ML20065J695
| ML20065J695 | |
| Person / Time | |
|---|---|
| Site: | 05000072 |
| Issue date: | 04/11/1994 |
| From: | Gehmlich D, Hardy B UTAH, UNIV. OF, SALT LAKE CITY, UT |
| To: | |
| Shared Package | |
| ML20065J689 | List: |
| References | |
| NUDOCS 9404180380 | |
| Download: ML20065J695 (152) | |
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N A Summary Of The Decommissioning Process a of The University Of Utah AGN-201M Reactor No.107 Final Report License No. R-25 Docket No. 50-72 Prepared By: - C. Ross Schmidtlein ' Darrell S. Hall . John S. Bennion - Enrique C. Estrada Henry F. Moeller q David M. Slaughter, Ph.D. - Gary M. Sandquist, Ph.D. April 11,1994 j University of Utah Nuclear Engineer Laboratory . Salt Lake City, Utah 84112 ln tm on Safety cer. k 1
. Dietrich K. Gehnilich Reactor Administrator
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9404180380'940413 DR ADOCK.05000072 PDR b --
Table of Contents Decommissioning Activities ................. .......... ..................... .. ........... .. I Results And Major Milestones .. .................. ..................................... 2 Supporting Documentation ................................................................ 4 Summary Of Decommissioning Activities ................................ . ............... 5 Appendices ........ ..... ............... .. ... ..... .. ... ................................... 6 Appendix A: AGN Parts List And Location Appendix B: Completed Disassembly Procedures Completed Form NEL-103: Dismantling Plan For UUAGN Reactor Completed Form NEL-104: AGN-201M Defueling Procedure Completed Form NEL-105: Procedure For Removing AGN Control Rods Completed Form NEL-106: Procedure For Removing Neutron Source Appendix C: Parts Transferred To Other Reactor Licenses Appendix D: Parts Disposed Of As Radiological Waste Appendix E: Parts Released As Unrestricted Waste Appendix F: Fuel ShipmentInformation l Appendix G: Survey Results Appendix H: Survey Instrument And Operation Data f i 1
A Summary of the Decommissioning Process of the University Of Utah AGN 20lM Reactor No.107 Final Report The final report provides a brief summary of the activities that assured the reactor was decommissioned in a safe manner complying with all NRC regulations, stipulations, and in accordance with the NRC approved decommissioning plan, " Decommissioning Plan, University Of Utah, AGN-20lM Reactor No.107, License No. R-25, Docket No. 50 72". This document contdnr. the survey results, the final destination records for the reactor parts, fuel transport records and the completed decommissioning procedures as carried out. Decommissioning Activities We decontaminated the equipment, structures and portions of the facility and site containing radioactive contaminates to a level that permits the property associated with University of Utah's AGN-20lM Nuclear reactor to be released for unrestricted use. A brief description of this plan is presented below. For a more detailed description of the decommissioning plan, see the NRC approved plan. The plan was implemented as follows:
- 1) Surveyed and disposed of the cement shielding blocks.
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- 2) Conducted defueling operations.
- 3) Surveyed all components of the reactor core, including the fuel.
- 4) Surveyed and disposed of the shielding water.
- 5) Created an NRC approved deconunissioning plan for the AGN-20lM.
- 6) Performed a detailed survey of the decommissioning area.
- 7) Transferred the fuel to the DOE.
l l 8) Disassembled the AGN.
- 9) Surveyed the remaining parts of the AGN.
l 10) Disposed of and decontaminated the reactor parts.
- 11) Scheduled a survey with the NRC to remove all decontaminated parts.
- 12) Prepared Final report on the decommissioning for the NRC.
When the NRC completes the final survey to confirm our results, the license will be surrendered to them. In the case of the University's AGN facility, the room in which the reactor is 1 ) I
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located is under license of the University's TRIGA reactor. In addition, some useful components from the AGN were transferred to the University of Utah TRIGA license (Lic. No. R-126; Doc. No. 50-284) or the Idaho State University reactor license (Lic. No. R-110; Doc. No. 50-284) rather than being disposed. Results And Major Milestones , The decommissioning process for the AGN 20lM closely followed the planned decommissioning activities. However small changes were made as the situation warranted to insure regulatory compliance and radiological safety.
. The preliminary steps for the decommissioning of the AGN-201M reactor began with the ,
survey and disposal of the cement shielding blocks surrounding the reactor. These blocks were found to be non-contaminated and were removed and disposed of on March 25, 1988.
. Defueling operations began and the reactor was defueled on August 18,1989. During the defueling steps, the Ra-Be neutron source and the fuel were n moved and surveyed in -
detail. At that time, all components in the n: actor core were removed and surveyed. The fuel and source were placed into safe storage waiting transfer to the DOE.
. The initial survey of the reactor core components began on September 9,1989. These surveys showed very little activity on any of the core components.
. On January 9,1989, the AGN-20lM's shielding water was analyzed for activity. No activity above background was detected and the water was disposed of by public sewer.
. On July 17,1990, the " Decommissioning Plan, University Of Utah, AGN-20lM Reactor No.107, License No. R-25, Docket No. 50-72", was completed. This plan has received NRC approval for decommissioning, and it contains in detail the steps and procedures that were used to decommission the AGN-201M reactor.
. The reactor fuel was shipped to Martin Marietta Energy Systems, at the Oak Ridge National Laboratory, for the DOE on February 5,1991.
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A considerable delay existed between the completion of the decommissioning plan and the . actual decommissioning of the reactor. This delay was due,in part, to the interest of the faculty - from University of North Texas State in acquiring the reactor. If the reactor was to be transferred, the decommissioning process would be changed to accommodate the reassembling of the reactor at the new site while maintaining regulatory and safety requirements. North Texas State ultimately decided against acquiring the reactor and decommissioning work following the current plan began again. During the delay instmmentation and personnel changed so it became necessary to duplicate some of the steps performed during defueling operations such as the decommissioning site and core component surveys to assure consistent and reproducible results.
. Another site survey was perfonned to insure as low as possible a background for component surveys. This survey was performed on March 25,1993. ,
. The next step in the decommissioning procedures was the disassembly and survey of the -
reactor. On April 6-8,1993, the reactor was disassembled and the interior components were surveyed. Also, all unsealed reactor components that were removed and surveyed during defueling operations were re-surveyed. Several options existed for the disposal of the AGN reactor components. These were; disposal as low level radioactive waste, disposal as non-radioactive waste to public land fill, and transfer to other reactor licenses i.e., the University of Utah's TRIGA license. The decision varied based on several factors which included: cost of disposal, value of the part, and contamination on the part. Parts from the core can had alpha contamination from contact with the fuel. Most of these parts were of no value outside the AGN so these parts were disposed of as low level radioactive
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waste. The graphite reflector was of value for future experiments conducted in the TRIGA reactor j program, and was therefore transferred to the University of Utah TRIGA reactor license. Outside l of the core can the main graphite reflector and lead shield were also deemed valuable and were 'l moved to the TRIGA reactor license. The control console and two drives were transferred to the ISU reactor license, i The main reactor tank, thermal column, and the access port covers were non-contaminated and will be disposed of in a public land fill pending the NRC's final survey results. Other waste being disposed of as low level radioactive waste are the paint chips from the thermal column, the wood plugs from the access ports, and the trash generated during decommissioning. These pieces 3
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were considered to be constructed from materials that did not allow accurate surveys with a high degree of confidence to be performed.
+ After the survey of the reactor components was completed the NRC was contacted to inform them of the progress. The confirmation survey of the parts from the reactor that are to be disposed of in a public land fill will be scheduled and performed by a contractor employed by the NRC. !
The NRC final inspection is the last requirement in the decommissioning process. When the NRC has performed a confirmation survey, the remaining reactor parts will be unrestrictedly released. Supporting Documentation i The attached appendixes contain the documentation which show our compliance with NRC regulations and the decommissioning plan. In Appendix A, the parts of the AGN-201M are numbered and described along with drawings. The intent is to clearly identify where the various parts are located in the reactor and establish an effective strategy to assure accurate record keeping for surveyed reactor parts. q Appendix B contains the disassembly procedures used during the decommissioning of the reactor. The completed procedure sheets documented the process and demonstrated compliance with the decommissioning plan. The Appendices C, D, and E together document the final disposition of all non fuel AGN-201M parts. Here each part or related group of parts are photographed and have listed their part numbers and fimd disposition. Appendix C's parts are transferred to the licenses of other nuclear reactor facilities. Appendix D's parts are disposed of as low level radioactive waste. Finally - Appendix E's parts are released for unrestricted disposal pending NRC approval. Fuel shipment information is located in Appendix F. The final disposition of the fuel is - documented by checklists, approval and transfer forms, and a list of the non-University of Utah individuals involved in the fuel shipping process. 4
Appendix G contains the results of the radiological surveys conducted during the decommissioning of the AGN-20lM reactor. This section contains surveys for: Facility, Concrete blocks surrounding the reactor, i Water shield, l Thermal column,
. Start up source and fuel, i Core components survey, and Parts to be unrestrictedly released The final appendix, Appendix 11, contains a list of the detectors used in the decommissioning of the AGN-20lM reactor. Listed are the Type, Make, Serial Number, Background, Efficiencies, Calibration Date, and Use of these detectors. Listing this information- ,
allows further documentation of the process involved in the decommissioning of the reactor. Summary of Decontaminating Activities Due to the low power level and design of the AGN-201M reactor, the activation of-materials was almost nonexistent. Parts outside the core can were not activated or contaminated. For components that are located inside the core can, alpha contamination measured on the order of-nano-curies was found on the surfaces that were directly in contact with the fuel. This was the - only radiological hazard found in the reactor. The exterior components which indicated no contamination will be released to general disposal after direct surveys from the NRC to conf' m n our results. In the process of decommissioning the AGN-201M reactor, certain items (wood, paint chips) due to their material characteristics and form, had to be considered low level waste even when results from radiation and swipe surveys indicated that these items were not activated or contaminated. Properly transferring selected components of the AGN reactor from its license to our TRIGA reactor license or other facilities allowed extending the usefulness of those components. i 1
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APPENDICES: 1 r I 9
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i l Annendix A: AGN-201M Parts List And Location The following is a list of the numbered parts of the AGN-20lM reactor. The i numbering system was used to facilitate the surveys of the reactors pans. This list gives i the part number used in the surveys, a description of the parts, and the parts location in the 'j reactor. Also for greater clarity two figures are included with the pan numbers and the pans location in the reactor. 1 Part # Description Location 1 Safety Rod #2 (Empty) Core Can 2 Course and Fine Control Rod Thimbles Core Can 3 "O" Ring Core Can Top Plate Core Can 4 Paint Chips from Thermal Column Thermal Column ' 5 Safety Rod #2 Parts Core Can 6 Core Can Assembly Bolts and Spring Core Can 7 Assembly Bolts And Washers (Core Can) Core Can -l 8 Core Support Rod Core Can 9 Quantity-2 Safety Rod Thimbles Core Can 10 Safety #1 with Parts Core Can 11 Course Control with Parts Core Can l 12 Fine Control Rod with Parts Core Can 13 Core Support Core Can 14 Core Can Top Plate Core Can 15 Core Can Bottom Plate Core Can 16 Polyethylene Disk Core Can 17 Graphite Reflector for Interior Core Can Core Can 18 Aluminum Core Can Core Can 19 Graphite Reflector Plate Core Can 20 Graphite Reflector Plate Core Can 21 Graphite Reflector (Bottom Interior Core Can) Core Can 22 Internal Themial Column Thennal Column 23 External Thermal Column Themial Column 24 Top Thermal Column Cover Plate Thermal Column 25 Bottom Thermal Column Cover Plate Thermal Column 26 Socket and Wrench Exterior to Core 27 Glory Hole / Port Covers Assembly with Covers Glory Hole / Access Port 28 Rod Drive Below Core Can 29 Rod Drive Below Core Can 30 Rod Drive Below Core Can 31 Rod Drive Below Core Can 32 Wood Plug in Access Pon Access Pon 33 Wood Plug in Access Pon Access Pon 34 Wood Plug in Access Pon Access Pon 35 Wood Plug in Access Pon Access Port 36 Wood Plug in Access Port Access Port 37 Wood Plug in Access Port Access Port 38 Wood Plug in Access Pon Access Pon Al
l 39 Wood Plug in Access Pon Access Pon 40 Wood Plug in Access Port Access Pon 41 Wood Plug in Access Pon Access Pon 42 Lead Plug in Access Pon Access 7on 43 Lead Plug in Access Port Access Port 44 Lead Plug in Access Pon Access Pon ' 45 Lead Plug in Access Port Access Port j 46 Lead Plug in Access Port Access Port l 47 Lead Plug in Access Port Access Port l 48 Lead Plug in Access Port Access Port i 49 Lead Plug in Access Port Access Pon 50 Lead Plug in Access Port Access Pon 51 Lead Plug in Access Pon Access Pon 52 Lead Plug in Access Pon Access Pon ) 53 Lead Plug in Access Pon Access Port l 54 Lead Plug in Access Port Access Port i 55 Lead Plug in Access Port Access Pon 56 Lead Plugin Access Port Access Port 57 Lead Plug in Access Pon Access Port 58 Aluminum Fuse Support Core Can 59 Alignment Screws Below Core Can 60 Polyethylene Rod Glory Hole 61 Graphite Plug in Access Pon Access Port 62 Graphite Plug in Access Port Access Port 63 Graphite Plug in Access Port Access Port 64 Graphite Plug in Access Port Access Port 65 Cadmium Plug Glory Hole 66 Graphite Plug in Access Pon Access Port _ 67 Graphite Flug in Access Pon Access Port 68 Graphite Plug in Access Port Access Port 69 Graphite Plug in Access Port Access Port 70 Aluminum Access Port Sleeve Access Port 71 Aluminum Access Port Sleeve Access Pon 72 Aluminum Access Port Sleeve Access Pon 73 Aluminum Access Port Sleeve Access Port 74 Graphite Reflector Column Surrounding Core Can 75 Bottom Lead Shield Ring Below Core Can 76 Bottom Lead Shield Ring w/ Access Ports Surrounding Core Can 77 Top Lead Shield Ring w/ Access Ports Surrounding Core Can 78 Top Lead Shield Ring Surrounding Core Can 79 . Bottom Lead Shield Plate Surrounding Core Can 80 Fission Gas Canister Exterior to Reactor 81 Wood Plug in Access Port Access Port 82 Wood Plug in Access Pon Access Port 83 Associated Core Assembly Bolts Core Can 84 Control Rod Support Plate .Below Core Can 85 Cadmium Disks Glorv Hole 86 Main Reactor Tank Main Reactor Tank 87 Reactor Console Exterior to Reactor
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Annendix B: = Comnleted Disassembly Procedures i The following dissassembly forms are listed in this appendix. Form: - . Status: Form NEL-103 Completed Form NEL-104 - No Completed Form Exists Form NEL-105 Completed with additional comments added Form NEL-106 Completed l 1 A
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Form NEL-103 RSC Approval: 5/25/88 Dismantling Plan for the University of Utah AGN 201 Reactor I. Introduction The Dismantling Plan for the University of Utah AGN-201 Reactor gives the general procedures to be followed for disassembly of the reactor. These procedures give more specific details regarding the preparation needed prior to disassembly and the actual disassembly steps themselves. NOTE: Check the items in the appropriate place as each step is accomplished. Maintain one master copy for reference. II. Preoaration Prior to Disassembly GO 3/15/51 1. Radiation Protection
- a. He following instruments will be checked for proper operation, then placed in the reactor room for use:
DU 3/ 2 5~l'# 1) Continuous air monitor or high volume air sampler. Ud i/25/93 2) Neutron survey meter (sphid "'C Neutron survey p meter). AW 4 - e r .5 e e w . o 77 GC J/2r/91 3) Beta-gamma dose rate survey meter (Cutie Pie or Radcctor), f EJ cf) 7nr/41 4) Contamination survey meter (thin window Geiger counter). ootct A . 2 > . % a
- b. He following supplies will be collected and placed in the reactor room for use -
as needed. UU 3/2T/9 1) Filters for air sampling. u") J/af/or 2) Smearing materials for wipe tests. c/3 vtr/+1 3) Containers for air samples and wipe test smears. ut> #A 4) Shielded storige container for storing the Ra Be startup source. c/> 3/ t r/ 5) Coveralls, bb coats, gloves, and shoe covers.
- 6) Radi.,acuve waste containers.
u @O #4T n /v1 7) Cadmium foil for core can insert. u!> Jr- @ 8) Respiratory protection equipment. l 00 3/2W43 2. Work Area and Tools j y) 3/z rAI a. Survey reactor room area in preparation for proposed activities.]M
@ J/t rA s b. Relocate equipment as necessary to maximize working area room.
m 3 / t r/o c. Collect the following tools and place in reactor room: uo 3/ z rAl 1) Hand Tools (socket and Allen wrenche) requirr d for disassembly.
@ hA 2) Handling tool for removing the Ra-Bo source.
u') " t/U 3) Lifting lugs and rigging for thermal column, core tank, and upper graphite reflector. W NA 4) Cart for transporting the core can to the designated storage area. c/o J/2 % r d. He following items will also be placed in the reactor room: u2 .7/2v/9? 1) Plastic bags for packing components. C4 3/ ara 1 2) Labels for dismantled components. cn 3 h r/ M 3) Camera with flash and film for photographically documenting the procedure at key stages. III. Detailed Disassembly Pmeedures NUE: _ The assembly pan numbers are correlated with the part listing on drawing number E-2-000100. (A) 1/1f/M 1. He Health Physicist will make a pre-disassembly radiological survey. . He will also initiate special access procedur personnel and equipment monitoring procedures and other procedures needed u keep radiation exposure as low as reasonably achievable. An operational check will be made of radiation rnonitoring 6, equipment present. If all equipment responds properly, the operation will proceed. m - 2. The Reactor Supervisor will brief the disassembly group on each step prior to its accomplishment, with clarification made,if necessary, of the tasks to be performed. QC MA 3. Insure that the temporary cadmium rod is in the glory hole and well fixed. l I B2 ] i
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Form NEL-103 RSC Approval: 5/25/88 NM 4. Remove bottom cover plate (2-000169). The gasket (2-000593) should come off with the cover. Bag the cover plate thumb screws (H-1007-10) and label. (fd hN 5. Insum that the control and safety rods have indeed been removed earlier, as declared. Label rods and store in approved fuel storage locations. Safe Rod Assembly: 1-000550 I Safe Rod Assembly 2-000550 II Coarse Control Rod Assembly 2-000550 III Fine Control Rod Assembly 2-000550 IV C/D M 6. Remove the three dash pots (2-000510), label and store for future shipment. (p AA 7. Remove the four control rod drive mechanisms. l
\ a. Console power off (neutron detection channels 1,2, & 3 remain on).
g) \ b. Disconnect rod drive power plugs. Identify and label each. 1
\ c. Remove (2 each) jam nuts (1/4-28) from the tie bolts and carefully lower
\ each rod drive frame assembly until free. Identify and label each frame Bag thejam nuts and label.
(/U 40 go 4// A 8. 9. Insert cadmium in the control and safety rod holes in the core can. i Remove the top cover plate (2-000226). The gasket (2-000591) should come off with the cover. Bag the eight cover plate bolts (H-1069-12) and label. C/O N/l 10. Dram the thermal column.
\ a. Obtain permission from the Health Physicist to drain thermal column water to sewer (a water sample will have been previously taken and analyzed for UV radioactivity as a basis for release of the water).
- b. Pump water to sewer until thermal column is as dry as possible.
NGTE: The entries for health physics recortis will be made in the Waste Log, i including: date/ time; estimated water volume dumped; gross sample results 3 D in pCi/ml, % of applicable mpc, estimated activity dumped. 1 4/M 3 11. Remove the thermal column (2-000139): NOTE: Thermal column could weigh 2,000 to 2,400 pounds. QO Nh/ a. Unbolt thermal column from reactor tank (16 each 3/4 inch bolts). Cy> WUN b. Attach lifting slingrd dy. ammm io crane and thermal column. j vp WOu c. Lift thermal column from well (the dynamometer will indicate the weight of the l lead-lined thermal column). Ibs. QO M/h 3 d. Remove thermal column from reactor and move to an appropriate space on the floor. Set thermal column on &&t ~per. /% A., C M N /7 c. label thermal column. Bag the 16 each h4 inch hold-down bolts and label. qs A< A 12. Remove the Ra-Be neutron source (H-3018) from the graphite reDector. Leak test the source and place it in the storage container. (f) /VA 13. Conduct a core survey. Since the core tank will not be opened at this time, an off gas sample will not be taken. A direct radiation survey and smear survey of the core tank top will be made. (f) M 14. Remove cadmium rod from glory hole (opemtor monitor neutron detector channels 1 through 3, H.P. representative monitor portable neutron survey meter response). Only a slight increase in reading may be noted. (Log any reading change.) BEFORE AFTER CRM: LOG: LINEAR: CM M 15. Remove glory hole tube.
