95 4.90 4.85 4.75 4.70 4.65 4.55 4.55 4.50 4.40

55 -- 8.85 8.60 8.30 8.05 7.85 7.65 7.35 7.15 7.00 6.80 6.65 6.45 6.30 6.20 6.05 5.90 15.85 5.70 5.65 5.50 5.45 5.35 5.30 5.25 5.15

60 1.55 1.2010.85 10.50 10.15 9.80 9.55 9.20 8.95 8.70 8.45 8.25 8.00 7.80 7.55 7.40 7.20 7.05 6.85 6.75 6.60 6.45 6.35 6.25 6.10

61 2.15 1.80 1.45 11.10 10.70 0.35 10.10 9.75 9.45 9.20 8.90 8.65 8.35 8.20 7.90 7.75 7.55 7.40 7.20 7.00 6.85 6.75 6.55 6.50 6.40

62 12.80 2.4012.05 1.65 11.30 0.90 10.65 10.25 9.95 9.70 9.40 9.10 8.85 8.55 8.35 8.15 7.90 7.70 7.50 7.30 7.20 7.05 6.85 6.75 6.65

0.7 0.8 0.9 1.2 1.5 2.0 2.1 12.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.773.8 3.974.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0

Notes:

1. Explanatory notes and limitations regarding the use of this table follow Table A.4-14.


Table A.4-9Fuel Qualification Table for a BWR Fuel Assembly

(Minimum required years of cooling time after reactor core discharge)Burnup, Enrichment (wt. % 235U)GWdIMTU 0.7 08 0.91.2 15 2.0 2.1 2.2 12.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.113.2 13.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0

10 0.65 0.65 0.60 0.60 0.60 0.60 0.60 0.6010.60 0.60 0.60 0.60 0.60 0.60 0.60 0.60 0.6010.6010.60 0.60 0.60 0.60 0.60 0.60 0.60 0.60 0.60 0.60 0.6010.60 0.60 0.60 0.60 0.60 0.60 0.6020 0.95 0.95 0.90 0.85 0.80 0.80 0.80 0.8010.80 0.75 0.75 0.75 0.75 0.7510.75 0.75 0.75 0.7510.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.7510.75 0.75 0.75 0.75 0.75 0.75 0.75

30 11.25 1.20 1.15 1.10 1.10 1.1011.10 1.1 1.10 1.10 1.10 1.05 1.05 1.05 1.05 1.05 1.05 1.05 1.05 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 0.95 0.95 0.95 0.95

39 -1.4~IL0, .40 1.4011.35 1.35 1.35 1.35 1.30 1.30 1.30 1.30 1.30 1.25 1.25 1.25. 1.25. 1.25 1.20 1.20. 1.20.1.20 1.20 1.20 1.15 1.15 1.15.1.15 1.15 1.15 1.15 1140 1.40 1.40 1.35 1.35 1.35 1.35 1.30 1.30 1.30 1.30 1.30 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.20 1.20 1.20 1.20 1.20 1.20 1.2045 . 1.60 1.60 1.60 1.55 1.55 1.55 1.55 1.50 1.50 1.50 1.50 1.50 1.50 1.50 1.50 1.50 1.45 1.45 1.45 1.45 1.45 1.45 1.40 1.40 1.40

50 1.85 1.85 1.85 1.80 1.80 1.80 1.75 1.75 1.75 1.75 1.75 1.75 1.75 1.75 1.70 1.70 1.70 1.70 1.65 1.65 1.65 1.65 1.65 1.60 1.6055 .2.10 2.10 2.10 2.05 2.05 2.05 2.00 2.00 2.00 1.95 1.95 1.95 1.95 1.95 1.95 1.95 1.90 1.90 1.90 1.90 1.90 1.85 1.85 1.85 1.85

602.35 2.35 2.35 2.30 2.30 2.30 2.25 2.25 2.25 2.20 2.20 2.20 2.20 2.20 2.20 2.15 2.15 2.15 2.15 2.10 2.10 2.10 2.10 2.05 2.05612.40 2.40 2.40 2.35 2.35 2.35 2.30 2.3012.30 2.2512.25 2.25 12.20 12.20 12.20 2.20 2.2012.20 2.20 2.15 2.1512.15 2.15 2.10 2.10622.45 2.45 2.45 2.40 2.40 2.40 2.35 2.35 2.35 2.30 2.30 2.30 2.25 2.25 2.25 2.25 2.25 2.25 2.25.2.20 2.20 2.20.2.2012.15t2.15

