ML20247Q541
| ML20247Q541 | |
| Person / Time | |
|---|---|
| Site: | 07109152 |
| Issue date: | 01/31/1989 |
| From: | EG&G IDAHO, INC. |
| To: | |
| Shared Package | |
| ML20247J808 | List: |
| References | |
| NUDOCS 8906060457 | |
| Download: ML20247Q541 (27) | |
Text
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- x CNSI RESPONSE TO COMMENTS ON DOE DOCKET NO.- 88-2-9152 JANUARY 1989 Ref
W. D. Jensen letter to A. A. Anselmo " Review on CNSI' Response To Comments on DOE Docket No. 88-2-9152," Dated 12/08/88. Y t 1 8906060457 890512 [DR ADOCK 07109152 PDR f lL-----_______--__.___________
i 1.2 PACKAGE DESCRIPTION OVESTION NO. 1 On page 1-6 under the heading of " Protrusions", the statement should be corrected to cite the cask lifting lugs as being the removable feature. CNSI RESPONSE The word "tiedown" will be replaced by " lifting". The statement will read as follows: There are no outer or inner protrusions. Lifting lugs are removed prior to transport. DOE REVIEH COMMENTS Response is adequate. OVESTION NO. 2 On page 1-6 in the last paragraph, the reference should cite Appendix 1.3 and the drawing number given should be added to the drawing list in Appendix 1.3. [^) CNSI RESPONSE t The word "section" will be replaced by " Appendix". The statement will read as follows: 1. General Debris Container The general debris container configuration as described in Part A of Section 1.1 consists of a genera 1 debris container (loaded with either a fuel pin sample cell or debris container) loaded into a 2R container in a shoring cage. A shipping configuration is shown in EG & G drawing THI 1113 in Appendix 1.3. The following is a description of these components. DOE REVIEW COMMENTS The drawing list in Appendix 1.3 was not updated as requested. ,CNSI RESPONSE (1/20/89) The drawing list in Appendix 1.3 has been revised to include EG&G drawing THI 1113 as well as all other drawings and figures included within the Appendix. im \\ GJ
f(j 1.3 APPENDIX PACKAGING DRAWINGS OVESTION The drawings have been reduced to the extent that not all the details and notes are legible. Provide a legible set of packaging drawings. CNSI RESPONSE 1 Full size drawing (CNS 1-13 C II REV. D) will be provided. The remaining THI full size drawings are not available to CNSI. ~l DOE REVIEW COSMENTS Stating that only one full sized drawing is being provided and that the other drawings are not available is not satisfactory. However, all required drawings have been located and included in the package. Additionally, the prints in Appendix 1.3 do not have the section number typed on the bottom of the pages to correspond with the sectiot. numbers listed in the drawing list. CNSI RESPONSE (1/20/89) All drawings included in Appendix 1.3 have been labeled with the appropriate section number as listed in the drawing list and have been included within the O submittal. l-l l l 1 /
- ,y 2.0 STRUCTURAL EVALUATION 00ESTION The consolidated application is incomplete in that the information in microfiche form referenced on page 2-213 has not been provided.
CNSI RESPONSE A copy of the microfiche was provided with the first SAR submittal Danuary 4, 1988). An additional copy will be provided upon request. DOE REVIEN CD MENTS Stating that the referenced microfiche was supplied and another provided upon request does not fully resolve the problem. Additional copies of the required material should be supplied. CNSI RESPONSE (1/20/89) Two aeditional copies of the subject microfiche have been included in the submittal of Revision 2 information. O 1 l t 7.0 OPERATING PROCEDURES Q OUESTION NO. 1 b Operation 7.1.7 should be expanded to address the need to check that the seal replacement is current with the seal replacement schedule. CNSI RESPONSE Operation 7.1.7 will read as follows: Inspect and clean lid gasket, 0-ring, drain seal, vent seal and gasketed surfaces. Replace the drain seal and vent seal. Verify that replacement of the 0-ring and lid gasket have been performed within the required replacement i schedule (see step 8.2.4). In addition to these requirements, replace any gasket or seal if it shows signs of wear or deterioration. DDE REVIEW 00MM.E!LTS Response was adequate. i 00ESTION NO. 2 O Operation 7.1.8.1. The certificate of ccmpliance requires that the test / vent port and drain line plug seal be replaced prior to each loaded shipment. The operating procedures should address these requirements and also state the torque requirement for the vent and drain plugs. CNSI RESPONSE Seal and gasket replacement has been specified in Operation 7.1.7, Operation 7.1.8.1 will read as follows: Payload weight shall not exceed 3,000 pounds. When loaded in a submerged fashion, both vent and drain plugs should be removed. Vent and drain plugs should be reinstalled after cask cavity is drained. Torque plugs to 12 ft-lbs. (f.l'ft-lb.) DQ N_01 QVER TOROUE. When positioning the lid onto the cask while loading in a submerged fashion, the lid shall be shimmed open to allow venting and drainage from the area between the 0-ring and flat lid gasket. DOE REVIEW CUPNENTS Response was adequate. __
