ML20081J850

Rev 1 to Final Rept, Summary of Decommissioning Process of Univ of UT AGN-201M Reactor 107

ML20081J850
Person / Time
Site:	05000072
Issue date:	03/17/1995
From:	Gehmlich D UTAH, UNIV. OF, SALT LAKE CITY, UT
To:
References
NUDOCS 9503280220
Download: ML20081J850 (174)

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A Summary Of The Decommissioning Process I of The University Of Utah AGN-201M Reactor No.107 )

l Final Report i Rev.1 License No. R-25 ,

Docket No. 50-72 j Prepared By:

C. Ross Schmidtlein Darrell S. Hall John S. Bennion Enrique C. Estrada Henry F. Moeller David M. Slaughter, Ph.D.

Gary M. Sandquist, Ph.D.

March 17,1995 Center for Excellence in Nuclear Technology, Engineering, and Research-C.E.N.T.E.R.

University of Utah Salt Lake City, Utah 84112 i

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Dietrich K.Gehmlich f

3 Reactor Administrator 0

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@f Table of Contents Decommissioning Activities ......................................... ......................... 1 Results And Major Milestones .... ............................................. ........ 2 E Supporting Documentation ............................................................ ....... 4 Summary Of Decommissioning Activities ............. ................ ........... ....... 5 Reactor Parts Disposition ............. .. ......... ........................... ............. 6 Fuel And Start-Up Source Disposition .................................................. 6 Concrete Block Disposition .................................................................... 6 Facility Disposition .............................. ................... ........ .. ... . ....... 7 Appendices ............. . ............ .... ............. ... ....... ...... .................. 8

- Appendix A: AGN Parts List And Location A1 to A4 Appendix B: Completed Disassembly Procedures Bl to B16 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 Cl to C9 Appendix D: Parts Disposed Of As Radiological Waste D1 to D9 Appendix E: Pans Released As Unrestricted Waste El to E6 Appendix F: Fuel Shipment Infomiation F1 to F16 Appendix G: Survey Results G1 to G77 Appendix H: Survey Instrument Data H1 to H4 Appendix 1: Survey Operation And Site Data Il to 112 Attachment : CENTER Response To NRC Document Review 1

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i A Summary of the Decommissioning Process l of the University Of Utah AGN-201M Reactor No.107 l Final Report This repon describes all decommissioning activities of the AGN at the CENTER in order to l verify that the UU AGN reactor was decommissioned in a safe manner, complying with all NRC ,

l regulations, stipulations, and in accordance with the NRC approved decommissioning plan, I L " Decommissioning Plan, University Of Utah, AGN-20lM Reactor No.107, License No. R-25, l 1

Docket No. 50-72." More specifically, this document contains the survey results, the final destination records for the reactor parts, fuel transport records and a description of all the completed decommissioning procedures.

Decommissioning Activities ,

l The equipment, structures, and portions of the facility and site containing radioactive contaminates were decontaminated to a level that permits the property associated with the University of Utah's AGN-20lM Nuclear reactor to be released for unrestricted use. A brief description of the decommissioning 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.

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 decommissioning plan for the AGN-20lM.

6) Perfonned a detailed survey of the decommissioning area.

7) Transferred the fuel to the DOE.

8) Disassembled the AGN.

9) Surveyed the remaining pans of the AGN.

10) Disposed of and decontaminated the reactor parts.

I1) Scheduled a survey with the NRC to remove all decontaminated parts.

12) Prepared Final report on the decommissioning for the NRC.

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When the NRC completes the final simey to confirm our results, the license will be - ]

surrendered to them. In the case of the Univershy's AON site, the room in which the AGN reactor l is located will be retained with the University's TRIGA reactor under the current TRIGA license. l 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 of. j i

Results And Major Milestones  ;

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The decommissioning preuss for the AGN-201M closely followed the planned decommissioning activities. However, small changes were made as needed to ensure regulatory compliance and radiological safety.

. The preliminary steps for the decommissioning of the AGN-20lM 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  !

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defueling steps, the Ra-Be neutron source and the fuel were removed and surveyed in detail. At that time, all components in the reactor 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 smveys showed very little removable contamination on any of the core components.

. On January 9,1989, the AGN-201M'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 received NRC l approval for decommissioning. It described in detail the steps and procedures that were to be used to decommission the AGN-20lM reactor.

. The reactor fuel was shipped to Martin Marietta Energy Systems at the Oak Ridge i National Laboratory for the DOE on February 5,1991.

