anac ~i international · 8mm to lomm for 304 st. stl. and 6mm to 8mm for copper plates may be...

September 2017

Revision 17C

ANAC ~I INTERNATIONAL

Atlanta Corporate Headquarters: 3950 East Jones Bridge Road, Norcross, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www.nacintl.com

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• ED20170092

Enclosure 1

List of Changes

NAC-STC SAR, Revision 17C

September 2017

Page I of2

List of Changes, NAC-STC SAR, Revision 17C

• Chapter 1

• Page 1-iii, modified the List of Drawings, where indicated. • Pages 1-iv thru 1-v, text flow changes. • Page 1.1-4, modified the last line of the second paragraph on the page. • Page 1.2-8, modified the first and second paragraphs on the page. • Pages 1.2-38 thru 1.2-39, modified Table 1.2-1, where indicated.

Chapter 2

• Page 2.1.1-3, modified the next-to-last paragraph on the page. • Page 2.4.4-7, modified text in paragraph 2.4.4.2.5. • Page 2.4.4-8, modified text in paragraph 2.4.4.2.7 and 2.4.4.2.8. • Page 2.4.4-10, modified the last row of Table 2.4-1

Chapter 3

• No changes.

Chapter 4

• Page 4.5-14, modified the second line of the paragraph in Section 4.5.2 .

• Chapter 5

• Page 5.4-4, modified the fourth paragraph on the page.

Chapter 6

• No changes.

Chapter 7

• No changes.

Chapter 8

• Page 8.1-6, modified the first paragraph of Section 8.1.3. • Page 8.1-9, modified the second and third paragraphs of Section 8.1.4.2. • Page 8.1-10, modified the second paragraph of Section 8.1.4.3, and added Items 1 thru 3. • Pages 8.4-1 thru 8.4-3, modified the third, sixth and tenth paragraphs of Section 8.4.1.

Chapter 9

• No changes .

• ED20170092 Page 2 of2

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• ED20170092

Enclosure 2

List of Drawing Changes


September 2017

Page 1 of 4

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NAC PROPRIETARY INFORMATION REMOVED

List of Drawing Changes, NAC-STC SAR, Revision 17C

Drawing 423-800, Sheet 1 of 3, Revision 19NP Sheet 1:

1. Added cloud to hide proprietary information added by DCR(L) 423-800-18PA.

Drawing 423-802, Sheets 1, 3 and 5of7, Revision 23

Sheet 1: 1. B.O.M., added Item 33, Qty "2" for Assy 99, Name "Screw Thread Insert", Material "St.

Stl.", Spec "Coml", Description Helicoil #1185-8CN", with symbol for delta note 33. 2. B.O.M., revised Item 28 Qty to "10", was "12" . 3. Revised delta note 28 that reads "Install Items 26, 27, 28, 32 & 33 (Screw Thread Inserts)

per manufacturer's instructions.", was "Install Items 26, 27, 28 & 32 (Screw Thread Inserts) per manufacturer's instructions.".

4. Revised note 7 by adding text to the end that reads "Alternate pre-bonded thickness of 8mm to lOmm for 304 St. Stl. and 6mm to 8mm for copper plates may be used."

5. Added delta note 33: "Thread insert length .5" to 1 "."

Sheet 3: 6. Zone B4, revised dimension to read, "161.0 (Lead Cavity)", was "161.0 (Lead)"

Sheet 5: 7. Zone A3, revised item balloon callout to "33" with delta note 33 symbol, was "28" and

revise text to "2X Yi-13 UNC-2B", was "2X Yi-13 UNC-2B x :[ 1.0".

Drawing 423-804, Sheet 1 of 2, Revision 12 Sheet 1:

1. Zone B7, revised counterbore to "0.62", was "0.56" for Item 7 counterbore feature .


1. Zones A6 & A5, removed weight callout under Assembly 99 and 98 callout.

ED20170092 Page 2 of 4

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1. Revised the material on item 3 (Plug) from "304 St. Stl." to "St. Stl." 2. Revised the description of item 3 from "Cajon #SS-2-PST" to 'Swagelok SS-2-PST".

Drawing 423-807, Sheets 1 thru 3 of 3, Revision 5 Sheet 1:

1. B.O.M., Item 8 (Plug), revised description to "PARKER #4 HP50N-SS", was "Made from MS51518845"

Sheet 2: 2. Zones F8 and D8, revised boss callouts to "SAE 11926" was "SAE 1514". 3. Zone A3, removed detail for Item 8 (Plug) modification.

Sheet 3: 4. Zone C7, revised boss callout to "SAE 11926" was "SAE 1514".

Drawing 423-811, Sheets 1 and 2of2, Revision 13 Sheet 1:

1. B.O.M., added Item 18, Name "Swage Ring Alt.", Material "304 St.Stl.", Spec "ASTM SA479", Description "1 1/2 Dia Bar".

2. B.O.M., revised Item 16 (Flange), Spec to "ASTM A276/A240", was "ASTM A276" and Description to "1 Bar/Plate" was "1 Bar".

3. Zone A6/7, relocated Item 9 (Washer) detail to sheet 2 and added detail for new Item 18 (Swage Ring Alt.).

Sheet 2: 4. Zone B8, removed all-around symbol from weld callout. 5. Added a Detail C-C with "Alternate Configuration" for spherical compression sleeve.

Drawing 423-812, Sheet 1of1, Revision 7 Sheet 1:

1. Zone E4, revised text to "USA/9235/B(U)F-96", was "USA/9235/B(U)F-85"


1. B.O.M., Item 2 (Washer), revised Spec to "ASTM A479/A276/A240", was "ASTM A479/A240" and revised Description to "Bar/Plate", was "5 Dia Bar/Plate" .

ED20170092 Page 3 of 4

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1. Revised note 2 to "(Deleted)", was "Assemble basket such that the notches in tubes (Item 5) are all directed towards the drain tube cut-out in the support disks.".

2. Revised portion of delta note 7 to read " .. .length by .28 from the largest ... ", was " .. .length by .28 [7] from the largest. .. ".

3. Zone F8, revised dimension to "(3.8)", was "(3.7)".


1. B.O.M., Item 1 (Plate), revised Material "6061-T651 AL.", was "6061-T6 AL.".

Drawing 423-878, Sheets 1 and 2 of 2, Revision 5 Sheet 1:

1. Added delta note 4 that reads: "Other side weld is optional.". 2. Added delta note 5 that reads: "Weld to be the full thickness ofltem 3 (Cladding).". 3. Zone 8A, revised weld callout to add fillet symbol and add delta note 5 symbol. 4. Zone 6A, revised weld note to "Both Sides TYP", was "All 4 Sides" 5. Zone F5/6, added fillet weld with note that reads "Both Sides TYP" with leader pointing

to top edge of cladding and added delta note 5 symbol. 6. Zone A6, removed "Scaled" from Detail A-A.

Sheet 2: 7. Zone C3, added delta note 4 symbol to weld callout.

ED20170092 Page 4 of 4

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• ED20170092

Enclosure 3

SAR Page Changes and LOEP


September 2017

Page I of I

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September 2017

Revision 17C

NAC-STC NAC Storage Transport Cask

SAFETY ANALYSIS REPORT

Non-Proprietary Version

Docket No. 71-9235

ANAC ~I INTERNATIONAL

Atlanta Corporate Headquarters: 3950 East Jones Bridge Road, Norcross, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www.nacintl.com

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NAC-STC SAR Docket No. 71-9235

September 2017 Revision 17C

List of Effective Pages

Chapter 1 Page 2.4.1-1 ............................. Revision 17

Page 2.4.2-1 ............................. Revision 17

Pages 1-i thru 1-ii .................... Revision 17 Page 2.4.3-1 ............................. Revision 17

Pages 1-iii thru 1-v ................ Revision 17C Pages 2.4.4-1 thru 2.4.4-6 ........ Revision 17

Page 1-vi ................................. Revision 17 Pages 2.4.4-7 thru 2.4.4-8 ..... Revision 17C

Pages 1-1 thru 1-11 ................. Revision 1 7 Page 2.4.4-9 ............................. Revision 17

Pages 1.1-1 thru 1.1-8 ............. Revision 17 Page 2.4.4-10 ........................ Revision 17C

Page 1.1-4 ............................. Revision 17C Page 2.4.5-1 ............................. Revision 17

Pages 1.1-1 thru 1.1-8 ............. Revision 17 Page 2.4.6-1 ............................. Revision 17

Pages 1.2-1 thru 1.2-7 ............. Revision 17 Pages 2.5.1-1thru2.5.1-37 ...... Revision 17

Page 1.2-8 ............................. Revision 17C Pages 2.5.2-1thru2.5.2-29 ...... Revision 17

Pages 1.2-9 thru 1.2-37 ........... Revision 17 Pages 2.6-1thru2.6-2 .............. Revision 17

Pages 1.2-38 thru 1.2-39 ....... Revision 17C Pages 2.6.1-1thru2.6.1-7 ........ Revision 17

Pages 1.2-40 thru 1.2-44 ......... Revision 17 Pages 2.6.2-1 thru 2.6.2-8 ........ Revision 17

Page 1.3-1 ............................... Revision 17 Page 2.6.3-1 ............................. Revision 17

Pages 1.4-1 thru 1.4-24 ........... Revision 17 Page 2.6.4-1 ............................. Revision 17

Pages 2.6.5-1 thru 2.6.5-2 ........ Revision 17

Chapter 2 Page 2.6.6-1 ............................. Revision 17

Page 2.6.7-1 ............................. Revision 17 Pages 2-i thru 2-lxvi ................ Revision 17 Pages 2.6.7.1-1 thru Page 2-1 .................................. Revision 17 2.6.7.1-17 .......................... Revision 17 Pages 2.1.1-1 thru 2.1.1-2 ....... Revision 17 Pages 2.6.7.2-1 thru Page 2.1.1-3 .......................... Revision 17C 2.6.7.2-19 .......................... Revision 17 Pages 2.1.1-4 thru 2.1.1-5 ....... Revision 17 Pages 2.6.7.3-1 thru Pages 2.1.2-1 thru 2.1.2-5 ....... Revision 17 2.6.7.3-11 .......................... Revision 17 Pages 2.1.3-1 thru 2.1.3-15 ..... Revision 17 Pages 2.6.7.4-1 thru Pages 2.2-1 thru 2.2-8 ............. Revision 17 2.6.7.4-59 .......................... Revision 17 Pages 2.3.1-1 thru 2.3.1-2 ....... Revision 17 Pages 2.6.7.5-1 thru Pages 2.3.2-1thru2.3.2-2 ....... Revision 17 2.6.7.5-4 ............................ Revision 17 Page 2.3.2-3 .......................... Revision 17B Pages 2.6.7.5-5 thru Pages 2.3.2-4 thru 2.3.2-5 ....... Revision 17 2.6.7.5-8 ......................... Revision 17B Pages 2.3.3-1 thru 2.3.3-2 ....... Revision 17 Pages 2.6.7.5-9 thru Pages 2.3.4-1thru2.3.4-3 ....... Revision 17 2.6. 7 .5-13 .......................... Revision 17 Pages 2.3.5-1thru2.3.5-2 ....... Revision 17 Pages 2.6.7.6-1 thru Pages 2.3 .6-1 thru 2.3 .6-5 ....... Revision 17 2.6.7.6-13 .......................... Revision 17 Page 2.3.7-1 ............................ Revision 17 Pages 2.6.7.7-1 thru Page 2.3.8-1 ............................ Revision 17 2.6.7.7-5 ............................ Revision 17