\ a. Remove glory hole Dange (2-000419) (2 each) by removing (4 each) socket HD machine screws,1/4-20 X 1/2 (H-1023-8).
(fO \ b. Remove glory hole Dange "0" ring (H-4009) (2 each).
\ c. Remove glory hole tube (2-000422). Extreme care should be taken when N
removing this tube. It should not be bent (straight pull) and if binding is excessive, it may be necessary to lift the core tank slightly to relieve the bind. 1 i B3 1
Form NEL-103 RSC Approvci: 5/25/88 COMMEffrS: NOTE: ne Health Physicist will monitor very closely the removal of the core can. All radiation and criticality monitors will be checked for proper operation just prior to the removal of the core, and surveys of radiation levels from the core can will be made continuousiv during removal. QC M 16. Core Can Removal (2-000114):
\ a. Make a refemce mark on the core can and graphite reflector for reassembly @) \\ orientation.
- b. Attach lifting frame with cap screws (sock HD.,10 X 24) to cott tank.
- c. Attach lifting frame and dynamometer to hoist. The dynamometer will monitor lifting loads.
NOTE: Hoist must be positiored with care to insure vertical alignment. Any deviation from the venical will cause binding of the core tank in the reflector - _ and shielding of the reactor. He unit being lifted weighs approximately 250 pounds. Tension should be applied with the hoist and the core tank lifting frame should be manipulated until any excess forte is relieved. .. Tension is then again applied. De misuse of the electrical hoist could cause damage to the reactor reflector,if binding occurs and foire is applied. A man will stand by the hoist circuit breaker (Panel B, Breaker #5) in the event of an "up" button failure of the hoist. Binding should be expected for approximately 4 inches until the thimbles have cleared the lower housing. Lb \ d. Lift the core tank from the reactor. MA '
- 17. Place an appropriate piece of cadmium in glory hole, g()p u AA 18. Conduct radiation survey to detemine direct radiation levels from the core can and removable surface contamination on the exterior surface of the can.
- 19. Transfer the core to its storage container.
- a. Rernove lifting frame.
- b. Seal and label core can container and hold in Reactor Room.
@ 4/W4 I 20. Health Physics will perform a radiation survey of accessible intemal surfaces to ascertain direct (induced) radiation levels and removable contamination levels. NOE: his concludes the nuclear portion of the disassembly process. The remaining disassembly will be conventional mechanical and electrical, with f, / j radiation surveys made as directed by the Health Physicist. C/d Y/1/5> 21. Remove the four eight access pon cover assembly (2-000476): cfd 4/F/5 > a. Remove the eight access pon cover assembly (2-000476) c4 y/r/U b. Use a pole to push from one end, while another person is at the other end of the port, remove the pon fillers (2 wood (2 000342),4 lead (2-000341),2 graphite (2-000340) each). (s?) VF/f/ c. Remove access pon flanges (2 000418) (8 each) by removing (4 cach) screws (H 1023-8)(socket HD mach., 1/4 - 20 1/2). Cn> 9/f/O d. Remove access port flange "0" rings (H-4008) (8 each). c,r > GN // r c. Remove access pon tubes (2-000420)(4 each). cA vh/ U f. Conduct health physics survey on the access port tubes. Q<> 4.r/t /U g. Label all pans and store. QO MA /77 22. Remove the outer graphite shield (2-000140).
'M> A/'A a. Make alignment marks in the graphite shield and lead shield ring #1.
(.p) Wi/9) b. Screw in lifting eyes. NOTE: The lifting eye size will be determined and acquired sometime after the B4
Form NEL-103 RSC Appmval: 5/25/88 thermalcolumn has been removed.
@ Nb 3 c. Attach sling to hoist. (The graphite reflector will weigh ~700 pounds.)
W 4/ r/ U d. Slowly raise graphite shield until clear of reactor.
- c. Actual reflector weight: lbs.
gd O!)/91 f. Transfer to appropriate storage ama and label. qc) 4/W 9 23. Remove the four lead shield rings. gu M/\ a. Make alignment marks on the first lead shield and reactor structure for
. reassembly.
GO 4/t/W b. Screw in lifting eyes. (perhaps the graphite mflector eyes can be used.) cg > 4/ v/"O c. Attach sling and dynamometer to hoist. - g) @ /9i d. Slowly raise lead ring; monitor for binding until clear of mactor. NOTE: 1. cad rings 1 and 4 weigh 600 pounds, ring 2 weighs ~900 pounds, and ring 3 weighs -800 pounds. Ud h/i'/9 ) e. Transfer to an appropriate storage area and label. Q() Wr/93 f. Place alignment marks on next ring, and repeat process for all four rings. Ring #1 (2-000123) Actual Weight lbs. , Ring #2 (2-000122) Actual Weight lbs. ' Ring #3 (2-000121) Actual Weight lbs. . Ring #4 (2 000123) Actual Weight Ibs. Od NI/b 24 Remove the core support plate (2-111253). , cp &A a. Place alignment marks on core support plate (top and bottom). l cg) Wi/ U b. From beneath reactor, remove hold-down bolts (H-1114-96) (4 each, right-hand l thread). Do not change position of tension nuts (H-2017). j CAUTION: Contml rod drive tie bolts are still attached to core support plate. Take care not to bend or break bolts. C/.Oh/f/O c. Manually lift plate from the top and transfer to floor area for storage. ou 4/HW 25. Remove the lead base plate shield (2-000124). 0cp 2)' Mi 4/P/M
- a. Make alignment marks on the lead base and reactor structure.
- b. Screw in lifting eyes.
y) 4'#/43 c. Attach sling and dynamometer to hoist. (This piece should weigh slightly less than the thermal column.) CM 4hhi d. Slowly raise lead base plate; watch for binding until clear of icactor. Actual weight: lbs. CCJ Y/iA 5 e. Transfer to floor area for storage. COMMENTS: C/O 5'N 26. Drain the shield water tank (2-000655),
- a. Obtain permission from the Health Physicist to drain shield water to sewer (a water sample will have been taken and analyzed for radioactivity as a basis for
( release of the water). I b. Connect hose to drain valve (H-3009) at bonom of shield tank and drain water [ NOTE: to sewer. Reactor manhole cover should be off. Entries will be made in the Waste Log. including: date/ time; estimated quantity dumped: activity of sample; estimated activity dumped. i c. Close drain valve and remove hose. k REMARKS:
@ 27. Reactor electrical and instrumentation disassembly:
B5
- Form NEL.103 RSC Approval:5/25/88 The elecuical and instrumentation cables will be disconnected in the following general sequence. They will be identified for future reassembly, surveyed, and packaged for transportanon.
i a. Nuclear Channel #1: I 1) Detector channel H.V. off, t
- 2) Ratemeter main power off.
- 3) Open and remove access manhole cover.
- 4) Remove detector dry well from reactor tank shield water.
- 5) Disassemble dry well.
- 6) Disconnect and tag pre-am (2) and H.V (1) cables.
- 7) Transfer components to clean area for radiological survey (gross smears),
and packing.
- b. Nuclear Channels #2 and #3:
- 1) Disconnect and tag H.V. cables at battery supply pack (rear of control console).
- 2) Remove detector dry wells from reactor tank shield water, yf) 3) Disassemble dry wells.
- 4) Disconnect and tag signal and H.V. cables.
- 5) Transfer components to clean area for radiological survey and packing.
- c. Main distribution cable:
- 1) Main power switch (left side reactor console) off.
- 2) Disconnect and tag P-15 (control console).
- 3) Disconnect and ta.g P 16 (control console).
- d. Miscellaneous:
- 1) Disconnect and tag monitor cable at control console. Pull it to storage i beneath reactor tank. l
- 2) Disconnect and tag main power cable. l
- 3) Remove the EARTHQUAKE SCRAM ASSEMBLY ball (H3005), bag and label.
- 4) Remove the THERMO SWITCH (E-10035).
- a. Labelelectricalleads. ,
- b. Disconnect electrical leads. '
- c. Label thermo switch and bag for shipment. l GO M 28. Console ,
The console will be retained in its present location until final disposition. l l B6
i rom re.L M RSC Approval: 5/25/88 University of Utah Nuclear Engineering Laborattry AGN.201 Reactor Defueling Procedure I. Intmduction This document gives the general procedures to be followed for defueling the AGN-201 reactor. These procedures give details regarding the preparations, monitoring, setup, general procedures and specific defueling procedures. NOTE: Check and date each item in the appropriate place as each step is accomplished. Maintain one master copy forreference. II. Prenaration Prior to Defueline
- 1. Radintion Protection
~
- a. The following instruments will be checked for proper operation, then placed in 1205-E for use:
- 1) High-volume airsampler.
- 2) Neutron survey meter (Texas Nuclear Bonner Sphere).
- 3) Beta / gamma dose rate survey meter (Eberline).
- 4) Contamination stuvey meter (TBM-3S),
- b. The following supplies will be collected and placed in the reactor room for use as needed. '
- 1) Filters for high-volume air sampling.
- 2) Smearing materials for wipe tests.
- 3) Containers for air filters and wipe test smears.
- 4) Shielded storage container for storing the Ra-Be neutron source.
- 5) Coveralls, lab coats, gloves, and shoe covers.
- 6) Radioactive waste containers.
- 7) Cadmium foil for core caninsert.
- 8) Respiratory protection equipment (retain at first-aid station unless required).
- 2. Work Area and Tools
- a. Survey reactorroom area in p eparation of defueling activities. ij
- b. Relocate equipment as necessary to maximize working area room.
- c. Collect the following tools and place in reactor room: '
- 1) Hand Tools required for disassembly (socket and Allen wrenches).
- 2) Handling tool for removing the Ra-Be source.
- 3) Lifting lugs and rigging for thermal column, core tank, and upper graphite reflector.
d.- The following items will also be placed in 1205-E:
- 1) Plastic bags for storing components.
- 2) Camera with flash and film for photographically documenting the procedure at key stages.
j_ III. Detailed Dienstembly Procedures i NOTE: The assembly part numbers are correlated with the part listing on drawing number E-2-000100. The ventilation system and air sampler should be operating during all disasssembly procedures. ,
- 1. A representative from the Radiological Health Department will perform a pre-defueling radiological survey.
- 2. The Reactor Supervisor will initiate special access procedures, personnel-and equipment monitoring procedures and other procedures as needed to keep personnel radiation exposures as low as reasonably achievable (ALARA). An operational check will be made of radiation monitoting equipment. If all equipment responds properly, the -
operation may proceed. The Reactor Supervisor will brief personnel involved in the defueling operation on each step prior to its completion, with clarification made, as 4 necessary, of the tasks to be performed.
- 3. Insure that the temporary cadmium rod is in the glory hole and well fixed.
- 4. Remove the top cover plate (2-000226). Drain the thennalcolumn.
B7
From NEL lLu RSC Approvah 5/25/88
- a. Obtain permission from the Health Physicist to dram thermal column water to sewer (a water sample will have been previously taken and analyzed for radioactivity as a basis for release of the water).
- b. Pump water to sewer until thermal column is as dry as possible.
NOTE: The entries for health physics records will be made in the Waste Log, including: date/ time; estimated water volume dumped; gross sample results in pCi/ml, % of applicable mpc, estimated activity dumped.
~
- 5. Remove the thermal column (2-000139):
NOTE: Hermal column is estimated to weigh 2,400 pounds.
- a. Unbolt thermal column fmm reactor tank (16 each 3/4 inch bolts).
- b. Attach lifting sling to crane and thermal column.
- c. Remove thermal coh,mn from reactor and move to an appropriate space on the floor. Set thermal ( olumn on plastic sheet or absorbent paper.
- d. Label thermal coltu m. Bag the 16 each 3/4 inch hold-down bolts and label.
- 6. Place borated paraffin aver Ra-Be source and perform radiation survey of thermal column cavity, Replace top cover plate and secure to flange at top of reactor tank until ready forremova' of neutron source. Survey exterior surface of top plate cover for radiation level and possible contamination; mark area as a radiation hazard as appropriate. .
- 7. Remove and survey e'.ch lead brick from thermal column. Use paper towels to dry the lead and dispose ritowels as low-level comaminated waste. Should any surface of a brick yield a dose rate greater than 3 times the background rate, label and segregate from unactivated bricks; place bricks on polyethylene sheeting until a confirmatory survey by a Radiological Health Dept. representative indicates release of the bricks for unrestricted use. Any activated or contaminated bricks will be retained by UUNEL
- 8. Remove bottom cover plate (2-000169). The gasket (2-000593) should come off with the cover. Bag the cover plate thumb screws (H-1007-10) and label.
- 9. Insure that the control and safety rods have indeed been removed earlier, as declared. Label mds and store in approved fuel storage locations.
Safe Rod Assembly: 2-000550 I Safe Rod Assembly 2-000550 II Coarse Contml Rod Assembly 2-000550 HI Fine Control Rod Assembly 2-000550 IV
- 10. Remove the three dash pots (2-000510), label and store for future disposition.
- 11. Remove the four contml md drive mechanisms.
- a. Console power off(neutron detection channels 1,2, & 3 remain on).
- b. Disconnect rod drive power plugs. Identify and label each.
- c. Remove (2 each) jam nuts (1/4-28) from the tie bolts and carefully lower each rod drive frame assembly until free. Identify and label each frame.
Bag thejam nuts and label.
- 12. Insert neutron absorberin the control and safety rod holes in the core can.
- 13. Remove the top cover plate (2-000226). The gasket (2-000591) should come off with the cover. Bag the eight cover plate bolts (H-1069-12) and label.
- 14. Remove the Ra-Be neutron source (H-3018) from the graphite reflector. Wipe test the source and place it in the storage container. Survey storage container.
- 15. Conduct a core survey. Since the core tank will not be opened at this time, an off gas sample will not be taken. A direct radiation survey and smear survey of the core tank top and environs will be made.
- 16. Remove cadmium rod from glory hole (operator monitor neutron detector channels 1 through 3, H.P. representative monitor portable neutron survey meter response). Only a slight increase in reading may be noted. (Log any reading change.)
BEFORE AFTER B8
From NEL-104 RSC Approval:9/25/88 CRM: LOG: LINEAR:
- 17. Remove glory hole tube.
- a. Remove glory hole flange (2-000419) (2 each) by removing (4 each) socket HD machine screws,1/4-20 X 1/2 (H-1023-8).
- b. Remove glory hole flange "0" ring (H-4009) (2 each).
- c. Remove glory hole tube (2-000422). Extreme care should be taken when removing this tube. It should not be bent (straight pull) and if binding is excessive, it may be necessary to lift the core tank slightly to relieve the bind.
COMMENTS: NOTE: The Health Physicist will carefully monitor the removal of the core can. All radiation and criticality monitors will be checked for proper operation just prior to the removal of the core, and surveys of radiauon . levels fmm the core can will be made continuously during removal. ~ 18. Com Can Removal (2-000114):
- a. Attach lifting frame with cap screws (sock HD.,10 X 24) to core tank.
- b. Attach lifting frame and to hoist.
NO'IE: Hoist must be positioned with care to insure venical alignment. Any deviation from the venical will cause binding of the core tank in the reflector and shielding of the reactor. The unit being lifted weighs approximately 250 pounds. Tension should be applied with the hoist and the core tank lifting frame should be manipulated until any uneven tension is relieved. Tension is then again applied. The misuse of the electrical hoist could cause damage to the reactor reflector, if binding occurs and force is applied. A man will stand by the hoist circuit breaker (Panel B, Breaker #5) in the event of an "up" button failure of the hoist. Binding should be expected for approximately 4 inches until the thimbles have cleared the lower housing.
- d. Lift the core tank from the reactor.
NOTE OFINTEREST: Other facilities have measured a loss of reactivity after removing the core tank : U.S Naval Postgraduate School and Colorado State University).
- 19. Place an appropriate piece of neutron absorber (Cd or In) in glory hole.
- 20. Conduct radiation survey to determine direct radiation levels from the core can and removable surface contamination on the exterior surface of the can.
- 21. Transfer the core to its storage container.
- a. Remove lifting frame.
- b. Seal and label core can container and hold in Reactor Room.
- 22. Health Physics will perform a radiation survey of accessible internal surfaces to ascenain direct (induced) radiation levels and removable contamination levels.
NOTE: This concludes the nuclear ponion of the disassembly process. The remaining disassembly will be conventional mechanical and electrical, with radiation surveys made as directed by the Health Physicist. B9
1 Procedura for Rem val cf AGN Control Rods NtL-105 Precautions: . Be sure proper ventilation and air sampling equipment is in operation during this procedure. Use gloves as necessary when handling potentially contaminated materials.
- 1. Remove the nuts securing the control rod drive asse ly to the AGN structure taking care to support the assembly as the last nut is removed. g4
- 2. oidin Carefully lower the /,
space beneath the reactor. control rod p% g binding and remove the assem
- 3. Survey the rod and record radiation levels in spaces provided below. Wipe the exterior surface of the fuel cladding to determine if-surface contamination exists. Note below any removable contamination discovered. / 0%
Instrument: W/6? - V T Serial No.: A R1/2 9 Calibration Date: M5 2 #% Max. level CR1 CR2 Fine Coarse M ~
@ contact C6 SMrl/
- N $ME! k.~
- AY' W0QpA Max. level
. 06 6mC/,c
@ l foot . C 3.EmC/.f ,c30 mc/w , c 7 qmqj,, @C00 4
Unscrew the fueled control rods from the remainder of the assembly'ahlIc'e'n the temporary storage container. Survey the drive assemblies for any residual contamination or activation. Note belosy any elevated radiation levels. Set the drive assemblies aside for future use as necessary. t/g75
- 5. Repeat steps 1 through 4 for each control rod. Insert borated paraffin between the control rods and secure container lid when all fuel has been loaded. /jpJ 6 ~.
Load borated paraffin into the reactor core through the control rod guide tubes assuring that ; the paraffin will remain in place. /A; 7. Place the temporary storage container in the Middle Fuel Storage Pit and secure until ready for shipment to DOE. y v
,y
- 8. Comments: w , i .x s ,
; ut, @vMdm (hm**'ed - So h) p,icJ . w cufcc/cW nwinmi . %oy, a 4;se 4hid&
dg - vm /mtwul.h g; .. " .. ,, TSIe " n "
,, w , Q - "
't ev dri,y as cLt et'>tbw""*5' d-m'/yN 1>t tW jW1h af N &k'k *A.
% Mbc( towwA +?hs Wht reabeS .-tA-e.Ctkc faE *.H'i' Date Procedure Started: 'Z- / 8 'I A CS /
fewvD Date Procedure Finished: C/r/8i ]gWI , Procedure mviewed and approved on behalf of the Reactor Safety Committee by: AGN Reactor Supervisor: M_ _ 7 b MgN
l l r 1 _ l Written on back of NEL-105 'l I
... plastic and placed in a temporary steel barrel. The barn:1 was secured in the middle fuel storage pit and will remain there pending transfer of fuel to DOE.-
i e 'b, b f
^
John S. Bennion l 1 1 o Bil
E , d s.- Procedures for Removal of Ra Be Neutron Source from AGN 201 Reactor Precautions: Be sure proper ventilation and air sampling equipment are operating during' this
, procedure. Gloves and personnel dosimetry must be wom throughout this {
procedure. j l
. I
- 1. Remove the top cover plate from the reactor and remove the borated paraffin covering the- !
Ra Be source.
- l
- 2. ' Using a remote swiping tool, obtain a wipe of the top of the source and the area immediately ~ ~.
surrounding the source. Minimize the exposure time and use the AGN tank to provide as much shielding as possible.
. . l
- 3. Analyze the wipe with both a contamination survey meter and gamma spectroscopy. Record ' i the results below.
1 Survey Instrument: 7d#/- 95 ~l Serial Number: o67124 Calibration Date: /s/21/EA Backgmund: SO Gross Counts: 70 i Net Counts: ao y j Comments: 4 gfgg7, j l Gamma Spectmscopy (Attach spectrum):
]
Instrument: I<Mmii [< Visible Peaks: obs&vic{ do-se , Mn -SC & /C-VO pads (W M baQ&) Radium Daughter Products- yes no 1 Comments: p
- 4. If any evidence of leakage of the neutron source exists, notify the Reactor Supervisor.
Otherwise, follow the remaining items of the procedure.
- 5. Place the neutron source transfer container next to the AGN reactor on the upper floor of the reactor room.