A considerable delay existed between the completion of the decommissioning plan and the actual decommissioning of the reactor. This delay was panially due to the interest of the faculty from University of North Texas State in acquiring the reactor. If the reactor was to be transferred, j t

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 l decided against acquiring the reactor and the current decommissioning was reinitiated During the l

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delay, instrumentation and personnel changed. Therefore,in order to ensure consistent and reproducible results, it became necessary to duplicate some of the steps performed during defueling operations, such as surveys of the decommissioning site and core components.

Another site survey was perfomied prior to component surveys to ensure that no contamination existed in the area surrounding the AGN reactor. This survey was performed on March 25,1993.

• The next step in the decommissioning procedures was the disassembly and survey of the reactor for fixed and removable contamination. 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: 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 manner of disposal varied for each component and was based on several factors including cost of disposal, value of the component, and level of contamination on the component.

Parts from the core can had alpha contamination from contact with the fuel. Most of these parts were of no value outside the AGN, thus these parts were disposed of as low level radioactive waste. The gmphite reflector was of value for future experiments conducted in the TRIGA reactor program and was therefore transferred to the University of Utah TRIGA reactor license. Outside of the core can, the main graphite reflector and lead shield were also deemed valuable and were moved to the TRIGA reactor license. The control console and two drives were transferred to the ISU reactor license.

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 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 informed of this progress. A contractoremployed by the NRC will be scheduled to perform the confim1ation survey of the parts from the reactor designated for disposal in a public land fill.

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The NRC final inspection is the last requirement in the decommissioning process. When the NRC has perfonned a confirmation survey. the remaining reactor parts will be released as non-contaminated waste.

Supporting Documentation 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-20lM are numbered and described along with drawings. The intent of this Appendix is to identify clearly where the various parts are located within the reactor and establish an effective strategy to ensure accurate record keeping fo' surveyed reactor pans.

Appendix B contains the disassembly procedures used during the oecommissioning of the reactor. The completed procedure sheets included in this appendix document the process and demonstrate compliance with the decommissioning plan.

The Appendices C, D, and E together document the final disposition of all non fuel AGN-201M parts. Each part or related group of parts have been photographed and their part numbers and final disposition have been listed. Appendix C's parts are transferred to the licenses of other nuclear n actor 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 infonnation is located in Appendix F. The final disposition of the fuel is documented by checklists, approval and transfer fonns, and a list of the non-University of Utah individuals involved in the fuel shipping process.

Appendix G contains the results of the radiological surveys conducted during the decommissioning of the AGN-201M reactor. This section contains surveys for:

Facility, Concrete blocks surrounding the reactor, Water shield, i Thennal column,  !

I Start up source and fuel, Core components survey, and 4

Parts to be unrestrictedly released The Appendix H 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 infonnation provides further documentation of the process involved in decommissioning the reactor.

The final appendix, Appendix 1, is an additional appendix insened in the first revision of this document in order to clarify the methodology of the decommissioning process. This section contains more detailed information conceming the actual perfoanance for the decommissioning tasks and surveys.

A copy of the document review of this final report and our response to the questions posed in the review is attached to this revision of the report. This attachment will answer the questions in the document review and give the relevant page numbers where this final decommissioning report was modified according to the document review. In this manner, all questions concerning the final disposition of the UU AGN reactor and facility should be answered.

A copy of the NRC approved decommissioning plan for the AGN has also been added as an attachment to this repon. The plan entitled," Decommissioning Plan University Of Utah AGN-201M Reactor No.107", will add clarity to the final decommissioning report's description of the steps and processes used to decommission the AGN reactor.

Summary of Decontaminating Activities Due to the low power level (5 watts) design of the AGN-20lM reactor and the low reactor power total (286.55 watt hours), the activation of materials was 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 hanal found in the reactor. The exterior components which indicated no contamination will be released to general disposal after direct surveys from the NRC to confirm our results.

In the process of decommissioning the AGN-201M reactor, certain items (wood, paint chips) had to be considered low level waste even when results from radiation and swipe surveys indicated that these items were not activated or contaminated. This is due to their material 5

m characteristics and form. Properly transferring selected components of the AGN reactor from its license to our TRIGA reactor license or to other facilities allowed the usefulness of those components to continue.

Reactor Parts Disposition A break down of the final status and disposition of the reactor parts is as follows:

Status: Part Numbers: Disposition:

Radiological Waste 1,2,4 to 13,18,32 to 41, and Disposed of Through 80 to 83 Radiological Health.

Transferred Parts 17,19 to 21,28 to 31,42 to 57, Shipped To Designated 61 to 79,85 and 87 Licensed Facility.

Non-Contaminated Parts 3,14 to 16,22 to 27,55,58 to 60, At AGN Facility Pending And Waste and 84. 86 Confim1ation Survey.

A description of these parts can be found in Appendix A.

Fuel and Start-Up Source Disposition The AGN-201M's fuel has been shipped to Martin Marietta Energy Systems at Oak Ridge National Laboratory and is no longer on site, as listed in Appendix F of this report.