.. Page 2.4-1 ............................... Revision 17

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September 201 7 Revision 17C

List of Effective Pages (continued)

Page 2.6.8-1 ............................ Revision 17 Pages 2.6.12.13-1 thru

Page 2.6.9-1 ............................ Revision 17 2.6.12.13-4 ........................ Revision 17

Page 2.6.10-1 .......................... Revision 17 Pages 2.6.13-1 thru 2.6.13-3 .... Revision 17

Pages 2.6.10.1-1 thru Pages 2.6.13.1-1 thru

2.6.10.1-2 ......................... Revision 17 2.6.13.1-2 .......................... Revision 17





Pages 2.6.11-1 ....................... Revision 17B Pages 2.6.13.4-1 thru

Pages 2.6.11.1-1 thru 2.6.13 .4-5 .......................... Revision 17

2.6.11.1-4 ....................... Revision 17B Pages 2.6.13.5-1 thru

Pages 2.6.11.2-1 thru 2.6.13.5-2 .......................... Revision 17

2.6.11.2-11 ..................... Revision 17B Pages 2.6.13 .6-1 thru

Page 2.6.11.3-1 ....................... Revision 17 2.6.13.6-2 .......................... Revision 17

Pages 2.6.12-1 thru 2.6.12-5 ... Revision 17 Pages 2.6.13.7-1 thru


Pages 2.6.12.2-1 thru Page 2.6.13.8-1 ........................ Revision 17

2.6.12.2-5 ......................... Revision 17 Page 2.6.13.9-1 ........................ Revision 17

Pages 2.6.12.3-1 thru Page 2.6.13.10-1 ...................... Revision 17

2.6.12.3-7 ......................... Revision 17 Pages 2.6.13.11-1 thru

Pages 2.6.12.4-1 thru 2.6.13.11-3 ........................ Revision 17



2.6.12.5-3 ......................... Revision 17 Pages 2.6.14-1 thru

Pages 2.6.12.6-1 thru 2.6.14-8 ............................. Revision 17



2.6.12.7-22 ....................... Revision 17 Pages 2.6.14.2-1 thru





Page 2.6.12.10-1 ..................... Revision 17 2.6.14.4-4 .......................... Revision 17

Page 2.6.12.11-1 ..................... Revision 17 Pages 2.6.14.5-1 thru

Page 2.6.12.12-1 ..................... Revision 17 2.6.14.5-3 .......................... Revision 17

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Page 2.6.14.6-1 ....................... Revision 17 Pages 2.6.16.3-1 thru






Page 2.6.14.10-1 ..................... Revision 17 Pages 2.6.16.6-1 thru





Page 2.6.15-1 .......................... Revision 17 2.6.16.8-7 .......................... Revision 17

Pages 2.6.15 .1-1 thru Page 2.6.16.9-1 ........................ Revision 17

2.6.15.1-2 ......................... Revision 17 Page 2.6.16.10-1 ...................... Revision 17


2.6.15.2-7 ......................... Revision 17 2.6.16.11-4 ........................ Revision 17



Pages 2.6.15 .4-1 thru Pages 2.6.16.13-1 thru


Page 2.6.15 .5-1 ....................... Revision 17 Page 2.6.16.14-1 ...................... Revision 17

Pages 2.6.15.6-1 thru Pages 2.6.17-1 thru

2.6.15.6-3 ......................... Revision 17 2.6.17-13 ........................... Revision 17

Page 2.6.15.7-1 ....................... Revision 17 Pages 2.6.18-1 thru

Page 2.6.15.8-1 ....................... Revision 17 2.6.18-6 ............................. Revision 17

Page 2.6.15.9-1 ....................... Revision 17 Pages 2.6.19-1 thru

Page 2.6.15.10-1 ..................... Revision 17 2.6.19-23 ........................... Revision 17


2.6.15 .11-3 ....................... Revision 17 2.6.20-20 ........................... Revision 17


2.6.15.12-2 ....................... Revision 17 2.6.21.-2 ............................ Revision 17

Pages 2.6.16-1 thru Pages 2.7-1 thru 2.7-2 .............. Revision 17

2.6.16-6 ............................ Revision 17 Pages 2.7.1-1thru2.7.1-2 ........ Revision 17




2.6.16.2-11 ....................... Revision 17 2.7.1.2-15 .......................... Revision 17

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2.7.1.3-9 ........................... Revision 17 2.7.8.3-13 .......................... Revision 17


2. 7.1.4-11. ........................ Revision 17 2.7.8.4-10 .......................... Revision 17

Pages 2.7.1.5-1 thru Page 2.7.8.5-1 .......................... Revision 17

2.7.1.5-3 ........................... Revision 17 Pages 2.7.9-1 thru 2.7.9-40 ...... Revision 17


2.7.1.6-16 ......................... Revision 17 2.7.10-12 ........................... Revision 17

Page 2. 7 .2-1 ............................ Revision 1 7 Pages 2.7.11-1 thru

Pages 2.7.2.1-1 thru 2.7.11-16 ........................... Revision 17

2.7.2.1-5 ........................... Revision 17 Pages 2.7.12-1 thru


2.7.2.2-9 ........................... Revision 17 Pages 2.7.13-1 thru


2.7.2.3-6 ........................... Revision 17 Pages 2.7.13.1-1 thru


2.7.2.4-7 ........................... Revision 17 Pages 2.7.13.2-1 thru

Page 2.7.2.5-1 ......................... Revision 17 2.7.13.2-2 .......................... Revision 17

Page 2.7.2.6-1 ......................... Revision 17 Pages 2.7.13.3-1 thru

Page 2.7.3.1-1 ......................... Revision 17 2.7.13.3-4 .......................... Revision 17

Pages 2.7.3.2-1 thru Pages 2. 7 .13 .4-1 thru

2.7.3.2-5 ........................... Revision 17 2. 7 .13 .4-8 .......................... Revision 17


2.7.3.3-3 .................. ; ........ Revision 17 2.7.13.5-2 .......................... Revision 17


2.7.3.4-2 ........................... Revision 17 2. 7.14-13 ........................... Revision 17

Page 2.7.3.5-1 ......................... Revision 17 Pages 2.7.15-1 thru

Page 2.7.3.6-1 ......................... Revision 17 2.7.15-16 ........................... Revision 17

Page 2. 7.4-1 ............................ Revision 17 Page 2.8-1 ................................ Revision 17

Page 2.7.5-1 ............................ Revision 17 Pages 2.9-1 thru 2.9-11 ............ Revision 17

Page 2. 7 .6-1 ............................ Revision 17 Pages 2.10.1-1 thru

Pages 2.7.7-1 thru 2.7.7-4 ....... Revision 17 2.10.1-4 ............................. Revision 17

Pages 2.7.8-1 thru 2.7.8-4 ....... Revision 17 Pages 2.10.2-1 thru


2.7.8.1-43 ......................... Revision 17 Pages 2.10.3-1 thru


2.7.8.2-2 ........................... Revision 17

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Pages 2.10.4-1 thru

2.10.4-288 ........................ Revision 17

Pages 2.10.5-1 thru

2.10.5-22 .......................... Revision 17

Pages 2.10.6-1 thru

2.10.6.-36 ......................... Revision 17

13 drawings in Sections

2.10.6.6 and 2.10.6.7

Pages 2.10.6-37 thru

2.10.6-88 .......................... Revision 17

Pages 2.10.7-1 thru

2.10.7-26 .......................... Revision 17

Pages 2.10.8-1 thru 2.10.8-24. Revision 17

Pages 2.10.9-1 thru 2.10.9-11 . Revision 17


2.10.10-11 ........................ Revision 17


2.10.11-8 .......................... Revision 17


2.10.12-31 ........................ Revision 17

4 drawings in Section 2.10.12

Pages 2.11.1-1 thru 2.11.1-2 ... Revision 17


Page 2.11.3-1 .......................... Revision 17

Page 2.11.4-1 .......................... Revision 17

Page 2.11.5c-1 .......................... Revision 17


Page 2.11.6.12-1 thru

2.11.6.12-62 ..................... Revision 17

Pages 2.11.6.13-1 thru

2.11.6.13-35 ..................... Revision 17


2.11.6.14-10 ..................... Revision 17

Page 2.11.6.15-1 ...................... Revision 17

Pages 2.11.7-1 thru 2.11.7-8 .... Revision 17


2.11.7.8-34 ........................ Revision 17


2.11.7.9-14 ........................ Revision 17


2.11. 7.10-5 ........................ Revision 17

Page 2.11.8-1 ........................... Revision 17

Pages 2.11.9-1 thru

2.11.9-10 ........................... Revision 17

Chapter 3

Page 3-i ................................. Revision 17B

Page 3-ii ................................... Revision 17

Pages 3-iii thru 3-vi .............. Revision 17B

Page 3-vii ................................. Revision 17

Pages 3.1-1thru3.1-12 ............ Revision 17


Pages 3.3-1 thru 3.3-6 .............. Revision 17

Pages 3 .4-1 thru 3 .4-44 ............ Revision 17

Pages 3.4-45 thru 3.4-86 ....... Revision 17B


Page 3.6-1 ................................ Revision 17


Pages 3.6.2-1thru3.6.2-3 ........ Revision 17


Pages 3.6.4-1 thru 3.6.4-24 ...... Revision 17


Chapter 4

Pages 4-i thru 4-iii ................... Revision 17

Pages 4.1-1thru4.1-9 .............. Revision 17

Pages4.2-1thru4.2-17 ............ Revision17

Pages 4.3-1 thru 4.3-4 .............. Revision 17

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Page 4.4-1 ............................... Revision 17 Pages 6.5.1-1thru6.5.1-21.. .... Revision 17

Pages 4.5-1 thru 4.5-13 ........... Revision 17 Pages 6.5.2-1 thru 6.5.2-20 ...... Revision 17

Page 4.5-14 ........................... Revision 17C Pages 6.6-1 thru 6.6-2 .............. Revision 17

Pages 4.5-15 thru 4.5-33 ......... Revision 17 Pages 6.7-1thru6.7-333 .......... Revision 17

Pages 4.6-1thru4.6-2 ............. Revision 17 Page 6. 8-1 ................................ Revision 17


Chapter 5 Pages 6.8.2-1 thru 6.8.2-2 ........ Revision 17

Pages 6.8.3-1 thru 6.8.3-20 ...... Revision 17

Pages 5-i thru 5-xiii ................. Revision 17 Pages 6.8.4-1 thru 6.8.4-34 ...... Revision 17

Pages 5-1 thru 5-3 ................... Revision 17 Pages 6.8.5-1 thru 6.8.5-34 ...... Revision 17

Pages 5.1-1thru5.1-30 ........... Revision 17 Page 6.8.6-1 ............................. Revision 17