- 6. Make sure a strong neutron absorbing material such as boron or cadmium has been inserted B12
., ,, y -rn-,-- e w- ~
into the core thmugh at least two contml rod guide tubes. Absorbing material: c42 mass: .?5~. / grams
- 7. Transfer the source from the AGN reactor to the transfer container using a remote handling tool and secure container. Wipe the soume while transferring to container. Also wipe and l survey the location of the reactor containing the source. Record data below.
Survey Instrument: // < k." C~/ Serial Number: ce7 - Calibration Date: X ?- h - W' h" harce Wioe geactor Wioe (QA .. sh:d m.:n, j Backi;round -l' Gross Counts Net Cotints Radiation level @ contact at source location: mr/hr , Gamma Spectroscopy (Attach spectrum): # d;;A ;ga,,/s;' #2#7^ '#'O#F " ' ' '
- Ms. %.-
Instrument: 1 Peaks: Comments: l l
- 8. Place lid on and secure neutron source container. Perform external radiation survey of l container. Mark container with radiation hazard signs and label with source activity. Store in i MEB 1205 A (Irradiation Facility Room).
External radiation survey of container: I Survey Instrument: Y,'eIore<^ Yfo P . Serial Number: / 7 'l Calibration Date: 6 A l2. "r 9 ->+t #* . i A vltsd jdibg1. M w MiMhtU t/47, &l Maximum dose rate @ gontact:h,I" ~ 31 & mr/hr c QN$9 ' (G[lf mM f detftd. Maximum dose rate @j fddt: _7 # mr/hr
- 9. ep! 6e@k secure top cover plate of reactor.
G..Q Surveys Perfomied by:
\/
bam' _ Date: M8/87 - Procedure reviewed and a approved /onThalf p/ 5f the / ReactZ6fSafety Comminee by: 7 AGN Reactor Supervisor: IMMN #88[4%Bd
. /, //
Date: M/d/Wh
~
l,' f/ B13 .
Annendix C: Parts Transferred To Other Reactor Licenses t The following are a set of pictures of the AGN-201M's parts that have been transferred to other reactor's licenses. The fomis that these pictures are on, contain a brief
, description, a summary of the radiological survey, and the specific reactor license that these parts are being transferred to.
.1 I
1 l
.Cl
MUt7535!YY l 91 UTAE ' Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 1 m _,. Memorandum ; To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN De ghsioning Staff
Subject:
Part Status and Location l Part
Description:
l Part #28 - Rod Drive ! 7Q, , , , .7 +-,?. . Part #29 - Rod Drive
$7. - , :
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*Of [ , 9f A,* . . ,' ' .% ..,
y;
,, , . _ ?
iWi /j ,. I. p T. 's ~
$.7 .
l} 'm j .Ej~ i
$? *, ' ' y L, f , ,
}Q , ' f . '
U 4'. h >r I r l 1 h .
.',. . s :
- n. ... - . . ye . ,
}.7 j s;4 4 it. .dPb
**4 s '- -
ith, ,
"4
,,:4
' (, .( .
~
't
) [ ',
I l l l l Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No ! contamination was detected: survey results are attached, l HP Technician: h_f 5.bl8 Date: G/Id bI l l Part Disposal (or Transfer): The two rod drives shown here were transferred from License No. R-25, Docket No. 50-72, to Idaho State University's Nuclear Facility, License No. R-110, Docket No.
- 50-284. p, p . . /, f yyg Reactor Superviso D J -
Date: C2 i I
-- - - . . . . - - . . . - . . . . - ~ . _ . . - . . . . - - - - - . _ . _ . . _ _ _ _ . _ _ _ . _ .
(- If58YBRSITY er UYAE Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 meten ammuma Memorandum i To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Decghoning Staff
Subject:
Part Status and Location Part
Description:
ggg . . Part #87 - Reactor Console s .
, ,t .
- j 1
4 '
- g. ..
- V l,_'
I I i Radiological Survey Results- I i Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey insults are attached. HP Technician: _Dorff 7.%fl Date: (- [36 /93 : 1 Part Disposal (or Transfer): The reactor console shown here was transferred from . License No. R-25, Docket No. 1 50-72, to Idaho State University's Nuclear Facility, License No. R-110, Docket No. 50-284. . g Reactor Superviso . , m Date: /93- ; C3 i
1 uw vansart , or l UTAE Mechanical Engineering Department 3209 MEB e - Salt Lake City, UT 84112
- _,, Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Decthhsloning Staff
Subject:
Part Status and Location Part
Description:
Pan #17 - Graphite Reflector from Top of Core Tank Pan #21 - Graphite Reflector from Bottom of Core Tank ; Part #18 - Graphite Reflector from Bottom of Core Tank l Pan #19 - Graphite Reflector Side Plate from Core Tank Part #20 - Graphite Reflector Side Plate from Core Tank Part #s 61,62,63,64,66,67,68,69 - T Graphite Plugs for Access Port
' W'd! !5
,-y4 Pan #s 42,43,44,45,46,47,48,49, 50,51,52,53,54,55,56,57 -
Lead Shielding Plugs in Access Pon
.. . r q
I' - u e. 1. Radiological Survey Results: Alpha, Beta, and Gamma contamination stuveys were conducted on these pans. No contamination was detected: survey results are attached. HP Technician: _ h oOfGlaAf Date: 6/d4T Part Disposal (or Transfer): The graphite reflectors from both the top and bottom of the core tank, the graphite inflector side plates from the core tank, the graphite plugs for the access pon and the lead shielding plugs in the access pon have been transferred from License No. R-25, Docket No. 50-72, to UUNEL's TRIG Lic e3 No, R 7 , Doc et No. 50-407. Reactor Supervisor: . J L' ~- Dam: C4 w 4- -- *g e --r+
I l vn vans:Tr ! l UTAE Mechanical Engineering Department 3209 A1EB e ' l Salt Lake City, UT 84112 WCLEAR EmmEnmo Memorandum l l To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN11hmmissioning Staff - l
Subject:
Part Status and Location Part
Description:
Part #65 - Cadmium Foil 1 .. s l ' "
~
l J . / ,:
? $;&;'
g , j (( 7.E t . ,T ' 4 x-b w l
)
E I g4 f'F[" ,
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{ m . l I7 y
'?
. r,,; ./ 4
%' i. (' ,
i 4 ,- t - i 'l -, 4.r n ,k. p &- f 1 Q Vr Q.uk & [ = Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conductui on these parts. No contamination was detected: survey results are attached. HP Technician: Thu n M G hff Date: 6/E f'i7 Part Disposal (or Transfer): The cadmium foil shown here were transferred from License No. R-25, Docket No. 50-72, to UUNEL's TRIGA License No. R-126 Docket No.50-407. Reactor Supervisor:. , ' . d te; b fM C5
WWtVERSITY ou UTAE Mechanical Engineering Department 3209 MEB 1 8 Salt Lake City, UT 84112 i wctiu s=muw.o Memorandum l To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN %dynissioning Staff
Subject:
Part Status and Location i , i Part - Description- 1 o Part #74 - Main Graphite Reflector i k ~
.a ~
1 k1 3m : 1
. v..e f.
. :Nl,'
UD ; l 1 s T , j \ s 1 3, , s Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No ! contamination was detected. Smvey msults am attached. l HP Technician: bu 9957kck[ Date: G/3b/q 7 Part Disposal (or Transfer): The main graphite reflector shown here were transferred from License No. R-25, Docket No. 50-72, to UUNEL's TRIGA License No. R-126 Docket No.50-407. Reactor Supervisor. i 3 !_ Qate: b Y C6
UlfIYRESITY or STAE Mechanical Engineering Department ' 3209 MEB e Salt Lake City, UT 84112 uucma suom suno Memorandum l To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 l From: AGN Dechhoning Staff
Subject:
Part Status and Location
]
8 Part
Description:
Part #30 - Rod Drive Part #31 - Rod Drive
.Y
/ I
,; (
'g \d .
y z,
, .; '} ;
I .g hT i f/ -,
- I*;I,j. '
dr ,c ' , .
% t.
Q . '. . j
'{.
}[ ~ '
~~.:., . :.y ^
- 9 l Radiological Survey Results:
Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached. HP Technician: hoJK%d Date: G/Tc [f h Part Disposal (or Transfer): The two Rod Drives shown here were transferred from License No. R-25, Docket No. 50-72, to UUNEL's TRIGA License No. R-126 Docket No.50-407. Reactor Superviso , ! *< Date: a
If2fYERSITY or UTAE Mechanical Engineering Department 3209 MEB O Salt Lake City, UT 84112 oum mou. Memorandum
' To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Dghissioning Staff
Subject:
Part Status and Location Part
Description:
Pan #70 - Aluminwn Sleeve for
; =
Access Port
- Pan #71 - Aluminum Sleeve for -l I
ik - Access Pon I k h A" . c Pan #72 - Aluminum Sleeve for
,f_;.gf;Jg
'Q ' Access Port I Pan #73 - Aluminum Sleeve for N ., Access Port
'hc.;
;*t ~.fi, *
. p' y'3 ;-
, y .
g .
. n ;w , r .
. ;y., fg . p;; u
.? y..
; n- .
rllb6,E^
';~. %QG .
,3g y -
- 2. s .g 3 .-
Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached. HP Technician: Do > udKhb Datr d7k'i 3 Part Disposal (or Transfer): The four aluminum sleeves for access ports shown here were transferred from License No. R-25, Docket No. 50-72, to UUNEL's TRIGA License No. R-126 Docket No.50-407. Reactor Superviso _ Date: M fM C8
UNIYERSITT or UTAE Mechanical Engineering Department s 3209 MEB 8 Salt Lake City, UT 84112 I met m o.om m mo Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN @hmissioning Staff
Subject:
Part Status and Location ] Part
Description:
Pan #75 - Lead Shielding Ring c ..
- j 1. <e Pan #76 - Lead Shielding Ring '
"X L. - .
..- Part #77 - Lead Shielding Rmg -
Part #78 - Lead Shielding Ring l r Pan #79 - Lead Shielding Ring 7
~
. i
~
'p L L
, ,. ., #g Q[i Tpg <; .,f,
- P 2
u., & m '~q ;; g , t Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached. HP Technician: D&8Gkth Date: 6/Tc/9 T Part Disposal (or Transfer): The five lead shielding rings shown here were transferred from License No. R-25, Docket No. 50-72, to the UNEL's TRIGA License No. R-126, Docket No. 50-407. f Reactor Supervis . , ,7 Date: 30 1 C9
. . - - . . . _ . _ .. ~___________-_-____-_-_________-__
~Annendix D:
-Parts To Be Disnosed Of As Radioloelcal Waste The following are a set of pictures of the AGN-201M's parts that have been set -
aside to be disposed of as radiological waste. The forms that these picmres are on contain a brief description, a summary of the radiological survey, and the method of disposal of the parts. O 1 4
-t 1
-l 1
-1 f1 i
UNfTERSITY or STAE l l Mechanical Engineering Department 3209 MEB l I e Salt Lake City, UT 84112 metan amusmua Memorandum l l To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco Ishning Staff
Subject:
Part Status and Location Part
Description:
, Generated Decommissioning Waste i
l
)
~. u. ;i D. . .r
,4 {, p- e,
*"u I-lT c ,
~~
Radiological Survey Results: The Direct Survey of the decommissioning waste showed nonremovable contamination from activation products. Activity was measured at 10 mci. Survey results are attached. HP Technician: Tflev8 WaO Date: 7hb l Part Disposal (or Transfer): The aforementioaed parts were segregated, packaged and labeled by the AGN Decommissioning Staff, prior to collection for disposal by the Radiological Health i Department, under ap roved procedures outlined m the Radiation Safety Manual. I s 1 Reactor Supervisor: - Date: 7///?.k D2
UNIVSRSITY or UTAE ' Mechanical Engineering Department s 3209 MEB e Salt Lake City, UT 84112 wuci.m suommma Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN D issioning Staff
Subject:
Part Status and Location Part
Description:
Part #2 - Safety Rod Guide Tubes Quantity-2
'" Part #9 - Control Rod Guide Tubes
~
Quantity-2 5 l n fl. :$h, L 1 ' V 19. k lJ' - -
.a \
'f f hN ' 7 ' !
' mw., 5;E s"
. .,px ,
' W/1;,60 e
,.- ,N . ,. , ,
, Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conducted on these parts. Alpha contamination was detected on both parts at .07nCi from U-235 and U-238. Survey results are attached. HP Technician: 3hwdMaN Date: N/97 Part Disposal (or Transfer): The aforementioned parts were segregated, packaged and labeled by the AGN Decommissioning Staff, prior to collection for disposal by the Radiological Health Depanment, under ap oved procedures outlined in the Radiation Safety Manual. Reactor Supervisor:
, j-~ b _ Date: b D3
5tfIYNRSITT or BTAE Mechanical Engineering Department 3209 MEB O Salt Lake City, UT 84112 Nuct.sAa amou<samo Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco %[loning Staff
Subject:
Part Status and Location Part
Description:
Pan #6 - AGN Screws & other pans Pan #7 - AGN Screws & other parts Pan #8 - Core Support - Pan #13 - Core Support Pan #83 - AGN Screws & other pans a e g
- ( SAE..,.
$. -+ .- "' , f.R
, 3 .a ;Q 3
j g f.
- _.e ;a A d m__: - - +$ '
l i 1
-- l Radiological Survey Results:
Alpha, Beta, and Gamma contamination surveys were conducted on these parts. All pans were alpha contaminated. Parts 6,7, and 83 at .07nCi, part 8 at .inCi, and part 13 at
.134nC1. All pans were contaminated with U-235 and U-238 isotopes. Survey results are attached.
HP Technician: ~Qruuf %fl' Date: vId47 Part Disposal (or Transfer): The aforementioned parts were segregated, packaged and labeled by the AGN Decommissioning Staff, prior to collection for disposal by the Radiological Health Deparunent, under approved procedures outlined m the Radiation Safety Manual. Reactor Supervisor: . - ~ Date: 7 d-m
W!!! V E R S I T V or WTAE Mechanical Engineering Department
/ 3209 MEB 8 Salt Lake City, UT 84112
=cma ammazamo Memorandum ITo: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Dec ssioning Staff
Subject:
Part Status and Location Part
Description:
__ . Part #18 - Core Can W-L 1 nl b
' 'h; -
.; .N k.A ; - -- :
- t. &
h . l l i Radiological Survey Results: i Alpha, Beta, and Gamma contamination surveys were conducted on these parts: survey results indicate alpha contamination of.07nCi from U-235 and U-238. Survey results attached. HP Technician: Trtru@~41a8 Date: t/kb Part Disposal (or Transfer): The aforementioned parts were segregated, packaged and labeled by the AGN Decommissioning Staff, prior to collection for disposal by the Radiological Health Depanment, under a proved procedures outlined in the Radiation Safety Manual. Reactor Supervisor: - Date: 7/7 3-D5 2 .
- . - _ . ~ ,. - . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
UMtYEE5I77 or UTAE Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 wuci.sa ammmma Memorandum 1 To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco kning Staff
Subject:
Part Status and Location Part
Description:
Part #80 - Vacuum Cylinder for Core 1 Gas Sampling )
'I
.s
..~
eny
-~: ~ , h
_. :,z;$~~ _ _,a. = - 7 g$t , ' ea - -- fr i ' Radiological Survey Results: Direct survey, LSC and Alpha wipes were performed on these parts. The exterior contained no contamination, while the interior was alpha contaminated with .27nCi. Survey results are attached. HP Technician: h8Ma/[ Date: 7 /?bT Part Disposal (or Transfer): The aforementioned parts were segregated, packaged and labeled by the AGN Decommissioning Staff, prior to collection for disposal by the Radiological Health Department, under approved procedures outlined in the Radiation Safety Manual. l Reactor Supervisor: y Date: F ' De 4
--m - y e - . . - , , -- ,-. . . _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _
. . . . . - = - -.
Untvtas!YY er WYAW Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 i ___ Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco (n%shoning Staff
Subject:
Part Status and Location Part
Description:
I Part #1 - Safety Control Rod #2 !
~0 1 Part #5 - Safety Control Rod #2 and
. j ..
Spring Assembly . Part #10 - Safety Control Rod #1 and j Spring Assembly ; Part #11 - Course Rod and Spring (*4 JD,w. - C '..1. Assembly Part #12 - Fine Control Rod and 1
., Spring Assembly l
') s~
g e '- { '* ' - ) 2 2
~ '[
- 4> -a - ,. \
? y -l C 0lp / d(Q[ ^-
- v. V$ a c s ;
v i .. ~ 'rl. M_r_w . I < A Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conducted on these parts. Contamination is specified as follows: Part 1 showed alpha contamination at .272nCi, Part 5 had alpha at .075nCi, Part #11 alpha contamination at .12 and Part #12 showed alpha contamination at.04nCi. Survey results are attached. HP Technician: 'hn m#nla8 Date: V/5'/43 Part Disposal (or Transfer)- l The aforrmentioned parts weit segregated, packaged and labeled by the AGN Decommissioning Staff, prior to collection for disposal by the Radiological Health I Department, under ap roved procedures outlined in the Radiation Safety Manual. Reactor Supervisor: i \ _[f.. . Date: ';?k/ . *A D7
UUtVRESITT or UTAE Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 mcmaxmmeaum Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Decom ning Staff
Subject:
Part Status and Location Part
Description:
Part #s 32, 33, 34, 35, 36, 37, 38, f 39,40,41,81,82 [ - Wooden Access Port Plugs - i b I n s 1.l .7 ,3 . g e g, PW : / - 1 s .t
- y. 44 d. ,, '. -
. % M* @Q .* w, yfrr. d $. s Radiological Survey Results:
Direct survey, LSC and Alpha wipes were performed on these parts. No removable contamination was detected, but due to the absorbing nature of the wood the parts must be considered contaminated by activation products at 10 mci. Survey res'ilts are attached. HP Technician: Thw #hf/ Date: N/97 Part Disposal (or Transfer): The aforementioned parts were segregated, packaged and labeled by the AGN Decommissioning Staff, prior to collection for disposal by the Radiological Health Department, under ap' ved procedures outlined in the Radiation Safety Manual. Reactor Supervisor: - Date: 77 1-e f'l D8
UNfYER3177 OF 3TAE Mechanical Engineering Department 3209 MEB 8 Salt Lake City, UT 84112 l w c m m a m maman.o Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Decom(ihing Staff -
Subject:
Part Status and Location Part
Description:
Part #4 - Paint Chips from Thermal [ Column j J
- a. ..
.A
~
,rj fhh, g %, _
i f/4 t et J 4 Radiological Survey Results: Direct survey, LSC and Alpha wipes were performed on these parts. No removable contamination was detected, but due to the absorbing nature the parts, they must be considered contaminated by activation products at 10 mci. Smvey results are attached. HP Technician: buff 7]ct/l Date: 7[v/07 Part Disposal (or Transfer): He aforementioned parts were segregated, packaged and labeled by the AGN Deconunissioning Staff, prior to collection for disposal by the Radiological Health Department, under approved procedures outlined in the Radiation Safety Manual. Reactor Supervisor: - Date: 7i L D9
Annendix E: , Parts-To Be Disnosed Of As Unrestricted Waste . The following are a set of pictures of the AGN-201M's parts that have been set , aside to be disposed of as unrestricted waste The forms that these pictures are on contain a brief description, a summary of the radiological survey, and the method of disposal of the parts. , O k i s 4
/
4 L i 4 El
UNf73RSITT OF UTAE Mechanical Engineering Department 3209 MEB 8 - Salt Lake City, UT 84112 mcun ammism.o Memorandum l To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 l From: AGN Deco ffming Staff
Subject:
Part Status and Location Part
Description:
Part #22 -Interior Steel Thermal i I Column Part #23 - Exterior Steel Thermal - 4. [#,.
~
N sJ s Column Pan #24 - Top of Thermal Column Cover Plate
- 4 Pan #25 - Bottom of Thermal 1
Column Cover Plate i l ! .J
~
, u < 4- ,.; ,
l s; <. y
- v. 4,4, .
q.a Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached. HP Technician: Th w 91lM)/ Date: 7 b !47 Part Disposal (or Transfer): The aforementioned parts were disposed of through non<ontaminated waste, j [} Reactor Supervisor: y Date: 3 / E2 1
i UNIVERSITT or , UTAR 1 Mechanical Engineering Department i 3209 MEB 8 Salt Lake City, UT 84112 wcma ammanum Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco oning Staff
Subject:
Part Status and Location Part
Description:
Pan # 27 - Port Covers and Glory Hole Covers With "O" Ring and Bolts - g g, . g': IU J w-T. t
$$*-(C a:
r
% 3% yn
- 7. -<.
+k
.. * ** ;1;*
; : s.