/ OUESTION NO. 3 There should be Operational steps, prior to 7.1.11, that require the cask to be decontaminated and a radiation survey performed including a determination of surface contamination to assure compliance with 10 CFR 71.47 and 71.87. CNSI RESPONSE Step 7.1.10 will be revised to include the following: 1. Decontaminate all external surfaces of the cask. 2. Perform a radiation and contamination survey of the cask to assure compliance with 10 CFR 71.47 & 71.87 limits, respectively. DOE REVIEW COM ENTS Stating that a survey should be conducted to insure that the a section of the Code of Federal Regulations is met is not sufficient. The appropriate limits, that apply to the situation, should be called out to ensure that the proper limits are met. If the limits are not to be called out in the text, then list the procedures that are to be utilized to accomplish this survey. This enables the NP.C to determine if the correct interpretation has been made of the limits that apply to the situation described in the procedures. CNSI RESPONSE (1/20/89) Step 7.1.10 has been revised to include the appropriate limits as specified in 10 CFR 71.47 and 71.87. 00ESTION NO. 4 Operation 7.1.14 should specify a torque requirement. CNSI RESPONSE Operation 7.1.14 will read as follows: Attach and hand tighten ratchet binders attaching upper overpack to lower overpack. DOE REVIEH CO M ENTS Stating that the ratchet binders should be hand tightened is no longer acceptable to NRC or DOE as a torque requirement. A specific torque limit should be listed with tolerances. CNSI RESPONSE (1/20/89) O Step 7.1.14 has been revised to specify that the ratchet binders be torqued to 100 ft-lbs 107.. E__ _ __ _ _ _ i
? 4 f(D 00ESTION NO. 5 In section 7.2, procedures for unloading the pa:kage, a statement should be made regarding compliance with the instructions of 10 CFR 71.89. CNSI RESPONSE f Section 7.2. will be revised to add: Prior to unloading the cask, verify if special instructions are required to safely open the package. DOE RFVIEW COPMENTS The concern that compliance with the instructions of the Code of Federal Regulations will be met, is not satisfactorily addressed by the pronosed change to the SARP. Stating " verify if special instructions are required to safely open the package," does not ensure compliance. The special instruction of 10 CFR 71.89 and when they are required should be listed. CNSI RESPONSE (1/20/89) Section 7.2 has been revised to include the sequence of events which will be followed prior to unloading the package. O QUESTION NO. 6 Ir. section 7.3, preparation of empty packages for transport, a statement should be made regarcing compliance with the requirements of 49 CFR 143.427. CNSI RESPONSE The following statement will be added to section 7.3. The requirements of 49 CFR 173.427 with respect to shipment of empty packages will be complied with. DOE REVIEW CODNENT Stating that the requirements of the Code of Federal Regulations with respect to empty packages will be complied with, does not constitute assurance that 4 the proper limits applying to this cask are being met. The appropriate limits should be spelled out and incorporated into the procedure. This ensures the reviewers, of this package, that the proper regulations are being met. CNSI RESPONSE (1/20/89) Section 7.3 has been revised to include the requirements as specified in O 49 CFR 173.427. _ _ _ _ _ _ _ _. _a
8.2 MAINTENANCE PROGRAM 00ESTION The requirement on gasket replacement is not in agreement with the replacement schedule given in the supplements dated December 20, 1982 and September 7, 1983 as referenced by the certificate of compliance. The replacement schedule is also stated in Condition 10(11) of the certificate of compliance. CNSI RESPONSE 8.2.4 will read as follows: Seals and gaskets will be replaced in accordance with the following periodic maintenance schedule. The 0-ring must be replaced quarterly. The flat lid gasket must be replaced annually. The test port and drain line seals must be replated prior to each loaded shipment. DOE REVIEW COMMENTS ( Response was adequate. OVESTION TO APPENDIX BA In Section 0.3, Item 19 requires verification that leak checks have been completed. Identify the leak test procedure which checks the vent and drain port seals Item 19(a). CNSI RESPONSE Item 19 will read as follows: (19) Verify the following leak checks have been completed: (a) Vent and drain ports (as per operation (16) above). (b) 0-ring seal (as per operation (14) above). (c) Flat gasket seal (as per operation (14) above). DOE REVIEW COMMENTS Response was adequate. l
r Revision 0 FIGURE 1.3.2.1 MODEL 1-13C II PACKAGE i OVERPACK ^ FOAM Vr 7/f w., -e DQWN \\ I ~~ t l L[AD INNER ~ll S,. / .r \\ l sunt / Y i ),. // 1'y j, 7, h b l .3MEL.L A i.:, / A p..