The start up source is also no longer on site. As listed in the Decommissioning Plan, page 4, it has been shipped to R AMP Inc. for ultimate disposal at the U.S. Ecological site in Beatty Nevada.

Concrete lllock Disposition The concrete blocks have been surveyed and removed from the AGN-20lM Facility as  ;

listed in the Decommissioning Plan, Appendix F. l l

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Facility Disposition 1 .l' 1

o The facility where the AGN is housed (Room 1205-E) is under License No. R-126, Docket No. )

. 50-407, of the University Of Utah's 100 kW TRIGA reactor. This area is the TRIGA reactor ' )

room, and therefore will remain a restricted area indefinitely. l 1

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APPENDICES:

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A 4 -Annendix A:

AGN-201M Parts List And Location j The following is a list of the numbered pans of the AGN-20lM reactor. The numbering system was used to facilitate the surveys of the reactors parts. This list gives the pan number used '

in the surveys, a description of the parts, and the pans location in the reactor. Also for greater clarity two figures are included with the pan numbers and the pans location in the reactor. -

Part 1 Description Location 1- Safety Rod #2 (Empty) Core Can 2 Course and Fine Control Rod Thimbles Core Can 3 "O" Ring Core Can Toa Plate Core Can 4 Paint Chips from Thenna. Column Thennal 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 .;

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 Pans Core Can 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 i 21 Graphite Reflector ( Bottom Interior Core Ca 1) Core Can 22 Internal Thermal Column Themial Column 23 External Thennal Column Thennal Column -

24 Top Thermal Column Cover Plate Thennal Column 25 Bottom Thermal Column Cover Plate Thennal Column 26 Socket and Wrench Exterior to Core 27 Glory Hole / Port Covers Assembly with Covers Glory Hole / Access Po 1 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 Port Access Port 33 Wood Plug in Access Port 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 Pon 37 Wood Plug in Access Port Access Pon 38 Wood Plug in Access Port Access Port 39 Wood Plug in Access Port Access Port A1

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Part 1 Description Location  ;

40 Wood Plug in Access Pon Access Port 41 Wood Plug in Access Port Access Port l 42 Lead Plug in Access Port Access Port- l 43 Lead Plugin Access Port Access Port 44 Lead Plug in Access Pon Access Port 45 Lead Plug in Access Port Access Port 46 Lead Plug in Access Pon AccessYon '

47 Lead Plug in Access Pon Access Port  !

48 Lead Plug in Access Port Access Port 49 Lead Plug in Access Port Access Port 50 Lead Plug in Access Pon Access Pon ,

51 Lead Plug in Access Port . Access Port 52 lead Plug in Access Port Access Port i 53 Lead Plug in Access Port Access Port i 54 Lead Plug in Access Port Access Port 55 Lead Plug in Access Port Access Port  ;

56 Lead Plug in Access Pon Access Port 57 Lead Plug in Access Port Access Port  !

58 Aluminum Fuse Support Core Can 59 Ali gnment Screws Below Core Can 60 Po;yethylene Rod Glory Hole  :

61 Graphite Plug in Access Port Access Port 62 Graphite Plug in Access Pon Access Port j 63 Graphite Plug in Access Pon Access Pon i H

64 Graphite Plug in Access Port Access Port 65 Cadmium Plug Glory Hole 66 Graphite Plug in Access Port Access Port 67 Graphite Plug in Access Port 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 Port 73 Aluminum Access Port Sleeve Access Port 74 Graphite Reflector Column Surrounding Core Car 75 Bottom Lead Shield Ring Below Core Can 76 Bottom Lead Shield Ring w/ Access Pons Surrounding Core Car l 77 Top Lead Shield Ring w/ Access Pons _ Surrounding Core Car 78 Top Lead Shield Ring Surrounding Core Car 79 Bottom Lead Shield Plate Swrounding Core Caa 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 Suaport Plate Below Core Can 85 Cadmium Jisks Glorv Hole 86 Main ReactorTank Main ReactorTank 87 Reactor Console Exterior to Reactor A2

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l Annendix B:

Comnleted Disassembly - Procedures l

The following disassembly forms are listed in this appendix. i Form: Ill!c Status:

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Form NEL-103 Dismantling Plan for the University of Utah AGN-201 Completed Reactor  ;

1 Form NEL-104 University of Utah Nuclear Engineering I_aboratoiy No Completed 4 AGN-201 Reactor Defueling Procedum Form Exists i 1

Form NEL-105 Procedure for Removal AGN Control Rods Completed )

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Form NEL-106 Procedures for the removal of Ra-Be Neutron Source Completed i l

from AGN-201 Reactor" i

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l Form NEL-103 Dismantling Plan for the University of Utah AGN-201 Reactor:

' The AGN reactor was already partially disissembled by the previous administration's decommissioning activities. The steps marked NA were either i i

unnecessary due to previous decommissioning activities, or unnecessary because the l reactor will not be reassembled. Below are listed the steps that are marked NA and the reason for this marking. This form was completed by C. Ross Schmidtlein.