- ) p, x b s._k a
Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached. HP Technician: hu y8/Tal/ __ Date: +b 9J Part Disposal (or Transfer): i The port and glory hole covers as well as the "O" ring and bolts were disposed of through non-contaminated waste. s 1 Reactor Supervisor: _ i
~_ ate: # !
1 a E3 j
UN!YER3377 OR UTAE Mechanical Engineering Department 3209 Ml'B N O Salt Lake City, UT 84112 mcma d, mci;io Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Dect(ngsjsioning Staff
Subject:
Part Status and Location Part
Description:
, g Part #58 - Aluminum Fuse Support !
Part #59 - Alignment Pins i
; gf Part #60 - Polyethelane Rod -
.s y "'
~
, f. , .
r_ . K*i i
! s
" ,h_..V['lr;h % \,
'l-
, ~. a. . ; .-
I .
~
a- : ,
..m s e
~,,2
& /. .. ,.
', i it
( .;7,s 4
,sg~ 5 i
- k. 4; ' .
- s. ,gi.,f[,lf; gk ? '. ,
3 - -' ku.L L e l Radiological Survey Results: Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached. HP Technician: huc8fC93ceN Date: N'1/M Part Disposal (or Transfer): The parts listed above were disposed of through non-contaminated waste. Reactor Supervisor: k - ate: 3 //
/ i b
UIIIVBBSITT l i or STAR Mechanical Engineering Department 3209 MEB 8 Salt Lake City, UT 84112 mcma ommma Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco oning Staff
Subject:
Part Status and Location i Part
Description:
Part #13 "O" Ring for Core Tank i V - Pan #14 - Core Tank Cover (upper) '
- L Part #15 - Core Tank Cover (lower) ,
V' r Pan #16 - Polyethelane Disk l p4 .. . Part #84 - Control Rod Support Plate l
' %- i C., [53d. ., *, % ' ,
. . a ;, . m.- . , , .
- ha a y v ,
+ ;.y. ,
5 ff } ,' ,-
. 3, 4 -[ g r Radiological Survey Results:
Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached. HP Technician: Talmef/3 N Date: -7 /9 /4J Part Disposal (or Transfer): The "O" ring, com tank covers, polyethelane disk and the control rod support plate were all disposed of through non-contaminated waste. i Reactor Supervisor: { d ate: 7/#/NN E5
i univaasr77 l or ) UTAE Mechanical Engineering Department l s 3209 MEB l O Salt Lake City, UT 84112 i Memorandum l mum ,mm, m To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Decomt [ning Staff
Subject:
Part Status and Location l Part
Description:
Part #86 - Main Reactor Tank < 3: [.,:.
, . _fn k~ .
4
. i *, - I l
Radiological Survey Results: ; i Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No l contamination was detected: survey results are attached. I l
- IIP Technician
- hof 99SNol/ Date: MllfN
. Part Disposal (or Transfer): The main reactor tank was disposed of through non-contaminated waste. Reactor Supervisor: -
~
ate: 3 //r Mt E6 l
Aooendix F: Fuel Shioment Information This appendix contains a copy of the paper work associated with the transfer of the AGN-201M's fuel from the University of Utah's reactor labomtory to the DOE at Oak Ridge Tennessee. This section is broken into three subsections these are
- 1) Fuel Transfer Check Lists
- 2) Fuel Transfer Forms
- 3) Fuel Transfer Correspondence List This break down is designed to show clearly the tracking, procedures, and correspondence necessary for the transpon of the AGN-20lM's fuel. -
h F1
- 1. Fuel Transfer Check Lists The following forms NEL-110, NEL-117, and NEL-118, are listed in this section.
These fonns demonstrate the document control procedures used during the fuel transfer and the final check lists performed to insure safety during the fuel shipment to the DOE.
l Form NEL 110 l AGN Fuel Shipment l Document Control l l The following docurnents pertaining to the shipment of the special nuclear material (SNM) from the i AGN-210M training reactor (NRC License No. R-25) will be maintained on file for a minimum I period of three years after shipment as required by 10 CFR 71.135.
/
.- 1,. Approved DOE Scrap Declaration No,ID 90-1 (Forms OR 658A, B, C, and D)
/,
, / 2. Manufacturer's Quality Excellence Program and Other Procurement Documents
- 3. DOE 7A, Type A Qualification (Mound Report) 1
[4,. NRC Approval of QA I cogram for AGN Fuel Shipment
.< NRC-Approved QA Program for AON Fuel Shipment 1 /c'/ 6. Y-12 Plant Authorization To Ship l
- 7. Form NEL-111, Primary Container Loading Procedure and QA Checklist: UU AGN 1/1
- 8. Form NEL-112, Primary Container Loading Procedure and QA Checklist: UU-AGN-2/1
- 9. Form NEL-113, Primary Container Loading Procedure and QA Checklist: UU AGN-3/1 O'[/3 0. Form NEL 114, Shipping Container Loading Procedure and QA Checklist: UU AGN-1
[jff 11. Form NEL-115, Shipping Container Loading Procedure and QA Checklist: UU-AGN 2
. /4 2. Form NEL-116, Shipping Container Loading Procedure and QA Checklist: UU AGN-3
/
/ ,3 Form .NEL-117, Hazardous Material Shipment Checklist and Transfer
, // 1 Form NEL-118, Hazardous Material Shipment Checklist and Transfer
- 5. Shipping Papers -
[ . DOE /NRC Form 741, Nuclear Material Transaction Report Form reviewed and appped b - Director, UUNEL: I_ / '/ Date: .9 8/ Radiation Safety 4 ~- ./ A56 Date: 2/f*/7/ Reactor Administrator: j d /' / 2 Date: 2 - F ~ 7/ F3
i Form NEL.ll7 AGN Fuel Shipment i llazardous Material Shipment Checklist and Transfer l 1 Date- Mfb/ Shipment No.: ZWW FZF - 1 Shipping Container Identification and
Description:
UU-AGN-1 and UU-AGN-2 (two nackagesh USA DOT 7A. Tvne A (DOT Spec.17H. 55 gallon steel drumsh Gross Weicht: 75 lbs. each package Contents: UN2918: Radioactive Material. Fissile. n.o.s. Carrier: T5.m.T ~ Vehicle No.: # 'I74 Y 949W( Driver: ~/Tno b L. S,S Current Chauffeur's bcense: 4 Cl 7 f 6 / 4 7 0 Check. Comments: . Review Of Physical Security Plan: 7 Medical Cenificate: 7 Special State Permits: [ To be obtained by driver Carrier Certificate ofinsurance: 7 Driver Logs: / Placards: Exclusive UseInstructions: [/ . Emergency Response Instructions: / Tie Downs / Blocking: / Final Post Loading Radiation Survey: / External Radiation Survey of Vehicle: / Bill of Lading: / Shipping Papers Signed: / Consignee Notified and , Authorized to Receive Shipment: /, Vehicle Seal No.: 1397/7 kd V Comments: 49 6 l'M O'"' Final Inspection: .
'A//g.le i /.50 Daemme: 2/r/4//.bo_,f Material Transfer: e s Material Re1 eased By: o//k sW'a Vf Duemme: 8 W G/ */6i70 A5 Material Received B -
?hfYk Daemme- Y 'E Y/ o?:52D AN =
Campus Securityhgeorty'dySw.dd[ Fom1 reviewed and app d by. j . Director, UUNEL: ( # A Date:[M8 Radiation Safety Offi /NN I [_iB . . Date: 1/f/4/ Reactor Administrator: / / ps Date:,jr- y - % F4
- Form NEL-Il8 AGN Fuel Shipment Hazardous Material Shipment Checklist and Transfer Date: 9/ , Shipment No.: ZWW - FZF - 2 Shipping Con:ainer Identification and
Description:
UU-AGN-3 (one onckace): USA DOT 7A. Tyne .A (DOT Snee.17H. 55-callon steel . drum): Gross Weight: 75 lbs. Contents: UN2918: Radioactive Material. Fissile. n.o.s. Carrier: % - JIit. IMdu LsN TS H1T"' ~ . Vehicle No.: 2 Y 5' / WPMP Driver: bt fL tb s Current Chauffeur's License: #. c _ f / ~1/07 Check: Commentn . Review Of Physical Security Plan: / Medical Certificate: / Special State Permits: / To be obtained by driver Carrier Certificate ofInsurance: / Driver Logs: 7 Placards: /' Exclusive Use Instructions: / Emergency Response Instructions: _/ Tie Down# Blocking: / Final Post-Loading Radiation Survey: / External Radiation Survey of Vehicle: '/ Bill of Lading: / Shipping Papers Signed: /- Consignee Notified and Authorir.ed to Receive Shipment: [ ~I Vehicle Seal No.: 7W7C LM Av Comments: 942.6 5M An Final Inspection:
/-
8I-280. Date/ rime: 1/ Sl% pi a t ! Material Transfer:
- /
Material Released B " Mm /[ // V Date/ rime: 6 8['/6F#57 Material Received B Nb Md Iuo Date/ rime:4 -06 '7/ 4 M M # Campus Security E [ m[A 4[' Form reviewed and ved b - - l Director, UUNEL: Date: I h
;_, RadiationSafetyOf e /$m / ,
Date: _3 r-/or Rextor Administrator: - / , -
/ MI# Date: 2 ~ @ f/
.F5
- 2. Fuel Transfer Forms The following forms are included in this section, Uranium Scrap Declaration ID 1, DOFJNRC FORM 741 Nuclear Materials Transactions Repo't, correction to DOE /NRC FORM 741, and the Bill Of Lading of the fuel shipment.
d i F6 l i
^ --
. - _ - -: ~- - - -
v United States Department of Energy . RECbiVcD REcuEsf c0. Oak Ridge Operations Office RE0 VEST FOR URANIUM SCRAP DISPOS 1 TION mT o q NgG i SECTION 1 * (TO SE COMPLETED BY SCRAP CENERATOR) 1 N (1) PREPARE IN QUADRUPLET; RETAIN 4TH COPT AND FORWARD THE ORIGINAL AND 2 $ltfeOWAtl6D4NMMdlWWFICE ADMIN!s THE SCRAP CINERAT!kG CONTRACT. 5' (AN ADDITIONAL COPY 5HOULD BE PREPARED & FORWARDED T FFICE HAVING JURISDICTION
? OVER THE CENERATING $$ ACCOUNTABILITY STATION VMEN DIFFERENT FROM THE CONTRACTING .
OF (2) IT !$ lHPEuTIVE TNAT A CCpt!TE AND CONCl3E DESCRIPT!CN CF THE S* RAP II FURNISHED WITN EACH REQU!5T. FCRMS CR i!!C lA AND CR*6583 MJsf BE UTitlIED FOR THIS PURPOSE. tU SY DLCLARAT10h NUMBER IN BLOCE 3 04, THll FORM. COMPLETED FORMS OR*658C AND 04 638D SHOULD BE ATTACHED C FORM CR*6588, URAN!UM $ CRAP SHIPPING DATA, $HCULD ALSD BE COMPLE!ED AND ATTACHED TO THIS REQUEST FCRM. .l 7 07 65!B. ANT WUM81R OF SCRAP DECLARATICNS MAY BE MADE B7 UTILIZING THE SAME FORMS C I, I (3) IF A NECATIVE STATEMENT 15 INDICATED FCR ITEM 4 SELCV, ClVE FULL DETAILS ON REVERSE $10! 0F THIS FCRM. N
's j1.T0: 2. FROM: .
U. S. Department of Energy University of Utah l OAK RIDGE OPERATIONS OFFICE PC$7 CFF*CI BOR "E" Dept. of Mechanical Engineering i car RIDCE, TENNEss!! 37E3: MtB 3209 ATTN CENTut stuP uuCE ENT erF!cE Salt Lake City UT 84112
- 3. oECLARATION uuMsEts ATTACHtD; ID-90-1
- 4. SCRAP 13 AVAILA!!E FOR IMw!0! ATE El.IVERf TO A REPROC!SscR. o YES o NO QECU!$ TOR HERE3Y Citi!FIES THAT TXE SCRAP CCVERED BY THIS REQUEST WILL 8E IN Cour0RMANCg wgTH AL THE #EQUIRED $w!Po!%: CATA ARE O!TA!LIS ON FCR4 C#-55*3 VWICH MAS 8EEN ATTACNEC NERETO.
- 5. DATE April 27,1990 6. s!CuTuRE 05 REQUESTOR 7. a=E AND T!?LE SECTION !!
M[M CONCURRENCE OF COCNIZANT DCE OPfIAT!Oks OFi!CE Uni er Reactor Assist. Pr: THE CESCRIPTIVE ANO Att OTHER OATA CN ATTACHED FORMS 04 4588, OR 658C, OR 6580 NAVE BEIN CNECK!C AND RE* VIEWED FOR COMPLET!NES$ AC ACO 'RACT. C.8 TFE UAAN!Uw Tf.:s OFFICI h!RERY CER*;FIES 1:tAs0VER sy Th!s s!:;EST. THAT OCE MAS ThE F1NANCIAL RESPON3151LITY FOR THE RECOVERT AND/OR
- 1. DATE
- 2. s!' 'ATURE
- 3. eCE OPERATIONS OFFICE P/0*iG A ', [g S&.W Branch Idaho Operations Office
!!C":0N
!!! - FOR USE SY THE C5"O IM RIP' YINC TO COCN!2 ANT ERDA CPERAfidNS OFFICES SIIGHTLY IREADIATED MATE:IIl The traniule scrap described in Scrap Declaration No. IL-S1 should be shirped to th Oak Ridge Y-12 Plant for rec 0very. Y-12 should receive the rRaterial in Project No.
F-GE-0221-05C. Please call D!.xie Bo'p p at TfS 626-2506 Courtesy copy of the 7h1 doc:: ment should be sent to John Miller, ORO-CfMO.for an auth l CC: A. Tdng, T-12 ; D. Bopp, T-12 ) l l cATE
. I' 0 10-1-90 ****
John H bhh 11er ORO-rafO bRM Ob 658A (REY. 3/T5) F7
- l
.j
United States Department of Ettergy SHIPPING Help 00 CODES' Oak Ridge Operations Office . URANIUM SCllAP SIIIPPING DATA A - C0rWERCIAL WHICIE (ARMD ESCORI) . 4 { B - Ct2MERCIAL VfulCl[ (LIL) _ C - COVERNMENT WNICit (AthED ESCORI)' 0 - Offl[E Melit 005 (SPTCiff IN REMARKS)
'DECLARA!!ON NO. SHIPPING C0515 TROM Pat $ TNT 10CAI!ON Of SMIPPlHC NUMBER OF SulfMN15 AkO/OR SCRAP IO: tMMn[R OT SillPPING '
69tlH00 REutilRID TOIAL NO. IRANSPORT SCRAP LOT NO. 00NIAINERS/5HlfM NI CODE INDEX LMIf$/SNIPMENT ERulN, IM. GAC RIDCt, IN. UEsitatY, R.I. Fl5SilE 15 fissitE lit fl551tE Il flSSil[ I!! fissitE Il FISSitE Ill 10-90-1 $250 0 m
= , ._
T L
--. b I
REMARKS 0 = Commercial Carrier
oint . cit-65o n : ( st W ~i/7ti) ,
United States Department of Energy Oak Ridge Operations Office 1. LOCATION OF_ SCRAP RIS:. 2 g g fi8p8 80-
,ygs,nr dtv nr utah _
zw sate 1- or 1 URANION SCRAP DECLARATION 3. SECURITY CLASSIFICATION OF SCRAP B UNCLASSIFIED o
' 4. SMIPPlue CoWTAlWER oATA (to4Dfo)
CONFIDENTIAL BY a SilAPE o COMPOSITION ,
- 5. Palmany (INhta) CONTAINER DATA stalAL TYPE stConIIV 6. SCRAP CODE, SNu CONTENT & CENERAffWG P90 JECT immets toot Gaoss WT !IDENfirl- TYPE trat no. (PouNost tation no. coor _
1KfGHT (GRAMS) ANSI GRAMS caoss TAat wtr WT. E CEAMs PROJECT W-AQ1 1 F CODE LNtAttitM U-235 U-235 200 Max. 20481 3 utseBER 20474 " W4 148.7* 19.5 29.0 492.3* " g g k) 20475 "
" 96.0 492.3* " "
W-AGi-2 F 200 Pbx 20470 3 O 20442 " C04 148.7* 19.5 29.0 4~ 20476 " 492.3* 96.0 W-AQ1-3 F 200 tbx 20478 3 20473 " / w4 297.4* 19.5 58.0
;" a " "
20469 ' 20386 " 20395 " 18.5 " 3.6 1 20391 " y " " c 20387 " 20393 " l " " 20389 ' 20394 "
" l " " " "
20390 " " "
? " "
20388 " " "
" a I 20392 " " "
" a 20396 " "
l " ." " 20385 " " " " l t i ,
, coNialmens TOTAL WEIGNT _ n l
3 CONTAlkERs l 21 TOTAL NET WT. ',' loIAL U
} SHIPPING CONTAINER TYPE CODE i
3380.8*_ AVERACE 19.'i TOTAL Ut35 659.2 N['h f Mb" % PRIMARY CONTAINER TYPE
-l oot-a (55 sat > A CODE I 7. REMARKS i i or PtAst:C aorite oor a (sto cat) 5 t *G51ailated values 2 Or PLASTIC DOTTLE !ooren(55 GAL) 2 C
PLA5flC BAG OR utAPPING
?
F = 6J or 1711 Dr7I' spec. - 55 gal. steel
!(oot-on(110 SAL) o 3 i druns ullh 3 iners.
a 2 statto netAt CAu not-se (sesciar su stoct 73 4 e i (Tc a (sPactry su stocr 73 a 3 ne tAncta sirro nerAt CAu 5 e i ornca (sPecary su stoct 73 6 5RM-OR-658C (REV. 3/78) 1 CSM0?iOT!N0! n S f F M dli n if n N ?d N Mi
~
,. r - _ - - . - -
i - - - . - - - - - Unitcd States Department of En:rgy
-l Dak Ridge Operattens Office DECLARATION NO. ._
- t. ID-90-1 ,
I DESCRIPTION OF DECLARED URANIUN SCRAP SilEET I 1 l . SHIPPING CONT. 0F . PRIMARY CONT. i SERIAL NO. I. D. NO. ' i SCRAP DESCRIPTION UU-N21-1 3- AGN Reactor core fttel diska: right-ciroslar cylinders of 25.6 on diarreter. Fbel is 19.5% enriched ID2 particles lxrangenconsly dispersed in iiolyethylene. h #20481: 1 cm thick, total disk mss = 652 g
#20474: 4 an thick, total disk mss = 2157 g l
#20475: 4 on thick, total disk mss = 2164 9 UU-N24-2 i
3- AGN Reactor core fuel diska: sanie description as alrne, i
#20470: 1 on thick, total disk mass = 657 9 l
#20442: 4 on thick, total disk mass = 2051 g
#20476: 4 cm thick, tot.a1 disk mss = 2065 g i
UU-M21-3 i 3- AGN Reactor core fuel disks: same description as alove.
#20-178: 2 an thick, total disk mas = 1267 g
//20473: 2 cm thick, total disk mas = 1269 9 3 #20469: 2 an thick, total dink mss = 1273 g o
I 12- NN Safety and control rcxl ftiel disks: right-ciroslar cylirxler of 4.7 cm dia-
~l meter and 4 an high, each disk is 79 g.
honogeneously dispersed in polynthylene. Fuel is 19.5% enriclwxl 102 [nrticles
//20386 #20395 #20391 i #20387 //20393 #20389 l #20394 #20390 #2038fl .
'#20392 #20396 #20385 ,
I i I 8 tusinuctionsi ine onctanaitos insesa snown su Tu urren a cur mAmo conute or inns toRM REMARKS i snoute se ins sAme muneen As TuAT snoww on fu countsronoina rann on-6sec. in suireine Amo retnnar comintwas snoute sE LISTED IW ThE sAME SEQUENCE As LISTED IW TM CoRREsPON-gDl#G
, Anoumisr0AM enEsEmi 04-454C. iE : CRAP um must DEsullPil0W teJsf IDEWilrY innierr in entsicat Diensions Att KNOWbt CoNsil:UENTS or att siExs ofunCSM inAwofrowres MAME AND M * FM N 1
- t na i nautne w y01 ,!- LOT
"&*- ,0 r%W<n sy~jg##">- e A;O ';p'*;
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- 3. Fuel Transfer Corresoondence List !
