ML22195A186
| ML22195A186 | |
| Person / Time | |
|---|---|
| Site: | 07105797 |
| Issue date: | 07/12/2022 |
| From: | US Dept of Energy, Office of Packaging and Transportation |
| To: | Storage and Transportation Licensing Branch |
| PSAVEROT NMSS/DFM/STLB 3014157505 | |
| Shared Package | |
| ML22195A181 | List: |
| References | |
| Download: ML22195A186 (32) | |
Text
71-5797 ENCLOSURE 4 CHANGE PAGES FOR SAFETY ANALYSIS REPORT FOR PACKAGING:
THE ORNL HFIR UNIRRADIATED FUEL ELEMENT SHIPPING CONTAINER, ORNL/TM-11656
ORNL/TM-V11656/V1 Rev. 14 SAFETY ANALYSIS REPORT FOR PACKAGING THE ORNL HFIR UNIRRADIATED FUEL ELEMENT SHIPPING CONTAINER VOLUME I Compiled by G.A. Aramayo C.M. Hopper J.R. Kirkpatrick D.M. McGinty J.T. Muecke J.C. Walls Latest Revision - Revision 14 Date of Revision - June
Prepared by OAK RIDGE NATIONAL LABORATORY Oak Ridge, TN 37831-6283 managed by UT-BATTELLE, LLC for the US DEPARTMENT OF ENERGY under contract DE-AC05-00OR22725
ORNL/TM-V11656/V1 Rev. 14 Page 1 of 2 LIST OF EFFECTIVE PAGES Volume I Page Revision Cover Page 14 ii thru iv (Table of Contents) 8/7/98 v (List of Figures) 13 vi (List of Tables) 13 vii-a thru vii-M (Summary of Revision 14 changes) 14 viii (Abstract) 8 1-1 11 1-2 14 1-3 thru 1-5 13 1-6 thru 1-7 5 1-8 thru 1-10 14 1-11 5 1-12 thru 1-13 14 1-14 thru 1-15 13 1-16 4 1-17 thru 1-22 13 1-23 4 1-24 13 2-1 4 2-2 thru 2-3 13 2-4 4 2-5 thru 2-6 5 2-7 7 2-8 5 2-9 4 2-10 2 2-11 4 2-12 2 2-13 thru 2-14 5 2-15 4 2-16 thru 2-21 5 2-22 7 2-23 5 2-24 thru 2-25 13 2-26 4 2-27 7 2-28 4 2-29 7 2-29a 13
ORNL/TM-V11656/V1 Rev. 14 Page 2 of 2 LIST OF EFFECTIVE PAGES Volume I 2-30 thru 2-31 4 2-A-1 4 2-B-1 4 2-C-1 11 2-D-1 4 2-E-1 5 2-F-1 5 3-1 4 3-2 thru 3-3 1 3-4 thru 3-6, and 3-7a 4 3-7 12 3-8 thru 3-12 1 3-13 4 3-14 1 3-15 thru 3-20 4 3-21 11 3-22 4 3-23 1 3-A-1 11 3-B-1 12 4-1 thru 4-2 13 4-3 thru 4-3a 12 4-4 thru 4-5 13 4-6 thru 4-7 4 4-8 thru 4-9 12 4-10 thru 4-11 4 4-12 13 4-13 4 4-A-1 4 4-B-1 4 4-C-1 Deleted 4-D-1 4 Note: All appendices in Chapter 4 contain reference documents. These reference documents do not reflect the revision number control system of the SAR since they were issued as separate documents.
5-1 6 5-2 thru 5-3 4
ORNL/TM-11656/V1 Rev. 14 Revision Log Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
14 x Rev. 14 of the SARP has three primary objectives: (1) the To Be Determined*
addition of fuel element combs as optional contents; (2) updating three Chapter 1 figures relating to the tie down band used for shoring the container on the transport vehicle; and (3) updating Chapters 8 and 9 of the SARP regarding
- CoC revision cask inspections. The changes are listed below.
number will be x The Cover Page and Lists of Effective Pages (LOEPs) for included upon both Volume 1 and Volume 2 were updated to Revision 14.
approval by the NRC.
The LOEPs were updated to identify pages changed in this revision as Revision 14.
x Updated the Revision Log for Revision 14 changes.
x Section 1.2.1.1 was updated to include a brief discussion on fuel element combs.
x Chapter 1 Figures: The drawings provided as Figures 1.3, 1.4, and 1.5 were updated to remove the tie down band since it is not credited or evaluated in the SARP.
x Chapter 1 Figures: The drawings provided as Figures 1.7 and 1.8 were updated to Revision 5 to add fuel element combs details.
x Clarified in Section 7.1 that the shoring ring that was removed from the certification drawings (SARP Figures 1.3 through 1.5) is depicted on ORNL drawing M-20978-EL-008B.
x Clarified that both labeling and markings on the containers are inspected for legibility in Section 8.2.
x Section 8.2.7 was revised to remove the implication of a periodic inspection of the containers since they are inspected prior to each shipment.
x Section 9.3.11 was revised to state that maintenance on the containers is performed as necessary to remove the implication of a periodic inspection.