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Revision 0 FIGURE 1.3.2.2 EXPLODED VIEW SECONDARY CONTAINERS FOR USE WITH 1-13C II, CASK per,pa t I. I ter i h V CNS 113C 11 cask tid --- Shicided container carrier lid 6 b: - Shielded container lid 9 I o l I TMI 2 fuel bearing-material bucket - Shielded container bhielded container carrier .A d i 9 .j CNS 113C ll cask \\ lo ri pa ti i er
--1 p t Revision 0-FIGURE 1.3.2.3 TMI-2 SHIELDED CONTAINER CARRIER 1" x 5 ft long i Web Sling j 2850 lb Capy-n b 4 b ' 1/2 Ton y / Shackle p T pg-k-h* L.L..b_ = gr tm ( s u Maximum Width 26.13 ( 2 e' [ Stainless lverall Steel rleight /.. 55 Gal 37.0 Drum (DOT 170) e r' (.............. .....N 1# w,
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Rsvision 0 l FIGURE 1.3.2.4 C 1 i TMI-2 SHIELDED CONTAINER FOR 1-13C II CASK Remov,a_ bl e g Lid-Alignment / Guide (2. Places) Eyebolt (5 Places) Lid Bolt / (4 Places) '\\ 8 \\ / 'N a s, b_ N N, ta n ess
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x- 'A ~ In i Height 't \\ a' N N, N \\ 1/2" Stainless Steel '. \\ (Side & Bottom) 1-2" Cast Lead 16" (Side & Bottom) Inside Diameter 1/4" Stainless Steel l' (Side & Bottom)
Revision 0 FIGURE 1.3.2.5 TMI-2 BUCKET FOR SHIELDED CONTAI!ER 15.38 " Outside Diameter Lifting - [ Cleat (2 Places) / x N 'x ( 23.75" Overall Height r liesh 1 y,s O Tipping Lug k'~ 'N s 'NN s,
R:vicion 0 FIGURE 1.3.2.6 (g TMI-2 FUEL - BEARING - MATERIAL BUCKET FOR SHIELDED CONTAI!ER 15.38 Outside Diameter 10.25" Inside Diameter k Test-s \\ \\ t Removable / es) N P t 24.2 " Overall Height Heavy Wire Mesh O s Tipping k_ Ch \\ Lugg- \\ \\__ Sealed s ( Q Void Space m THI-2 l FUE L-BEARING-fiATE RI AL BUCKET FOR 'HIELDED CONTAINER 1
l i C 4.5 D!A - 926.13 DI A --21.5 DIA -16 DIA 10.25 O! A-1 p m.___....___.. / ((((//j / / pictDc0 courAlten cannlca / -GHIE1DED CONTA16 (55 GAL DRUM) / / / =.=- ( z /////////////////> /**" * ' ' ' ' ' ' ' ' / ---~f. / ///ff ff f f ff / f f f2 /' / // // / / i / I elGuRE .s.2.7 l SHIPPING CmFIGURATIM WITH SHIELDED CNTAltER FOR FISSILE MATERIAL l i
r5 L SAFETY ANALYSIS REPORT FOR MODEL CNS 1-13C II PACKAGE TO 10 CFR 71 TYPE "B" PACKAGING P. REQUIREMENTS Revision I June 1988 Submitted By: EG&G IDAHO, INC. l 1 1955 FREMONT AVE. IDAHO FALLS, IDAHO 83415 p) a l'p
1-13 C II Revision I June 1988 l Change Sheet Remove Insert Cover Sheet Cover Sheet Page 1-6 Page 1-6 Pages 7-1 through 7-10 Pages 7-1 through 7-10 Page 8-3 Page 8-3 Page 8-9 Page 8-9 4 i
C ' ^ '. L s,e ~ n Revision 1 June 1988 p;c 5 e. Heat Dissipation 'There_ are no special devices used for -the ; transfer..or dissipation of heat.' The package maximum design capacity is 800-watts. Refer to Section 3.0 for the thermal evalu'ation of the 1-13C.II Package. 1, e Coolants l There are no coolants involved. o Protrusions There are no outer or inner protrusions. Lifting lugs are removed' prior to transport. e Shieldina-4f Cask walls provide a shield thickness of 5 inches lead and 1-1/4 -(' inch steel. Cask ends provide a minimum of 6 inches lead and 1 . inch steel. The contents will be limited such that the shielding provided will assure compliance with dose rate. limits as specified in 10CFR71. B. Fissile Material Containers ,a 1.- General Debris Container The general debris container configuration as described in Part j'7 A of Section 1.1 consists of a general debris container (loaded with either a fuel pin sample cell or debris container) loaded into a 2R container in a shoring cage. A shipping configuration q. 3 is shown in EG & G drawing TMI 1113 in Appendix 1.3. n, The following is a description of these components. 1-6 j
Revision 1 June 1988 7.0 OPERATING PROCEDURES This chapter describes.the ge'neral, procedures for loading and unloading-the Model 1-13C II Shipping Package. '7.1 Procedures'for'Loadina' Package l l 7.1.1 Loosen. and release ratchet binders securing. uppe: overpack to E lower overpack. 7.1.2 Remove upper overpack by attaching suitable hooks to' lif ting. . lugs. ' Care should be taken during this operation so that-the overpack is not damaged while setting it down. 7.1.? Determine if cask must be recoved from ' lower overpack in order to load. If so, attach two lif ting ears to cask walls and torque lifting ear. bolts to 200 ft.-lbs. (i 101. lubricated or dry). Cask may then be lifted vertically from lower overpack ( and carefully placed in position for loading. 7.1.4 Using proper radiological precautions, loosen vent plugs to - relieve potential internal cask pressure prior to loosening and removal of the 12: bolts which secure the cask lid to the cask body. 7.1.5 Remove the lid by attaching a suitable hook to the 1.id lifting lug. Care should be taken during this operation so that the lid gasket and 0-ring are not damaged. 7.1.6 Inspect the cask interior to ensure that there are no loose articles. 7.1.7 Inspect and clean lid gasket 0-ring, drain seal, vent seal and gasketed surfaces. Replace the drain seal and vent seal. l 7-1