During the shipping procedures the following personnel were involved with the shipment of the AGN-20lM's fuel. These People were j J. H. Miller Oak Ridge Operations Office l CSMO ' P.O. Box 2001 Oak Ridge, TN 37831 M. A. Thom EG&G Idaho, Inc. : P.O. Box 1625 l Idaho Falls,ID 83415-3126 ; Adolphus King . Martin Marietta Energy Systems, Inc. i P.O. Box 2009 ' Oak Ridge, TN 37831-8169 Bob Berry EG&G Idaho, Inc. P.O. Box 1625 Idaho Falls, ID 83415-4113 A. J. Vinnola, Jr. EG&G Idaho, Inc. Fuel Manager P.O. Box 1625 Idaho Falls,ID 83415-7112 F16 --
Aooendix G: Survey Results The following are the results of the suneys conducted during the decommissioning of the AGN-20lM reactor. Included in this appendix are the survey results from:
- 1) Preliminary Defueling Surveys.
- 2) Concrete Block Surveys.
- 3) AGN Water Survey.
- 4) Thermal Column Survey.
- 5) The Fuel Surveys.
- 6) The Core Component Surveys.
- 7) Facility Survey For Continued Decommissioning Activities.
- 8) AGN Component Surveys. J
- 9) The Surveys For Parts To Be Released For Unrestricted Use.
These different sections will allow easy identification of the parts of the reactor and the final disposition of those parts. i l l G1
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- 1. Preliminary Defueline Surveys i i
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University of Utah Nuclear Engineering Laboratory AGN-20lM Decommissioning Project Concrete Block Surveillance Procedure 1 Introduction I This report details the procedure to be followed during the removal of the concrete block used as shielding for the University of Utah Nuclear Engineering Laboratory (UUNEL) AGN-20lM nuclear reactor. The removal of the block is a necessary first step in the decommissioning process of the AGN reactor. Surveillance of the block is required to preclude the release of potentially contaminated material from UUNEL. This procedure has been developed by the staff of UUNEL in collaboration with and the approval of the University of Utah R
' adiological Health Department (UURHD) following guidelines established by the -
U.S. Nuclear Regulatoly Comnu,ssion. Safety Considerations The removal of the concrete block requires transferring the block fro,a its present location onto wooden pallets while monitoring the block to assure contaminated block is not removed from UUNEL. It has been estimated that there are approximately 5700 block enclosing the AGN reactor as shielding. Moving such a large number of blocks presents a great potential for injury to personnel and laboratory equipment. Therefore, at any time work is in progress in laboratory, the safety of personnel must be of primary concern. Carelessness, horse-play, and unsafe arocedure will not be tolerated of the personnel engaged in the block remova and surveillance project. In addition, the overhead crane is not to be operated without the pernussion and/or presence of UUNEL staff. Furthermore, the TRIGA reactor tank will be covered with plastic shecting whenever blocks are moved to pn vent contamination of TRIGA tank water by concrete dust. General Procedure The block will be monitored with portable survey meters, viz. Technical Associates Model TBM 3S " friskers." Readings will be made such that the bottom surface of the detectoris nominally one inch from the surface of the block. In order to reduce variability in the readings, only one person will be allowed to perform the survey portion of the procedure per shift. The survey will be performed during the transfer of block onto the pallets as follows. Each pallet is to be loaded with five to seven layers of block (depending upon the lifting capacity of the overhead crane and other safety considerations) with-each layer compnsed of 15 blocks com?actly arranged. The first stage of the survey involves passing the frisker over 15 alocks (i.e., one pallet layer) in situ. 'Any blocks with readings found to be in excess of the maximum allowable activity will be marked and set aside for retention within UUNEL. Blocks with an acceptable G6
7 activity level, which is defined in the next section, will be loaded onto the pallets in such a way that the surface of the block which was surveyed in the first stage is placed face down on the pallet or previously loaded layer of block. 'Ihe second stage of the survey therefore involves passing the frisker over this surface of the block; any blocks with readings in excess of the maximum will again be marked and set aside. Following the loading of each layer, a record will be made on the special survey form prepared by UURHD (see attached sheet) in which the pallet number, number of block, maximum reading (in cpm), and the number of blocks set aside are recorded. In this manner, individual pallets will be loaded. Plastic sheeting will be used to cover loaded pallets to pmvent accidental contamination. A radiation safety technician from UURHD will be contacted to perform an independent survey of loaded pallets to verify and assure blocks exceeding the criteria of acceptability are not released from UUNEL. Upon completion of the block transfer and surveillance, and the final independent survey by UURHD, the sealed utility door located on the west wall of the reactor room will be opened to allow for the removal of approved block. The overhead crane will be used to aid in the transfer of the pallets from UUNEL onto - flatbed trucks. Following removal of the loaded pallets, the utility door will be resealed as quickly as possible to minimize TRIGA reactor downtime. Steps will be taken to assure adequate security of the UUNEL during the entire period the utility entrance is breached. Acceptable Activity Limits The criterion for the rejection of concrete block as contaminated material as recommended by the Radiological Health Department is a measurable count rate in excess of twice the average area background count rate on the day of measurement. The avemge area background in the vicinity of the present location of the block runs between 100 to 150 c?m on the TBM 35. Blocks exceeding a count rate of 250 cpm on any surface will be rejected as contaminated material. These blocks will be marked and set aside. Blocks with a count rate at or below 250 cpm will be stacked on pallets and will be removed from UUNEL. ; Final Discosition 1 Once the blocks have been surveyed, and only those at or below the acceptable activity limit have been transferred onto pallets, they will be subjected to a final survey to be performed by UURHD. Following approval by UURHD that the block meet the criteria of acceptability, the block will be transferred to the University of Utah Broad Form License No. UT18-00001. The block will subsequently be released from UUNEL to a preapproved contactor for final disposition. l l G7 d
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Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning Meter used: /b Il 8 Serial #: 6I7/2 d , Bkg for meter: iC O cpm Calibration Date: .- WJ' / Mark for Maximum Reading Number Set Aside Palet Number of Blocks (cpm) (above background)
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b Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning Meter used: 70A1-33 Serial ff : C87 /SL7 Bkg for meter: / y/) cpm Calibration Date: Q // 9 / P 7 _
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Mark for Maximum Reading Palet Number Set Aside Number of Blocks (cpm) (above background) l R0 220 0 L 90 23 0 0 3 , 40 IC/0 or zu o emmenusee I 6n. l l SURVEYED BY: 61/l f '/ bD(( $ !TV ' DATE: f I /k 7
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Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning Q Meter used: ~7~SN - 3 $ % Bkg for meter: / 57) cpm Serial #: dSF7/2@ Calibration Date: (1/l_f/,9) N. Mark for Palet Number of Blocks Maximum Reading (cpm) Number Set Aside
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Special Form for Concrete Blocks Survey ' for the AGN Reactor Decommissioning Meter used: 'TA N - 3') Serial #: _C421629 Bkg for meter: #6 cpm Calibration Date: ci f 6 - fa G Mark for Maximum Reading Palet Number Set Aside Number of Blocks (cpm) _(above background) (%' 4s Iso & L1 r;
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Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning Meter used: Tf6M-86 Serial #: 68;'l l ??/ 4 Bkg for meter: ,/fy7) cpm Calibration Date: Cf -l6-b ? l Mark for Maximum Reading Number Set Aside Palet Number of Blocks (cpm) (above background) I3 l, N l} IUh h u Ls IV I UD p Nt/s lT + tt yJ l 6 6 g Y' Yl 15 ll/O P
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Special Form for Concrete Blocks Survey for the AGN Reactor Decormnissioning Meter used: hNdhcpm Serial #: ,) ' Bkg for meter: ff) Calibration Date: 6//l9/h) Mark for Maximum Reading Number Set Aside Palet Number of Blocks (cpm) (above background) {f Y 9 b1 I6 (90 O LL
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Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning Meter used: f'3 Serial #: O f') / 2 9 Bkg for meter: /f) cpm Calibration Date: J7/15/D Mark for Maximum Reading Palet Number Set Aside Number of Blocks (cpm) (above background) O l$ 17 0 g2 Ig W IS '\0 6)
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1 Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning Meter used: T A ,vl - 5 Serial #: 6 b' 7 i A #l Bkg for meter:_fy) . cpm Calibration Date: C/, f if f A 'l Mark for Maximum Reading Palet Number of Blocks Number Set Aside _(cpm) (above background) Ih f( )T ')C. ([lI !Y (W .O l) ir NO S (9 . LS ,c WO & n ,r ibo @ - 3 is ISO @L , N(Lv 'S l(39 y b l I SURVEYED BY: [<
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Special Form for Concrete Block Pallet Survey ' for the AGN Reactor Decommissioning Meter used: T/ WN Serial #: bb /hY ! Bkg for meter: @ /Or) cpm Calibration Date: 6 /tf Averaged beta detection officiency: ,D l (counts / disintegration) Pallet Side Monitored Maximum Reading Number Facing: (cpm) it i G bo el4 g 10 0 P4 b9 /Oc 64 v1 /CD 05 E lo
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Special Form for Concrete Block Pallet Survey-for the AGN Reactor Decommissioning Meter used: Th h!)N Serial #: Ob6 //M Bkg for meter: 190 cpm Calibration Date: 0 !M @ Averaged beta detection officiency: M (counts / disintegration) Pallet Side Monitored Maximum Reading Number Facing: (cpm)
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1 Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning , Meter used: / l" Serial #: OO /2. i Bkg for meter: /60 cpm Calibration Date: 47 //S /[7 1 Mark for Maximum Reading Number Set Aside l Palet Number of Blocks (cpm) (above background) LI 15 )60 & LL (G tro V C3 /5 /70 g LL/ y( ll(y gp Q l s is ;zo p R$t g ax-I s- />o f9 E LI I5 (2 2 9 8% a ,: ,u g
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Special Form for Concrete Block Pallet Survey for the AGN Reactor Decommissioning Meter used: [Mkh U Serial #: _ d$h //eY Bkg for meter: /Bu cpm Averaged beta detection efficiency: Calibration Datei 6!K fff
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i Special Form for Concrete Block Pallet Survey for the AGN Reactor Decommissioning Meter used: T/>W4$ Serial #: OM/0d i Bkg for meter: /']n cpm Averaged beta detection efficiency: Calibration Date:
, S'F 6/2(ff[
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Special Form for Concrete Block Pallet Survey ' { for the AGN Reactor Decommissioning Meter used: h5 Serial #: OL(, /s,/ Bkg for meter:go.t4o cpm Averaged beta detection efficiency: Calibration Date:
.47 4[offII j (counts / disintegration)
Pallet Side Monitored Maximum Reading Number Facing: (cpm) to N l% 4v6 20 W i24 e 5 b
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I Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning Meter used: >/ -35 Serial #: < /2 7 /2 9 Bkg for meter: '1// cpm Calibration'Date: / ? /J/ , 'h9 Mark for Maximum Reading Number Set Aside Palet Number of Blocks (cpm) (above background)
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Spacial Form for Concrcto Diocko Survsy for th3 AGN Rocctor-Dscommic31oning l Meter used: T 6 el 3 S Serial #: C 8 '7 1 'l 9 Bkg for meter: cpm Calibration Date: I t / i e / s. 7 Mark for . Maximum Reading i Number Set Aside Palet Number of Blocks (cpm) (above background)' flF FO O O I S' 00
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Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning Meter used: 7dit1D Serial #: 86 6 / 6 / Bkg for meter: 90 cpm Calibration Date: (#/25-!f-)- Averaged beta detection efficiency: <48 (counts / disintegration) 1 Mark for.' , l' Maximum Reading Number Set Aside Pallet Number of Blocka (com) (above background) <
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- r. i s i Special Form for Concrete Blocks Survey for the AGN Reactor Decommissioning Meter used:_ TT5 nA 35 Serial #: 092332 Bkg for meter:_ 50 cpm Calibration Date: I/9/86 l
1 Averaged beta detection efficiency: .20 (counts / disintegration) l i kMark for Maximum Reading Number Set Aside
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c Special Form for Concrete Blocks-Survey for the AGN Reactor Decommissioning Meter used: [dM 3 $ Serial #: OM /M[" Bkg for meter: M) cpm Calibration Date:' 6 /,77/[9' Averaged beta detection efficiency: /d7 (counts /cY1sintegration) Mnrk for Maximum Reading
,Pn11et Number of Blocks (cpm) Number Set Aside
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- 3. AGN Water Survey
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AGN Water Sample 1S/89 Background j 46764 Water 1 - 47278 2 - 46025 3 - 46732 2 46388 4 - 46407
Background
45834 46246 46040 net = 348 Activity = 343 = 0.56 nCi/l 533 m : f JNS. Bennion G29 i l 4
1 l Analysis of AGN Shielding Water September 22,1989 Counted sample of water from AGN tank on HPGe detector for 30 minutes. No observable photopeaks besides Co-60 and Mn-54 background and K-40. Sample was taken on 9/2/89 and counted the same day. _
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I THE UNIVERSITY. J
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J Memorandum 26 February 1990 4 To: Gary Sandquist, Director - Nuclear Engineering Laboratory. From: Byron Hardy, Health ~ Physicist , Radiological Health Ret Survey of AGN thermal Column On 23 February 1990, I performed a spot check for evidence of _ residual contamination on the lead shielding (bricks) which had been removed from the AGN reactor. Using a ' calibrated TBM-3 contamination survey meter I found no detectable . radioactive contamination on. bricks originating.in the AGN reactor. *
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1 . . _ , , , Radiological Health Department
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100 Orson spencer Hall
. Salt Lake City. Utah 84112 (tt01) 5816141 G32
- 5. Fuel Surveys b
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m. Ra Be Neutron Source 5/17/89 - Moved source container from shielded location on upper level of reactor room near AGN to lower level against the TRIGA tank in the NE comer to provide shielding. Concrete blocks were placed around container to prevent access to the hot spot where surface radiaton dose is approx.120 mr/hr. Radiation levels were as follows: Max surface dose of concrete shield: 3 mr/hr Max dose at three feet: Max dose on tope surface of shield: 2 mr/hr The movement of the source was recorded by the EPA's PIC detector. Before movement , the reading was approx.16 r/hr. (Normal background is approx. 9.8 - 10.4 pr/hr) Transfer of the container by crance to the lower level resulted in a spike which decreased as the source was placed on the lower level. (Background reading regained) The lower level provides much mon: shielding as the line of sight to the detector must pass through the foundation, ground, etc. When transfened behind the tank, the PIC reading was back to normal. Leak Tested 8/22/89 - Nolan Smith RHD Nb o S."Bennion
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FwmHEIA01 RSC Approvsh $/2548 AGN COMPONENT RADIATION SURVEY RECORD ICRM - Survey Form #: Survey location AGN Reactor. Nuclear Engineering Lab. Survey Date: gx2y/g) TTEM SURVEY SURVEY GROSS NET NETd= mrem / hour (a surfami NO. GENERAL DESCRIIrTION INSR(3) TYPE (4) cpn epn 100cm2 cx 5 7 Total
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3 y .ac N I .2. D / 6 '*#d< B// 3 3 0 2M89 pr161 3 W104>w 3 3 hfA b2,1 b3 'fto N'"' u%d+u DETECIVR USED: REMARKS: (1) Backgromd counting rata at /2Cf At 613 (locatim) was: cpn = dpm = micrnAr. (2) Background counting rats for this instrummt was: cpn = dpm. "Ihe 11D at 95% cmfilmce level was: net dpm = ne pCi. No wipes wipes showed removable contamination above the LLD, except from the following items: x W44rmf s t%g>n. 01 habjverwcA' 04 ^ $ (3) SurveyInstrument Codes: TAGM = Technical Associates portable G-M with pancake pube (thin window): Serial #: 66 7/ A9 Catits ation Date: /lz3/d'l Other::=ltxclW /tfedt.A /9 # T170 & ^7/28/69 3*/ L U-Whh iWdd $3-) $*fA'02:3% (4) Survey Type Codes. D = Direct Survey over the entire surface of the object. WA = 100-300 cm2 wipe camted with an alpha detector. WG = 100-300 cm2 wipe counted with a portable G-M. WL = 100 300 cm2 wipe counted with a liquid scintillation counter (311). WGS = 100 300 cm2 wipe counted with a gam.ns spectmmeter. SURVEY PERFORMED BY: ([/ M hA G37 .
-l PenaNEL 101 Rsc Approvah 5/25/ss AGN COMPONENT RADIATION SURVEY RECORD PORM Survey Form #:-
SurveyImtion AGN Reactor. Nuclear Eneineerine T 2h. Survey Dale: 6/zv/M 9 nEM SURVEY SURVEY GROSS . )Er NET h mremA-(a =wfM NO. CENERALDESCRFDON INSTR (J) TYPE (4) cpm cpm .100 an2 a 8 y Total s H t but 'mk ( .;r/ a o m .2. p /t m aj%r M J t/ 5 O Mt36 STtk %290 dpw n Lj ] Wh gy 74 ' j1gi &fJ wg,,a p ava, o-5 C er e fcts ' D- D w ~R/G B>f S~ * ' 3 O Tbo21 flo71- 801CO ch> r WA 3 6,i c,b3 953 +/usia. wsu . ' DETECTOR USED: REMARKS: (1) Background counting rate at (locanen) was: , cpm = . dpm = mrundir. (2) Background conting rate for this instrument was: q _ epm = _ apm. The LLD at 95% conrulence level was: net dpm = net pCi. No wipes wipes showed removable contaminauon .j above the LIE, except from the following items: 1
=J (3) SurveyInstrumera Codes:
I TAGM = Tecimical Associates portable G-M with pancake probe (thin window): Serial #: Calibtstion Date: Other- ) (4) SuivoyType Codes: , D = Direct Survey over the entire surface of the object . ! WA = 100-300 cm2 wipe counted with an alpha detector. j WG = 100-300 can2 wipe counted with a portable G-M. 1 4 WL = 100 300 cm2 wipe counted with a liquid acintillation counter H (3 ).
~ WOS = 100 300 an2 wipe counted with a gamma spectrometer. , !
I SURVEY PERFORMED BY:- C b -~ i 1 G38 . m
Pesm NEL.101 : RSC Approval:$/25/B8 AGN COMPONENT RADIATION SURVEY RECORD PORM Survey Form #: Survey Iecation AGN Reactor. Nuclear Engineerine 12h. ~ Survey Date: e/Xh9 TEM SURVEY SURVEY GROSS NET NET h ,,mremhw (e ==fM NO. GENERAL DESCRIPDON INSTR (3) TYPE (4) cpn cpm ' 100 cm2 a 8 7 . Total Sc-z n ul Ont. I 4 aog?3 c2/ D /T '*V/w $fy I ^ 3 D 2 3 Nk 2519f 38080 cigm. t 3 h/d ll29 III] . Ibl6 fmpQ d gwp,u_.
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3 O JJY>7I 218 toy 3eif30 cf>m a 3 h/A SW1 STO 787 dyn/aAh Ma.e sa-2 FwA ont 3 $t 205% .2 D /6 "Vlw (2iY 3 5 o ano svn nao 6 3 3 NA 139 932, 767 W 5n4C / swfact DETECIDR USED: REMARKS: 4 (1) Backgromd counting rate at /Ao C M E/4 (location) was: cpm = dpm = nrem/br. (2) Background counting rate for this instrument was: cpm = dpm. The 11D at 95% canradence level was: net dpm = net pCi. No wipes wipes showed removaNe contamination above the 11D, except from the foDowing items: tv Z,utlagm 7cp
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(3) Survey Irstrw..ere Codes: TAGM = Technical Associates portable G-M with pancake probe (thin window)c Serial #: Calibration Date: Other: .;n > Ladk hiedd l9 4 2950 ca), 7/28/91 3* l-~W o& Mhl.lMarhjnd>t. hulef y) / 4 fd2l:C;t
- (4) Survey Type Codes:
D = Direct Survey over the entire a= face of the objea.
- WA = 100 300 cn2 wipe counted with an alpha detector.
WO = 100 300 cen2 wipe counted with a portable O.M. .; WL = 100-300 cm2 wipe counted with a liquid sciraDistion counter (3HK 4 WOS = 100 300 cm2 wipe counted with a gamma spectrometer, SURVEYPERIORMED BY: ( '/ ado _u j __ v - 4 G39 . 7 +- h+.,, - , , , . Em
. 4 . - . _- -. - _ _ . _.. . ._. .