Pages 5.2-1thru5.2-40 ........... Revision 17 Pages 6.8.7-1 thru 6.8.7-25 ...... Revision 17

Pages 5.3-1 thru 5.3-33 ........... Revision 17

Pages 5.4-1 thru 5.4-3 ............. Revision 17 Chapter 7

Page 5.4-4 ............................. Revision 17C

Pages 5.4-5 thru 5.4-41 ........... Revision 17 Pages 7-i thru 7-ii .................... Revision 17

Pages 5.5-1thru5.5-61 ........... Revision 17 Pages 7-1 thru 7-3 .................... Revision 17

Page 5.6-1 ............................... Revision 17 Pages 7.1-1 thru 7 .1-13 ............ Revision 17

Pages 5 .6.1-1 thru 5 .6.1-9 ....... Revision 17 Pages 7.2-1 thru 7.2-5 .............. Revision 17

Pages 5.6.2-1 thru 5.6.2-20 ..... Revision 17 Pages 7.3-1 thru 7.3-9 .............. Revision 17

Pages 5.6.3-1thru5.6.3-13 ..... Revision 17 Pages 7.4-1 thru 7.4-4 .............. Revision 17

Pages 5.6.4-1 thru 5.6.4-34 ..... Revision 17 Page 7.5-1 ................................ Revision 17

Page 5.6.5-1 ............................ Revision 17 Pages 7.6-1 thru 7.6-5 .............. Revision 17

Pages 5.6.6-1 thru 5.6.6-57 ..... Revision 17

Chapter 6 Chapter 8

Pages 6-i thru 6-ix ................... Revision 17 Page 8-i thru 8-ii ................... Revision 17B

Pages 6.1-1 thru 6.1-6 ............. Revision 17 Page 8-1 ................................... Revision 17

Pages 6.2-1 thru 6.2-11 ........... Revision 17 Pages 8.1-1thru8.1-5 .............. Revision 17

Pages 6.3-1 thru 6.3-10 ........... Revision 17 Page 8.1-6 ............................. Revision 17C

Pages 6.4-1 thru 6.4-2 ............. Revision 17 Pages 8 .1-7 thru 8 .1-8 .............. Revision 17

Page 6.4.1-1 ............................ Revision 17 Pages 8.1-9 thru 8.1-10 ......... Revision 17C

Pages 6.4.2-1 thru 6.4.2-9 ....... Revision 17 Pages 8 .1-11 thru 8 .1-12 ....... Revision 17B

Pages 6.4.3-1 thru 6.4.3-29 ..... Revision 17 Pages 8.1-13 thru 8.1-24 .......... Revision 17

Pages 6.4.4-1 thru 6.4.4-30 ..... Revision 17 Pages 8.2-1 thru 8.2-2 .............. Revision 17

Pages 6.5-1 thru 6.5-2 ............. Revision 17 Pages 8.2-3 thru 8.2-6 ........... Revision 17B

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Pages 8.2-7 thru 8.2-8 ............. Revision 17

Page 8.3-1 ............................... Revision 17

Pages 8.4-1 thru 8.4-3 ........... Revision 17C

Page 8.4-4 ............................... Revision 17

Pages 8.4-5 thru 8.4-14 ......... Revision 17B

Chapter 9

Page 9-i ................................... Revision 17

Pages 9-1 thru 9-13 ................. Revision 17

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NAC-STC SAR

Docket No. 71-9235

Drawin~ Number 423-800, sheets 1-3

423-800, sheets 1-3

423-802, sheets 1-7

423-803, sheets 1-2

423-804, sheets 1-3

423-805, sheets 1-2

423-806, sheets 1-2

423-807, sheets 1-3

423-209

423-210

423-257

423-258

423-811, sheets 1-2

423-812

423-843

423-859

423-870

423-871

423-872

423-873

423-874

423-875, sheets 1-2

423-878, sheets 1-2

423-880

423-880

423-900

423-901

455-800, sheets 1-2

Revision No.

Rev 19pCil

Rev 19NP(1l

Rev 23

Rev14

Rev 12

Rev 8

Rev 13

Rev 5

Rev 0

Rev 0

Rev2

Rev2

Rev 13

Rev7

Rev 6

Rev 1

Rev7

Rev 5

Rev 6

Rev2

Rev 3

Rev 11

Rev 5 Rev 2p(I)

Rev lNP(ll

Rev 8

Rev 3

Rev2

List of Drawings

Title Cask Assembly - NAC-STC Cask

Cask Assembly - NAC-STC Cask

Cask Body - NAC-STC Cask

Lid Assembly - Inner, NAC-STC Cask

Details - Inner Lid, NAC-STC Cask

Lid Assembly - Outer, NAC-STC Cask

September 2017

Revision 17C

Port Coverplate Assy - Inner Lid, NAC-STC Cask

Assembly, Port Cover, NAC-STC Cask

Impact Limiter Assy - Upper, NAC-STC Cask

Impact Limiter Assy - Lower, NAC-STC Cask

Balsa Impact Limiter, Upper, NAC-STC Cask

Balsa Impact Limiter, Lower, NAC-STC Cask

Details - NAC-STC Cask

Nameplates- NAC-STC Cask

Transport Assembly, Balsa Impact Limiters, NAC-STC

Attachment Hardware, Balsa Limiters, NAC-STC

Fuel Basket Assembly, PWR, 26 Element, NAC-STC Cask

Bottom Weldment, Fuel Basket, PWR, 26 Element, NAC-STC Cask

Top Weldment, Fuel Basket, PWR, 26 Element, NAC-STC Cask

Support Disk and Misc. Basket Details, PWR, 26 Element, NAC-STC Cask Heat Transfer Disk, Fuel Basket, PWR, 26 Element, NAC-STC Cask

Tube, NAC-STC Cask

Alternate Tube Assembly, NAC-STC Cask

Shielded Thermal Shunt Assembly, NAC-STC Cask

Shielded Thermal Shunt Assembly, NAC-STC Cask

Package Assembly Transportation, NAC-STC Cask

Transportation Package Concept, NAC-STC Cask

Assembly, Transport Cask, MPC-Yankee (1) Proprietary and Non-proprietary drawing versions are only included in their respective SAR versions .

1-iii

NAC-STC SAR

Docket No. 71-9235

Drawing Number 455-801, sheets 1-2

455-820, sheets 1-2

455-870

455-871, sheets 1-2

455-871, sheets 1-3

455-872, sheets 1-2

455-872, sheets 1-2

455-873 455-881, sheets 1-3

455-887, sheets 1-3

455-888, sheets 1-2

455-891, sheets 1-2

455-891, sheets 1-3

455-892, sheets 1-2

455-892, sheets 1-3

455-893

455-894

455-895, sheets 1-2

455-895, sheets 1-2

455-919

414-801, sheets 1-2

414-820

414-870

414-871, sheets 1-2

414-872, sheets 1-3

414-873

414-874

414-875

414-881, sheets 1-2

414-882, sheets 1-2

September 2017

Revision 17C

List of Drawings (continued)

Revision No. Title

Rev4 Assembly, Transp01i Cask, NAC-MPC

Rev 3 Spacers, Transport Cask, MPC-Yankee

Rev 5 Canister Shell, MPC-Yankee

Rev 8 Details, Canister, MPC-Yankee

Rev 7P2 Details, Canister, MPC-Yankee

Rev 12 Assembly, Transportable Storage Canister (TSC), MPC-Yankee

Rev llPl Assembly, Transportable Storage Canister (TSC), MPC-Yankee

Rev4 Assembly, Drain Tube, Canister, MPC-Yankee Rev 8 PWR Fuel Tube, MPC-Yankee

Rev4 Basket Assembly, 24 GTCC Container, MPC-Yankee

Rev 8 Assembly, Transportable Storage Canister (TSC), 24 GTCC Container, MPC-Yankee

Rev 1 Bottom Weldment, Fuel Basket, MPC-Yankee

Rev 2PO Bottom Weldment, Fuel Basket, MPC-Yankee

Rev 3 Top Weldment, Fuel Basket, MPC-Yankee

Rev 3PO Top Weldment, Fuel Basket, MPC-Yankee

Rev 3 Support Disk and Misc. Basket Details, MPC-Yankee

Rev2 Heat Transfer Disk, Fuel Basket, MPC-Yankee

Rev 5 Fuel Basket Assembly, MPC-Yankee

Rev 5PO Fuel Basket Assembly, MPC-Yankee

Rev2 Retainer, United Nuclear Test Assy, MPC-Yankee

Rev2 Cask Assembly, NAC-STC, CY-MPC

RevO Canister Spacer CY-MPC

Rev 3 Canister Shell, CY-MPC

Rev6 Details, Canister CY-MPC

Rev6 Assembly, Transpo1iable Storage Canister (TSC), CY-MPC

Rev2 Drain Tube Assembly, CY-MPC

RevO Shim, Canister, CY-MPC

RevO Spacer Shim, Canister, CY-MPC

Rev4 Fuel Tube, Transportable Storage Canister (TSC), CY-MPC

Rev4 Oversize Fuel Tube, Transportable Storage Canister (TSC), CY-MPC

1-iv

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NAC-STC SAR

Docket No. 71-9235

September 2017

Revision 17C

List of Drawings (Continued)

Revision Drawin2 Number No. Title

414-887, sheets 1-4 Rev4 Basket Assembly, GTCC, CY-MPC

414-888, sheets 1-2 Rev4 Canister Shell, GTCC, CY-MPC

414-889, sheets 1-3 Rev7 Assembly, Transportable Storage Canister (TSC), GTCC, CY-MPC

414-891 Rev 3 Bottom Weldment, Fuel Basket CY-MPC

414-892, sheets 1-3 Rev 3 Top Weldment Fuel Basket CY-MPC

414-893, sheets 1-2 Rev2 Support Disk and Misc. Basket Details CY-MPC

414-894 Rev 0 Heat Transfer Disk, Fuel Basket CY-MPC

414-895, sheets 1-2 Rev4 Fuel Basket Assembly CY-MPC

Yankee-Class Reconfi~ ured Fuel Assembly YR-00-060 RevD3 Yankee-Class Reconfigured Fuel Assembly

YR-00-061 RevD4 Yankee-Class Reconfigured Fuel Assembly Shell Weldment

YR-00-062, Sheet 1 RevD4 Yankee-Class Reconfigured Fuel Assembly Top End Fitting Assembly

YR-00-062, Sheet 2 RevD2 Yankee-Class Reconfigured Fuel Assembly Top End Plate

YR-00-062, Sheet 3 RevDl Yankee-Class Reconfigured Fuel Assembly Top End Template

YR-00-063 RevD4 Yankee-Class Reconfigured Fuel Assembly Bottom End Fitting Assy.