13 x Rev. 13 of the SARP principally involves (1) removal of 22 RRD-FE-3, Specification for High Flux Isotope Reactor Fuel Elements, from Vol. I, Chapter 4, Appx. C; (2) the replacement of several controlled fuel fabrication drawings in Vol. I, Chapter 1, with two simplified fuel drawings which depict the salient fuel attributes relevant to the SARP analyses; and (3) changes to both Volumes of the SARP in support of (1) and (2).
x The Cover Page and Lists of Effective Pages (LOEPs) for both Volume 1 and Volume 2 were updated to Revision 13.
The LOEPs were updated to identify pages changed in this revision as Revision 13.
vii-a
ORNL/TM-11656/V1 Rev. 14 Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
x Updated the Revision Log for Revision 13 changes.
x List of Figures, pg. v: Removed the listings for Figures 1.9 -
1.10 and 1.12 - 1.17 and replaced the detailed drawings previously included as Figures 1.7 and 1.8 with simplified drawings.
x List of Tables, pg. vi: Deleted Table 1.1SARP Controlled Fabrication Drawings. Swapped order of Tables 4.1 and 4.2 and changed title of Table 4.2 from HFIR fuel element containment boundary to Characteristics of Irradiated HFIR Fuel.
x Section 1.2.1.1: Moved and amended the content from the first paragraph of page 1-3 to the first paragraph of Section 1.2.1.1. Removed the sentence referencing the HFIR Fuel Specification. Added a clarifying note to the end of the second paragraph that states that burnable poison is used to control power distribution during reactor operation.
x Section 1.2.3: Added a clarifying sentence regarding a polyethylene wrapping that the fuel element(s) are shipped in. Clarified the listed weights of the inner and outer fuel elements as follows to conform with weights listed in SARP Chapter 2: from 104 lb to 103.5 lb (inner); and from 202 lb to 205 lb (outer). Clarified that the fuel cladding thickness is an average of at least 0.010 in. thick, rather than a minimum of 0.010 in. thick. Clarified that the boron content listed for the inner fuel element (2.8 g) is a nominal amount.
Removed sentence referencing the elemental makeup and impurity limits detailed in the HFIR Fuel Specification and clarified that the weight percentages of uranium isotopes given provide a general description of the radioactive contents.
x Chapter 1 Figures: Replaced Figures 1.7 and 1.8 with drawings which contain an appropriate level of detail.
Removed Figures 1.9, 1.10, and 1.12 - 1.17.
x Section 1.4: Deleted Reference 6 for the HFIR Fuel Specification, RRD-FE-3.
x Section 2.1.2: Replaced references to Chapter 1, Figures 1.11 and 1.12 through 1.17 with Refer to Chapter 1, Figs.
1.7, 1.8, and 1.11.
x Section 2.2: Clarified that the inner and outer fuel element weights are 103.5 lbs. and 205 lbs., respectively, to be consistent with what is assumed in Chapter 2 analyses.
x Section 2.7.2: Fig. 1.8 (outer fuel element drawing) is called out in Table 2.3 as depicting the plutonium nitrate container; Figure 2.6 is given as the correct figure on pg 2-24. Both of these are incorrect, and an editorial change has been made to vii-b
ORNL/TM-11656/V1 Rev. 14 Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
cite the correct figure [Figure 2.4]. Additionally, a formatting error was corrected in Table 2.3.
x Section 2.9: Deleted reference to Figures 1.9, 1.10, and 1.12 through 1.17 from the last sentence in the section.
x Section 4.1: Made several editorial-type changes as follows:
Amended the first sentence of Section 4.1. Deleted the second sentence which details the activity of each element (the activities are provided elsewhere in Chapter 4). Deleted the last sentence of the first paragraph referring to a table on page 4-2 and made clarifications and editorial changes regarding the tables which appear on page 4-2. Changed the final sentence of the third paragraph to read Plate-type fuel assemblies are illustrated in Figures 1.7, 1.8, and 4.1.
x Sections 4.1.3 and 4.1.4: References to Appendix C (which is the current revision of RRD-FE-3, Specification for High Flux Isotope Reactor Fuel Elements) in these sections have been deleted.
Changed the third sentence of Section 4.1.4 from All HFIR fuel plates are vacuum sealed at over 550°C for 3 h with a maximum pressure of 1 x 10-4 torr during 70% of the anneal to All HFIR fuel plates are program annealed at high temperature, followed by a controlled cooldown rate.
This change reflects current fuel plate production processes.
Made an editorial change to the final sentence on pg. 4-4 as follows: The following sampling or verification process is changed to The following verification processes are Changed the Frequency per plate for Item #5, Destructive test to verify clad thickness and bond quality from 1 per 171 inner plates and 1 per 369 outer plates to state that the sample size and frequency are based on trending data of minimum clad thickness. This change reflects current fuel plate production processes.
Changed the first sentence of pg. 4-5 from During the initial qualification of the fuel plate fabrication process, three plates per lot to During the fuel plate fabrication process, a representative number of plates from different fuel plate lot numbers are destructively tested. This change reflects current fuel plate production processes.