4 FaanNEb101 RSC Appe,at: 5/25/88 AGN COMPONENT RADIATION SURVEY RECORD PORM Survey Form #: Survey Location AGN Reactor. Nuclear Engineerine i A Survey Date: B/2r/!O TIT.M SURVEY SURVEY GROSS PEr NET h mramA~- fa antam) NO. GENERALDESCRDTION INSTRM) TYPEM) cpn cpm '100am2 ,a 8 7 Total . 512-Z Fiuk vat 5 t 4 se aonc, 12- D IT~"//w19 (Y y 4 3 D .2 /410 . u2/483 30YlO dpm . Y 3 DVA /232 /227 /U 3 dp n/g,44,3g4g Cca a M fsak M f it .20 9 8 8 .2 D l6 4'w t 6IT . 6 f 3 D M73') .2473A 3573odpm ( " 3 wp nt 94y M9 4""/& wrAu Ce a M rutbat b 4 ao M ,;z D , Ib"'#bvfkt h 3 D .2229o 2218'5 360 dem b 3 WA 48*1 Y8o W1 4~ /aksdna DETECIDR USED. REMARKS: (1) Background cointing rase at (location) was: cpn= dpm = mrern/hr. , (2) Background cotating rate for this instrument was: _ epm = dpm. The LLD at 95% confulence level was: net dpm = net pCi. No wipes wipes showed removable contarninarian alove the LLD, except from the foDowing items: (3) SurveyInstrument Codes: TAGM = Technical Associates portable G-M with pancake probe (thin window): Serial #: Calitration Date: _ Other: * (4) Survey Type Codes: D = Direct Survey over the entire surface of the object. WA = 100 300 an2 wipe counted with an alpha detector. WO = 100 300 cm2 wipe coumed with a portable O.M. WL = 100-300 an2 wipe counted with a liquid scirsillation coumer (3H ). WOS = 100-300 cm2 wipe counted with a gamrru spectromew. SURVEY PERPORMED BY: I v vbu- > G40
, , , . , - , .. - ~ . . . - _ . - - - - -
i Pona NEL 101 RSC Approvat:5/25/B8 AGN COMPONENT RADIATION SURVEY RECORD TORM I 4
. Survey Form #:
Survey Location AGN Reactor. Nuclear Engineering Lab. Survey Date: _ ghr/69 TTEM SURVEY SURVEY GROSS NEl' NET dnm mremAmrIs surface) NO. GENERALDESCRFi1ON INSTR (3) TYPE (4) cpn epm 100 an2 a S y Total Luvu Mo faa thst 7 e .2 03% 2 D /r ~/V/w p7 7 << 3 0 xM3 486 <Nm d,nw
-) 3 WA 7ty 75 7 iix %hs h wha b c%ud%d 2038T fiud06L 2 D Ib'"Yw 0>1 0 **
') D v2b]/3. ALYDT YD480 dgm O '-
3 w /l 647 Ho Ho c4~/uAh w4ut DETECIOR USED: REMARKS. (1) Background countmg rate a (locatim) was: cpn = dpm a mran/hr. (2) Background counting rate for this instrument was: cpm = dpn. The 11D at 95% corAiare level was: net dpm = net pCi. No wipes wipes showed removaNe contami=% above the 11D, except from the foDowing hams: (3) Survey Instrument Codes: TAGM = Technical Associates portable G-M with pancake probe (thin window): Serial f: Calibration Date: Other: (4) Survey Type Codes: D = Direct Survey over the entire surface of the object. - WA = 100-300 cm2 wipe counted with an alpha detector.
- WG = 100-300 an2 wipn counted with a portable G M.
WL = 100 300 cm2 wipe counted with a liquid scintillation counter (3H ). WGS = 100-300 cm2 wipe counted with a gamma spectrometer. SURVEY PERR)RAED BY: - ME2 - - x G41 .
. . = . . - .= - -
s i AGN Core Surveys (Fuel) August 24-25,1989
- 1. Core Fuse
- 2. Safety Rod #1 (SRI)
- 3. Safety Rod #2 (SR2)
- 4. Coarse Rod #3 (CR3)
August 24,1989 Core Fuse #20110 6.8g fixed alpha 72104,40069 cpm removable 691,639,682 cpm Ludlum ct # PRO 2152 scalar # 33640 eff. Pu-239 = 69.5% p,y 12 mR/hr @ contact
#1:= TBM - 3S = 087129 a background = 8 cpm; ,y = 0.02 mR/hr ,
SR1; Order of removal.
- 1. #20386 wt - 79g.
~
removable (x 509,488,513 cpm = 724 dpm (entire surface) fixed a 28925,27884 cpm = 41620 dpm
#1 p,y- 18 mR/hr @ contact
#2:= Ludlum #7950 Model 19 calibrated 7/28/89
- 2. #20395 wt - 79g.
removable a 496,526,491 = 726 dpm (entire surface) fixed a 25263,24435 = 36350 dpm
#2 ,y- 16 mR/hr @ contact #2
- 3. #20391 wt. 79g.
removable a 658,610,625 = 910 dpm (entire surface) fixed cx 24885,21093 = 35810 dprn G42
- _s _*+ -_- .__- , _.-__-u
l l l
#3 p,y- 16 mR/hr @ contact #2 l
- 4. #20387 wt. 79g.
removable a 735,784,797 = 1111 dpm (entire surface) I fixed a 225224,25052, = 36290 dpm
#4 p,y- 16 mR/hr @ contact #2 1
August 25,1989 #2 back = 0.02 mR/hr a back = 7 cpm SR2; Order of Removal:
- 1. #20393 wt. 79g. -
removable a 1109,1118,1146 = 1618 dpm (entire surface) fixed a 20618,26465 = 38080 dpm
#1 ,y- 15 mR/hr max.@ contact #2
- 2. #20389 wt. 79g.
removable a 547,558,536, = 787 dpm (endre surface) fixed a 25391,18350 = 36530 dpm
#2 ,y- 15 mR/hr max.@ contac' #2
- 3. #20394 wt. 79g.
removable a 976,074,866 = 1350 dpm (entire surface) fixed a 24660,26145 = 37620 dpm
#3 p,7- 10 mR/hr max.@ contact #2
- 4. #20390 wt. 79g.
removable a 1195,1261,1241 = 1773 dpm (entire surface) fixed a 21440,21540 = 30990 dpm
#4 ,y- 16 mR/hr max. @ contact #2 Coarse: Order of Removal:
- 1. #20388 wt - 79g.
removable a 455,456,443 = 649 dpm (entire surface) fixed a 24831,24647 = 35730 dpm
#5 ,y- 16 mR/hr max.@ contact #2
- 2. #20392 wt. 79g.
removable a 463,513,486 = 701 dpm (entire surface) fixed a 25650,18930 = 36910 dpm
#6 p,7- 16 mR/hr max.@ contact #2
- 3. #20396 wt. 79g.
removable a 4759,778,756 = 1100 dpm (entire surface) fixed a 30960,27225 = 44550 dpm
#7 p,7- 15 mR/hr max.@ contact #2
- 4. #20385 wt. 79g.
, removable a 665,661,614, = 930 dpm (entire surface) fixed a 28134,25690 = 40480 dpm
#8 ,y- 16 mR/hr max. @ contact #2 back u = 8 cpm ,
,y = 0.02 mR/hr (#2)
[/ )h I A
'Johr(s.~Benniorf l
1
~
G44 ,
Pann NEL 101 RSC Appovat: 5/25/88 AGN COMPONENT RADIATION SURVEY RECORD PORM Survey Fcrm #: Survey Location AGN Reactor. Nuclear Encineerine Lab. ' Survey Date: '
/ '
ITEM SURVEY SURVEY GROSS NET NET <hn mremhtr (S aurface) NO. GENERAL DESCRD'I1ON INS 1R(3) TYPE (d) cpn cpn 100 can2 a 8 y Total j 7, y i, , , . '!:[ . "T'*k G/Vl 1) l n X l's ,
', , ~/
l ' l u b b'A m D . 2. -b C ,,x i iv'A 4 0 o a <. (su r;k - A a,pcJrf [l>i / be% O ,, IY an k, t o . i ~ s
,'1 '
,Z L t :.uf u i v. D 1+l11.24 l': 7 34 Lil.C
]
'.el b. ~ t,d d '>d 9l d
, Fw /> 5 L
') J/ ), d'1 I /_ 'l2 ; fx & ) / $ ntl!kt l
'$ ii l r,< .$ a j) /%$9 /G5' 3 ..![MO
", H iMA b'l L0 h .Q DETECIDR USED: REMARKS:
(I) Ba:kground counting rate at /k ' c ' a ' dC T (location) was: cpn= dpn= mrem,%r. (2) Background counting rate for this instrument was: cpn= den. The LLD at 95% confidece level was: net dpn = net Ci. No wipes wipes showed removable contamia=% above the LLD, except from the following items: 7,1cin r - Dic r o n d/h % .h c., w E. % %L , ci c, / md//,. L a< %m ,' (3) Survey Instrument Codes: y cp n TAGM = Technical Associates portable G-M with pancake pn>be (thin window): Serial #: OB 7 /41 Calibration Date: ' /2 7 /#N Other; (.2< tl l1 Lsn. ' l'Id02.11.1 la,t'h y, Sc n.f.I( +1 ffC'/c.) cts lne$ Lf < (4) SurveyTypeECodes:Mvl+n & f.> ~Z 4 :P /2.(; 3 (alduTL.27/tgl&l \ D = Direct Survey over the entire surface of the object. ) I WA = 100 300 crn2 wipe counted with an alpha detector. WG = 100-300 crn2 wipe counted with a portable G.M. 1 i WL = 100 300 cm2 wipe counted with a liquid scintillation counter 11 (3 ). WGS = 100300 cm2 wipe counted with a gamma spectrometer. I SURVEY PERFORMED BY: h. Lsvb ^ G45 ,
Forma NEL 101 RSC Approvat:5/25/B4 ' AGN COMPONENT RADIATION SURVEY RECORD PORM Survey Form #: Survey Location AGN Reactor. Nuclear Encineering iih. Survey Date: c: / L /*'t UD4 SURVEY SURVEY GROSS NET NETdpm mrem.hur (e nrfanel NO. GENERAL DESCRIPHON INSTR (J) TYPE (4) cpn y Total epm 100 cm2 a 8 Y. '&f 4 . E.lmh ,J O i</ w/4 0,v V i sulluw O wtr1 k p 337 Tpo
^
LI ptA 71 C7 lc4 -
% i.). p
$ 4 1403 El.AJL A D / 5 &$. (. */
T l.ti//wv. , D /3707 /3k3 4 370 1 i dh (y ( L'> lia b 'l tac ty a .z2 !):$ fc &l> eel o () t ( '~K/h j$,1 4 L L6td A~ i) V M 7 YfLb3 7L H 0 V n WA 45.;t H8 '72 I , DETECTOR USED: REMARKS: J r .I a , (1) Background counting rate at a #6i3 /2Of ' (location)was: a cpm = dpm a mram/hr. (2) B eckground counting rate for this istrument was: _ epm = dpm. The 11D at 95% confkimee level was: net dpm = net pCi. No wipes wipes showed removable contamination above the 11D, except from the following items. -
.1 (J) SurveyInstrument Codes:
TAGM = Technical Associates portable G-M with pancake probe (thin window): Snial #: Calitration Date: Other: i (4) Survey Type h l D = Direct Survey over the entire surface of the object. WA = 100-300 cm2 wipe counted with an alphs detector. WG = 100-300 cm2 wipe counted with a portable G.M. i WL = 100-300 cm2 wipe counted with a liquid scintillation countar (3H). WOS = 100-300 crn2 wipe counted with a gamma spectrometer. SURVEY PERIORMED BY: D . " 3 (> - - -
/
G46 .
; . . .. . . . - . ~. .. ,. ,
e t
)
Passa NEL-101 - RSC Appnyval: 5/25/S8 AGN COMPONENT RADIATION SURVEY RECORD PORM Survey Form #: Survey 12x:ation AGN Reactor. Nuclear Engineering 1 ah. Survey Date: _ .*/ k /F/ TEM SURVEY SURVEY GROSS NET NETdam mrem >hmr (a mnf-i NO. GENERAL DESCRIPTION l INSTR (3). TYPE (4) cpra . cpn- 100 an2 81 8 7 Total zua o,s t , . . 7 .r/ .p.V p :;
. (5's . .' 6t *u. 9 /t / -/i/4. ,9,'t
*7 4 fh lA.,,vu~ D f I%y' (,l3 30 (v%)O 9 n LvA fu rib M ^
i s uf /)i $ir-
$ 4 . 4,-/1 V, L]ylv Er. D lY *+All ? ?f' 8 L.el Iw.n D 'ict.vl quxo 7 KgG
~
h y\/ /1 580 5]h 10H[ N fs0 OtSL ' sf ..to J 70 E bEdhlt. [)
/ [ m / M d. [37.
0 't YYYrtru.' I) ObT1 YCS$T Q ((D T " WA l'I8 (94 DEL - DETEC11DR USED: REMARKS. t (1) Background co=ums rate at (location) was: cpn= dpm = nwen/hr. (2) Background counting rate for this instrument was: cpm = dpm. The LLD at 95% confidence level was: net dpm = net pCi. No wipes wipes showed rernovable contamination above the LLD, except from the following insns: (3) SurveyInstrument Codes: TAGM = Tacimical Associatas portable G-M with paneske pobe (thin window): Serial #: Calilration Date: Other: 1 (4) SurveyType Codes: D = Drect Survey over the entire surface of the object. WA = 100-300 cm2 wipe counted with an alpha detector. WO = 100-300 cen2 wipe counted with a portable G-M. WL = 100-300 con 2 wipe counted with a liquid scin: Elation counter (3 H ). 2
. as# ,,_ WGS = 100-300 cm wipe counted with a gamma Mo..m.
')
SURVEY PERf0RMF.D BY: r v h+ /k0 2 - - G47 - 1 d
, , ., - . . - , , - - - , . ~w - -- - ,-- -
Pona NEL 101 RSC Approvat: 5/25/58 AGN COMPONENT RADIATION SURVEY RECORD IORM Survey Location Survey Fcrm #: AGN Reactor. Nuclear Engineerine Lab. Survey Date: _- # % /1 '/ . TEM SURVEY SURVEY CROSS NET nil &En mrem /hnur (a surface) NO. GENERAL DESCRFnON INSTR (3) TYPE (4) cpm epm 100 cm2 a 8 7 Total
& r.> 0 K . / I) ff - 9 q@l JU $AVO D .'N r f p'f so L wl[wtw O Yflll 45 G.1 V)I f *7 10 >' kVA 19.)- l80 %}
cL .a ao ' 43Efsh Tilhtbl () {O C < Nin th
't "
ludhw t) bo W 79 t' [vit /*7 /1 /8 DETECIVR USED: REMARKS: (1) Background countmg rate at (locatimi) was: cpm = dpm = mrem /hr. (2) Background counting nte for this instrument was: _ cpm = - dpm. The 11D at 95% catfidence level was: net dpm = net pCi. No wipes wipes showed removable contaminataon above the LLD, except from the following items: (3) SurveyInstmment Codes: TAGM = Techmcal Associates portable G-M with pancake prote (thin wiidow): Serial #: Calitration Date: Other: (4) SurveyType h D. Direct Survey over the entire surface of the object. WA = 100-300 an2 wipe counted with an alpha detector. . I WO = 100-300 cm2 wipe counted with a portable G-M. WL = 100-300 cm2 wipe counted with a liquid scintination counter H (3 ). ) WOS - 100 300 cm2 wipe counted with a gamma spectrometer. SURVEY PERFORMED BY: r bN 3
-t- - O> --
G48 -
AGN Surveys August 30,1989 Fission Plate
- 1. Max. p,y@ contact #1 = 8mR/hr fixed a = 2 cpm gross = 0 net removable n = 0 wt - 2506 g.
- 2. #20475 wt. - 2164g.
p, y(#3) 14 mR/hr,15 mR/hr fixed a 15994,23948 = 34460 dpm emovable a 27,48 = 69 dpm/100cm2
- 3. #20471 wt. - 2157g. >
p, y(#3) 15 mR/hr max. on contact fixed a 13765,17549 = 25250 dpm removable a. 57,71 = 102 dpm/100cm2
- 4. #20476 wt. - 2065g.
p, y(#3) 14 mR/hr max. on contact fixed a 26215,15619 = 37720 dpm removable a76,65 = 109 dpm/100cm2
- 5. #20442 wt. - 2051g.
, y(#3) 15 mR/hr max. on contact fixed a 9085,18328 = 26370 dpm removable a 78,45 = 112 dpm/100cm2
- 6. #20469 wt. - 1273g.
p, y(#3) 15 mR/hr max. on contact fixed a $3049,34284 = 76330 dpm removable ct 501,402 = 721 dpm/100cm2 G49
- 7. #20473 wt. - 1269g.
, y(#3) 14 mR/hr max. on contact fixed a 46848,75819 = 109090 dpm removable a 461,602 = 866 dpm/100cm2
- 8. #20478 wt. - 1267g. _
,y(#3) 14 mR/hr max. on contact fixed a 51117,41131 = 73550 dpm removable a 754,406 = 1085 dpm/100cm2
- 9. #20470 wt. - 657g.
, y(#3) 13 mR/hr max. on contact ,
fixed a 40024,40694 = 58550 dpm removable a 197,199 = 286 dpm/100cm2
- 10. #20481 wt. - 652g.
, y(#3) 14 mR/hr max. on contact fixed a 43894,42357 = 63157 dpm removable a 173,211 = 304 dpm/100cm2 a background at 5 cpm
- 3:= Eberline Ion Chamber Model RD-2A Serial # 1263 Calibrated 7/28/89 Polyethylene disc 473g. background 0.02
, y (#1) 0.03,0.02 mR/hr gross fixed a 0 net,47 net,3 net,55 cpm removable a 9 net,18 net,10 net 3p)6 S*Benmon!