From NEL-103:

II.1. b. 4) Ra-Be source previously removed.

II.1. b. 7) Fuel previously removed.

II. 2. c. 2) Ra-Be source previously removed.

II. 2. c. 4) Fuel previously removed, manually lifted can.

III. 4) Plates previously removed. .

III. 6) Part previously removed.

III. 7) Rods previously removed.

III. 8) Rods and fuel previously removed.

III.10) Thermal column previously drained. 1 III.12) Ra-Be source previously removed.

III. 13, 14 .15 ,16 ,17 ,18, 19) Fuel, rods, and source previously removed.

III. 23. a) Reactor will not be reassembled.

III,24. a) Reactor will not be reassembled.

111. 25. a) Reactor will not be reassembled. l III. 26) Shield water previously drained.

III. 27,28) Console previously removed.

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Form NEL-103 RSC Approval:5/25/88

- Dismantling Plan for the University of Utah AGN 201 Reactor I. Intmduction  :

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. Prenaration Prior to DimumblX 0 0 .3/2.5/52 1. ~ Radiation Pmtecuon  :

a. He following instruments will be checked for proper operation, then placed in the reactorroom for use:

OU 3/2Slw 1) Continuous air monitor or high volume air sampler.

C/d 3/IS/M 2) Neutron survey meter (p.dd "iC Neutron survey yg meter). ^%M 4 -W sw:%. o '??

64 7/X/#>J 3) Beta-gamma dose rate survey meter (Cutie Pie or Radector). ITs3 i  ;

aC J/zr/43 4) Contamination survey meter (thin-window Geiger counter). w o. 7pa ogm l

b. He following supplies will be collected and placed in the reactor room for use l as needed.

(/J 7/25/9 1) Filters for air sampling. l u"> J/25/or 2) Smeanng materials for wipe tests. '

0 6 vr.r/+1 3) Containers for air samples and wipe test smears.

uD #A 4) Shielded storage container for storing the Ra-Be startup source.

ua 3/tr/o 5) Coveralls, lab coats, gloves, and shoe covers.

6) Radioactive waste containers.

L@W #A'Jtrh 7) Cadmium foil for core can insen.

(4) JINM 8) Respiratory protection equipment.

6/d 3/2fA3 2. Work Area and Tools Cp 3/trA1 a. Survey reactor room area in preparation for proposed activities.N c/> 3/4rA 3 b. Relocate equipment as necessary to maximize working area room.

ce 3 /1r/4> c. Collect the following tools and place in reactor room: -

ury 3/z rAI 1) Hand Tools (socket and Allen wrenches) required for disassembly.

@ kA 2) Handling tool for removing the Ra-Be source.-

OD % r/M 3) Lifting lugs and rigging for thermal column, core tank, and upper graphite reflector.

W A/A 4) Can for transponing the core can to the designated storage area.

c/o 3/trAr d. The following items will also be placed in the reactor room:

tr> 2/25/6 ? 1) Plastic bags for packing components.

CM 3/z/A> 2) labels for dismantled components.

cn 3h r/M 3) Camera with flash and film for photographically documenting the procedure at key stages.

III. Detailed Disassembly Pmeedures NOTE: De assembly part numbers are correlated with the part listing on drawing number E-2-000100.

Cf.) Vlf/M 1. He Health Physicist will make a pre-disassembly radiological survey. He will also initiate special access procedures, personnel and equipment monitoring l procedures and other procedures needed to keep radiation exposure as low as l reasonably achievable. An operational check will be made of radiation monitoring l

.i equipment present. If all equipment responds properly, the operadon will proceed. l LM'q17/95 2. De 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.

C$ NA 3. Insure that the temporary cadmium rod is in the glory hole and well fixed.

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Form NEL-103 g

RSC Approval: 5/25/88 Gk N 4. Remove bottom cover plate (2-000169). De gasket (2-000593) should come off with the cover. Bag the cover plate thumb screws (H-1007-10) and label.

. (g) NN - 5.

Insure 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: 2-000550 I  ;

Safe Rod Assembly 2 000550 II l Coarse Control Rod Assembly 2-000550 III L Fine Control Rod Assembly 2-000550 IV C@ NA 6. Remove the three dash pots (2-000510), label and store for future shipment.  !