_,e il[ Revision 1 June 1988- -Verify that replacement.of.the 0-ring and lid gasket have been performed within the required replacement schedule. (see step 8.2.4). In addition to these requirements replace; any gasket or seal if it shows signs of wear or deterioration. 7.1.8 Load'eask 7.1.8.1 Payload weight shall not exceed 3,000 pounds. When-loaded in a submerged fashion, both vent and drain I plugs should be removed. Vent and drain plugs should be reinstalled after cask cavity is drained. Torque plugs to 12 ft-lbs. ( l ft-lb.) QQ HQI QER TOROUE. When positioning the lid onto the cask while loading in a submerged fashion, the lid shall be shimmed:open to allow venting and. drainage from the area between the 0-ring and flat.11d gasket.- '7.1.8.2 Special Ootions for Loading Fissile Material For guidelines formulated for the detailed procedure for col'necting nuclear core assembly debris from the reactor vessel in the shielded container of 2R Vessel see section 7.1.8.2.1. For guidelines formulated for a detailed procedure of collecting fissile material or surface contaminated material from the reactor vessel by special buckets see section 7.1.8.2.2. 7.1.8.2.1 Shielded Container with 2R Vessel Ootion 7.1.8.2.1.1 Samole Collection a. Weigh the debris shielded container with debris bucket or fuel pin sample cell prior to loading with core assembly debris. (See Section 1.3.1.2). L 7-2
Revision 1 June 1988 b. Place an open debris shielded container on a platform with either the debris bucket or the fuel pin sample cell in the bottom of.the debris shielded container. Lower the container into the reactor vessel. 7.1.8.2.1.2 Samole Collection from the Reactor Vessel a. Samples will be collected from the reactor vessel. b. Samples will be individual chunks of i debris and/or small gravel / fines whose volume will not exceed the volume of the cavity of the debris bucket in the I debris shielded container. (See Section 1.3.1.2) c. Other samples will be short sections of fuel rod pins whose volume will not exceed the volume of the fuel pin sample cells. (See Section 1.3.1.2.) 7.1.8.2.1.3 Placement of Samples in Debris Shielded Container l Place the sample in the appropriate f debris bucket or fuci pin sample cell within the shielded container. I 7.1.8.2.1.4 Closure of Container Close the lid on the debris shielded container. 7-3 C.
4 Revision 1 June 1988 7.1.8.2.1.5 Drainina Container and Samole a. Raise the platform with the debris shielded container (s) above the surface of the water. b. Allow the debris shielded container (s) to drain and drip-dry until no water is discharged from the container (s). c. Tighten the lid locking bolt and jam nut on the container (s). 7.1.8.2.1.6 Placement of 1.oaded Debris Shielded Containers in 2R Vessels a. Heigh the loaded shielded debris container (s) after draining. b. After a debris shielded container is thoroughly drained and
- weighed, transfer the container to a 2R vessel.
Shore up the debris container in the 2R vessel as shown. (See Section 1.3.1.3.) 7.1.8.2.1.7 Close 2R vessel Der orescribed orocedures Loading Cask with 2R Vessels Verify that the total net weight of the
- amples to be placed in the shipping cask is less than 15.4 kg.
a. Place shoring for the first 2R vessel in the 1-13C II cask. (See Section 1.3.1.3.) 7-4
r Revision 1 June 1988 b. Transfer the first 2R vessel to the 1-13C II cask, being sure that vessel is aligned per shoring drawing. c. Place additional shoring over the first vessel and repeat the transfer and shoring procedure for the second and third vessels. 7.1.8.2.2 Shielded Debris Container Ootion 7.1.8.2.2.1 Samole Collection a. Obtain the shielded container (see section 1.3.1.5) with a 10.25" diameter bucket or 15" dian,eter bucket for the shielded container. Heign the shielded container and the 15" diameter bucket if it is to be used. The 10.25" diameter bucket w/ shielded container does not require weighing. b. Place the shielded container loaded l with the appropriate bucket into the reactor vessel. 7.1.8.2.2.2 Collection of Sample from the Reactor Vessel a. Samples will be collected from the reactor vessel. b. Samples will be individual chunks of debris and/or small gravel / fines l whose volume will not exceed the { volume of the cavity of the bucket. 7-5 l l i
Revision 1 June 1988 c. Weigh the sample to verify it contains no more than 60 Kg of fissile material. 7.1.8.2.2.3 Placement of Samoles in Shielded Container a. Place the sample in the appropriate bucket. Fissile material will be placed in the 10.25" diameter THI-2 fuel-bearing-material bucket,. (See Section 1.3.2.6.) 7.1.8.2.2.4 Place the lid on the container. 7.1.8.2.2.5 Raise the., container above the surface of the water. 7.1.8.2.2.6 Drainino Bucket and Samole a. Allow the container to drain until no water is discharged from the container. b. Install and tighten the lid bolts (4) on the container. 7.1.8.2.2.7-Placement of Loaded ' Shielded Containers in Shielded Container Carrier a. Transfer the shielded container to the shielded container carrier. b. Close shielded container carrier drum. 7-6 i
f ~~ Revision 1. June 1988 7.1.8.2.2.8 Loadina Cask with Shielded Container' Carriers ~ a. Place shoring for the. -shielded container carrier in the ~ 1-13C II cask. b. Transfer the shielded container carrier to the 1-13 II cask. 7.1.9 Remove the ' lid shims and secure the lid to. the cask body by torquing the 12 lid bolts to 270 ft-lbs. - 10% lubricated (360 ft-1bs. -10% dry). 7.1.10 Prepare the assembled package for shipment in accordance with the following. 7.1.10.1 Decontaminate all external surfaces of the cask. 7.1.10.2 Perform a - radiation and contamination survey of the cask to ' assure compliance with 10 CFR 71.47.& 71.8i. limits, respectively. 7.1.10.3 Perform a lid .s eal leak test in accordance with Section 8.1.3. 7.1.11 If cask has been removed from lower overpack for loading, use lifting ears to place it back in lower overpack on transport vehicle. Remove lifting ears. NOTE: UPPER OVERPACK HILL NOT FIT ON CASK TOP AND RATCHEf BINDERS CANNOT BE TIGHTENED IF LIFTING EARS ARE LEFT ON CASK. 7.1.12 Verify that package is oriented on transport vehicle per Figure j' 7.1.1-1. Verify that distance from cask centerline to transport vehicle tie-down lug is 76 inches. 7.1.13 Install the overpack, verifying that tiedown lugs are oriented to trailer tiedown assemblies and that ratchet binder lugs are aligned vertically. 7-7 i