0.7 0.8 0.9 1.2 1.5 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.812.9 13.0 13.1 13.2 13.3 3.4 3.5 36 .7 .8 .940 .14.2 43 .4 .54.6 14.7 14.8 14.9 5.0

Notes:I. Explanatory notes and limitations regarding the use of this table follow Table A.4-14


Table A.4-10Fuel Qualification Table for 25 PWR/EPR Fuel Rods (U0 2)

(Minimum required years of cooling time after reactor core discharge)Burnup, Enrichment (wt. %

2 35U)

GWd/

MTU 0.7 0.8 0.9 1.2 1.5 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0

10 0.30 0.30 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

20 0.30 0.30 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

30 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

39 .0.25.0.25.0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

40 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

45 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

50 0.30 0.30 0.30 0.30 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

55 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30

60 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30

61 0.40 0.40 0.40 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.30 0.30

62 0.40 0.40 0.40 0.40 0.40 0.40 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35

65 . 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.35 0.35 0.35 0.35 0.35 0.35

70 0.50 0.50 0.50 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45

75 0.65 0.65 0.60 0.60 0.60 0.60 0.60 0.60 0.60 0.60 0.50 0.50 0.50 0.50

80 - . 0.85 0.85 0.75 0.75 0.75 0.75 0.75 0.70 0.70 0.70 0.70 0.70 0.70 0.70

85 1.05 1.00 1.00 1.00 0.90 0.90 0.90 0.90 0.85 0.85 0.85 0.85 0.85 0.85

90 1.25 1.25 1.25 1.15 1.15 1.15 1.10 1.10 1.10 1.00 1.00 1.00 1.00 0.95

07 08 0.9 1.2 1.5 2.0 2.1 2.2 2.3 2.4 2.512.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 .6 L4.714.814.9 5.0

Notes:


CoC 9358 Appendix AA4Pg 1 f2Page 12 of 20

Table A.4-11IFuel Qualification Table for 9 PWRIEPR Fuel Rods WOO2

(Minimum required years of cooling time after reactor core discharge)Burnup, Enrichment (wt. % 235U)GWd/ .- - ---- - - - - - - - - - - - -

MTU 0.7 0.8 0.91.21. 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.513.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.010 0.5 0.5025 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

20 0.5 0.5025 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.2510.25 0.25 0.25 0.25 0.25 0.25 0.25

30 0.25 025 0.25 0.250.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25,

39 10.25,0.25_0.2510.25.0.25,0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

40 0.25 0.25.0.25.0.25 0.25 0.25.0.25 0.25 0.25.0.25 0.25 0.25.0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.2510.25 0.25 0.25 0.25 0.2545 0.25 0.25 0.25 0.25 0.25.0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25.0.25.0.25 0.25 0.25 0.25 0.25 0.25 0.20.5.5025.5

50 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.2510.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

55 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

60 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

61 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

62 10.2510.2510.2510.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.2510.25 0.25 0.25 0.25 0.25

65 -0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.2510.2510.25 0.25 0.25 0.25

70 0.25 0.2510.2510.25 0.25 0.2510.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

75 0.25 0.25 0.25 0.25 0.25 0.2510.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

80 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

85 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.2510.25

90 0.25 0.25 0.25 0.25 0.25 0.25 0.2510.25 0.25 0.25 0.25 0.25 0.2510.25

10.7 10.8 10.9 11.2 11.5 12.0 12.1 12.2 12.3 12.4 12.5 12.6 12.7 12.8 12.9 13.0 13.1 13.2 13.3 13.4 13.5 13.6 13.7 13.8 13.9 14.0 4.1 4.2 43 .44.5 14.6 14.74.4950

Notes:



Table A.4-12Fuel Qualification Table for 25 BWR Fuel Rods (U0 2)

(Minimum required years of cooling time after reactor core discharge)

Burnup, Enrichment (wt. % 235U)GWd/MTU 0.7 0.8 0.9 1.2 1.5 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0