()L) A/A 7. Remove the four control rod 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 i i cach rod drive frame assembly until free. Identify and label each frame. .

Bag thejam nuts and label.  ?

C#3 M, 8. Insert cadmium in the control and safety rod holes in the core can.

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9. 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 NA 10. Drain 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 CM 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 records will be made in the Waste 1.og, including: date/ time; estimated water volume dumped; gross sample results j in pCi/ml, % of applicable mpc, estimated activity dumped.

@ Y/UU 11. Remove the thermal column (2-000139):

J NOTE: hermal column could weigh 2,000 to 2,400 pounds.

QO Ml/'n a. Unbolt thermal column from reactor tank (16 each 3/4 inch bolts).

F/th7 b. Attach lifting sling W,. to crane and thermal column.

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c. Lift thermal column from well (the dynamometer will indicate the weight of the l

lead-lined thermal column). Ibs.

QO W/h3 d. Remove thermal column from reactor and move to an appropriate space on the floor. Set thermal column on M==' par. /% A CM Md c. 1.abel thermal column. Bag the 16 each 3/4 inch hold-down bolts and label.

gp ara 12. Remove the Ra Be neutmn source (H 3018) from the graphite reflector.1.cak test the source and place it in the storage container.

Cg) MA 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.

(N MM 14. Remove cadmium rod from glory hole (operator monitor neutron detector channels 1 l through 3 H.P. representative monitor portable neutron survey nxter response). 1 Only a slight increase in reading may be noted. (Log any reading change.)

BEFORE AFTER CRM:

LOG: l LINEAR:

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15. 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).

QO \ b. Remove glory hole flange "0" ring (H-4009) (2 each).

\ c. Remove glory hole tube (2-000422). Extreme care should be taken when

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removing this tube. It should not be bent (straight pull) and if binding is l excessive, it may be necessary to lift the core tank slightly tc, relieve the bind.

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Form NEL-103 RSC Approval: 5/25/88 COMMEN13: q NGIE: . De Health Physicist will monitor very closely the removal of the core i can. All radiation and criticality monitors will be checked for proper i operation just prior to the removal of the core, and surveys of radiation levels from the core can will be made continuously during removal.

C/d M 16. Core Can Removal (2-000114):  ;

\ a. Make a refemce mark on the core can and graphite reflector for reassembly orientation.

([l \- \

b. Attach lifting frame with cap screws (sock HD.,10 X 24) to core tank.

c. Attach lifting frame and dynamometer to hoist. 'Ihe dynamometer will monitor lifting loads.

NO'IE: Hoist must be positioned with care to insure vertical alignment. Any deviation fmm the vertical will cause binding of the core tank in the reflector and shielding of the reactor. The unit being lifted weighs appmximately 250 pounds. Tension should be applied with the hoist and the core tank lifting frame should be manipulated until any excess force 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 l man will stand by the hoist circuit breaker (Panel B, Breaker #5) in the  ;

event of an up" bunon failure of the hoist. Binding should be expected for j approximately 4 inches until the thimbles have cleared the lower housing. 1 CN \' d. Lift the core tank from the reactor.

17. Place an appropriate piece of cadmium in glory hole.

( g)d U

ANA M ,

18. Conduct radianon survey to determine ducct radiation levels from the core can and removable surface contanunation on the exterior surface of the can.

19. Transfer the core to its storage container.

a. Remove lifting frame.

b. Seal and label core can container and hold in Reactor Room.

4d 4/6Y4 7 20. Health Physics will perform a radiation survey of accessible internal surfaces to ascertain direct (induced) radiation levels and removable contamination levels.

NOTE: This concludes the nuclear portion of the disassembly process. The remaining disassembly will be conventional mechanical and electrical, with radiation surveys made as directed by the Health Physicist.

C#l N, /# 1> 21. Remove the four eight access pon cover assembly (2-000476):

cg) 4h/D a. Remove the eight access pon cover assembly (2-000476) c4 p/FM3 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).

Ca> dh/ c. Remove access pon rianges (2-000418) (8 each) by removing (4 each) screws (H-1023-8)(socket HD mach., 1/4 - 20 1/2).

(M Y/f/D d. Remove access pon flange "0" rings (H-4008) (8 each).

c4) WI//r e. Remove access pon tubes (2-000420) (4 each).

c/O M/ 73 f. Conduct health physics survey on the access pon tubes.

cs<>4G/D g. Label all pans and store.

QOM/I/77 22. Remove the outer graphite shield (2-000140).

"(f t> M4 a. Make alignment marks in the graphite shield and lead shield ring #1.

b. Screw in lifting eyes.

(K) 4hNUIE:

/'D De lifting eye size will be determined and acquired sometime after the H5

(

Fonn NEL-103 RSC Approval: 5/25/88 thermal column has been removed.