G50
ru Inspection of AGN Fuel June 15,1990 All containers secure Radiation levels at surface of containers: Black.can: 0.2 mR/hr max. Bottom core: 1.5 mR/hr max. Top core: 1.8 mR/hr max. Fission plate: 0.9 mR/hr max. Radiation levels, Disk # 20470
@ contact Beta shield closed: 1.4 mR/hr Beta shield open: 28 mR/hr @ 1 foot Beta shield closed: 0.2 mR/hr Beta shield open: 4.0 mR/hr Instrument:
Eberline E-5008 Geiger Counter SN 1015 Calibrated 12/18/89
/ b. ,
S. Bennioif 1 i i G51
.i
- 6. Core Comoonent Surveys G52
Background Readings September 9,1989 a counter: 6 cpm 4 cpm 4 cpm 3 epm (#1) TBM - 35 #087129 Calibrated 6/23/89 40 - 60 cpm = 0.015 - 0.02 mR/hr (#2) Ludlum Model 19 #7950 Calibrated 7/28/89 (#3) Eberline Model RD-2A #1263 Calibrated 7/28/89 AGN Core Can External Surface p, y(#1): 0.03 mR/hr gross count fixed cx: 8 cpm gross / entire surface 6 dpm/ entire surface ' removable a: gross DPM 1 top 6 cpm,2 cpm net ~' 3 dpm/100-300cm2 8 bottom 3 cpm < MDA 9 middle 11 cpm 10 dpm/100cm2 2 top 5 cpm 1 dpm/100cm2 10 middle 7 cpm 4 dpm/100cm2 5 bottom 4 cpm < MDA 3 top 5 cpm 1 dpm/100cm2 11 middle 4 cpm <MDA 4 top 10 cpm 9 dpm/100cm2 12 middle 12 epm 12 dpm/100cm2 6 bottom 6 cpm 3 dpm/100cm2 inside of glory hole 10 cpm gross 9 dpm/ entire inside surface Bottom Flange ' p,7(#1): 0,03 mR/hr gross max. on contact removable: 12 cpm gross = 12 dpm/ flange surface G53
Top Flange p,y (#1): 0.03 mR/tr gross max. on contact removable a.: 10 cpm gross = 9 dpm/ flange surface a background check: 7 cpm,3 cpm,7 cpm,8 cpm, = 6 cpm Internal Core Can Surveys _ p,y (#1) Top half = 0.01 mR/hr max. on contact gross Bottom half = 0.025 mR/hr max. on contact gross fixed a: N/A removable a: gross DPM . I top 5 cpm <MDA 2 middle 6 cpm < MDA - 2 top ' 8 cpm 3 dpnV100cm2 10 middle 3 cpm <MDA 12 middle . 12 cpm - 9 dpm/iO0cm2 4 top 4 cpm < MDA 3 top 5 cpm 1 dpnV100cm2 11 middle 4 cpm <MDA 7 bottom 6 cpm <MDA 6 bottom 2 cpm <MDA 8 bottom 4 cpm <MDA 5 bottom 8 cpm 3 dpm/100cm2 Bottom Flange (interior wipe) = 6 cpm gross <MDA Top Flange (interior wipe) = 13 cpm gross 10 dpm / entire surface a background check: 10 cpm,2 cpm,7 cpm,4 cpm, = 6 cpm Bottom Cover Plate
, y (#1) inside - 0.02 mR/hr max on contact gross outside - 0.025 mR/hr max on contact gross fixed a: inside - 8 cpm gross 3 dpm/ entire surface (entire surface) outside - 6 cpm gross - <MDA removable a: inside - 12 cpm gross 9 dpm/ entire surface outside - 3 cpm gross <MDA ,
Top Cover Plate G54
p, Y (#1) inside - 0.03 mR/hr max on contact gross outside - 0.03 mR/hr max on contact gross fixed ot: inside - 4 cpm gross <MDA outside - 5 cpm gross <MDA removable a: inside - 7 cpm gmss 1 dpm/300cm2 outside - 3 cpm gross I dpm/300cm2 Control and Safety Rod Guide Tubes SR1 external surveys p, y (#1) 0.03 mR/hr max on contact gross fixed a: 5 cpm gross <MDA . removable a: 6 cpm gross <MDA intemal surveys P,Y N/A fixed a: N/A ' removable a: 4 cpm gross <MDA CR external surveys
, Y (#1) 0.04 mR/hr max on contact gross fixed a: 10 cpm gross 6 dpm/ entire surface ._
removable a: 4 cpm gross <MDA external surveys
,Y N/A fixed a: N/A removable a: 7 cpm gross 1 dpm/ entire surface SR2 external surveys
, y (#1) 0.03 mR/hr max on contact gross fixed a.: 6 cpm gross <MDA removable a: 14 cpm gross 10 dpm/ entire surface ,
intemal surveys .; E,Y N/A fixed a: N/A-u ~ ~ - G55 --- 1 d
removable a: 9 cpm gross 13 dpm/ entire surface FR extemal surveys - p, y (#1) 0.04 mR/hr max on contact gross fixed a: 10 cpm gross 4 dpm/ entire surface removable a: 6 cpm gross <MDA , intemal surveys-
,y (#1) N/A <
fixed a: ' N/A removable a: 7 cpm gross <MDA nimble p, y (#1) 0.05 mR/hr fixed a: 69 cpm / entire surface 89 dpm/ entire surface removable a: 69 cpm gross 89 dpm/ entire surface Control and Safety Rods - SRI Fuel Cladding - external surveys p, y (#1) 0.03 mR/hr max on contact gross _ fixed a: 4 cpm gross <MDA removable a: 11 cpm gross 7 dpm/ entire surface intemal surveys
,y (#1) N/A fixed a: N/A removable a: 90 cpm 119 dpm/entim surface Spring p, y (#1) 0.03 mR/hr max on contact gross fixed a: 14 cpm gross 10 dpm removable a: 40 cpm gross 47 dpm End Plug
, y (#1) 0.03 mR/hr max on contact gross q
fixed a: 3 cpm gross <MDA l removable a: 8 cpm gross 1 dpm/ entire surface
-l G56 ,
l
Washer
, y (#1) 0.03 mR/hr max on contact gross fixed a: 5 cpm gross diDA removable a: 6 cpm gross <MDA SR2 Fuel Cladding external surveys
, y (#1) 0.03 mR/hr max on contact gross fixed a: 5 cpm gross <MDA
. removable a: 6 cpm gross <MDA a background check: 3 cpm,4 cpm,5 cpm,7 cpm = 5 cpm internal surveys P,y (#1) N/A fixed a: N/A removable a: 96 cpm gross 131 cpm /inside scrface Washer p, y (#1) 0.02 mR/hr max fixed a: 3 cpm gross diDA removable a:: 5 cpm gross <MDA Graphite
, y (#1) 0.04 mR/hr max on contact gross '~
fixed a: 12 cpm gross 10 dpm/outside surface - removable a: 12 cpm gross 10 dpm/ outer surface Spring p, y (#1) 0.02 mR/hr max on contact gross fixed a: not counted (may injure detector) removable a: 9 cpm gross 6 dpm/ outer surface End Plug p,y (#1) 0.02 mR/hr max on contact gross fixed a: 4 cpm gross <MDA removable a: 5 cpm gross <MDA (.
/%
hoJn 5. Bennion N G57 ,
I AGN Surveys 1 i' 9/12/89 Background 2,5,3 cpm: average: 3 cpm Ludlum Model 1000 sn: 33640 and an a probe PR021524 ! TBM-35 sn: 087129 back= 0.03 mR/hr -1 AGN poly disc p,y (#1): 0.04 mR/hr removable a (inscribed side): - 19 cpm l removable a (non inscribed side): 12 cpm fixed a (inscribed side): 40 cpm Washed with micro solution
~
fixed a (inscribed side): 6 cpm fixed a (non-inscribed side): 6 cpm All wipes approx.100 cm2 AGN graphite reflector #8 removable a: 7 cpm After wiping with acetone: 5 cpm
,y < MDA graphite reflector #6 removable a: 5 cpm After wiping with acetone: 7 cpm
,y. < MDA graphite reflector removable a: 6 cpm After wiping with acetone: 8 cpm o p,y. < MD A i
l G58 l
Background check: 6,3,6,6 cpm: average 5 cpm graphite #5 removable a: 3 cpm After wiping with acetone: 6 cpm p,y < MDA graphite #4 removable a: 3 cpm After wiping with acetone: 3 cpm p,y < MDA graphite #3 removable a: 9 cpm After wiping with acetone: 4 cpm
,y < MDA graphite #2 removable a: 5 cpm After wiping with acetone: 7 cpm
,y < MDA graphite #1 removable a: 11 cpm
' Af ter wiping with acetone: 6 cpm
,y < MDA G59 i
10/4/89 l Fuse Support U-235 approx. 90 dpm removable 9R/89 Control Rod 1 - Identify-90/89 - 130 removable a contamination Ludlum a probe sn: PR021524 Model43-1 Scaler sn: 33640
Background:
3,4,4: average: 4 cpm exterior surface: 5 cpm - 4 cpm = 1 cpm net interior decontaminated by Byron L. Hardy Xetec sn: 11964A)21819 Model 318-A2 w/ ext 6 M Pmbe _- Calibrated 7/13/89 Interior count rate: less than detectable (<1 cps)
,y < MDA TBM 35 Background #087129 cal. back=.025mR/hr Fuse Support Decontaminated by Bryon L. Hardy removable ot: 2 cpm gross < MDA fixed ot: 14 cpm gross
,y(TRM-35): 0.04 mR/hr gross = 0.015 mR/hr max on contact 2nd Decontamination fixed a: 8 cpm gross over surface removable a: 5 cpm gross
,y .05 mR/hr max gross 3rd Decontamination - soak in dilute HNU 3 p,y .05 mR/hr max gross - unremovable G60
Control Rod 2 (identify) 9/7/89: - 120 dpm removable cx - Decontaminated by Byron L. Hardy interior: removable cx: 5 cpm gross = 1 epm net fixed cx: 2 cps max (Xetec) , 2nd Decontamination by Bryon L. Hardy fixed cx: less than detectable with Xetec removable cx: 6 cpm gross , exterior; fixed a: 3 cpm gross removable a: 2 cpm gross ,- p,y. < MDA Course Rod interior: removable cx: 8 cpm gross fixed cx: < MDA (<1 cps)
,y. < MDA '
exterior: removable cx:
=
i
~
XXV - l
r";_ 11/21/89 Fine Rod sealed in plastic: no detectable contamination: 4 polyethylene discs 1 graphite disc I spring 1 fastening plug Coarse Rod background Ludlum Model 43-1, Ludlum Model 1000 4,3,4 xetec 0-1 cps background
^
clading: interior a: 5,6,7 gross exterior removable a: 11,6,5 interior p,y 2 cps max - Xetec # 11964, model 318A, cal. 7/13/89 exterior p,y 1 cps max > Spring removable a: 5,2,5 gross
,y max 1 cps fixed a: 5,4,4 gross Washer .
removable a: 3,7,4 gross
,y 0 cps fixed a: 4,3,5 Graphite removable a: 2,6,6 gross p,y- I cps max fixed a: 5,7,4 End Cap removable a: 4,5,6 gross
,y 0 cps fixed a: 6,5,3 gross ;
Course Rod Scaled in Plastic. G61 -
1 11/22/89
Background
a: 6,2,4 ave. 4 cpm Ludlum Alpha Probe (model 43-1) sn: FR021524
- ,7: 0-1 cps Xetec SR1 Graphite p,y. I cps max gross removable a: 4,4 cpm gross fixed a: 4,5 cpm gross ,
Spring
,y: 1 cps max gross removable a: 4,3 cpm gross fixed a: 4,4 cpm gross .
Washer P,7. O cps removable a: 2,5,6 cpm gross fixed a: End Cap
,y. O cps removable a: 6,4 cpm gross fixed a: 2,5 cpm gross Cladding external removable a: 7,4,4 cpm gross / entire surface internal removable a: 5,5 cpm gross / entire surface
,yint. & ext.: max reading 1 cps gross fixed a ext: 4,5 cpm gross SRI Components Sealed in Plastic.
l G62 e^w
t Core Reflector Bottom: removable n (entire surface): 14,13,12 cpm gross Top: removable a (entire surface): 12,7,9 cpm gross Bottom (surface adjacent to fuel only): removable a: 10,9,16 cpm gross SR2 Cladding extemal removable a: 4,4 cpm gross / entire surface intemal removable a: 64,70,46 cpm gross / entire surface . p,y fixed a ext: 11/24/89 background a: 4,4,5 cpm p,y. 0-1 cps SR2 Cladding Sealed in Plastic-will either dispose or decontaminated waste End cap, graphite, washer - previously sealed in plastic spring: p,y. O cps Xetex #11964 removable a: 4,5 cpm gross fixed a: 5,3 cpm gross Spring was sealed in plastic. Aluminum Core Support (approx.14" long, hollow) removable a: 15,10 cpm gross Contaminated-sealed in plastic. Screws, miscellaneous hardwood sealed in plastic. T s John S. Bennion 1 G63
. 1 Form NEI-101 RSC Approval:5/25/88 AGN REACTOR DECOMMISSIONING & DISASSEMBLY AGN COMPONENT RADIATION SURVEY RECORD FORM Survey Form #
Survey Location AGN Reactor. Nuclear Eneineerine I2b Survey Date r-#-M9 NET ITEM SURVE{ SURV Y GROSS NET mRemAour(G surface) NO. GENERALDESCRIPTION INSTR (3) (TYPE1 (4) cm2 M 7* cpm8 n Total 1 See M k C.> P'Pe. SPF 1moA 4 maA o
- 7. n f., F PL SPC < n>M < moA o
.5 >>
r, pet spe < ~ M t ~oA o 4 a. GFPC S'Pt ' mob ' m oA o ' s >> AFPc s pc <~A s m oA a f or f., t* PC S ?C. < moe Ama4 o 7 r, fFPG SPc. ' M 4 +"M o 8 si & pre Cl% e ,., o A a m n4.
- ci so (, F* P6 S PC- < m a A- t ma4 O
y w /sFPd GPe not was o '
o >
& FRL SPc t.mostwoAs iz i, (, F PC. S PC. &n a4 imp) o <
DETECTOR COUNTING YIEIE USED: REMARKS: M [ h[Q f,- 2/ M 4 /g svn P 2 i kbUe a>Same Cpf O. I(oS @ gp =o y kv y.d cmr (mc/ A') x si.o e/w 1 (1) Background counting rate at (3) SurveyInstrument Codes.
't was cpm = TAGM = Technical Associates portable GM with dpm = mrem /hr. pancake probe (thin window).
Direct radiation levels from the (area, Serial # item (s)) surveyed (were, were not) $ background radiation levels. Exceptions: [ (,As p/w pn,prreestc,s rw-(4) Survey Type Codes: D = Diret Survey over the entim swface of the object. (2) Background counting rate for this instrument SG = 100-300 cm2 wipe counted with a portable GM. was - cpm = dpm. The SL = 100 300 cm2 wipe counted with a liquid LLD at 95% confklencelevel was net scintillationcoimtar(3H). dpm = net pCi. No wipes above the SGS = 100 300 cm2 wipe counted with a gamma LLD, except from the foDowing items: spectrometer. - S PC soo-Voced w;fe w a r w l Y a-q~5 fr. p er M n varre-SURVEY PERFORMEDBY: MffW bd G64
, -_e
Fonn NEL 101 - RSC Appnwal: 5/25/88L
- AGN REACIDR DECOMMISSIONING & DISASSEMBLY '
AGN COMPONENT RADIATION SURVEY RECORD FORM t SurveylAcation : Sevey Fonn # AGN Reactor. Nuclear Eneineerine bh. Survey Date NET TTEM . > SURVEY SURVEY GROSS NET _sket,. =n-Anur te erf-i cpm que 100 an2 7 NO. GENERALDESCRIPTION INSTR (J) TYPE (4) 8 a Toad k e L u. 15 &pk S R2 won n M 'e I4
- a e m 0.4 ss=.oA * -
, _j[ of N !
't
$ #>9 O k $ oet Y O fy k^ n "
sne OA 4.ma4 o ~ 17 (pFPC Stt imod. L'*'P.6. g . 1 76 it " t m ok sos, s4 o 41 to to t 4.nr 0.4 4 m c4 o ' 7p # " tat,at 4.e 04 e
~g ; h no
. et 4.o4pA 4.oor94 e '
Tl k N flY S$ '**' DA* All' O A * ' n it Ab FFL GA* <~04 4
- 1 s4
- DETECTOR COUNTING YlELD USED: ' REMARKS g g/ . g f gg g j ,
bl.y flose % /bY'bM , , Je,ume By onotas- @ lMeV 15A ro& Couni' '58' ty . > (1) Background counting rate at (J) Savey Instrument Cades was . cpm = TAGM = Technical Assocatw portable GM with ~ dpm = mrem /hr. pancake probe (thin window). Direct rediation levels from the (area, Serial # item (s)) surveyed (were, were not) s 6 F Pe. - Ca r F +.o I tr'a r r'r 8W * ' - background radiatien levels. Eacepnons (4) Survey Type Codes. (2) Background counting rate for this instrumet D = Diret Survey over the entire safece of the object. > was 50 = 100 300 cm2 wipe counsad with a ponable GM.. epm = dpm. The . SL = 100-300 cm2 wipe counsed with a liquid LLD at 95% confsdence level was ' net dpm = scintiDationcounter(3H). _ not pCi. No wipes above the , SGS = 100 300 con 2, ipe counted with a gamma ' LLD, except from the foDowing items: specsmaneest. Syg * !*
- se p C* O <<ts p JMkk eD
- ns.
gas Clw ro rst C ovMY r- t SUIG ** j.
- SURVEY PERPORMEDBY: _ W/L /~N
-G65
, . . , = ,
- - . - - - . i.~w. ,. , n , iw- ,.
From Back of Form NEL-101 hem General Description 2 1 Lead Shield East 100cm T.C. out/Fuelin 2 Lead Shield West 100cm2 T.C. out/ Fuel in 3 Izad Shield North 100cm2 T.C. out/Fuelin 4 Lead Shield South 100cm2 T.C. out/ Fuel m 5 Bottom of AGN Thermal Column,just after removal of T.C., fuel, and SourCC in 6 Sidewall of Theimal Core Receptacle, East Fuel in, Thermal Core out 7 Sidewall of Thermal Core Receptacle, West Fuel in, Thermal Core out 8 Sidewall of Thermal Core Receptacle, Nonh Fuel in Thermal Core out - 9 Sidewall of Thermal Core Receptacle, South Fuel in, Thermal Core out 10 Graphite Reflector Rim North, Thermal Core out, Fuel in 11 Graphite Reflector Rim South, Thermal Core out, Fuel in 12 Graphite Reflector Rim East. Thermal Core out, Fuel in 13 Graphite Reflector Rim West, Rermal Core out, Fuel in 14 Fuel Cover, Thermal Core out, Fuelin 15 Ra-Be Source in core just after removed 5/4/89 16 Contml Rod 1 (CRI) Fuel Element 17 Control Rod 2 (CR2) Fuel Element 18 Fine Control Rod Wipe 19 Spring Assay Wipe (CR2) 20 Course Control Rod Spring Assay Wipe 21 CR1 Spring Assay Wipe 22 Fine Control Rod Spring Assay Wipe 23 Course Control Rod Fuel Wipe
-h%. -
? . .
Q9 hn S. Bennion-G66
1 i 1 1
- 7. Second Facility Survey
]
I i i G67
AGN DECOMMISSIONING i RPR 50C. CONTAMINATION WIPE TEST RESULTS User: SwIqu d - M'd Group #: % Cate: 3/Z r/i 7 Task #: NA Bldg / Room (s): _!2M- E NEG Isotopes used: 'M M e kc- OLtH COUNTING INSTRUMENT DATA Model, serial f: tS- no o HMN r? Prograq/ Setup: T ~- Preset: I minutes or - counts Units of Readout: cP " O ata attached Counting Channel: Til f21 I31 or entered here: Backgrounds b OTi ! Isotope: I4 M>> Efftetency: ( Expected Not Response to 1 RCL b(' \ Isotope: Efficiency: 0 L4' ('M ' Expected het Response to 1 RCL: IN WIPE TEST COUKTING RESULTS (A) Enter "100" for a 100 cat ,gp, ,, .3gg. for a 300 cat ,gp,, {B) Net response in each channel in saae units es recorded above. If the not response in any channel exceeds that expected for 1.RCL of any isotope: lC[ enter the likely nuclide and
;0, enter the multiple of the RCL.
[A] x [B] [C] [D] Ling Ob.iect or location Arga . Net > Channel Resoonse Likely Multiple
.(g_), Ill I21 I31 Isotone of RCL 1 L ow W Jm- ( h G V /
2 c c.<mpwl Av esa\ 1,; c,/ cg l 3 ~Jm; sa CL W- i (A ' 4 me, iw ac L J To t. C' O ! 5 3/2 r h 1 m Tu t- v '- q'. i 6 l KG 7 7 \ 7 I TL J C G: \ 8 __ b TGts c.h 7: \ 9 \ 10 I 11 i 12 ' 13 ! 14 G68
i --- d u x v e y iiar-O """"$"""^" NUCLEAR ENGINEERING L AB 1205-F _ sy. D ARREu. a Au.W
- DATE: -d 2 h
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TABLE o - Ge(Li) : i. m ~,,, m a o a x s
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Ox - w O os 1205 k) ' W-ua? E.M I SURVEY METER (S) USED: -
.LUDLUM MICRO-R SERIAL #12911 h (VIPE LOCATIONS results attached)
CAllBRATED 3/8/93 1205-A t.pT. A. TBM-33 DIRECT READINGS IN mR/hr SERI AL "G93127 i3ac kqun d : O D i ML CALIBRATED 7/28/92 G69 EXIT
j(-) t/V gaup y p e 4 =os r- 6 g [*~l20J-6.
' 20 Hs, 42 Hs
, ELT 4.63 MIN EL7 , -16'.40LMIN 3lUl 3 CH 1 2.00 CEN
'CH I 8500 CPM.~ ;
99.99 2FX,' , 70.50 2ax
,_ST i 1 00 MIN ST. 1.00 MIN CH 2 .CH 2 13.00 CPN j5.00 CPM 55.38 2ax 51.60 '2*x 9 aupe r 3 ca mpe r pns 7 a *ns ig 2'8 Hn ELT 27 Ha 6.88 min
..ELT. 18.65 min-CN 1 CH 1 7.00 CP'N 75.42 2aX 3.'0 0 UPN. )
99.99 2*N '
,-CAL 780 MEN ST 1.00 min . ST 1.00 gl's CH 2 ~
CH 2
', jB.00 CPN poo a 47.11 2ax i3.00 CPN 55.38 2FX CNT CH H12 ITIME'S' SCR $ 4MPI F 4 S A"88 F N O, eng g 8 AQC NO onc .3 CALC 1 4$ 'g, ,
33 g, PST. . . . ELT 9. 2 5 M l"N ELT
!.00 MIN 21.00 MIN CH I . ,2.00 2aX CH 1 CH ]
OL 4.00 CPN 7.00 CPM 317 U 99,99 2aA CH 2 ST 1.00 MIN 75.42 2as 2 00 2a's ST 1 00 MIN-397 L CH 2 CH 2 ' 655 U , 17.00 CPN 18.'00 CPM 48.47 2F% 47 11 2ax campsF 5 S4*PLF , ans 1n
- 1 50% S 30 Hs ,
21 HH ELT 1 1'. 5 0 M'I N ELT '2.37 MIN. CH I ~ CH I 12.00'CPN 6.00 ,CPN 57.66 2ai ST 1.'00'M1H 81.33 20% ST 1.00 MIN CH 2 CH 2 . ..
- 18.00.CP,M' 15.00 CPM
- . . ~ .
47.11 2aX ~!