~ (4 g 7,:. Retfision 1 June 1988-C. ,s ' U 7.1.14 ' Attach and hand tighten ratchet binders attaching upper.overpack to lower overpack. l. l 7.1.15 Inspect the package for proper labeling required :to meet applicable regulations. L 7.1.16 Secure package to transport vehicle using appropriate tiedowns. 7.2 Procedures for Unloadina the Packace l' 7.2.1- !!ove. transport vehicle to unloading site. 7.2.2 Perform a visual inspect!on of unopened package ' exterior. Record any significant observations. 7.2.3 Prior.'to' unloading the cask, verify if special instructions are required to safely open the package. 7.2.4 Repeat steps 7.1.1 to 7.1.3 above. 7.2.5 Loosen drain and vent' plugs six (6) turns to vent pressure generated by decay heat. d 7.2.6 Repeat steps 7.1.4 to 7.1.5. 7.2.7 Unload cask. 7.3 Preparation of Emoty Packages for TranspAr_t r The 1-13C II shipping package requires no special transport preparation. when empty. Standard. loading and unloading procedures outline above shall be followed. The requirements of 49 CFR 173.427 with respect to shipment of empty packages will be complied with. L 7-8 __ _ _ z ___ i
4 4 4 i i Revision 1 June 1988 l 7.4 Prccedures For Shioment of Packages Which Generate Combustibig_ Sun Procedures for preparing packages for shipment which radiolytically generate combustible gases are outlined below. These procedures are divided into two categories: a. combustible gas control by inerting, and b. combustible gas suppression. 7.4.1 Combustible Gas Control by Inertina a. Dewater the secondary container. The bulk of the free water is removed from the secondary container by displacing the water with nitrogen gas. b. Inert the secondary container (and, if necessary, the cask). The inerting operation is done at the dewatering station just before the cask is loaded. Inerting is performed if the hydrogen generated will be greater than 5*/. in any portion of the package. Inerting is intended to limit the oxygen concentration to less than 51. including any oxygen that is radiolytically generated. If a leak path can develop between the secondary container and the cask, the cask will also be inerted; (The inerting of the cask shall be performed according to a special procedure.) c. Sample the gas in the package (and cask, if inerted). d. Load the secondary container. 7-9
n. Revision 1 June 1988 . ( 7,4.2 Combustible Gas Suooression a. Dewater the secondary container. See paragraph 7.4.5.a. b. Install the combustible gas suppression system (e.g., a vapor pressure catalytic recombiner). c. Sample the gas in the secondary container and measure static pressure. This will assure that the combustible gas control method is working properly. d. Load the secondary container. L 7-10 .__________a
e in,.y y.: Revision l' June 1988 L. .F ,1p
- NOTE:
RELEASE OF PRESSURIZED R-12 IN CASK TO THE: > ATMOSPHERE WILL' CONTAMINATE TEST AREA. (13) Reconnect Freon R-12 source at vent port. (14)- Pressurize (area between gasket and 0-ring) to the established pressure from Figure 1. Record pressure. (15) Allow 10 minutes dwell time after pressurization of cask. ~ (16) Using leak detector check area'around contact surface-br'. ween lid and cask, bolt connection areas, vent port ' and test rig adaptor assembly. Record Results'. (17)
- If results of leak check are acceptable, proceed to
(( next step. If leakage rate in. excess of acceptance ( criteria is detected, disassemble cask and inspect for damage to seals and casks surfaces. Repeat. test as required. Record Results (18) Record Temperature e (19) Verify the following leak checks have been completed: (a) Vent and drain ports (as per operation (16) above). (b) 0-ring seal (as per operation (14) above). i (c) Flat gasket seal (as per operation (14) above). 8-9 =
p 1 i h' SAFETY ANALYSIS REPORT FOR MODEL l-13C II PACKAGING TO 10 CFR 71 TYPE "B" PACKAGING REQUIREMENTS REVI$10N 2 JANUARY.1989 Submitted By: EG&G IDAHO, INC. 1955 FREMONT AVE. IDAHO FALLS, IDAHO 83415 O I -mmm____m___m ___.-_..-m__.m. - _ -..-. _ _. _ _ _ - _. _ _ _ __--____m_.__.________m ._____m._-___- ._ __.._ __.__._._ _. _ _. _. -..__U
=m i, C' ./ aj, 1-13C II Revision 2 > J-January 1989 Change Sheet EssaQy_t Insert Cover Sheet Cover Sheet Table of Contents Table of. Contents 1.3. Appendix 1.3 Appendix (Papas 1-11.and 1-12) All Drawings of Section 1.3.1 Drawings: 1.3.1.1, Sheets 1 and 2 1.3.1.2, Sheets 1, 2 and 3 1.3.1.3 1.3.1 4 1.3.1.5, Sheets 1'and 2 1.3.1.6 l 1.3.1.7 I 1.3.1.8 Pages 7-7 through 7-11 Pages 7-7 through 7-13 1 .a 9 ______m______________ - _ _ - _ _ _ _ _. _ _ _ _ _. _ _ _ _ _ _ ____________._____._____._____________.__.____..________..__________________-____________j
7, l Revition 2-January 1989 L t TABLE OF CONTENTS , p. d Page s 1.- GENERAL INFORMATION...................... 1-1 1.1 Introduction..................... 1-1 1.2 Package Description.................