Added a clarifying statement that the fuel inside the containment boundary is a solid non-dispersible material and removed the final two sentences of Section 4.1.4.
x Section 4.5 and Chapter 4, Appx. C: Deleted Appendix C.
x Table 6.2, pg. 6-5: Replaced references to ORNL drawings E-42118 and E-42126, which are fabrication drawings, with vii-c
ORNL/TM-11656/V1 Rev. 14 Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
Figure 1.7 (inner fuel element) and Figure 1.8 (outer fuel element). Additionally, the weight listed for the inner fuel element was changed from about 104 lbs to about 103.5 lbs for consistency with the listed weights elsewhere in the SARP.
x Section 7.1: Added a clarification to Step 6 which directs the user to place the element in a polyethylene wrap or bag to protect it from dust and moisture.
x Section 8: Replaced reference to Appendix C with Section 4.1.4. Appendix C was removed from Chapter 4, and fuel verification tests are discussed in Section 4.1.4.
x Tables 9-1 and 9-2: Added polyethylene foam to Q-list for the inner and outer fuel elements.
x Section 9.3.3: Moved and amended information regarding the fuel fabrication process in the design control section from pg. 9-12 to 9-11.
Changed refer to Chapter 1, Figures 1.3 through 1.10, 1.12 through 1.17 to refer to Chapter 1, Figures 1.3 through 1.8 in the fourth line of the third paragraph.
Removed parenthetical note regarding the HFIR Fuel Specification in Chapter 4, Appendix C, at the end of the fourth paragraph.
x Section 9.3.5: Under "Instructions, Procedures, and Drawings," removed "(NOTE: This document is found as Appendix C in Chapter 4, 'Containment.')"
x Section 9.3.9: Under "Control of Processes Affecting the Fuel Elements," removed "(NOTE: This document is found as Appendix C in Chapter 4, 'Containment.')"
Under "Control of Processes Affecting the Fuel Elements,"
removed "Section X of" from the third line of the second paragraph.
12 x Rev. 12 of the SARP addresses a latent error found in 21 Appendix B of the Chapter 3 thermal analysis. The amount of melting predicted to occur in this postulated scenario was skewed by the use of pre-machined HFIR fuel element side plate thicknesses in the calculations rather than the final assembly dimensions. Additionally, the A2 value previously calculated has been updated to the latest regulations. Vol. II of the SARP is not affected by these changes; thus, the only change in Vol. II is to the revision level.
x The Cover Page and LOEPs for both Volume 1 and Volume 2 were updated to Revision 12. The LOEPs were updated to identify pages changed in this revision as Revision 12.
vii-d
ORNL/TM-11656/V1 Rev. 14 Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
x Updated the Revision Log for Revision 12 changes.
x Section 2.1.2: Revised language in first full paragraph of pg.
2-2 from 0.1 Ci (A2 quantity) to an A2 quantity since the previous A2 quantity is no longer applicable under current regulations.
x Section 2.7.3: Revised the second sentence of the section to state less than an A2 amount of radioactive material will be released. This section has been updated for the revised analysis which corrects a latent error in Chapter 3, Appendix B, and updates the A2 value to be consistent with current regulations.
x Section 3.5: Revised the third sentence of the fourth paragraph in Section 3.5 (pg. 3-7) to state an A2 amount of radioactive material will be released....
x Ch. 3, Appendix B, LOEP, pg. 3-B-1: Editorial change to update revision level for pages 3-B-1, B-1 through B-4, B-8, and B-9.
x Ch. 3, Appendix B, Summary, pg. B-1: Changed the predicted amount of melted fuel in the fourth sentence to reflect the revised analysis in Chapter 3, Appendix B.
x Ch. 3, Appendix B, pgs. B-2 through B-4 and B-8: Revised the applicable portions of the calculation section of Ch. 3, Appendix B, and provided references to the correct drawings for side plate dimensions for the inner and outer fuel elements. Updated the conclusion of calculation analysis to reference to reflect that the Appendix B test now begins at the NCT maximum temperature of 169ºF.
x Ch. 3, Appendix B, References, pg. B-9: The references to the manufacturing side plate drawings were deleted.
References for the side plate dimensions now call out the fuel assembly drawings in Chapter 1.
x Section 4.1, pg. 4-3 and (new) pg. 4-3a: Discussions of the fuel material and associated A2 values for the inner and outer fuel elements were updated to reflect the current regulations.
x Section 4.3.3, pgs. 4-8 and 4-9: This section was updated to reflect that, at a minimum, releases of greater than 90 % of the fuel from an inner element and greater than 34% of the fuel from an outer element are necessary to release an A2 vii-e
ORNL/TM-11656/V1 Rev. 14 Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
amount of material. Additionally, the second paragraph was updated to reflect that the analysis in Ch. 3, Appendix. B, concludes that less than 25% of the fuel-bearing material from a fuel element will melt in the HAC thermal test when the container is not present.