YR-00-064 RevD4 Yankee-Class Reconfigured Fuel Assembly Nozzle Bolt and Alignment Pin

YR-00-065 RevD2 Yankee-Class Reconfigured Fuel Assembly Fuel Basket Assembly

YR-00-066, Sheet 1 RevD5 Yankee-Class Reconfigured Fuel Assembly Fuel Tube Assembly

YR-00-066, Sheet 2 RevD3 Yankee-Class Reconfigured Fuel Assembly Fuel Tube Assembly

Yankee Rowe Damaged Fuel Can 455-901 Rev OPO Can Assembly, Damaged Fuel, MPC-Y ankee

455-902, sheets 1-5 Rev OP4 Can Details, Damaged Fuel, MPC-Yankee

Connecticut Yankee Dama2ed Fuel Can 414-901 Rev 1 Assembly, Damaged Fuel Can, CY-MPC

414-902, sheets 1-3 Rev 3 Details, Damaged Fuel Can, CY-MPC

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NAC-STC SAR

Docket No. 71-9235

Drawing Number Revision

No. Title

April 2011

Revision 17

Connecticut Yankee Reconfigured Fuel Assembly

414-903, sheets 1-2 Rev 1 Reconfigured Fuel Assembly, CY- MPC

414-904, sheets 1-3 Rev 0 Details, Reconfigured Fuel Assembly, CY- MPC

STC-LACBWR System Components

630045-800, sheets 1-2 0 Assembly, Transport Cask, MPC-LACBWR

630045-820 0 Spacer, Transport Cask, MPC-LACBWR

630045-870 2 Shell Weldment, Canister (TSC), MPC-LACBWR

630045-871, sheets 1-4 2 Details TSC, MPC-LACBWR

630045-872, sheets 1-2 1 Assembly, Transportable Storage Canister (TSC), MPC-LACBWR

630045-873 1 Assembly, Drain Tube TSC, MPC-LACBWR

630045-877 1 Bottom Weldment, Fuel Basket, MPC-LACBWR

630045-878 1 Top Weldment, Fuel Basket, MPC-LACBWR

630045-881, sheets 1-2 1 Fuel Tube Assembly, MPC-LACBWR

630045-893 1 Suppmi Disk, Fuel Basket, MPC-LACBWR

630045-894 1 Heat Transfer Disk, Fuel Basket, MPC-LACBWR

630045-895, sheets 1-3 1 Fuel Basket Assembly, 68 Element BWR, MPC-LA CB WR

630045-901 0 Assembly, Damaged Fuel Can (DFC), MPC-

LA CB WR

630045-902, sheets 1-2 1 Details, Damaged Fuel Can (DFC), MPC-LACBWR

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NAC-STC SAR

Docket No. 71-9235

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Revision 17

storage licensing requirements also provide added safety for transport conditions. The design

features of the NAC-STC include: inner and outer lids, redundant seals at each containment

boundary penetration, cavity penetrations located in the inner lid, and a puncture-resistant outer

shell and outer lid.

This Safety Analysis Report is written for transport cask licensing only. Design features related

to storage cask licensing are included for clarity and for ease of review.

The NAC-STC closure design provides dual lids for transport and storage operations, as well as

protection of the vent and drain ports that are located in the inner lid. This design permits

perfo1mance of a periodic verification leak test on the containment seals prior to transport

following extended storage. Both the inner and outer lids are installed during transport and

storage.

The inner lid and its 0-rings are the major removable components in the primary containment

boundary. Two concentric 0-rings are used to seal the inner lid to the cask cavity flange. An

0-ring test p01i connects to the annulus between the two 0-rings to permit leak testing .

The vent and drain port coverplates, which protect the vent and drain ports located in the inner

lid, are also part of the primary containment boundary of the cask. Each coverplate is sealed by

two concentric 0-rings.

As described in Section 4.1, the inner 0-rings of the inner lid and two coverplates are the

containment boundary for contents (either directly loaded fuel or a loaded transportable storage

canister) that is loaded for transport without interim site storage. The outer 0-rings of these

components are the containment boundary for directly loaded fuel that is to be transported after

an extended period of storage.

The inner lid and coverplate 0-rings may be either metallic or non-metallic as shown in the

License Drawings. However, metallic 0-rings must be used when the NAC-STC is directly

loaded for long-term storage or for the transport of canistered contents. The metallic 0-rings

provide long-term sealing capability in an elevated temperature and radiation environment.

1.1-3

NAC-STC SAR

Docket No. 71-9235

September 2017

Revision 17C

The outer lid provides a sealed secondary closure for transport and storage operations using a

single 0-ring. The 0-ring may be either metallic or non-metallic. The outer lid protects the

inner lid and the vent and drain ports from external puncture events.

There are two penetrations in the top forging: an interlid port, which serves primarily as a drain

for the interlid region, and a pressure port, which may house a transducer that monitors the

pressure in the interlid region during storage. During transport, the pressure port is closed by a

threaded plug. The pressure pmi plug is covered by the transpo1i port coverplate. The interlid

and pressure port penetrations in the top forging are protected by SA-705, Type 630, 17-4

precipitation-hardened (PH) stainless steel port covers with two Viton 0-rings.

The body of the NAC-STC is a smooth right-circular cylinder of multiwall construction,

consisting of stainless steel inner and outer shells separated by lead gamma radiation shielding,

which is poured in place. The center section of the inner shell is fabricated from Type 304

stainless steel. At each end of the inner shell center section, inner shell rings fabricated from

Type XM-19 stainless steel provide the transition to the bottom inner forging and the top forging.

The outer shell is also fabricated from Type 304 stainless steel. The inner and outer shells are

welded to the Type 304 stainless steel top forging, which is a ring that is machined to mate with

the inner and outer lids. The inner and outer shells are also welded to the Type 304 stainless

steel bottom inner and outer forgings, respectively. The cask bottom consists of the two forgings

and a plate with neutron shield material sandwiched between the bottom inner forging and the

bottom plate. Neutron shield material is also placed in an ammlus that surrounds the cask outer

shell along the length of the cask cavity. The neutron shielding material is a solid synthetic

polymer (NS-4-FR). The neutron shield annulus is enclosed by a Type 304 stainless steel shell

and by end plates that are welded to the outer shell. Two pressure relief valves are provided in

the bottom of the neutron shield annulus to relieve pressure in the neutron shield annulus due to a

severe thermal accident condition (fire). Neutron shielding is also provided on the top of the

cask by a layer ofNS-4-FR enclosed in the inner lid.

Redundant lifting capability for the NAC-STC is provided by four lifting trunnions welded to the

top forging at 90-degree intervals. Rotation trunnion recesses are located on the outer shell near

1.1-4

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• NAC-STC SAR

Docket No. 71-9235

April 2011

Revision 17

holes for the attachment of a lid-lifting device and for the attachment of the upper transport

impact limiter. As shown on Drawing 423-805, the 0-ring groove on the underside of the outer

lid is either square to accommodate a metallic 0-ring or has a truncated triangular shape to

accommodate a Viton 0-ring.

1.2.1.2.4 Ports and Po1i Covers

The NAC-STC design includes five ports: three in the inner lid and two in the top forging. The

vent, drain and interseal test ports are recessed in the im1er lid and provide access to the cask

contaimnent. Recessed in the top forging are two noncontaimnent ports, the interlid port for

interlid region drainage and outer lid 0-ring leak testing, and the pressure port, which is provided

for monitoring of the pressure in the interlid region during storage.

The vent port is a 1.0-inch diameter penetration through the inner lid and is closed by a

quick-disconnect valved nipple (quick disconnect). The quick disconnect is not considered to be

a contaimnent barrier. The vent port is used to access the cask cavity following the fuel loading

to drain, diy, leak test and backfill it with inert gas prior to transport. The vent port coverplate

uses a two 0-ring design, similar to the im1er lid. The 0-rings may be either metallic or non-

• metallic, depending on the cask use. Metallic 0-rings are used for storage and for transport

following storage. Either metallic or non-metallic 0-rings may be used for transport without

interim storage after loading. The outer metallic 0-ring provides the primary contaimnent seal

for transport after storage, while the inner 0-ring (either metallic or non-metallic) provides the

primary contaimnent seal for transport without interim storage after loading

•

The drain port is a 1.0-inch diameter penetration through the inner lid that is used to fill and drain

the cask cavity. The drain port is also closed by a quick disconnect, which is not considered to

be a contaimnent barrier. Similar to the vent port, the drain port coverplate uses a two 0-ring

design. The 0-rings may be either metallic or non-metallic, depending on the cask use. Metallic

0-rings are used for storage and for transport following storage. Either metallic or non-metallic

0-rings may be used for transport without interim storage after loading. The outer metallic 0-

ring provides the primary containment seal for transport after storage, while the inner 0-ring

(either metallic or non-metallic) provides the primary containment seal for transport without

interim storage after loading. Alignment marks on the top surface of the inner lid and the top

forging assist in aligning the drain port in the lid and the drain tube in the cask cavity. The

interseal test port is also closed by a quick disconnect, which is not considered to be a

containment baiTier. The interseal test port contaimnent is a threaded plug with a metallic 0-ring .

1.2-7

NAC-STC SAR

Docket No. 71-9235

September 201 7

Revision 17C

The pressure port, located in the top forging, houses the transducer that monitors the pressure in the

interlid region during storage. The pressure transducer is removed during transpo1i. The interlid

port penetrates the top forging into the region between the inner and the outer lids and serves as a

drain for the interlid region and as a port to pressurize the interlid region for seal testing purposes.

The interlid port is closed by a quick disconnect. The basic geometry of the interlid and pressure

ports and port covers is identical. Each port has a 4.5-inch diameter opening that is a minimum of

1.1 inches deep. Concentric with the port opening is a 2.93-inch diameter bore. This bore acts as a

lead-in to the 2.875-inch diameter bore that serves as the sealing surface for the two Viton 0-rings

in the port cover.

Both of the port covers are fabricated from SA-705, Type 630, H1150, 17-4 PH stainless steel.

The port covers resemble a cup-shape and have the geometrical appearance of a thick round end

plate with a cylindrical body. The end plate of the pmi cover is 4.5 inches in diameter and 1.0

inch thick. The three 3/8 - 16 UNC port cover bolts, which are fabricated from SA-193, Grade

B6, Type 410 stainless steel, are countersunk flush with the top of the port cover. There are two

Vi ton 0-rings on the cylindrical body of the port covers with a seal test port between the 0-rings.

A retainer is bolted to the open end of the cylindrical body of the port cover to retain the 0-rings

and the spacer between them after assembly. The port cover design permits the thick end plate to

absorb an impact, while any deflection of the end plate results in the 0-rings sliding in the bore

of the port with the seal maintained.

The basic geometry of the vent pmi and coverplate, and the drain port and coverplate, are

identical to each other. Each port has a 6.53-inch diameter opening in the inner lid that is 1.8

inches deep. Concentric with the port opening is a 3.25-inch diameter bore that houses the

1.0-inch diameter quick disconnect. As shown in Drawing 423-806, the 1.0-inch thick vent and

drain port coverplates are fabricated from SA-240, Type 304 stainless steel. When installed, the

port coverplates are recessed 0.8 inch below the top surface of the inner lid. The vent and drain

port coverplates are sealed to the inner lid by the metallic 0-rings on the bottom face of each port

coverplate. The four 1/2 - 13 UNC port coverplate bolts are fabricated from SA-193, Grade B6,

Type 410 stainless steel. The bolt holes are countersunk so that the bolt heads are flush with the

top of the port coverplate.