- 1. 3 1.2.1 Packaging..................
1-3 1.2.2 Operational Features............ 1-9 1.2.3 Contents of Packaging............ 1-9 1.3 Appendix....................... 1-11 2. STRUCTURAL EVALUATION.................... 2-1 2.1 -Structural Design.................. 2-1 2.1.1 Discussion................. 2-1 2.1.2 Design Crite *............... 2-4 2.2 Heights and Centers of Gravity............ 2-6 2.3 Mechanical Properties of Materials.......... 2-7 2.4 General Standards for all Packages.......... 2-il 2.4.1 Minimum Package Size............ 2-11 ( j' 2.4.2 Tamperproof Feature............. 2-11 V 2.4.3 Positive Closure.............. 2-11 2.4.4 Chemical and Galvanic Reactions....... 2-11 2.5 Lifting and Tiedown-Standards for All Packages.... 2-11 2.5.1 Lifting Devices............... 2-11 2.5.2 Tiedown Devices............... 2-51 2.6 Normal Conditions of Transport............ 2-66 2.6.1 Heat.................... 2-66 2.6.2 Cold.................... 2-77 '2.6.3 . Reduced External Pressure..........
- 2. 6. 4 -
Increased External Pressure......... 2-78 2.6.5 Vibration.................. 2-81 2.6.6 Hater Spray................. 2-81 g 2.6.7 Free Drop.................. 2-81 2.6.8 Corner Drop................. 2-91 2.6.9 Compression................. 2-91 2.6.10 Penetration................. 2-91 2.6.11 Conclusions................. 2-91 O 1
Revision'2 .lanuary'1989 TABLE OF CONTENTS (CONT'D) Ej 2.7 Hypothetical Accident Conditions...........- 2-92 2.7.1 Free Drop.................... 2-92 2.7.2 Puncture.................. 2-110 2.7.3 Thermal................... 2-112 2.7.4 Immersion - Fissile Material........ 2-116 2.7.5 Immersion - All Packages.......... 2-116 2.7.6 Summary of Damage............... 2-116 2.8 Special Form..................... 2-117 2.9 Fuel Rods...................... 2-117 2.10 Structural Evaluation Appendices........... 2-117 2.11 Appendix - Engineering Drop Test for 1-13C II Shipping Package.................. 2-169 2.12 Attachment...................... 2-213 3. THERMAL EVALUATION..................... 3-1 3.1 Discussion...................... 3-1 3.2 Summary of Thermal Properties of Materials...... 3-5 3.3 Technical Speci,fications of Components........ 3-8 3.4 Thermal Evaluation for Normal Conditions of Transport..................... 3-8 ~
- 3. 4.1 -
Thermal Model................ 3-8 fm 3.4.2 Maximum Temperatures............ 3-20 l\\ >) - 3.4.3 Minimum Temperatures............ 3-31 3.4.4 Maximum Internal Pressures......... 3-31 3.4.5 Maximum Thermal Stresses.......... 3-36 3.4.6 Evaluation of Package Performance for Wormal Conditions of Transport.......... 3-36 3.5 Hypothetical Accident Thermal Evaluation....... 3-37 3.5.1 Thermal Model................ 3-37 3.5.2 Package Conditions and Environment..... 3-37 3.5.3 Package Temperatures............ 3-38 l 3.5.4 Maximum Internal Pressures......... 3-56 3.5.5 Maximum Thermal Stresses.......... 3-56 3.5.6 Evaluation of Package Performance for Hypothetical Accident Thermal Conditions. 3-66 3.6 Appendix....................... 3-67 l l 4. CONTAINMENT......................... 4-1 4.1 Contaiment Boundary................. 4-1 4.1.1 Containment Vessel............. 4-1 4.1.2 Containment Penetration........... 4-1 4.1.3 Helds and Seals............... 4-2 l /' 4.1.4 C1osure................... 4-2 l ( l v. ii I _ -- - a
Revision 2 j January 1989. TABLE OF CONTENTS (CONT'D) . py l ) 4.2 Requirements for Normal Conditions of Transport.... 4-3 v/ 4.2.1 Containment of Radioactive Material..... 4-3 4.2.2 Pressurization of Containment Vessel.... 4-3 4.2.3 Containment Criterion............. 4-5 4.3 Containment Requirements for Hypothetical Accident Conditions....................... 4-5 4.3.1 Fission Gas Products............ 4-5 4.3.2 Containment of Radioactive Material..... 4-5 4.3.3 Containment Criterion............ 4 4.4 Appendix....................... 4-15 ^' 5.0 SHIELDING EVALUATION.................... 5-1 g 5.1 Discussion and Results................... 5-1 I 5.2 Source Specification................. 5-2 5.3 Model Specifi cation................. 5-3 5.4 Shielding Evaluation................. 5-13 5.5 Appendix - References................ 5-18 6.0 . CRITICALITY EVALUATION................... 6-1 6 6.1 Discussion and Results................ 6-1 l i - '( 6.2 Package Fuel Loading................. 6-1 N 6.3 . Model Speci fi cati on................. 6-1 6.4 Criticality Calculation............... 6-1 6.5 Critical 8enchmark Experiments............ 6-7 6.6 Appendix........................ 6-8 7.0 OPERATING PROCEDURES.................... 7-1 1 7.1 Procedures for Loading Package............ 7-1 ] 7.2 Procedures for Unioading Package........... 7-9 7.3 Preparation of Empty Package for Transport...... 7-10 7.4 Procedure for Shipment of Packages Which i Generate Combustible Gases............. 7-11 l 8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM.......... 8-1 8.1 Acceptance Test................... B-1 l 8.1.1 Visual Inspection.............. 8-1 8.1.2 Structural and Pressure Tests........ 8-1 8.1.3 Leak Tests................. 8-1 8.1.4 Component Tests............... 8-2 8.1.5 Tests for Shielding Integrity........ 8-2 8.1.6 Thermal Acceptance Tests........... 8-2 e I( iii w-