10 0.30 0.30 0. 25 0.250 .25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

20 0.30 0.30 0. 25 0.250 .25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

30 0.30 0.30 0.300 .30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30

39 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35

40 0.40 0.40 0.40 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35

45 0.45 0.45 0.45 0.45 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40

50 0.60 0.60 0.60 0.60 0.55 0.55 0.55 0.55 0.55 0.55 0.55 0.55 0.55 0.55 0.55 0.55 0.55 0.55 0.50 0.50 0.50 0.50 0.50 0.50 0.50

55 0.75 0.75 0.75 0.75 0.75 0.70 0.70 0.70 0.70 0.70 0.70 0.70 0.70 0.70 0.65 0.65 0.65 0.65 0.65 0.65 0.65 0.65 0.65 0.65 0.65

60 1.00 1.00 1.00 1.00 0.90 0.90 0.90 0.90 0.90 0.85 0.85 0.85 0.85 0.85 0.85 0.85 0.85 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75

61 1.05 1.05 1.00 1.00 1.00 1.00 1.00 0.90 0.90 0.90 0.90 0.90 0.90 0.85 0.85 0.85 0.85 0.85 0.85 0.85 0.85 0.75 0.75 0.75 0.75

62 1.10 1.05 1.05 1.05 1.05 1.00 1.00 1.00 1.00 1.00 0.90 0.90 0.90 0.90 0.90 0.90 0.85 0.85 0.85 0.85 0.85 0.85 0.85 0.85 0.85

65 1.05 1.05 1.00 1.00 1.00 1.00 1.00 1.00 1.00 0.90 0.90 0.90 0.90 0.90

70 1.20 1.20 1.20 1.15 1.15 1.15 1.15 1.15 1.15 1.10 1.10 1.10 1.10 1.10

75 1.45 1.45 1.45 1.40 1.40 1.40 1.30 1.30 1.30 1.30 1.25 1.25 1.25 1.25

80 1.70 1.70 1.65 1.65 1.60 1.60 1.60 1.50 1.50 1.50 1.45 1.45 1.45 1.45

85 2.15 2.05 2.00 2.00 1.95 1.85 1.85 1.80 1.80 1.70 1.70 1.65 1.65 1.6590 2.60 2.55 2.50 2.40 2.35 2.30 2.20 2.15 2.15 2.10 2.00 2.00 1.95 1.95

10.7 10.8 10.9 11.2 11.5 12.0 12.1 12.2 12.3 12.4 12.5 12.6 12.7 12.8 12.9 13.0 13.1 13.2 13.313.4 13.513.6 3.7 3.8 3.9 4.0 4.1 4.2 14.3 14.4 14.5 4.6 14.7 14.8 4.9 5.0

Notes:



Table A.4-13Fuel Qualification Table for 9 BWR Fuel Rods (U0 2)

(Minimum required years of cooling time after reactor core discharge)Burnup, Enrichment (wt. % 235U)GWd/

MTU 0.7 0.8 0.9 1.2 1.5 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0

10 0.25 0.25 025 0.25025 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

20 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

30 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.2539 - 0.25 0.25.0.250.25 0.25 0.25 0.25 0.25 0.25.0.2510.25 0.25 0.25 0.25 0.25 0.25 -0.25 0.25 0.250.25 0.25 0.25 0.25 0.25 0.2510.25 0.25 0.25 0.2510.25 0.25

40 0.225 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

45 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

50 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

55 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

60 0.30 0.30 0.30 0.30 0.30 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.25

61 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.25 0.25 0.25

62 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.32 0.25 0.32

65 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35

70 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40

75 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40

80 • 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45 0.45

85 .0.50 0.50 0.50 0.50 0.50 0.50 0.50 0.50 0.50 0.50 0.50 0.50 0.50 0.50

90 0.60 0.6010.5510.55 0.55 0.55 0.55 0.5510.55 0.55 0.55 0.55 0.55 0.55

0.7 0.8 0.9 1.2 1.5 2.0 2.1 2.2 2.3 2.4 2.5 2.61 2.7 2.8 2.9 3.0 3.1 3.2 13.3 3.4 13.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 14.4 4.5 4.6 4.7 4.8 4.9 5.0