1.2-8

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NAC-STC SAR

Docket No. 71-9235

April 2011

Revision 17

Table 1.2-1 Design Characteristics of the NAC-STC (continued)

Design Characteristics Dimension 1 Material

Yankee-MPC Canister Fuel Basket

- End Weldments 0.5 x 68.98 dia. Type 304 Stainless Steel

- Support Disks 0.5 x 69.15 dia. Type 17-4 PH Stainless Steel

- Heat Transfer Disks 0.5 x 68.87 dia. Type 6061-T651 Aluminum Alloy

-Tube 7.80 x 7.80 x 0.048 Type 304 Stainless Steel encasing neutron absorber

- Spacers 2.5 dia. Type 304 Stainless Steel

- Tie Rods (8) 1-1/8 dia. Type 304 Stainless Steel

Yankee-MPC Canister GTCC Basket

- Support Walls 2.5 x 111.3 Type 304 Stainless Steel

- Support Disks 1.0 x 68.98 dia. Type 304 Stainless Steel

-Tube 8.32 x 8.32 x 0.25 Type 304 Stainless Steel

CY-MPC Canister Fuel Basket

- End W eldments 0.5 x 68.98 dia. Type 304 Stainless Steel

- Support Disks 0.5 x 69.15 dia. Type 17-4 PH Stainless Steel

- Heat Transfer Disks 0.5 x 68.87 dia. Type 6061-T651 Aluminum Alloy

-Tube 8.72 x 8.72 x 0.048 Type 304 Stainless Steel encasing neutron absorber

- Oversized Tube 9.12 x 9.12 x 0.048 Type 304 Stainless Steel encasing neutron absorber

- Spacers 2.88 dia. Type 304 Stainless Steel

- Tie Rods (6) 1-5/8 dia. Type 304 Stainless Steel

1. Dimensions in inches unless otherwise noted .

1.2-37

NAC-STC SAR

Docket No. 71-9235

September 2017

Revision 17C


Design Characteristics Dimension1 Material CY-MPC Canister GTCC Basket

- Support Walls 1.75 x 141.5 Type 304 Stainless Steel

- Support Ribs 1.25 x 141.5 Type 304 Stainless Steel

- Tube (Inside Dimension) 8.74 x 8.74 x 0.375 Type 304 Stainless Steel

Seals (0-rings) for Storage Configuration

- Inner Lid

- Inner 0.25 dia. x 72.251 dia. Type 321 Stainless Steel

- Outer 0.25 dia. x 73.497 dia. Type 321 Stainless Steel

- Port Coverplates

- Inner 0.125 dia. x 3.875 dia. Type 321 Stainless Steel

- Outer 0.125 dia. x 4.500 dia. Type 321 Stainless Steel

- Outer Lid 0.250 dia. x 82.060 dia. Type 321 Stainless Steel

- Port Covers

- Primary 0.103 dia. x 2.675 dia. Viton

- Secondary 0.103 dia. x 2.675 dia. Viton

I. Dimensions in inches unless otherwise noted.

1.2-38

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NAC-STC SAR

Docket No. 71-9235

September 201 7

Revision 17C


Design Characteristics Dimension1 Material

Seals (0-rings) for Immediate Transp011 Configuration

- Inner Lid

- Inner 0.25 dia. x 72.251 dia. Viton2

- Outer 0.25 dia. x 73.497 dia. Viton2

- Port Coverplates

- Inner 0.125 dia. x 3.875 dia. Viton or Type 321 Stainless Steel

- Outer 0.125 dia. x 4.500 dia. Viton or Type 321 Stainless Steel

- Outer Lid 0.250 dia. x 82.060 dia. Viton2

- Port Covers

- Primary 0.103 dia. x 2.675 dia. Viton

- Secondary 0.103 dia. x 2.675 dia. Viton

I. Dimensions in Inches unless otherwise noted. 2. 0.25 diameter, Type 321 stainless steel 0-rings (same as storage configuration) may also be used .

1.2-39

NAC-STC SAR

Docket No. 71-9235

Table 1.2-2 NAC-STC Design Basis Directly Loaded Fuel Characteristics

Westinghouse PWR Fuel

Parameter 17 x 17 15 x 15

Maximum Number of Assemblies 26 26

Maximum Assembly Weight, lbs' 1467 1440

Maximum Assembly Length, in 160 160

Active Fuel Length, in 144 144

Fuel Rod Cladding Zircaloy-4 Zircaloy-4

Maximum Uranium, kgU 464 465

Maximum Initial 235 U, wt% Note 2 Note 2

Minimum Initial 235U, wt% Note 3 Note 3

Maximum Burnup, MWD/MTU 45,000 45,000

Maximum Assembly Decay Heat, kW 0.85 0.85

Maximum Cask Decay Heat, kW 22.1 22.1

Minimum Cool Time, yr Note 3 Note 3

April 2011

Revision 17

Framatome-Cogema

17 x 17 17 x 17 Ref.4

26 26

1463 1472

162 162

144 144.25

Zirconium Alloy Zirconium Alloy

464 464

Note 2 Note 2

Note 3 Note 3

45,000 45,000

0.85 0.85

22.1 22.1

Note 3 Note 3 '

I. Actual assembly weights are provided for information only. A conservative weight is used for analysis. These assemblies are the design basis fuel assemblies for the structural, thermal and shielding evaluations. The fuel used for the criticality evaluation is the Westinghouse I 7x l 70FA. Physical properties for the OF A assembly are provided in Table 6.2-1.

2. Based on criticality analysis. Maximum initial enrichment is variable between 4.2 and 4.5 wt% 235U. 3. Minimum initial enrichment and cool time are based on a fuel loading table, shown in Table 5.4-5. 4. Similar to the Framatome-Cogema 17 x 17, except with expanded fuel characteristics.

1.2-40

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NAC-STC SAR

Docket No. 71-9235

September 2017

Revision 17C

The vent port and the drain po1i are located in the inner lid and are each protected by a port

coverplate. The primary containment boundary at the vent port and at the drain port is the port

coverplate and its 0-rings. The 0-ring is located in the bottom surface of the port coverplate. A

second 0-ring is also located in the bottom surface of the port coverplate, inside of, and

concentric with, the first 0-ring.

The forty-two 1 1/2 - 8 UN inner lid bolts are preloaded by an installation torque to restrain

rotation of the edge of the inner lid and to maintain a containment seal for the critical load

condition. This condition is a uniformly distributed pressure resulting from the impact of the

basket and cavity contents on the inner surface during a top end or top corner impact. The

critical design load condition for the inner lid bolts, as listed in Table 2.7.1.6-2, Section 2.7.1.6,

is a 54.7 g top corner impact (10 CFR 71 Hypothetical Accident Condition). The critical design

load condition for the inner lid is the top end impact, Section 2.7.1.6.

The outer lid is bolted to the top forging by the thirty-six 1 - 8 UNC outer lid bolts, which are

installed to a specified torque. The torque provides a total bolt preload that exceeds the

maximum applied bolt load for the critical load condition, preventing any lid and 0-ring

movement that might result in a loss of secondary seal integrity. The critical design load

condition for the outer lid bolts, as listed in Table 2.7.1.6-4, Section 2.7.1.6, is a 51.3g side

impact (10 CFR 71 Hypothetical Accident Condition). The critical design load condition for the

outer lid is the pin puncture accident condition. The NAC-STC outer lid bolts are loaded by the

interlid region pressure, the 0-ring compression force, and by either the impact limiter crush

force during a top end or top corner impact, or by a concentrated center load during a pin

puncture impact. The outer lid seal is provided by an 0-ring, which is tested by pressurizing the

interlid region.

In addition to the main closure, the secondary closure boundary of the NAC-STC also includes

the two ports located in the top forging-the interlid p01i and the pressure port. Each of these

ports is protected and sealed by a recessed, bolted port cover with two Viton 0-rings. The port

covers are installed with new 0-rings just prior to transport (a slightly different port cover is

installed during storage operation). The seal at each port cover is verified by pressure-testing the

annulus between the two Viton 0-rings.

The neutron shielding material, NS-4-FR, is a solid synthetic polymer that absorbs the neutron

radiation emitted by the cask contents. In addition to the radial neutron shielding along the cask

2.1.1-3

NAC-STC SAR

Docket No. 71-9235

April 2011

Revision 17

length, neutron shielding is provided in the axial direction at each end of the cask by circular

layers ofNS-4-FR enclosed in the inner lid and in the cask bottom.

Four external trunnions are welded to the top forging of the NAC-STC at 90-degree intervals

around the circumference of the cask. These trunnions are provided for lifting and handling the cask. Either a redundant (four trunnions) or a nonredundant (two trunnions) lifting system may

be used. However, each pair of opposing trunnions are conservatively designed to satisfy the

heavy lifting requirements of NUREG-0612 for a nonredundant lift, as well as the requirements

of 10 CFR 71.45(a) and paragraph 607 of IAEA Safety Standards Series No. TS-R-1. Two

rotation trunnion recesses are welded to the bottom outer forging near the bottom of the cask.

The neutron shield is cut out to accommodate the placement of the rotation trunnion recesses, which are used to attach the bottom of the cask to the transport vehicle and to rotate the cask

from the vertical lifting position to the horizontal position and vice-versa.

As discussed above, two transport impact limiter configurations are used with the NAC-STC

cask to limit the impact loads that may act on the cask. The impact limiters absorb the energy of a cask drop impact through the crushing of the wood in the limiters. A balsa impact limiter design must be used when the NAC-STC is transporting spent fuel or GTCC waste in the

CY-MPC canister configuration. When transporting directly loaded fuel or the Yankee-MPC canister, either the redwood or balsa impact limiter configuration may be used.

The NAC-STC fuel basket is constructed of stainless steel and has a capacity of 26 PWR fuel

assemblies. The fuel basket has a cylindrical shape with a series of support disks that provide

lateral support for the square, stainless steel fuel tubes, which encase neutron absorber sheets or

plates on each of the four sides. The support disks are separated and supported at 4.87-inch intervals by a threaded rod and spacer nuts at six locations. Aluminum heat transfer disks are

located in the central region of the fuel basket and are supported by the six threaded rods and spacer nuts. The stainless steel support disks have adequate strength at the basket temperatures

that occur during the transport and/or storage of 26 design-basis PWR fuel assemblies.

For the Yankee Class fuel and GTCC waste, the Yankee-MPC transportable storage canister

(canister) serves as the enclosure of the spent fuel assemblies, damaged fuel cans and GTCC

waste. The Y ankee-MPC canister has a capacity of up to 3 6 Yankee Class spent fuel elements,

or 32 Yankee Class fuel elements and four damaged fuel cans in the four basket corners, or up to

24 loading positions for GTCC waste. Similarly, the CY-MPC canister serves as the enclosure for the Connecticut Yankee spent fuel, damaged fuel cans and GTCC waste. The CY-MPC

canister has a capacity of up to 26 Connecticut Yankee spent fuel assemblies or up to 24

2.1.1-4

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NAC-STC SAR

Docket No. 71-9235

2.4.4.2.3 Shielding Materials

September 2017

Revision 17C

The primary shielding materials used in the NAC-STC-lead and NS-4-FR-are completely

enclosed and sealed in stainless steel. As previously described, there are no potential reactions of

these materials with the stainless steel or with the copper fins.