Revision 2. January 1989' TABLE OF CONTENTS (CONT'D) 8.2 Maintenance Program................. 8-2' 8.2.1 Structural and Pressure Tests........ 8-2 8.2.2 Leak Tests................. 8-2 8.2.3 Subsystem Maintenance............. 8-2 8.2.4 Valves and Gaskets on Containment Vessel... 8-3 8.2.5 Shielding.................. 8-3 8.2.6 Thermal................... 8-3 8.2.7 Appendix - Leak Test Procedures....... 8-3 1' \\ 4 \\ iv u r .m
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Revision 2 January 1989 )/- 1.3 APPENDIX .LJ ' 1.3.1 Drawinas 1.3.1.1-CNS Drawing No. E-1436 - 111, Rev. D., "CNS 1-13C II Shipping Cask" '1.3.1.2 GPU Nuclear Drawing No. 2E-3200-1040, Rev. O, " General Debris Shielded Container - 1 Assy & Fuel Pin Sample. Shielded Container - 2 Assy". 1.3.1.3 EG&G Drawing No. THI - 1113. "THI II Shoring Shielded Container in 2R Container and 2R Container in Shipping Cask General Arrangement Proposal". 3.3.1.4 EG&G Drawing 422790, Rev , "TMI-2, Shielded Container Carrier Assembly". b) f 1.3.1.5 EG&G Drawing 422795 (2 pgs.), "THI-2 Shielded Container for CNS 1-13C II Cask Assembly". 1.3.1.6 EGr.,G Drawing No. 423627, "THI-2 Fuel-Bearing-Haterial Bucket for Shielded Container". 1.3.1.7 EG&G Drawing No. 423626, "TMI-2 Bucket for Shielded Container". 1.3.1.8 EG&G Drawing No. 423747, "THI-2 Bucket Base Assembly". 1 1-11
".ar ,i Revision 2 January 1989 i 1.3.2 Sketches Q; 1.3.2.1 Model 1-13C II Package 1.3.2.2 Exploded View Secondary Containers for Use with 1-13C II Cask 1.3.2.3 THI-2 Shielded Container Carrier. 1.3.2.4 Shielded Container for 1-13 II Cask 1.3.2.5 TMI-2 Bucket for Shielded Container i 1.3.2.6 TMI-2 Fuel-Bearing-Material Bucket for Shielded Container 1.3.2.7~ Shipping Configuration Hith, Shielded Container for Fisslie Material. 9 l l l 6 1-12 w_________ _m_.-____m___mm_m_____.__.. m_.______.
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Revision 2 January 1989 7.1.8.2.2.8 Leadina Cask with Shielded Container O Carriers a. Place shoring for the. shielded. container carrier in-the 1-13C II-cask. b. Transfer-the shielded container carrier to the 1-13 II' cask. 7.1.9 Remove the lid shims and secure the lid to the cask body by. torquing the 12 lid bolts to 270 ft-lbs. i 10%. lubricated (360 ft-1bs. i 101 dry). 7.1.10 Prepare the assembled package for shipment in accordance with the following. 7.1.10.1 Decontaminate all external surfaces of the cask. 7.1.10.2 Perform a radiation and contamination survey of the [ cask to assure compliance with 10 CFR 71.47 & 71.87 ( limits, respectively. The measured radiation level should not exceed the following: 7.1.10.2.1 200 millirem / hour on the excessible external surface of the cask; .1 7.1.10.2.2 10 millirem / hour at any point two (2) ~ meters from.the vertical plane projected from the outer edges of the vehicle or conveyance; 7.1.10.2.3 2 millit im/ hour in any normally occupied positions of the vehicle. I k] V l 7-7 I' 1
Revisich 2 January.1989 7.1.10.2.4 The measured radioactive level of
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-non-fixed contamination should not b 2 exceed 22 dpm/cm for beta-gamma-emitting radionuclides; and 2.2 2 dpm/cm for all other alpha emitting radionuclides. 7.1.10.3 Perform a lid seal leah test in accordance with Section 8.1.3. 7.1.11 If cask has' been removed from lower overpack for loading, lifting ears to place it back in lower overpack on transport vehicle. Remove lifting ears. NOTE: UPPER OVERPACK HILL NOT FIT ON CASK TOP AND RATCHET BINDERS CANNOT BE TIGHTENED IF LIFTING EARS ARE LEFT ON CASK. ['s 7.1.12 Verify that package is oriented on transport vehicle per Figure \\ 7.1.1-1. Verify that distance from cask centerline to transport vehicle tie-down lug is 76 inches. 7.1.13 Install the overpack, verifying that tiedown lugs are oriented to trailer tiedown assemblies and that ratchet binder lugs are aligned vertically. 7.1.14 Attach and hand tighten ratchet binders attaching upper overpack to lower overpack. Torque the ratchet binders to 100 ft-lbs i 10%. 7.1.15 Inspect the package for proper labeling required to meet l appitcable regulations. (As per Step 7.3.5) 7.1.16 Secure package to transport vehicle using appropriate tiedowns. D