11 x The Cover Page and LOEPs for both Volume 1 and Volume 20 2 were updated to Revision 11. The LOEPs were updated to identify pages changed in this revision as Revision 11.
x The Summary of Revision page in Volume 1 was replaced with a detailed revision log in Volume 1. The Summary of Revision page in Volume 2 was revised to refer the reader to the detailed revision log in Volume 1.
x Section 1.1 and the introductory paragraph in Chapter 6 were revised to clarify that since current regulations no longer use Fissile Classes. A Criticality Safety Index of 0.4 is specified in the CoC.
x An editorial change was made to Section 1.1 to clarify that the containers comply with regulations in effect as of the date of the original application.
x Section 1.2.1, a typographical error was corrected related to the wood post glued to the inside wood base 4 1/4 inches from the center of the cask, as this dimension is shown on drawing M-20978-EL-002, Rev. E (included as Figure 1.3) x Table 1.1 was revised to correct the drawing number listed for the HFIR Outer Fuel Element - Outer Side Plate.
x Figure E-20 in Appendix E of Chapter 2 was replaced with a copy that was redrawn to improve legibility. Revision level indicated for this figure was not changed because no technical changes were made in the figure.
x The LOEPs for Appendix C of Chapter 2 (page 2-C-1) was revised to change the indicated revision level of page 42 from Rev 4 to Rev 7. Page 42 was previously revised as part of the revision 7 update, but the indicated revision level was inadvertently left at Rev 4 on the LOEPs.
x The microfiche previously included as Appendix 3.6.A was replaced with a printout of the microfiche contents to facilitate conversion of the document to an electronic format. The associated title page for the appendix was revised to delete reference to the microfiche.
vii-f
ORNL/TM-11656/V1 Rev. 14 Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
x Photos 1-6 in Chapter 4, Appendix A were replaced with more legible copies. Revision level indicated for this appendix was not changed because no content changes were made in the appendix.
x Appendices B and D in Chapter 4 were replaced with more legible copies. Revision level indicated for these appendices was not changed because no content changes were made in the appendices.
x Chapter 9, Section 9.1, Introduction, first paragraph, added wording to clarify that users of the containers must be registered Users and must maintain an acceptable Quality program.
x Editorial changes were incorporated in Chapter 9 to reflect current organizational structure, current document identifiers, and make minor clarifications.
CoC Rev 19 made editorial changes in the CoC, and no changes to the SARP. 19 10 x Volume 1 and Volume 2 cover pages were revised to update 18 the revision level and date.
x The lists of effective pages for Volumes 1 and 2 were revised to reflect the changes in Revision 10.
x The summary of changes page for each volume was revised to list changes in revision 10 of the document.
x Sections 1.2.1.1, 1.4, 4.5, 9.3.3, 9.3.5, 9.3.6, and 9.3.9 were revised to cite the most recent revision of the fuel element specification, RRD-FE-3.
x Table 1.1 was revised to cite the most recent revision of the drawings listed in the table.
x Drawings M-20978-EL-002E and M-20978-EL-003E, included as Figures 1.3 and 1.4 were revised to include the trefoil label required by 49 CFR 172 Appendix B.
x Drawings E-42118, E-42126, D-42114, and D-42122, included as Figures 1.7, 1.8, 1.14, and 1.17 respectively, were updated to incorporate editorial changes and to reflect the results of improved inspection techniques implemented at the fuel fabricator.
x Chapter 4, Appendix C was revised to include the most recent revision of RRD-FE-3, the fuel element specification.
9 x Volume 1 and Volume 2 cover pages were revised to update 17, 16, 14, 13, 12 the revision level and date.
vii-g
ORNL/TM-11656/V1 Rev. 14 Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
x The lists of effective pages for Volumes 1 and 2 were revised to reflect the changes in Revision 9.
x The summary of changes page for each volume was revised to list changes in revision 9 of the document.
x Drawings M-20978-EL-002E and M-20978-EL-003E, included as Figures 1.3 and 1.4 respectively, were revised to include new plywood specifications that facilitate maintenance on the containers. (CoC Rev 14 included approval of changes in the plywood specification shown on drawings M-20978-EL-002E and -003E.)
x Drawing M-20978-EL-008E, included as Figure 1.5, was revised to update nameplate information. (CoC Rev. 13 included approval of nameplate changes on drawing M-20978-EL-008E. CoC Rev. 12 included reference to the September 1996 submittal, however it did not include approval of the change.)
x Drawings D-42114 and D-42122, included as Figures 1.14 and 1.17 respectively, were revised to change the maximum allowable distance between the fuel area and the edge of the fuel element plate. These changes were based on use of more sensitive radiographic inspection techniques by the fuel fabricator. (CoC Rev 17 included approval of changes in the allowable distance between the fuel area and edge of the fuel element plate as shown on drawings D-42114 and D-42122. These drawing changes were originally submitted in August 2007. Revision 16 of the CoC cites the August 2007 submittal but the revised drawings were not listed until Revision 17 of the CoC.)