N Yf/N c. Attach sling to hoist. (1he graphite reflector will weigh ~700 pounds.)

d e/r/U d. Slowly raise graphite shield until clear of reactor,

e. Actualreflectorweight: lbs.

(g) O/ k/92 f. Transfer to appropriate storage area and label.

4 23. Remove the four lead shield rings.

y)g/r/95v/A a. Make alignment marks on the first lead shield and reactor structure for reassembly.

(j() 4/f/77 V/v/W b. Screw in hfting eyes. (perhaps the graphite reflector eyes can be used.)

cg > c. Attach sling and dynamometer to hoist.

g)V/t/91 d. Slowly raise lead ring; monitor for binding until clear of reactor.

NOTE: lead rings 1 and 4 weigh 600 pounds, ring 2 weighs ~900 pounds, and ring 3 weighs ~800 pounds.

Od h/f/'/) e. Transfer to an appropriate storage area and label.

(g) Wr/fJ 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 lbs.

C/t) M/f/ D 24. Remove the core support plate (2-111253).

cgf NA a. Place alignment marks on core support plate (top and bottom).

cg) 4h / 67

b. From beneath reactor, remove hold-down bolts (H-1114-%) (4 each, right-hand thread). Do not change position of tension nuts (H-2017).

CAUTION: Control rod drive tie bolts are still attached to core support plate.

Take care not to bend or break bolts.

Ot) 9/f/O c. Manually lift plate from the top and transfer to floor area for storage.

00 O/H%r 25. Remove the lead base plate shield (2-000124).

(/2J ' M1 a. Make alignment marks on the lead base and reactor structure.

99 9/WM b. Screw in lifting eyes.

y.; W/H+3 c. Attach sling and dynamometer to hoist. (This piece should weigh slightly less than the thermal column.)

Ot) 4/Fh3 d. Slowly raise lead base plate; watch for binding until clear of reactor.

Actual weight: lbs.

@l I //fA3 c. Transfer to floor area for storage.

COMMENTS:

N M 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 i release of the water).

I b. Connect hose to drain valve (H.3009) at bottorn of shield tank and drain water

[) NOTE:

to sewer. Reactor manhole cover should be off.

Entries will be nude in the Wasic Log, including: dateAime; estimated quantity dumped; activity of sample; estimated activity dumped.

c. Close drain valve and remove hose.

i REMARKS:

hC-) 27. Reactor electrical and instrumentation disassembly:

H6

Form NEL-103 RSC Approval: .V25/88 ;

He electrical and instrumentation cables will be disconnected in the following -

general sequence. Dey will be identified for future reassembly, surveyed, and . ,

packaged for transportation.

4 a. NuclearChannel#1:

1) Detector channel H.V. off.

) 2) Ratemeter main power off.

\ 3) Open and remove access manhole cover.

\ 4) Remove detector dry well from reactor tank shield water.

i 5) Disassemble dry well.

! 6) Disconnect and tak nre-am (2) and H.V (1) cables.

7) Transfer componeut.s to clean area for radiological survey (gross smears),

and packing.

b. Nuclear Channels #2 and #3:

I 1) Disconnect and tag H.V. cables at battery supply pack (rear of control console). .

f

2) Remove # mar dry wells from reactor tank shield water.

([ I 3) Disassemble dry wells.

I

4) Disconnect and tag signal and H.V. cables.

i 5) Transfer components to clean area for radiological survey and packing.

I

c. Maindistributioncable:

_l 1) Main power switch (left side reactor console) off.

i

2) Disconnect and tag P-15 (control console).

i

3) Disconnect and tag P-16 (control console).

i

d. Miscellaneous:

i

1) Disconnect and tag monitor cable at control console. Pull it to storage

! beneath reactor tank.

2)' Disconnect and tag main power cable.

3) Remove the EARTHQUAKE SCRAM ASSEMBLY ball (H3005), bag i and label.

4) Remove the THERMO SWITCH (E-10035).

i

a. Labelelectricalleads.

b. Disconnect electncal leads.

c. Label thermo switch and bag for shipment.

De console will be retained in its present location until final disposition.

B7

Form NEL-104 University of Utah Nuclear Engineering Laboratory AGN-201 Reactor ,

Defueling Procedure:

Defueling was conducted by the previous reactor administration. The Form NEL-104 was created under this previous administration. After conversation with personnel from this administration it was determined. that the form NEL-104 was followed in detail during the defueling. Unfortunately the c'empleted version of this form can not be found.

This form was completed by John S. Bennion.

-i ,

l B8

L' RSC Approvst mm .