Notes:


CoC 9358, Appendix AA Page 15 of 20

Table A.4-14Fuel Qualification Table for MOX PWR/BWR 25 Rods and MOX PWR/BWR 9 Rods

9 Rods 25 Rods

Burnup, GWd/MTHM 0.5 wt.% of 0.7 wt.% of 0.5 wt.% of 0.7 wt.% of235u 235U 235U 235u

10 0.25 0.25 0.25 0.25

20 0.25 0.25 0.30 0.30

30 0.25 0.25 0.50 0.50

40 0.25 0.25 0.95 0.95

45 0.25 0.25 1.25 1.25

50 0.35 0.35 1.70 1.70

55 0.40 0.40 2.20 2.10

60 0.45 0.45 2.80 2.70

62 0.55 0.55 3.75 3.65

Notes:

1. Explanatory notes and limitation regarding the use of this table are provided on thefollowing page.


Notes:

General

" Use burnup and enrichment to lookup minimum cooling time in years. Licensee isresponsible for ensuring that uncertainties in fuel enrichment and burnup are correctlyaccounted for during fuel qualification.

" For values not explicitly listed in the tables, round burnups up to the first value shown,round enrichments down, and select the cooling time listed.

* U0 2 Fuel with an initial enrichment less than 0.7 (or less than the minimum providedabove for each burnup) or greater than 5.0 wt. % 235U is unacceptable for transportation.

* Shaded areas in these Tables indicate fuel is not analyzed for loading.

For Fuel Assemblies

* Burnup = Assembly Average burnup." Enrichment = Assembly Average Enrichment.* Fuel assembly with a burnup greater than 62 GWd/MTU is unacceptable for

transportation.

For Fuel Rods

* Burnup = Maximum burnup.* Enrichment = Rod Average Enrichment.* When transporting 25 or less fuel rods, the rods shall be placed in a specially designed

25 pin can.* When transporting 9 or less fuel rods, the rods shall be placed in the 3x3 region of the

25 pin can.* Fuel rods with a burnup greater than 90 GWd/MTU are unacceptable for transportation.

Example: Per Table A.4-8, a PWR assembly with an initial enrichment of 4.85 wt. % 235Uand a burnup of 41.5 GWd/MTU is acceptable for transport after a 3.95-year cooling time asdefined by 4.8 wt. % 235U (rounding down) and 45 GWd/MTU (rounding up) on thequalification table (other considerations not withstanding).


olson Rod Locations impty Guide Tube Locations I

Note: This configuration indicates the relative location of the poison rods withinthe guide tubes and does not provide any other fuel class specificinformation. Any other configuration of poison rods that is rotationallysymmetric is also acceptable.

Figure A.4-1PRA Insertion Locations for WE 14x14 Class Assemblies


'olson Rod Locations IGuide Tube Locations

Note: This configuration indicates the relative location of the poison rodswithin the guide tubes and does not provide any other fuel class specificinformation. Any other configuration of poison rods that is rotationallysymmetric is also acceptable.

Figure A.4-2PRA Insertion Locations for WE 15x15 Class Assemblies


JI lI ~ ll~i~ I I IPoison Rod LocationsEmpty Guide Tube Locations

Note: This configuration indicates the relative location of the poison rods within theguide tubes and does not provide any other fuel class specific information.Any other configuration of poison rods that is rotationally symmetric is alsoacceptable.

Figure A.4-3PRA Insertion Locations for BW 15x15 Class Assemblies

CoC 9358, Appendix AA Page 20 of 20CoC 9358, Appendix A.4 Page 20 of 20

I I I I I

Poison Rod LocationsEmpty Guide Tube Locations I

Note: This configuration indicates the relative location of the poison rods within the guide tubesand does not provide any other fuel class specific information. Any other configuration ofpoison rods that is rotationally symmetric is also acceptable.

Figure A.4-4PRA Insertion Locations for BW 17x17 and WE 17x17 Class Assemblies

Documents

Revision 2 to Transnuclear, Inc. (TN) Application for Approval of the TN-LC ... · 2020. 8. 14. · A TRANSNUCLEAR AN AREVA COMPANY May 4, 2012 E-32623 U. S. Nuclear Regulatory Commission