Therefore, there are no potential reactions associated with the cask shielding materials.

2.4.4.2.4 Criticality Control Material

The criticality control material is a sheet consisting of boron carbide mixed in an aluminum

alloy. This material is effectively a sheet of aluminum that is in contact with the aluminum alloy

fuel tubes and is exposed to the cask cavity environment. This material is protected by an oxide

layer that formed sho1ily after fabrication. The existing oxide layer effectively precludes further

oxidation of the aluminum. Consequently, there are no potential reactions associated with the

aluminum-based criticality control material.

2.4.4.2.5 Energy Absorbing Material

The NAC-STC utilizes redwood and balsa wood for energy absorption in the impact limiters.

The wood is completely enclosed (sealed) in stainless steel and there are no potential reactions

between the wood and the stainless steel shells. The wood may be coated with a preservative

prior to installation in the impact limiter shell and blocks of wood may be glued together with an

epoxy adhesive. These are standard applications of preservatives and adhesives, so no post

application reactions will occur.

There are no potential reactions associated with the energy absorbing material.

2.4.4.2.6 Cellular Foam and Insulation

The NAC-STC utilizes layers of expansion foam and strips of insulation in the solid neutron

shield regions. The expansion foam permits thermal expansion of the solid neutron shield

material during normal operation, and the insulation protects the expansion foam during final

closure welding of the neutron shield shell to the end plate. The foam and the insulation

arenonflammable, nontoxic and noncorrosive silicone products that are used in the casks in a

standard design application .

2.4.4-7

NAC-STC SAR

Docket No. 71-9235

September 2017

Revision 17C

There are no potential reactions associated with the silicone expansion foam or insulation.

2.4.4.2.7 Lubricant and Grease

The dry film lubricants used with the NAC-STC meet the performance and general

compositional requirements of the nuclear power industry. One example is NEVER-SEEZ®

lubricant, which can be used on rotating bearing surfaces. Another example is Neolube®, which

can be used on threaded/mechanical connection surfaces. In addition, Dow Corning High

Vacuum Grease is an example of what can be used as an adherent/lubricant to lubricate and

retain the 0-ring seals in their grooves. None of these example lubricants contain elements or

compounds prohibited by the NRC. NEVER-SEEZ® is a superior, high temperature, anti-seize

and extreme pressure lubricant that contains flake particles of pure nickel, graphite and other

additives in a special grease caiTier. Neolube® is 99% pure furnace graphite particles in

isopropanol. It has excellent radiation resistance and high chemical purity. It dries as a thin,

non-corrosive film with excellent adhesion, does not migrate, and is non-freezable. Dow

Corning High Vacuum Grease is a stiff, nonmelting, nonoxidizing, non gumming silicone

lubricating material that is insoluble in most solutions. There are no potential reactions

•

associated with these lubricants or grease. Other lubricants and greases maybe used as •

alternatives to the examples given provided they meet the performance and general

compositional requirements of the nuclear power industry.

2.4.4.2.8 Seals

The NAC-STC utilizes seals formed from silicone rubber, and Viton. Viton is a silicon

elastomer. Elastomer 0-rings are used for transport cask applications because of their excellent

short-term sealing capabilities, ease of handling, and more economical cost. All of the seal and

gasket materials have stable, non-reactive compositions. There are no potential reactions

associated with the NAC-STC seal materials.

2.4.4.3 General Effects of Identified Reactions

No significant potential galvanic or other reactions have been identified for the NAC-STC. The

only potential chemical reaction identified for the NAC-STC is that of aluminum with the spent

fuel pool water. As discussed in Section 2.4.4.2.2, it is possible at higher temperatures (above

150-160°F) that a flammable concentration of hydrogen might be generated by the

2.4.4-8

•

• NAC-STC SAR

Docket No. 71-9235

April 2011

Revision 17

aluminum/water reaction and accumulate beneath the canister shield lid during the canister

closure operations. The danger of potential ignition of the hydrogen is precluded by the

operating controls and procedures presented in Chapter 7. Therefore, no adverse conditions can

result during any phase of cask operations for normal, off-normal, or accident conditions.

2.4.4.4 Adequacy of the Cask Operating Procedures

Based on the results of this evaluation which resulted in only one identified reaction, aluminum

in pool water, it is concluded that the NAC-STC operating controls and procedures presented in

Chapter 7 are adequate to minimize the occunence of hazardous conditions.

2.4.4.5 Effects of Reaction Products

No significant potential chemical, galvanic, or other reactions have been identified for the NAC

STC. Therefore, the overall integrity of the cask and the structural integrity and retrievability of

the spent fuel is not adversely affected for any cask operations throughout the design basis life of

the cask. Based on the evaluation, there will be no change in the cask or fuel cladding thermal

properties, and there will be no binding of mechanical surfaces, no change in basket clearances,

• and no degradation of any safety components either directly or indirectly, since there are no

significant reactions identified .

• 2.4.4-9

NAC-STC SAR

Docket No. 71-9235

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Revision 17C

Table 2.4-1 Summary ofNAC-STC Materials Categories and Operating Environments

ITEM MATERIAL ENVIRONMENT

Stainless Steels/ Alloys 304, 304L, XM-19, 17-4PH, Sealed Internal

Ni Alloy, 410 Open Internal/ External

Nonferrous Metals ASTM B152 Cu, Sealed Internal 6061-T651 Aluminum Alloy Open Internal/External

Shielding Materials NS-4-FR, Chemical Copper Enclosed Grade Lead

Criticality Control Materials Boroncarbide Enclosed

Aluminum 1100

Energy Absorbing Materials Balsa Wood, Redwood Enclosed

Cellular Foam/Insulation Silicone (HT-810 & 800), Enclosed Silicone Caulk (Dow Corning)

Lubricants & Greases Never-Seeze® Sealed Internal

Neolube® Open Internal

High Vacuum Grease® by Dow Corning

Seals & Gaskets Silicone Rubber, Viton Sealed Internal

Open Internal/ External

2.4.4-10

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NAC-STC SAR

Docket No. 71-9235

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Revision 17

How to Specify 0-Rings °""Otes

Metallic 0-Rlng

l . Tubing OD ; f Wall Thlcll:neu

{Thirty-S.COnd$) ! I (Tnouun6tlu)

I !

II Bllm--alm II Materials

1-Alloy 718 7 -Stainless 2-StainleA &eel 304

Steel 321 8-Stainless 3-Alumimlm Steel 316 4-~r 9-Slainltta 5-AllW 60Cl Slffl 347 6-AllOf"-750 X-AsSpecilied

Eumple: U2312..03625SEA Tt>e abD"" Hampi.. U2312-Qall25SEA. lndlcaln a type 321 elalnlffs &IHI Cl-fl:i'19, fu. /2.38 mm) tuba •in .. 012 C0.30 mm) wall llliconeu, J.ti2S"' !92.0t! mm) OC. aell-energlz.O (IC) •nd ,001-.002" 10,0310.IJS mm) .11.,., coatiri;.

t I

Met•llle ~ing OD (Inches) (Tnouu.ndth1)

Type SE-Setf-ene rgized

on ID PF-Pre111ure fill~ NP-Not tall·

-rgized, not pressure filled

SO-Self-ene rgizltd on OD

SX-Sell-ene rgized as spec.

eo.ttnp A-Silver .001 / .002 C0.03/0.051 N--None B--Sllver .00'2/ .003 10.05/0.08) P-Lead .001 I .002 10.DJ/0.05) 0-Tellon• .0011.003 (0.03/0.08) A-Indium .001 /.002 (0.03/0.05) E-Teflon .003/.00410.08/0,10) T-Nickel .001/.00210.()310.05) L-Copper .001 /.002 (0.0310.05) v-Qold .00051.00110.0210.0J)

X-A&Spec~d

Fluorocarbon MetalJlc C-Rjngs Fluorocarnon Met.alhc c-Rings (deslgnated MCA) amdesi~ned for static aealing on machinery or eciuipment and are availllble tor internal pressure. external pressu~. or uial pl9SSUre 10/00 applications. Because c-Rings are designed wilh an open side on the pressure side of tile installation. the seal i& self-energizing. Fluorocarbon C-Rinps are offerad in round or irregular shaP9$ in a broad range ol sizes from .126'" (3,2 mm) OD x .D.32" 10.81 mm) tiw ~ight to over 300'' 17020 mm) OD x z· (50,80 mm) tree neight. They are svaii.~ in a wide variety of metal alloys and metallic or Teflon coatin05. Sealing application temperature range is from cryogenic to 3.DOO" F. (16509 C.); pressure tolerances are from 10- torr to 100,000 psi (6.804 atmJ. Where customer requirements are large, the C-Ring provides the lowest unit price of any high per1ormance seal on 1he market

•Tlf!On d CluPanl~ ~ T-.

@Helimflex Components Division Telephone (803) 783-1880 P.O. Bo.x. 9BB9 FAX 1803) 783-4279 Columbia. South Carolina 29290

4.5-13

NAC-STC SAR

Docket No. 71-9235

4.5.2 Blended Polytetrafluoroethylene (PTFE) 0-rings

September 201 7

Revision 17C

This section contains applicable technical data from a typical manufacturer of blended

polytetrafluoroethylene (PTFE) 0-rings. The PTFE 0-rings are manufactured from virgin

(unreprocessed) polytetrafluoroethylene base material filled with plastic. One product that

satisfies the design requirements is the Fluoroloy K 0-ring manufactured by the Furon Company,

which has an operating temperature range of -450°F to +650°F. NAC has completed

supplemental 0-ring testing and has determined that the operating range of the PTFE 0-rings can

be extended to 73 5 °F. A description of tests performed and the results are contained in Ce1iified

Test Report D9-3362-1, Applied Technical Services, Inc., February 8, 1989.

4.5-14

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NAC-STC SAR

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biasing, the limiting shift scenario corresponds exactly to the position of the fuel assembly in the

cavity, i.e., top dose rates are maximized when the fuel assembly is shifted up and bottom dose

rates are maximized when the fuel assembly is as far down in the cavity as possible. For radial

biasing, the two different shift scenarios are limiting for different transpmi conditions. The

maximum fuel assembly axial shift is limiting for normal conditions because upper plenum and

upper end fitting hardware move adjacent to the location in the radial shield where the radial lead

shield ends. The limiting shift is downward for accident conditions due to the bottom axial lead

slump, which is adjacent to the lower end fitting hardware source.

The first step in determining limiting PWR dose rates for the directly loaded cask is the

generation of dose rate response functions for generation of minimum cool time tables. For each

array size, at each of 4 bumup, 15 enrichment, and 18 cool time combinations, dose rate profiles

are calculated for both normal and accident transport conditions. Using these dose rate profiles,

the maximum radial dose rates at 2 meters from the railcar are tabulated for normal conditions.

Minimum cool times are calculated to ensure that a decay heat limit of 850 W/assembly is not

exceeded and that the dose rate at 2 meters from the railcar does not exceed 9.5 mrern/hr. The

9.5 mrern/hr analysis limit was chosen to provide margin against the 10 mrem/hr regulatory limit.