University of Utah Nuclear Engineering Laboratory i AGN.201 Reactor Defheling Piscedure i

- 1. Intmanedan This document gives the general pow 4-w to be followed for defueling the, AGN-201 ,

reactor. These pmcedures pve details regarding the preparations, monitonng, setup, general 4-eand va M*Hagprocedmes.-

NOM: Check and date each s, tem in the appropn, ate place.as each step is na d Maintain one master copy for reference.  ;

- II. M- - := Prkeinbef>=Hne

1. Radianon Ppecnon '

~

a. De fouowmg instruments wiu be chantred for proper operation, then placed in 1205-E foruse:

1) High-volume airsampler.

2) Neunon survey meter (Texas Nuclear Bonner Sphere).

3) Beta / gamma dose rate survey meter (Eberline).

4) canenminneian survey _ meter (TBM-3S).

b. He fouowing supplies will be canaewd and placed in the reactor room for use as needed.

1) Fibers for high-vohune air sampling.

. 2) Smeanng materials for wipe tests. '

3) Containers for air filters and wipe test smears.

4 4) Shielded storage container for storing the Ra-Be neutron source.

5) Coveralls, lab coats, gloves, and shoe covers.

6) Radianerive waste containers.

7) radminm failfor core caninsert. .

8) Respiratory pra'a*iaa eq -h- =^ (retain at first-aid station unless required). l J

~

2. Work Ama andTools

a. Survey reactorroom area in preparation of defueling activities.

b. Relaense e r : == as nece=enry to maximize working area room.

c. Caltect the fo kming tools and place in reactor room:

~1) Hand Tools required for dienteamhly (socket and Allen wrenches).

2) Handlirig tool for removing the Ra-Be source..

3) Lifting lugs and rigging for thermal column, core tank, and upper graphite reDector.

d Defollowingitemswillalsobeplacedin 1205-E:

1) Plastic bags for storing ces-mts.

2) camera with flash and film for photographically documenting the .

ruwd e at key stages.

III. Detailed Disassernbly Pmcedures NOTE: he ===amhly part numbers are contlated with the part listing on drawing number E-2-000100. He ventilation system and air sampler should be operanng during all disasssembly stocedures.

1. A representative from the Radiological 3ealth Department will perform a pre-defueling radiological survey.

2. The Reactor Supervisor will initiate special access procedures, personnel and eqa rue.et monitonng pmcedures and other procedures as needed to keep personnel radiation exposures as low as reasonably achievable (ALARA). An operanonal check will be made of radiation monitoring equipment. If all equipment responds properly, the operation may proceed. He Reactor Supervisor will brief personnel involved in the ,

defueling operation on each step prior to its completion, with clarification made, as necessary, of the tasks to be >'unued.

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 thermalcolumn.

B9

,. . - . - - .. . ~ . -

'~

RSC Approval:$/25/8b

a. Obtain perminnian from the Health Physicist to drain thermal column water l so newer (a water sample will have been previously taken and analyzed for a radioactivity as a basis for release of the water).

b. Pump water to sewer until thermal column is as dry as possible.

NO'IE: The entries for health physics records will be made in the Waste Log, including: dateAime; **ima*A water volume dumped; gross sample results in pCihnl, % of applicable mpc, estimated activity dumped.

~

5. Reneve the thermal enlumn (2 000139):

NCTIE: 'Ibermal column is estimawd to weigh 2,400 pounds.

a. Unbolt thermal column from reactor tank (16 each 3/4 inch bolts).

b. Attach lifting sling to crane and thermal column.

c. Remove thermal column from reactor and move to an appropriate space on the floor. Set thermal column on plastic sheet or absorbent paper.

d. Label thermal column. Bag the 16 cach 3/4 inch hold-down bolts and label.

6. Place borated paraffin over Ra-Be source and perform radiation survey of thermal column cavity. Replace top cover plate and secure te flange at top of reactor tank until ready for removal of neutron source. Survey exterior surface of top plate cover -

for radianon level and possible contamination; mark area as a radiation hazard as appropnate.

7. Remove and survey each lead brick from thermal column. U wper towels to dry the lead and dispose of towels as low-level contaminated was. 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 rods and store in approved fuel storage locations.

Safe Rod Assembly: 2-000550 I l Safe Rod Assembly 2-000550 II Coarse Control Rod Assembly 2-000550 III 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 control rod 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 cach) jam nuts (1/4-28) from the iie bolts and carefully lower each rod drive frame assembly until free. Identify and label each frame.

Bag thejam nuts and label.

12. Insert neutron absorber in 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 Il 10

o 1 RSC Approval:5/25/88 r

CRM- i 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).  !

p c. Remove glory hole tube (2-000422). Extreme care should be taken when l 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: ,

i l

l NOTE: The Health Physicist will carefnlly 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 cononuously during removal.