'51.60 2ax i l
'l l
G70 ! l
'l
l 1
- 8. AGN Component Surveys 1
1
' 11 l
l l e 1 1 1 l 4 l i i i l
)
1 G71
l Part # Direct Counting Alpha epm LSC cpm Description 1 0.02 mR/hr Safety Rod #2 (Empty) 2 0.02 mR/hr Course and Fine Contml Rod nimbles 3 0.02 mR/hr 0 0/0 "O" Ring Core Can Top Plate 4 0.02 mR/hr Paint Chips from Thermal Column 5 0.02 mR/hr Safety Rod #2 Parts 6 0.02 mR/hr Core Can Assembly Bolts and Spring 7 0.02 mR/hr Assembly Bolts And Washers (Core Can) 8 0.02 mR/hr Core Support Rod 9 0.02 mR/hr Quantity-2 Safety Rod Thimbles 10 0.02 mR/hr Safety #1 with Parts 11 0.02 mR/hr 1 Course Control with Parts 12 0.02 mR/hr Fine Control Rod with Parts 13 0.02 mR/hr Core Support 14 0.02 mR/hr 0 OA) Core Can Top Plate 15 0.02 mR/hr 0 0/0 Core Can Bottom Plate 16 0.02 mR/hr 0 0/0 Polyethylene Disk ' 17 0.02 mR/hr 0 0/0 Graphite Reflector for Interior Core Can 18 0.02 mR/hr Aluminum Core Can 19 0.02 mR/hr Graphite Reflector Plate 20 0.02 mR/hr Graphite Reflector Plate 21 0.02 mR/hr 0 0/4 Graphite Reflector (Bottom Interior Core Can) 22 0.02 mR/hr 0 - Intemal Thermal Column
- - _ _ = _ - _ _ _ _ _ - _ _ - - _ _ - _ - _ _ _ _ _ - - - - . .
s r e v e o e t a C t a l p ht l i n p r w n t t t n t no no no no m r e v y o r o r o r o o r o t r o no n t r t r u e o h P P P P P P P P P P o o o v b l P P P P P l o o C c n s s s s s s s s s s s s s s s s s s s s s s s s s C C n e r m e e e e e e c e c e c e c e c e c e c e c e c e c s e s e s e s e s e l a n m s v v v v c c c c c c c c c c c c c c c n m u W s A A A A A A A A A A c c c c c u o d A i i i i r r r r D D D D n n n n n n n n n n An An An An An l n s e o C n l a r d d i i i i i i i i i i o o o do h C l e d g g g g g g g g g g i i i i i T a t e v u u u u u u u u u u g g g g g l a l a u k o R R R R l l l l l l l l l l u u u u u m n e c C P F P P P P P P P P l P l P l P l P l P m r h o no d d d d d d d d d d d d e e T S o o o o o o o o o o a a d a d a d a t x h P o o o o o o o o o o e e e e e E I
'p tom /
e W W W W W W W W W W L L L L L o t l o T o I I B y r l o G M 0/ 0
/ M 0 /
0
/
0
/
0
/
0
/
0
/ M 0/ 0
/
0
/
0
/
0
/
0
/ S 0/
0
/ M 0/ 0 0 O 0 0 O 0 0 0 0 0 0 O 0 0 0 0 0 0 O 0 0 O 0
/
0
/
0 0 0 1 0 0 0 2 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 r r r r r r r r r r r r r r r r r r r r r r r r h h h h h h h h h h h h h h h h h h h h h h h h / / / / / / / / / / / / / / / / / / / / / / / / R R R R R R R R R R R R R R R R R R R R R R R R m m m m m m m m m m m m m m m m m m m m m m m m 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 4 5 6 7 8 9 0 1 2 3 4 5 6 7 8 9 0 1 2 3 4 5 6 2 2 2 2 2 2 2 3 3 3 3 3 3 3 3 3 3 4 4 4 4 4 4 4 l!
i. 47 0.02 mR/hr 0 0/0 Lead Plug in Access Pon 48 0.02 mR/hr 0 0/0 Lead Plug in Access Port 49 0.02 mR/hr 0 04 Lead Plug in Access Port 50 0.02 mR/hr 0 0/0 Lead Plug in Access Pon , 51 0.02 mR/hr 0 0/0 Lead Plug in Access Port 52 0.02 mR/hr 0 0/0 Lead Plug in Access Pon 53 0.02 mR/hr 0 0/0 Lead Plug in Access Port 54 0.02 mR/hr 0 0/0 Lead Plug in Access Pon 55 0.02 mR/hr 0 05) Lead Plug in Access Port 56 0.02 mR/hr 0 OM Lead Plug in Access Port 57 0.02 mR/hr 0 0/0 Lead Plug in Access Port 58 0.02 mR/hr 0 0/0 Aluminum Fuse Support
@ 59 0.02 mR/hr 0 0/0 Alignment Screws 60 0.02 mR/hr 0 0/0 Polyethylene Rod 61 0.02 mR/hr 0 0/0 Graphite Plug in Access Port 62 0.02 mR/hr 0 OM Graphite Plug in Access Port 63 0.02 mR/hr 0 OM Graphite Plug in Access Port 64 0.02 mR/hr 0 0/0 Graphite Plug in Access Port 65 0.02 mR/hr 0 0/0 Cadmium Plug 66 0.02 mR/hr 0 0/0 Graphite Plug in Access Port 67 0.02 mR/hr 0 OM Graphite Plug in Access Port 68 0.02 mR/hr 0 OM Graphite Plug in Access Pon 69 0.02 mR/nr 0 OS Graphite Plug in Access Pon 70 . 0.02 mR/hr 0 OS Ahuninum Access Pon Sleeve
m _ .. 71 0.02 mR/hr 0 0/0 Aluminum Access Pon Sleeve 72 0.02 mR/hr 0 0/0 Aluminum Access Pon Sleeve 73 0.02 mR/hr 0 OM Aluminum Access Pon Sleeve 74 0.02 mR/hr 2 04 Graphite Reflector Column 75 0.02 mR/hr 0 OM Bottom Lead Shield Ring 76 0.02 mR/hr 0 OA) Bottom Lead Shield Ring w/ Access Pons 77 0.02 mR/hr 1 0/0 Top Lead Shield Ring w/ Access Pons 78 0.02 mR/hr 0 OM Top Lead Shield Ring
~
79 0.02 mR/hr 0 '0/0 Bottom Lead Shield Plate 80 0.02 mR/hr 0 0/0 Fission Gas Canister 81 0.02 mR/hr 0 0/0 Wood Plug in Access Pon 82 0.02 mR/hr 0 DM Wood Plug in Access Port h 83 0.02 mR/hr 0 0/0 Associated Core Assembly Bolts 84 0.02 mR/hr 0 OS Control Rod Suppon Plate 85 0.02 mR/hr 0 0/0 Cadmium Disks 86 0.02 mR/hr see below see below Main ReactorTank 87 :0.02 mR/hr Reactor Console l l l_ _ _ _ _ _ - _ ___ _ _ _ _ _ _ _ _ _ _ _ . .. . _ .
- 9. Unrestricted Component Survey h
e k I l G76
Parts to be released as unnstricted waste. Core Can Cover, Top Part # 14 Direct Counting Alpha cpm LSC cpm Description A 0.02 mR/hr 0 OA) exterior B 0.02 mR/hr 0 OA) interior Core Can Cover, Bottom Part # 15 Direct Counting Alpha cpm LSC cpm Description A 0.02 mR/hr 0 0/0 exterior B 0.02 mR/hr 1(0) 0/0 interior Polyethylene Disk " Part # 16 Direct Counting Alpha cpm LSC cpm Description A 0.02 mR/hr 0 0/0 Opposite Disk Sides B 0.02 mR/hr 0 0/0 Opposite Disk Sides Hermal Column. Interior (22) And Exterior (23) Part # Direct Counting Alpha cpm LSC cpm Description 22/23 A 0.02 mR/hr 0 0/0 1/4 of Wall, Interior (22) B 0.02 mR/hr 0 0/0 1/4 of Wall. Interior (22) C 0.02 mR/hr 0 OA) 1/4 of Wall Interior (22) D 0.02 mR/hr 0 0/0 1/4 of Wall Interior (22)
E 0.02 mRJhr 0 OM Interior Floor (22) F 0.02 mR/hr 0 0/0 1/4 of Wdl. Exterior (23) G 0.02 mR/hr 0 0/0 1/4 of Wall. Exterior (23) H 0.02 mR/hr 0 0/0 1/4 of Wall. Exterior (23) I 0.02 mR/hr 0 OM 1/4 of Wall. Exterior (23) J 0.02 mR/hr 0 OM Exterior Floor (23)
'Ihennal Column Cover Plate Part # Direct Counting Alpha cpm LSC cpm Description 24/25 o A 0.02 mR/hr 0 OTO Top (24)
N B 0.02 mR/hr 0 OM Bottom (25) Access Port And Glory Hole Pans Part # 27 Direct Counting ~ Alpha epm LSC cpm Description A 0.02 mR/hr 0 0/0 Access Pon Sleeve B 0.02 mR/hr 0 OM Access Port Sleeve C 0.02 mR/hr 0 OM Access Pon Sleeve D 0.02 mR/hr 0 0/0 Access Port Sleeve - E 0.02 mR/hr 0 OM Access Port Sleeve F 0.02 mR/hr 0 0/0 Access Port Sleeve G 0.02 mR/hr 0 OM Access Port Sleeve H 0.02 mR/hr 0 OM Access Port Sleeve i
I 0.02 mR/hr 0 OS Access Port Cover J 0.02 mR/hr 0 OS Access Port Cover K 0.02 mR/hr 0 0/0 Access Port Cover L 0.02 mR/hr 0 0/0 Access Port Cover M ' O.02 mR/hr 0 0/0 Access Port Cover N 0.02 mR/hr 0 0/0 Access Port Cover 0 0.02 mR/hr 0 0/0 Access Port Cover P 0.02 mR/hr 0 0/0 Access Port Cover Q 0.02 mR/hr 0 0/0 Access Port And Glory Hole *O"-Rings R 0.02 mR/hr 0 OM Glory Hole Sleeve S 0.02 mR/hr 0 OM Glory Hole Cover T 0.02 mR/hr 0 0/0 Glory Hole Cover d U 0.02 mR/hr 0 OM _ Glory Hole Sleeve V 0.02 mR/hr 0 0/0 Associated Bolts And Nuts Alignment Screws ~ Part # 59 Direct Counting Alpha cpm LSC cpm Description A 0.02 mR/hr 0 0/0 Core Can Alignment Screw B 0.02 mR/hr 0 OS Core Can Alignment Screw I Part #'s Direct Counting Alpha cpm LSC cpm Description 3 0.02 mR/hr 0 0/0 Core Can "O"-Ring l 58 0.02 mR/hr 1(0) 0/0 Aluminum Fuse Support 60 0.02 mR/hr 0 l 0/0 Polyethylene Rod l
r Control Rod Support Plate Part # 84 Direct Couating Alpha cpm LSC cpm Description A 0.02 mR/hr 0 0/0 Interior Side With Rods B 0.02 mR/hr 0 0/0 Exterior Side Reactor Main Tank Part # 86 Direct Counting Alpha cpm LSC cpm Description A 0.02 mR/hr 0 0/0 1/4 Base Plate, Interior Of Bottom Section B 0.02 mR/hr 0 0/0 1/4 Base Plate. Interior Of Bottom Section C 0.02 mR/hr 0 0/0 1/4 Base Plate Interior Of Bottom Section o D 0.02 mR/hr 0 0/0 1/4 Base Plate, Interior Of Bottom Section E 0.02 mR/hr 1(0) OM 1/4 Wall, Interior Of Bottom Section F 0.02 mR/hr 1(0) 0/0 1/4 Wall, Interior Of Bottom Section G 0.02 mR/hr 0 0/0 1/4 Wall, Interior Of Bottom Section H 0.02 mR/hr 0 0/0 1/4 Wall, Interior Of Bottom Section I 0.02 mR/hr 0 0/0 1/4 Rod Drive Cylinder Plus Ceiling J 0.02 mR/hr 0 OM 1/4 Rod Drive CylinderPlus Ceiling K 0.02 mR/hr 0 0/0 1/4 Rod Drive Cylinder Plus Ceiling L 0.02 mR/hr 0 0/0 1/4 Rod Drive Cylinder Plus Ceiling M 0.02 mR/hr 0 3/0 1/8 Base Plate N 0.02 mR/hr 0 02 Bottom Section Door Both Sides 0 0.02 mR/hr 0 OM I/8 Bottom Section P 0.02 mR/hr 0 0/0 1/8 Bottom Part Of Big Cylinder
Q 0.02 mR/hr 0 OS 1/8 Bottom Of Big Cylinder Wall Q1 0.02 mPJhr 0 0/0 Top Access Port On Tempemture Gage Side , Q2 0.02 mP/hr 1(0) OM Top Access Pon On Temperature Gage Side R 0.02 mR/hr 0 OS 1/8 Top Of Big Cylinder Wall RI 0.02 mR 3 0 0/0 Bottom Access Pon On Temperature Gage Side R2 0.02 mR/nr 1(O' 0/0 Bottom Access Pon On Temperature Gage Side S 0.02 mR/hr 0 0,0 1/8 Base Plate T 0.02 mR/hr 0 OS 1/8 Bottom Section U 0.02 mR/hr 0 OM 1/8 Bottom Pan Of Big Cylinder V 0.02 mR/hr 0 0/0 1/8 Bottom Of Big Cylinder Wall W 0.02 mR/hr 0 OM 1/8 Top Of Big Cylinder Wall g X 0.02 mR/hr 1(0) OM I/8 Base Plate 3 Y 0.02 mR/hr 0 0/0 1/8 Bottom Section Z 0.02 mR/hr 0 0/0 1/8 Bottom Part Of Big Cylinder AA 0.02 mR/hr 0 OM 1/8 Bottom Of Big Cylinder Wall BB 0.02 mR/hr 0 OM 1/8 Top Of Big Cylinder Wall BB1 < 0.02 mR/hr 0 2/0 Glory Hole CC 0.02 mR/hr 0 0/0 1/8 Base Plate DD 0.02 mR/hr 0 OM 1/8 Bottom Section - EE 0.02 mR/hr 0 OM 1/8 Bottom Pan Of Big Cylinder FF 0.02 mR/hr 0 0/0 1/8 Bottom Of Big Cylinder Wall GG 0.02 mR/hr 0 OM 1/8 Top Of Big Cylinder Wall IIH 0.02 mR/hr 0 0/0 1/8 Base Plate II 0.02 mR/hr 0 OM 1/8 Bottom Section And Part Of Big Cylinder
h JJ 0.02 mR/hr 1(0) 0/0 Bottom Section Door Both Sides KK 0.02 mR/hr 0 0/0 1/8 Bottom Of Big Cylinder Wall KKI ' O.02 mR/hr 0 OM Bottom Access Pon KK2 0.02 mR/hr 0 0/0 Bottom Access Pon 11 0.02 mR/hr 0 0/0 1/8 Top Of Big Cylinder Wall LLI 0.02 mR/hr 0 0/0 Top Access Port 112 0.02 mR/hr 0 0/0 Top Access Pon MM 0.02 mR/hr 0 27/0 1/8 Base Plate NN 0.02 mR/hr 0 0/0 1/8 Bottom Section OO 0.02 mR/hr 0 OM 1/8 Bottom Pan Of Big Cylinder PP 0.02 mR/hr 0 0/0 1/8 Bottom Of Big Cylinder Wall { QQ RR 0.02 mR/hr 0.02 mR/hr 0 0 0/0 0/0 1/8 Top Of Big Cylinder Wall 1/8 Base Plate SS 0.02 mR/hr 0 0/0 1/8 Bottom Section TT 0.02 mR/hr 0 0/0 1/8 Bottom Pan Of Big Cylinder UU 0.02 mR/hr 0 OM 1/8 Bottom Of Big Cylinder Wall UU1 0.02 mR/hr 0 0/0 Glorv Hole VV 0.02 mR/hr 0 OM 1/8 Top Of Big Cylinder Wall WW 0.02 mR/hr 1(0) 0/0 1/8 Base Plate XX 0.02 mR/hr 0 0/0 1/8 Bottom Section YY 0.02 mR/hr 0 0/0 1/8 Bottom Pan Of Big Cylinder 2Z 0.02 mR/hr 0 0/0 1/8 Bottom Of Big Cylinder Wall AAA 0.02 mR/hr 0 0/0 1/8 Top Of Big CylinderWall BBB 0.02 mR/hr 0 0/0 1/4 Top Of Big Cylinder
CCC 0.02 mR/hr 0 OM 1/4 Top Of Big Cylinder DDD 0.02 mR/hr 0 OM 1/4 Top Of Big Cylinder EEE 0.02 mR/hr 0 OM 1/4 Top Of Big Cylinder FFF 0.02 mR/hr 0 0/0 1/4 Interior Cylinder Wall GGG 0.02 mR/hr 0 OM 1/4 Interior Cylinder Wall HHH 0.02 mR/hr 0 OM 1/4 Interior Cylinder Wall III 0.02 mR/hr 0 0/0 1/4 Interior Cylinder Wall ; JJJ 0.02 mR/hr 0- 0/0 Interior Cylinder Floor 9 m e
Anoendix H; Survey Instruments And Operation Data The following survey instruments were used during the decommissioning process of the AGN 201M reactor. Liquid Scintillation Counter. Mau: Beckmrm LS-7000 Serial Number: 7700259
Background:
Ch.1 = 9+-6 cpm / Ch. 2 = 17+-8 cpm Efficiencies: (wipes) H-3 = .03 / C-14 = .04 / P-32 = .60 / I-125 = .35 CaEbration Date: Calibrated monthly Instrument Used: Preliminary Defueling (console wipes), Facility Survey, AGN Components, Unrestricted Release Windowless Gas Flow Proportional Counter. Make: Ludlum Model 2200 scalar Serial Number: 19788
Background:
0-5 cpm Efficiencies: (wipes) alpha = .35 Calibration Date: 5/21/93 Instrument Used: Core Components , AGN Components, Unrestricted Release Thin Window G-M. Make: Technical Associates TBM-3S Serial Number: 093127
Background:
50+-20 cpm Efficiencies: C-14 = .05 / P-32 = .27 j Calibration Date: 728/92,7/26/93 Instmment Used: AGN Components, Unrestricted Release . > Thin Window G-M. Make: Technical AssociatesTBM-3S Serial Number: 087129
Background:
60-150 cpm Efficiencies: C-14 = .04 / P-32 = .23 Calibration Date: 12/22/88 (blocks), 6/23/89 (defueling) Instrument Used: Concrete Blocks, Defueling, Core Components Thin Window G-M. Make: Technical Associates TBM-3S q Serial Number: 066164
Background:
70-140 cpm Efficiencies: Cl-36 = .22 Calibration Date: 6/25/87 Instrument Used: Concrete Blocks ( 1 HI
r Thin Window G-M. Make: Technical Associates TBM-3S Serial Number: 092332
Background:
50 cpm (blocks) Efficiencies: Cl-36 = .22 Calibration Date: 12/22/88 Instrument Used: Preliminary Defueling, Concrete Blocks Pressurized Ion Chamber Make: Victorten 450P Serial Number: 172
Background:
N/A Efficiencies: N/A Calibration Date: 2/6/89 Instrument Used: Defueling Micro R Meter Make: Ludlum Model 19 Serial Number: 7950
Background:
.03 mR/hr Efficiencies: N/A Calibration Date: 7/28/89 Instrument Used: Defueling, Core Components Ludlum Alpha Scintillation Make: Ludlum 43-1 PRO #02132 Serial Number: 33640
Background:
0-1 cpm Efficiencies: alpha 31% Calibration Date: Instrument Used: Defueling High Purity Ge Crystal Make: EG&G ORTEC Serial Number: 25-P-K72
Background:
10 nCi Efficiencies: Varies with energy Calibration Date: at each use Instmment Used: AGN Shield Water Survey EPA Detectors: The following detectors have their background and efficiencies determined by the EPA. These detectors are rotated out every year and are no longer on site. Ion Chamber Make: Eberline Serial Number: 289
Background:
N/A x Efficiencies: N/A i Calibration Date: 1/22/89 i Instrument Used: Defueling i l i 112 l l
Ion Chamber Make: Eberline E-5008 Serial Number: 1015
Background:
N/A Efficiencies: N/A Calibration Date: 12/18/89 Instrument Used: Defueling Ion Chamber Make: Eberline RD-2A
' Serial Number: 1263
Background:
N/A Efficiencies: N/A Calibration Date: 7/28/89 Instrument Used: Defueling, Core Components l 1 l l H3
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