Cool times heeded to reach these limits are calculated using linear interpolation on the entire

array of maximum dose rates. The linear interpolation is valid because of the exponential

decrease in source term and, thus, dose rate as a function of time. The interpolated cool time is

rounded up to the next integer year. A sample minimum cool time generation for the 14x 14

reference assembly at 40,000 MWd/MTU is shown in Table 5.4-3. Repeating this analysis for all

fuel types and burnups results in the complete loading table shown in Table 5.4-5. Based on the

loading table, maximum radial dose rates for each fuel type are shown in Table 5.4-4.

The minimum cool times are used to calculate maximum accident condition dose rates at 1 meter

from the cask. The 1000 mrern/hr limit is not exceeded at any of the calculated minimum cool

times.

Based on the radial dose rate results for normal and accident conditions and their application to

the minimum cool time table, the 14x14 reference assembly provides maximum dose rates. Thus,

top axial and bottom axial response functions have been executed for this assembly only. This

ensures that the maximum axial dose rates for the directly loaded system are captured, and that

variations in burnup, enrichment and minimum cool time are thoroughly examined .

5.4-3

NAC-STC SAR

Docket No. 71-9235

September 201 7

Revision 17C

A summary of the limiting source terms for each transport condition and detector biasing is given

below. All limiting source terms are taken from the 14x14 reference fuel assembly.

Normal Conditions Accident Conditions

Detector Burn up Enrichment Cool Time Burn up Enrichment Cool Time

Biasing IMWd/MTU] [wt% 235U] [Years] [MWd/MTU] [wt% 235U) [Years]

Radial 40,000 2.3 10 45,000 2.3 14

Top Axial 30,000 2.3 6 45,000 2.3 14

Bottom Axial 40,000 2.3 10 45,000 2.3 14

Three-Dimensional Dose Rates for Directly Loaded Fuel

Further detail on the three-dimensional dose rates are presented in Figures 5.4-1 tln·ough 5.4-6 for

the limiting 14x14 reference assembly. Maximum dose rates are tabulated in Tables 5.4-6 and

5.4-7.

The maximum normal conditions surface dose rate is 3 66 mrem/hr at an axial elevation between

the radial neutron shield and the upper impact limiter. At 1 meter from the surface of the neutron

•

shield shell, the maximum dose rate is 20.3 mrem/hr. This dose rate defines the transport index. •

The maximum normal conditions dose rate at 2 meters from the cask railcar is 9.5 mrem/hr and

occurs at an axial elevation adjacent to the upper plenum and upper end-fitting elevations. The

maximum accident conditions dose rate at 1 meter from the cask is 665 mrem/hr and occurs at

the cask midplane. The top and bottom axial dose rates are small when compared to the radial

dose rate for the same transport conditions.

Dose rate variations from heat fins in the neutron shield are examined explicitly using azimuthal

detectors that span the entire length of the neutron shield. As shown in Figure 5 .4-4, peaks in the

neutron dose rate correspond to dips in the gamma dose rate, and vice versa. Thus, the neutron

dose rate increase resulting from the ducting is offset by the reduction of the gamma dose rate

resulting from the additional shielding provided by the fins. The use of thicker heat fins, which

have a pre-bonded thickness of 8mm to 1 Omm for 304 stainless steel and 6mm to 8mm for

copper plates, is acceptable as the increased heat fin thickness results in neutron doses that are

within the statistical unce1iainty of the existing shielding analysis (i.e.,< lo').

Detector descriptions for dose rates on the side of the STC are given in Tables 5.4-8 and 5.4-9 for

normal and accident conditions, respectively. Note that an axial height of 0.0 cm corresponds to •

the bottom of the STC cavity.

5.4-4

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NAC-STC SAR

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Any evidence of permanent deformation, cracking, galling of the load bearing surfaces or

unacceptable dye penetrant results shall be cause for rejection of the rotation trunnion recesses or

related welds.

8.1.2.3 Hydrostatic Testing

A hydrostatic test shall be performed on the NAC-STC cask containment boundary, prior to final

acceptance of the cask, in accordance with the ASME Code, Section III, Division I, Article

NB-6200. The hydrostatic test pressure shall be at least 76 psig, which is 150 percent of the

Maximum Normal Operating Pressure. This test shall be performed in accordance with approved

written procedures. All pressure retaining components, appurtenances, and completed systems

shall be pressure tested.

The vent port will be used for the test connection. Only the vent port quick-disconnect will be

installed during the testing. The hydrostatic test will be performed with the inner lid and the

drain port coverplate installed and torqued .

The hydrostatic test system components, although not part of the cask containment boundary,

will be visually inspected prior to the start of the hydrostatic test. Leakage from the valves or

connections will be corrected prior to the start of the hydrostatic test.

The test pressure gauge installed on the cask will have an upper limit of approximately twice that

of the test pressure. The hydrostatic test pressure shall be maintained for a minimum of 30

minutes, during which time a visual inspection is made to detect any evidence of a leak. Any

evidence of a leak during the minimum hold period will be cause for rejection.

After completion of the hydrostatic test, the cask containment boundary will be dried and

prepared for visual and/or dye penetrant inspections as appropriate. The components of the cask

containment boundary shall be visually inspected. All accessible welds within the cavity shall be

liquid penetrant inspected. Any evidence of cracking or permanent deformation is cause for

rejection of the affected component.

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NAC-STC SAR

Docket No. 71-9235

8.1.2.4 Pneumatic Bubble Testing of the Neutron Shield Tank

September 2017

Revision 17C

A pneumatic bubble test of the neutron shield tank will be performed in accordance with Section

V, Article 10, Appendix I, of the ASME Code following final closure welding of the bottom

closure plates. The pneumatic test pressure shall be 12.5 + 1.5/-0 psig, which is 125 percent of

the relief valve set pressure. The test shall be performed in accordance with approved written

procedures.

During the test, the two relief valves on the neutron shield tank will be removed. One of the relief

valves threaded connections will be used for connection of the air pressure line and test pressure

gauge. The other relief valve connection will be plugged with a threaded plug.

Following introduction of pressurized air into the neutron shield, a 15-minute minimum soak

time will be required. Following completion of the soak time, approved soap bubble solution will

be applied to all fin to shell, shell to end plate, and end plate to outer shell welds. The acceptance

criteria for the bubble test will be no air leak from any tested weld as indicated by continuous

bubbling of the solution. If an air leak is indicated, the weld shall be repaired in accordance with

approved weld repair procedures and the pneumatic bubble test shall be repeated until no

unacceptable air leak is observed.

8.1.3 Leakage Tests

Fabrication leakage rate testing is performed on both the NAC-STC transport cask containment

boundary weldment (without the inner lid and inner lid vent and drain port coverplates installed)

during fabrication prior to lead pouring (without the inner lid and inner lid vent and drain port

coverplates installed) upon completion of cask body fabrication (i.e., following lead pouring and

final cask assembly) to demonstrate that the containment boundary weldment, as fabricated, will

provide an appropriate containment capability. The inner lid and with the inner lid vent and

drain port coverplates installed will be leakage rate tested as part of the final fabrication leakage

rate testing per SAR Section 8.1.3.2.

The leakage rate testing of the NAC-STC containment boundary and closures will be performed

in accordance with the requirements and standards contained in ANSI N14.5-1997 and the

ASME Code, Section V, Article 10 using approved written procedures to confirm that the

leakage rate meets the containment criteria established in Chapter 4 (e.g., leaktight for the NAC

STC containment boundary weldment; leaktight for Containment Condition B closures with

metallic seals; or a cumulative leakage rate :S 9.3 x 10-5 cm3/sec (helium) for Containment

Condition A closures with Viton 0-ring seals). Personnel performing the leakage tests shall be

qualified in accordance with Section 8.5 of ANSI N14.5-1977.

8.1-6

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NAC-STC SAR

Docket No. 71-9235

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leak testing operations. Upon removal of the external fitting, the valve in the quick-disconnect closes automatically. The design and selection of the quick-disconnects is based on similar

equipment and procedures used with other NRC-approved storage and transport casks. For

transport, the quick-disconnects are sealed inside the transport containment boundary using a

bolted coverplate fitted with two 0-ring seals.

There are no rupture disks on the NAC-STC.

Two self-actuating pressure relief valves are installed on the external shell of the neutron shield

to provide for venting of vapor from the shielding material during transport thermal accident

conditions. These valves have stainless steel bodies and an operating pressure range of zero to 200 psig with an adjustable cracking pressure within this range. The cracking pressure is set at

10 psig. These relief valves do not provide a safety function, but have been designed to

minimize recovery efforts in the unlikely event of a neutron shield overpressure condition.

8.1.4.2 Gaskets

As described in Section 8.1.3, the containment boundary of the NAC-STC may use either

metallic 0-rings or non-metallic Viton 0-rings. The two 0-ring types require different 0-ring

groove designs and, therefore, may not be used interchangeably and must be used with the inner

lid, vent and drain port coverplates and outer lid having the appropriate 0-ring groove machined

in the component. Metallic 0-rings must be used for direct loading of the NAC-STC with fuel

for extended storage and for loading of a transportable storage canister (for transport). For direct

loading of fuel for immediate transport, either metallic or non-metallic 0-rings may be used.

The outer lid, inner lid, drain port coverplate, vent port coverplate, interlid port cover, pressure port cover, and interseal test plug gaskets are 0-rings. For transport after an extended period of

storage, the containment boundary is formed by the outer metallic 0-ring of the inner lid, the

outer metallic 0-rings on the vent and drain port coverplates, and the interseal test plug metallic 0-rings for the inner lid, the vent port coverplate and the drain port coverplate. The inner

metallic 0-rings of the inner lid, vent port coverplate and drain port coverplate, the metallic

0-ring of the outer lid, and the Vi ton 0-rings of the interlid and pressure port covers provide a

secondary closure to the cask contents. For immediate transport, the containment boundary is formed by the inner 0-rings of the inner lid and vent and drain port coverplates. A second

boundary is formed by the 0-rings of the outer lid and interseal and pressure po1i covers.

The 0-ring replacement schedule depends upon the 0-ring material. The metallic 0-ring(s) of

any component shall be replaced prior to reinstallation of the component. Viton 0-rings are

inspected prior to each use and replaced as necessary. The Viton 0-rings of the interlid and

pressure ports will be visually inspected prior to each use, and replaced if necessary. The Vi ton

8.1-9

NAC-STC SAR

Docket No. 71-9235

September 2017

Revision 17C

0-rings shall be replaced at least once every two years during cask transport operations, or prior

to transport if they have been installed longer than two years (i.e., after extended storage).

The containment boundary 0-ring shall be tested and maintained in accordance with the

Maintenance Program Schedule of Table 8.2-1 and the leak test criteria of Section 8.2.2.

8.1.4.3 Miscellaneous

The removable transport impact limiters consist of redwood and balsa wood. License drawings

and the supporting analyses specify the crnsh strengths of the redwood and balsa wood to be

6240 psi± 620 psi and 1550 psi± 150 psi respectively. For manufacturing purposes, verification

of the impact limiter material is accomplished by verifying the densities of the wood. Three

samples from each redwood board are to be tested for density, and the average density of the samples shall be 23 .5 ± 3 .5 pounds/cubic foot. Each 15-degree and 30-degree pie shaped section

of the impact limiter shall have a density of 22.3 ± 1.2 pounds/cubic foot in accordance with the License Drawings. The moisture content for any single redwood board must be greater than 5 percent, but less than 15 percent. The average moisture content for a lot of redwood used in

impact limiter construction must not be greater than 12 percent.