CoC Rev 15 made no changes to the SARP. 15 8 x Volume 1 cover page was revised to update the revision 13, 12 level and date.
x The list of effective pages for Volume 1 was revised to reflect the changes in Revision 8.
x The summary of changes page for Volume 1 was revised to list changes in revision 8 of the document. (No changes were made to Volume 2.)
x Minor editorial changes were made in the Table of Contents, List of Figures, List of Tables, and Abstract to address discrepancies identified by an internal self-assessment.
vii-h
ORNL/TM-11656/V1 Rev. 14 Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
x Drawings E-42118 and E-42126, included as Figures 1.7 and 1.8 respectively, were revised to change reference to drawings: M-11524-04-101-D and M-11524-04-102-D to M-11524-OH-101-D and M-11524-OH-101-D. (CoC Rev 13 included approval of these drawing changes - CoC Rev 12 included reference to the request for this change but did not include approval of the change)
CoC Rev. 11, no changes were made to the SARP 11 7 x Volume 1 and Volume 2 cover pages were revised to update 9 the revision level and date.
x The lists of effective pages for Volumes 1 and 2 were revised to reflect the changes in Revision 7.
x The following changes were made to incorporate clarifications included in the DOE letter from Michael Wangler to Charles MacDonald of NRC, dated February 26, 1992:
o Table 2.1 was revised to include bolting material properties o Section 2.7.1.2 and Section 6.4 of Appendix C were revised to clarify acceptable strength of the closure bolts.
o Section 2.7.6 was revised to include a summary of cumulative damage.
o Table 6.2 was revised to add a value for density for the Al cermet.
6 x Sections 1.2.3, 4.1, 5.2, and Table 6.2 were revised to 10 change the maximum U235 content from 2.6 kg to 2.63 kg and from 6.8 kg to 6.88 kg for the inner and outer fuel element containers, respectively.
x An existing supplement was added to the fuel element specification, included as Chapter 4 Appendix C, to ensure that all fabrication documentation is included in the SARP. The supplement provided specifications for U3O8 provided by ORNL to the fuel fabricator.
5 Revision 5 was the first revision of the SARP submitted for 9, 8 NRC review. A detailed description of the changes incorporated in this revision is not available. The changes included in revision 5 addressed the final set of comments from the DOE review in preparation for submitting the document to the NRC vii-i
ORNL/TM-11656/V1 Rev. 14 Revision Description of Changes Approved by NRC Certificate of Compliance (CoC)
Revision Number:
for upgrading the CoC from B( )F to B(U)F. The following pages were changed in revision 5:
Chapter 1 x 1-1 through 1-4; 1-6; 1-7; 1-11; 1-18; 1-19; 1-21; & 1-22.
Chapter 2 x 2-2; 2-3; 2-5 through 2-8; 2-13; 2-14; 2-16 through 2-24; 2-27; selected pages in Appendix C, selected pages in Appendix E; and selected pages in Appendix F.
(CoC Rev 8 invoked the maintenance program and operating procedures from ORNL/TM-11656 (submitted with May 30, 1991 DOE letter), but did not invoke new bolt specification, etc.
for upgrade to meet B(U)F. CoC Rev 8, and prior revisions cited ORNL/ENG/TM-9 as the applicable safety analysis.
CoC Rev 9 upgraded the designation from B( )F to B(U)F.
Drawings included in SARP, Rev. 5, Chapter 1 cited correct bolt specifications and blocking device. Procedures described in SARP, Rev. 5, Chapter 7 included blocking device. With the upgrade to B(U)F designation, references to ORNL/ENG/TM-9 were removed from the CoC and replaced with ORNL/TM-11656.)
4-0 This document was prepared to demonstrate compliance with Not applicable then-current regulations and allow upgrading the CoC from B( )
to B(U)F. Revisions 0 through 4 were reviewed by DOE, but not by the NRC. Revisions 1 through 4 addressed comments that resulted from DOE review of the SARP in preparation for submittal to NRC. A detailed description of the changes incorporated in revisions 1 through 4 is not available. See the ORNL letter from H. A. Glovier to H. Randall Fair of DOE, dated April 26, 1991,
Subject:
Responses to DOE-HQ Evaluation of Q0/Q1/Q2 Questions on the DOE Certificate of Compliance (No. 5797) License Renewal Request for the High Flux Isotope Reactor Unirradiated Fuel Shipping Containers for submittal of SARP revision 4 changes.
vii-j
is 31.5 OD by 45.75 inches high and has a cavity 17.38 inches ID by 31.12 inches long. The gross weights are 660 and 1050 pounds, respectively.
The bottom plate is welded to the shell. Sixteen 3/8-inch x 1-inch ASTM A449-Gr C carbon steel bolts and ASTM A563-GR C carbon steel nuts with stainless steel flat and lock washers attach the lid to a 2 x 2 x 1/8-inch ASTM A36 structural steel angle flange welded around the top of the outside of the shell.
A 1/8-inch thick neoprene gasket lies between the lid and the angle flange. The gasket does not provide a pressure seal; its purpose is to exclude rainwater. The gasket does not provide a pressure seal because the sealing surfaces were not machined nor maintained parallel during fabrication; four weep holes are provided in the angle flange to ensure venting.
Three 1 x 1 x 1/8-inch ASTM A36 steel reinforcing angles are welded around the outside of the shell, one at the midpoint and one 15 inches above and below the midpoint. An additional 2 x 2 x 1/8-inch reinforcing angle is welded to the shell at the lid flange angle. Six inches of laminated Douglas fir plywood lines the inside of the shell and acts as thermal insulation. The plywood is lined with 1-inch of polyethylene foam, which serves as a shock absorber to protect the contents from physical damage. In the outer fuel element model, a 2-inch diameter wood post is glued to the inside wood base 4 1/4-inches from the center of the cask to make it impossible to load both inner and outer fuel elements into the container.