l* 3 Revision 2 January 1989 7.2. Procedures for Unloadina the Packaae l ( NOTE: - PRIOR TO UNLOADING CASK, THE FOLLOWING SEQUENCE OF EVENTS FOR UNLOADING A PACKAGE CONTAINING QUANTITIES OF RADI0 ACTIVE MATERIAL IN EXCESS OF TYPE "A" QUANTITIES SPECIFIED IN 10 CFR 20.205(b) SHALL BE RECEIVED, MONITORED AND HANDLED BY THE l LICENSEE RECEIVING THE PACKAGE IN ACCORDANCE WITH THE. L REQUIREMENTS OF 10 CFR 20.205 INDICATED BELOH.. 7.2.1 Prior to opening cask, verify the following: 7.2.1.1 The removable radioactive contamination on the cask 2 external surface is less than 22 dpm/cm, Alpha and 2 220 dpm/cm, Beta-Gamma. 7.2.1.2 Determine the form and quantity of-radioactive material of the cask contents. The limits are specified in the table in 10 CFR 20.205(b)(1). 7.2.1.3 The radiation levels are as specified in Step 7.1.10.2. 7.2.2 Move transport vehicle to unloading site. 7.2.3 Perform a visual inspection of unopened package exterior. Record any significant observations. 7.2.4 Repeat steps 7.1.1 to 7.1.3 above. 7.2.5 Loosen drain and vent plugs six (6) turns to vent pressure generated by decay heat. 7.2.6 Repeat steps 7.1.4 to 7.1.5. 7.2.7 Unload cask.
Revision 2 January 1989 7.3 Preparation of Emotv Packaaes for Transoort n The 1-13C II shipping package requires no special transport preparation when empty. Standard loading and unloading procedures outlined above shall be followed. The requirements of 49 CFR 173.427 with respect to shipment of empty packages will be complied with. 7.3.1 Verify that the radiation level at any, point on the external surface does not exceed 0.5 millirem / hour. 7.3.2 The removable radioactive surface contamination on the external 2 surface does not exceed 22 dpm/cm Beta-Gamma emitting 2 radionuclides, and 2.2 dpm/cm all other Alpha emitting radionuclides. 7.3.3 The cask should not contain more than 15 grams of uranium-235. 7.3.4 The removable radioactive surface contamination on the internal 2 p surface (cavity) does not exceed 2200 dpm/cm Beta-Gamma 2 emittir.g radionuclides; and 220 dpm/cm all other Alpha emitting radionuclides. 7.3.5 Cask labeling should meet DOT specifications 49 CFR 172.500. The label " EMPTY" should be affixed to the cask. 7.3.6 The lid should be properly closed to prevent any leakage. 7.3.7 The external cask lifting lugs should be removed for transport. 7.3.8 The impact limiters should be properly installed. 7.3.9 Visual inspection of all external cask surfaces, impact limiters and trailer shall be performed and any defects shall be repaired. t (j \\ 7-10
ny. Revisien 2 January 1989 N' 7.4 Procedures For Shinment of Packaaes Which Generate Combustible Gases Procedures for preparing packages for shipment which radiolytically generate combustible gases are outlined below. These procedures are divided into two categories: a. combustible gas control by inerting, and b. combustible gas suppression. 7.4.1 Combustible Gas Control by Inertina a. Dewater the secondary container. The bulk of the free water is removed from the secondary container by displacing the water with nitrogen gas. b. Inert the secondary container (and, if necessary, the A cask). - The inerting operation is done at the dewatering k station just before the cask is loaded. Inerting is performed if the hydrogen generated will be greater than 5% l in any portion of the package. Inerting is intended to l. limit the oxygen concentration to less than 5% including any oxygen that is radiolytically generated. If a leak path can develop between the secondary container and the l cask, the cask will also be inerted. (The inerting of the cask shall be performed according to a special procedure.) ~ c. Sample the gas in the package (and cask, if inerted). d. Load the secondary container. e ____m____m_____.___.___._m-._.____-.-_
L ] p L Revisicn 2 [ January 1989 7.4.2 Comb! stible Gas Suppression
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- a. Dewater the secondary container. See paragraph 7.4.5.a. I:l' b. Install the combustible gas suppression system (e.g.,' a-vapor pressure catalytic recombiner). \\;, c. Sample the rjas in the secondary container and measure static pressure. This will assure that the combustible gas control mathod is working properly. I 1 d.- Load the secondary container. O m -______.___.___m._._______.______.______.___a_
Revision 2. FIGURE 7.1.1-1 ORIENTATION OF 1-13C II PACKAGE ON TRANSPORTER y TOP OVERPACK TIE-DOWN LUGS b ALIGNED WITH TRAILER TIE-DOWN b l \\ m ~ l- \\ N._ } ~' [ f / N \\ f \\ j Direction i Trailer Width 96, ( of Travel 3 u-y .+ l i s / / \\ r 4 / ) 76" < = l 1 Cask Centerline to tie-down lug 76" Trauer rie-Dain .b l l (3 7-13 -s. e}}