Following final closure welding of the transport impact limiter stainless steel shell, a leak test of

the shell welds shall be performed to verify weld integrity. The following are acceptable test

methods, which may be selected from to verify weld integrity:

1. A test may be performed by evacuating the impact limiter to 75 mbar and performing a

30-minute test to determine if there is any increase in the impact limiter pressure. Any

detected leak shall not exceed 1 x 10-2 cm3 /sec. If a leak exceeding this value is detected,

the cause of the leak shall be determined, and the weld repaired and retested.

2. A positive pressure leak test may be performed on each impact limiter to ensure the leak

tightness of the impact limiter shell welds. Remove the test plug and install the necessary

piping to convey oil-free air or gas to the inside of the impact limiter shell. Apply an air

or gas pressure to the inside of the impact limiter shell to initiate the test. Allow the

system to stabilize for at least 15 minutes. Spray all the outside welds with foaming

bubble solution. Examine the limiter welds for indications of continuous bubble

formation. All leaks detected shall be repaired and the leak test re-performed until there

are no leak indications. Upon the completion of leak testing, the test plug shall be

reinstalled.

3. After final closure welding of the transport impact limiter stainless steel shells, a PT

examination may be performed on all shell welds to verify weld integrity.

8.1-10

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NAC-STC SAR

Docket No. 71-9235

8.4 Cask Body Fabrication

8.4.1 General Fabrication Procedures

September 2017

Revision 17C

The NAC-STC cask body is a welded structure of stainless steel plates and forgings. Chemical

Copper lead is poured in place between the inner and outer shells to serve as the main gamma

shielding material. NS-4-FR is poured in place between the neutron shield shell and the outer

shell. NS-4-FR is also form fit between the bottom inner forging and the bottom plate and in the

inner lid. Welding on the NAC-STC shall be performed in accordance with the requirements of

the ASME Code and the American Welding Society (A WS) Structural Welding Code - Steel

(ANSI/AWS D.1-1) as specified on the NAC-STC License Drawings and Section 8.1.1.

The general fabrication procedures for the NAC-STC are summarized, herein, to facilitate an

understanding of the component configurations and the weld locations shown on the license

drawings.

Each of the two inner shell rings (upper and lower) is rolled from Type XM-19 stainless steel

plate and seam welded longitudinally. The outside diameter of each inner shell ring is machined

to the defined transition section dimensions. The minimum length of each Type XM-19 shell ring

shall be in accordance with the License Drawings. The central inner shell sections are each

rolled from Type 304 stainless steel plate and seam welded longitudinally. The number and

length of the individual inner shell sections to be used to obtain the required total inner shell

length is optional. The im1er shell sections are girth welded to each other and the inner shell rings

are girth welded on each end of the inner shell. Longitudinal seam welds in adjacent inner shell

sections shall be offset at a minimum of 15 degrees for girth-welded sections.

After initial rough machining and final weld preparation, the top forging and the bottom inner

forging are individually welded to the opposite ends of the inner shell/inner shell ring weldment

to form the cask cavity. The preparation, examination, and acceptance procedures for the welds

are described in Section 8 .1.1 and defined on the License Drawings. Following inspection and

acceptance of the welds, the top forging and the outside diameter of the cask cavity weldment are

final machined. Following final machining of both sides of the inner shell, an ultrasonic

thickness test of the inner shell wall of the cask cavity shall be performed to confirm that the wall

thickness of any location on the shell is not less than 1.46 inches (37.1 mm). A wall thickness at

• any location ofless that 1.46 inches (37.1 mm) will be cause for rejection. Rejected areas of the

8.4-1

NAC-STC SAR

Docket No. 71-9235

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shell wall can be repaired by weld overlay using approved written weld overlay procedures.

Fallowing repair, the repaired areas shall be examined in accordance with the original inspection

requirements and acceptance criteria.

Following thickness testing, the cask cavity weldment, which is the NAC-STC primary

containment boundary, shall be hydrostatically tested according to ASME Code, Section III,

Subsection NB-6000, as described in Section 8.1.2.3. The cask cavity weldment is dried, the

primary containment boundary welds are liquid penetrant examined in accordance with ASME

Code, Section V, Article 6, and the welds are accepted in accordance with ASME Code, Section

III, Subsection NB-5350. The cask cavity weldment is then helium leak tested to verify that the

Containment System Fabrication Verification leak rate is satisfied, as described in Section 8.1.3.

Each of the outer shell sections is rolled from Type 304 stainless steel plate and seam welded

longitudinally. The number and length of outer shell sections to be used to achieve the required

total outer shell length is optional. The outer shell sections are girth welded to each other and the

inside diameter of the "outer shell weldment" is final machined. Longitudinal seam welds in

adjacent outer shell sections are offset at a minimum of 15 degrees for girth-welded sections.

The outer shell weldment is welded to the cask cavity weldment at the top forging/outer shell

interface to form the "body weldment." The preparation, examination, and acceptance

procedures for the welds are described in Section 8.1.1 and defined on the License Drawings.

The body weldment is inverted (closure end down) in a pit or other sheltered location m

preparation for lead pouring. A temporary dam extension and supports are welded to the open

end of the outer shell to permit the full length of the lead shell to be poured and to maintain the

outer shell position. "Backing bars" are tack-welded on the inside diameter of the outer shell

overlapping the end of the weld prep and on the top surface of the bottom inner forging

overlapping the outside diameter of the forging (adjacent to the outside diameter of the inner

shell). The backing bars prevent the lead contamination of the welds when the outer shell/bottom

outer forging weld and the bottom outer forging/bottom inner forging weld are performed after

cask body cooldown following the lead pour. Lead pouring preparations, the pour itself, and the

cooldown are performed in accordance with the lead pour requirements and procedures as

described in Section 8.4.2.

Following cooldown, the cask may be moved to a location that is more suitable for the

fabrication activities that are to follow. The temporary dam extension and supports at the open

8.4-2

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NAC-STC SAR

Docket No. 71-9235

September 2017

Revision l 7C

end of the outer shell are removed and the lead is machined to its final configuration, including

facing off the backing bars to ensure that no lead remains on the weld side of the backing bars.

The bottom outer forging is welded to the outer shell and to the bottom inner forging with the

backing bars preventing lead contamination of the welds. The weld examination and acceptance

criteria are described in Section 8.1.1 and defined on the License Drawings. The NS-4-FR

neutron shield material is installed in the bottom forging of the NAC-STC. The NS-4-FR is

machined to obtain the specified 2-inch thickness and to provide a groove around the outside

diameter. A backing bar is tack-welded on the inside diameter of the bottom outer forging in the

groove in the NS-4-FR and flush with its surface. The bottom plate is positioned and welded to

the bottom outer forging. The weld examination and acceptance criteria are described in Section

8.1.1 and are defined on the License Drawings.

The outside diameter of the outer shell is then machined to the specified final dimensions. If

required to achieve dimensional compliance with the License Drawings, additional localized

machining of the inner shell will be performed. Remachined areas of the inner shell shall be

re-examined by ultrasonic testing to confirm that the minimum thickness of 1.46 inches (37.l

mm) is maintained. Upon completion of final machining and prior to removal from the machine,

the dimensional inspection of the inside diameter and cylindricity of the cavity shall be

performed. Using calibrated M&TE, the inside diameter at 0, 45, 90 and 135 degree radial

locations shall be measured. This measurement shall be repeated at a minimum of 6 axial

locations through the bore of the inner shell. Using calibrated M&TE, a "sweep" of the entire

length of the bore at the same radial locations previously measured and also a "sweep" of the

diameter at the same axial locations will be performed. The combination of these two inspections

will demonstrate the actual diameter and cy lindricity of the inner shell bore. Calibrated

inspection equipment and approved written procedures will be used to perform the final

dimensional inspections.

The Type 17-4 PH stainless steel lifting trunnions are welded to the top forging. The Type 17-4

PH stainless steel rotation trunnion recesses are welded to the outer shell at its juncture with the

bottom outer forging. Both the lifting trunnion and rotation trunnion recess weld surfaces are

prepared with a minimum 0.25-inch thick overlay of Inconel. The shear ring and the neutron

shield upper end plate are welded to the top forging. The weld examination and acceptance

criteria are described in Section 8.1.1, and are defined on the License Drawings .

8.4-3

NAC-STC SAR

Docket No. 71-9235

June 2017

Revision 17B

The explosively-bonded stainless steel/copper (SS/Cu) heat transfer fins extending through the

neutron shield are welded (only the stainless steel is welded) to the upper end plate and to the

outer shell. Following liquid penetrant examination of the fin to outer shell welds, the 24 neutron

shield shell plates are prepared for installation and 1/8-inch thick expansion foam is applied to

the interior surface using approved adhesive in accordance with the License Drawings. The

neutron shield shell plates are individually positioned and welded to the stainless steel extended

tip of the SS/Cu fins. These closure welds are then examined and accepted in accordance with

the requirements of the License Drawings. The cask is then placed in the inve1ied position

(closure end down). Following an installation procedure that has been approved by NAC and by

the material supplier, the NS-4-FR neutron shield material is installed by pouring into each of the

24 regions between the fins in the NAC-STC neutron shield cavity. After the NS-4-FR has

hardened, expansion foam (Section 4.5.3) is installed in the open end of the neutron shield. The

inside and outside diametrical (curved) surfaces of the expansion foam are covered by a

protective thermal insulation material (Fiberfrax, see Section 4.5.4). The 24 sections of the

neutron shield bottom end plate are each positioned and welded to the outer shell, the fins, the

neutron shield shell, and to each other. All of the neutron shield and fin welds are liquid

penetrant examined and accepted in accordance with the License Drawings. The neutron shield

tank is leak tested using the pneumatic bubble method to verify shell integrity.

The Type 17-4 PH stainless steel outer lid forging and the Type 304 stainless steel inner lid

forging are machined to the specified final dimensions. The NS-4-FR neutron shield material is

installed in the top of the inner lid following an installation procedure that has been approved by

NAC and by the material supplier. The exposed surface of the NS-4-FR is machined to obtain

the specified 2-inch thickness and the coverplate is welded to the inner lid body. The weld

examination and acceptance are in accordance with the requirements of the License Drawings.

The top surface of the inner lid is then final machined.

The remaining fabrication details (including the installation of the drain line) are then completed.

Following machining of the structural steel support disks and the aluminum heat transfer disks,

the components will be individually inspected for dimensional compliance to the License

Drawings to ensure that each disk meets the stated tolerances. The diameter of each disk is

measured using a calibrated external micrometer. The openings in each disk are inspected using

a calibrated three coordinate measurement machine. The machining center may also be used for

these inspections if previously qualified and calibrated. In the case of the diametral tolerances of

8.4-4

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anac ~i international · 8mm to lomm for 304 st. stl. and 6mm to 8mm for copper plates may be...

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