1.2.1.1 Fuel. The radioactive contents of the research reactor fuel elements that are typically classified as MTR-type fuel (such as HFIR) are contained in a fuel matrix and clad in aluminum which together provide a containment that withstands the combined effects of the structural and thermal tests for normal and accident conditions when transported in the HFIR unirradiated fuel element containers. The salient design features of the assembled fuel element are provided in Figures 1.7 and 1.8. The detail containment boundary information is included in Chapter Four, Containment, Section 4.1, Containment Boundary. Optional combs constructed of 6061 aluminum and spot welded to form concentric rings at the top of each element may be installed on fuel elements as necessary to provide the fuel plates with end stiffening and proper separation to reduce the probability of a flow blockage accident during reactor operation (refer to Figs. 1.7 and 1.8).
Each fuel core, which constitutes a rectangular parallelepiped, consists of two mating sections: (1) a fuel section, varying in thickness across the width, and (2) an aluminum filler section which in the inner fuel element contains a burnable poison in the form of B4C. The fuel and burnable poison surface densities are varied across the width of each plate to help control the power distribution during reactor operation.
1-2 Revision 14
FullSizeDrawingAttached
Figure1.3.DrawingM20978EL002E(RevisionF).
18 Revision14
FullSizeDrawingAttached
Figure1.4.DrawingM20978EL003E(RevisionG).
19 Revision14
FullSizeDrawingAttached
Figure1.5.DrawingM20978EL008E(RevisionD).
110 Revision14
ZZ1[\] y mega qiatbm bnshbb Z ^ÿÿ^ sg iamrÿi{
yxÿbvÿasi_b3 1{d { ^ÿÿ^ km ^ÿÿ^
y\
^ÿÿ^
^ÿÿ^
irbÿslimb qiatbm
{\\ÿabhg aam baÿ
bnshbb
1yZ
{zlyÿk_ÿZj [
y1[\ y1c[ 1Z 1yZ
^i^
^j^
ah
^_^ 1{
0 0 1c[
1{ y1[\
1{
1c[
a_ilbwywy a_ilbwywy
sihmÿ 3grÿ^i^ 3grÿ^j^ 3grÿ^_^
n1 y {[1[\ {y1[\ ((1c[
y\ Zd1[\ Z[1\\ Zc1yZ a_ilbwyw amirsÿiaÿaenuÿkagq fnhÿnkmbhÿblbrbmllnkmbh
1[\ÿegqeÿlbmmbha fnhÿgbhÿblbrbmllgbh
1Z[
[1[\
5 5 fnhÿnkmbhÿblbrbmlly\[\ÿlja fnhÿgbhÿblbrbmll[\ÿlja d1[\
abhgilÿkrjbhaÿmnÿjbÿasb_gfgb3ÿjpÿnubh
a_ilbwywy
[
MNÿUVWRPNRQRXYST aegssgqÿ_nmigbhÿfnhÿkghhi3gimb3ÿ nkmbhÿefghÿblbrbmÿiaabrjlp aegssgqÿ_nmigbhÿfnhÿkghhi3gimb3ÿ gbhÿefghÿblbrbmÿiaabrjlp rZ\dcbl\\Z rZ\dcbl\\{
567689:ÿ<=ÿ>?@A6BB9CC9ÿDEFÿBG9ÿ>HÿI9J6FBK97BÿEDÿL79F8=ÿ 1234562781ÿ57 64 0 qbbhilÿasb_gfg_imgna
_ikmgnÿk_lbihÿbvkgsrbmw klbaaÿnmebhugabÿasb_gfgb3 3grbagnaÿihbÿgÿg_eba ipÿshn_baaÿnhÿrimbhgilÿ?g_lk3gqÿsi_tiqgqÿi3ÿaegssgqÿrimbhgila hbrnobÿjkhhazjhbitÿb3qba meimÿeiaÿmebÿsnaagjglgmpÿnfÿlbiogqÿiÿhbag3kbÿ_nmiggqÿipÿnfÿmeb eilg3bÿblbrbmaÿ?shgrihglpÿ_elnhgbÿi3ÿflknhgb&ÿrbmillg_ÿblbrbma fhi_mgna ` zi n1
[ abbÿ3_ÿ hbogagna 3bagqbh hbogbubh v1i1a1 isshnob3 nsa1ÿrqh miatÿl3h aifbmp _1_1ÿrqh rigmÿrqh 3imb fi_glgmp e1f1g1h1 jl3q1
ÿn1 cd\\
qhisegmbÿnÿmebÿakhfi_bÿnfÿipÿefghÿ_nrsnbmÿifmbhÿfgilÿ_lbigq ÿÿ3b_grila ` 1\{
?shgrihglpÿ_nssbh&ÿlbi3&ÿg_tbl&ÿaglobh&ÿmenhgkr&ÿi3ÿmgÿnhÿ_ihjnz 3bagqbh 3imb aifbmpÿiilpam 3imb isshnob3 3imb aeillÿnmÿjbÿkab31ÿrbh_khpÿgÿipÿfnhrÿaeillÿjbÿasb_gfg_illpÿshbl
_lk3b3ÿgÿmebÿshn_khbrbmÿnfÿilkrgkrÿhiuÿrimbhgilaÿi3ÿgÿill ÿ3b_grila ` zi shn_baagqÿi3ÿrikfi_mkhgqÿnsbhimgna1
ÿ !"!# ÿ ÿ$" " !%&ÿÿ ' (ÿ ÿ#) *# (&ÿÿ# ÿ)"( ÿ" ÿ!ÿ!+ ÿ iqlba ` \ l{\}
",,- ",%&ÿ,) * ! ÿ ÿ- .-* ÿ.ÿ!+ ÿ#. )"!# ÿ ÿ !"! ) !
, !"# (ÿ#ÿ!+ ÿ( "$#/ &ÿÿ ÿ!+"!ÿ!+ ÿ- ÿ ÿ(# ,* - ÿ.ÿ" %ÿ#. )"!# &ÿÿ fgllbma zi rix1 miatÿlbi3bh 3imb v1i1ÿasb_gilgam 3imb rigmÿrqh 3imb
" " "!- &ÿ) !+(&ÿ ÿ , ÿ(# ,* (ÿ#ÿ!+ ÿ( "$#/ ÿ)"%ÿ !ÿ#. #/ ÿ ri_egbÿfggae yZ[ rix1
#0"! ÿ #/+! ÿ.ÿ!+ 1ÿÿÿ*#"2#*#!%ÿ# ÿ" -) (ÿ$#!+ÿ ,!ÿ!ÿ!+ ÿ- ÿ.&ÿÿ 3bagqÿhbogbubh 3imb _fq1ÿ_nmhnlÿrqh 3imb nsbhimgnaÿrqh 3imb 3uq aem ag~b hbo
ÿ. ÿ(")"/ ÿ -*!#/ÿ. )ÿ!+ ÿ- ÿ.ÿ" %ÿ#. )"!# &ÿÿ" " "!- &ÿÿ
) !+(&ÿ ÿ , ÿ(# ,* (ÿ#ÿ!+ ÿ( "$#/ 1ÿÿ3 "$#/ ÿ)"( ÿ"0"#*"2* ÿ. ÿ a_ilbw
- . )"!# ÿ!ÿ2#(( ÿ" ÿ !ÿ!ÿ2 ÿ- (ÿ. ÿ!+ ÿ - ÿ" (ÿ" ÿ!ÿ2 ÿ
iaÿjkglm
!- (ÿ- ÿ 4- !ÿ.ÿ!+ ÿ. $" (#/ÿ, ! ",! 1
Drawing Attached Fig. 1.7. HFIR Fuel Unirradiated Inner Element Certification DrawingM-11524-OH-106 (Rev. 5).
1-12 Revision 14
Drawing Attached Fig. 1.8. HFIR Fuel Unirradiated Outer Element Certification DrawingM-11524-OH-107 (Rev. 5).
1-13 Revision 14
ORNL/TM-V11656/V2 Rev. 14 SAFETY ANALYSIS REPORT FOR PACKAGING THE ORNL HFIR UNIRRADIATED FUEL ELEMENT SHIPPING CONTAINER VOLUME 2 Compiled by G.A. Aramayo C.M. Hopper J.R. Kirkpatrick D.M. McGinty J.T. Muecke J.C. Walls Latest Revision - Revision 14 Date of Revision - June
Prepared by OAK RIDGE NATIONAL LABORATORY Oak Ridge, TN 37831-6283 managed by UT-BATTELLE, LLC for the US DEPARTMENT OF ENERGY under contract DE-AC05-00OR22725
ORNL/TM-V11656/V2 Rev. 14 Page 1 of 1 LIST OF EFFECTIVE PAGES Volume 2 Page Revision Cover Page 14 ii thru iii (Table of Contents) 8/7/98 iv (List of Figures) 8/7/98 v (List of Tables) 8/7/98 vi (Summary of Revision changes) 14 6-1 11 6-2 0 6-3 2 6-4 1 6-5 13 6-6 thru 6-9 4 6-9a thru 6-12 2 6-13 thru 6-18 1 6-19 3 6-20 thru 6-25 1 6-26 3 6-27 thru 6-34 1 6-35 thru 6-37 4 6-A-1 4 6-B-1 4 6-C-1 4 6-D-1 4 7-1 13 7-2 14 7-3 4 8-1 13 8-2 14 8-3 4 8-4 14 8-5 0 9-1 thru 9-5 11 9-6 4 9-7 thru 9-8 13 9-9 4 9-10 11 9-11 thru 9-13 13 9-14 11 9-15 13 9-16 14 9-17 thru 9-20 11
ORNL/TM-11656/V2 Rev. 14 Page 1 of 1 Summary of Revision Changes Volume 2 Changes incorporated in Volume 2 are summarized in the revision log included in Volume 1 of this document.
vL
post prevents loading both the inner and outer element into the outer container.
- 7. Place the container lid on the container and install the lid hold down bolts. Torque all lid bolts to 20 ft-lbs.
- 8. Install security seal and record number on shipment documentation.
- 9. Conduct a radiation survey to verify compliance with applicable radiation and contamination limits.
- 10. Transfer the loaded container to the storage area or shipping vehicle by a fork lift which lifts from under the container. Use appropriate tiedown to stabilize the container during movement by the fork lift.
- 11. HFIR unirradiated fuel element containers, when loaded with fuel, are shipped off-site in a sole-use vehicle. The HFIR fuel element container is provided with a removable shoring ring (depicted on ORNL drawing M-20978-EL-008B) which may be used to shore or tiedown the container during shipments. Appropriate shoring shall be used in the transportation of those containers.
- 12. Complete appropriate shipment documentation.
7.2 Procedures for Unloading Package Only one fuel element is to be removed at a time from a container. The following generic sequence shall be used for unloading operations:
- 1. Conduct Health Physics survey to verify that the package is received in compliance with the radioactive and contamination limits.
- 2. Move loaded container to unloading area using a fork lift under the container. Use appropriate tiedowns to stabilize the container during movement by the fork lift.
- 3. Verify that security seal is intact. Remove the seal.
- 4. Remove the lid hold-down bolts and then remove the lid-lifting blocking device. Remove the lid with an approved lifting assembly at the user facility. Place the lid on blotter paper to prevent the spread of any potential contamination.
- 5. Remove the fuel element from the container and transfer the fuel within the facility according to the procedures of the facility.
7-2 Revision 14
8.1.5 Tests for Shielding Integrity Since the unirradiated HFIR fuel elements required no shielding to demonstrate compliance with radiation limits, no test for shielding integrity was required. Before each shipment, surveys are conducted to verify that radiation levels are within acceptable guidelines.
8.1.6 Thermal Acceptance Tests Since the unirradiated HFIR fuel elements required no thermal design considerations during normal transportation, no thermal acceptance tests were required. Therefore, the requirements of this section are not applicable.
8.2 Maintenance Program Visual inspections will be conducted as part of the preparation process for shipping unirradiated fuel. Table 8.1 contains an inspection guideline for these containers. Qualified quality assurance inspectors will inspect the cask for external and internal physical damage to the container to include identification of dents and scratches on the outer container, water damage to the plywood, and wear of the gasket.
The cask will be considered unacceptable for use if the paint has been scratched such that labeling or markings are unclear or incomplete. Dents which have perforated the container will render the cask unacceptable for immediate use until further evaluations or modifications can be made. Plywood will be replaced if water damage has occurred. Gaskets will be replaced prior to use if gaskets are worn or brittle.
8.2.1 Structural and Pressure Tests 8.2.1.1 Structural Integrity. Evaluations of the structural integrity of the HFIR shipping containers have been made for: a) impact forces due to normal and hypothetical accident drop conditions of 10 CFR 71, and b) the container lid lifting system.
Testing results as discussed in Chapter 2, Structural Evaluation, conclude that the HFIR unirradiated fuel element shipping container complies with the applicable regulations for structural integrity. Further evaluations of structural damage which may results from use will be made after visual inspections identify problems.
8.2.1.2 Pressure. No pressure tests will be conducted for the containers. The regulations require that the shipping package be adequate to ensure that the containment vessel will suffer no loss of contents if subjected to an external pressure of 25 psig. The 1/8-in.
neoprene gasket between the lid and the angle flange does not provide a seal, and a weep hole is provided to ensure that the container is not sealed. Hence, the external and internal pressures on the cask will 8-2 Revision 14
these inspections are, therefore, adequate to verify the integrity of the package during use.
8.2.7 Miscellaneous Prior to each shipment, the containers are inspected for damage, missing hardware, legibility of labels and markings, etc. The containers will be repainted, and any degraded hardware replaced, as necessary.
8-4 Revision 14
All inprocess, final, and inservice inspections and inspection personnel will be independent from the individual(s) performing the activity being inspected.
9.3.11 Test Control Test requirements are defined in applicable specifications or in other special project documents.
9.3.11.1 Acceptance Tests - Use of the Package. Test control measures are employed to ensure that the necessary tests are planned, are performed properly to specified requirements, and are documented to indicate that items have demonstrated their ability to perform satisfactorily in service. A test plan will be prepared for each test required on each container.
9.3.11.2 Maintenance Tests. Visual inspections are conducted as part of the preparation process for shipping unirradiated fuel. These inspections include the following: a visual inspection of the inside of the container, a visual inspection of the outside of the container, a check for contamination, a verification that all lid bolts are present, an inspection of the gasket surface and replacement if signs of degradation are observed, and an inspection of the lid-lifting blocking device to ensure all parts are in place and in working condition.
Qualified quality assurance inspectors inspect the cask for external and internal physical damage to the container to include identification of dents and scratches on the outer container, water damage to the plywood, and wear of the gasket. The cask is considered unacceptable for use if the paint has been scratched such that labeling is unclear or incomplete. Dents that have perforated the container will render the cask unacceptable for use until further evaluations or modifications can be made. Plywood will be replaced if water damage has occurred. Gaskets will be replaced prior to use if gaskets are worn or brittle.
Maintenance is performed as needed based on the results of the inspections.
Maintenance of the HFIR fuel is not addressed in this section. The fuel is enclosed in a fuel assembly. As such, after the initial fabrication and testing, no maintenance is performed.
9-16 Revision 14