~ 18. Core Can Removal (2 000114):

a. Attach lifting frame with cap

b. Attach lifting frame and st. to hcu, screws (sock.HD.,10 X 24) to core tan NOTE: Hoist must be positioned with care to insure vertical alignment. Any_

deviation fmm the venical will cause hinding of the core tank in the reflector and thiaMing of the reactor. 'Ihe unit being lifted weighs approximately 250 poc uls. 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 elecuical hoist could cause '

d==*=,e 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. Bindmg should be expected for 4

.m. : =!y 4 inches until the thimbles have cleared the lower housing. -

d. Lift the core tank frorn the reactor.

NCrrE 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. Removeliftingframe,

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 ascertain direct (induced) radiation levels and removable contamination levels.

NOTE: This concludes the nuclear ponion of the disassembly process. The remaining die ==ambly will be conventional mechanical and electrical, with radiation surveys made as directed by the Health Physicist.

B11

. f - . .

• v

~

Form : NEL-105 .

H ' Procedure for Removal AGN Control' Rods:

The following additional comments are hand written on the back of the original-.

Form NEL-105 and are a continuation of step 8, the comments section.

"... plastic and placed in a temporary steel barrel. The barrel was secured in the middle fuel

-storage pit and will remain there pending transfer of fuel to DOE."

These comments were written by John S. Bennion. This form was completed by John S.  !

- Bennion.

a l

l 1

i l

l B12 g -

w- c - o +-- w

. Procedure for Removil of AGN Control Rods 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. gs

2. Carefully lower the control rod gvoiding binding and remove the assembly from the crawl space beneath the reactor. fg

3. Survey the rod and record radiation levels in spaces provided below. Wipe the exterior surface of the fuel cladding to determine i$ surface contamination exists. Note below any  ;

removable contamination discovered. / c7$

Instrument: '7)f h/ - y S Serial No.: r) 27 /2 9 Calibration Date: M i 2 M 93 )

CR1 CR2 Fine Coarse N Max. level

@ contact . O b SI M /g

• O6 6yge ,0 M h MCO(pg N. %i s 06$mC4x-Max. level i

@ t root *03Em24r .030Mehr . o ? %jg,_ %C00 l 4 Unscrew the fueled control rods from the remainder of the assembly'ahlIc#'$ e the temporary storage container. Survey the drive assemblies for any residual contamination or i activation. Note belovj any elevated radiation levels. Set the drive assemblies aside for future  !

use as necessary. /p  :

5. Repeat steps 1 through 4 for each control rod. Insert boratedparaffin between the control rods and secure contamer lid when all fuel has been loaded. /p/

6. Load borated paraffin into the reactor core through the control rod guide tubes assuring that the paraffin willremain in place. /g

7. Place the temporary storage container in the Middle Fuel Storage Pit and secure until ready for shipment to DOE. / vfy f

)

i

8. Comments: w , .>e s . (hnduy%d - @ 9-)

_ F W A . M 'v th^ '_ Oy,Ve_44 h4b -

l pu wt: n o MehW 80% . no .eccMG c.mla,%Jlm l sg , a .. .. .. ,,

SRI; " *'

j w,Q >< ..

lVc &c fts *)h L'Ot tit (MhtDNbs &sery/c/ /t>t tbstf fcyfrix Q( ifGL f ttHlfY VYN

<%w) e &ta mAics 5.[M't M<Wsd Date Procedure Started:

I

/8'I ms m.m. me&<t .i Date Procedure Finished: C/2/87 pgg i

Procedure reviewed and approved on behalf of the Reactor Safety Committee by:

AGN Reactor Supervisor: M 6 28 h fp

Form NEL-106 Procedures for the removal of Ra He Neutron Source from AGN-201 Reactor:

The form NEL-106 was completed by John S. Bennion.

Il14

Procedures for Removal of Ra Be Neutron Source from AGN-201 Reactor

• Precautions: Be sure pmper ventilation and air sampling equipment are operating during this l' procedure. Gloves and personnel dosimetry must be worn throughout this procedure.

1. Remove the top cover plate from the reactor and remove the borated paraffin covering the Ra-Be source.

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.

3. Analyze the wipe with both a contamination survey meter and gamma spectmscopy. Record the results below.

Survey Instrument: ~7/$#l- 95 Serial Number: o67129 Calibration Date: /4/nlE4

Background:

50  ;

Gross Counts: 70 Net Counts: do m I

[f.

Gamma Spectroscopy (Attach spectrum):

Instrument: Shinssi [< ,

Visible Peaks:

obs&vid Co-fo , Mn -SC & &VO ,eends (W M

• • %")

Radium Daughter Products: ves / no Comments:

l

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 B15

R into the core through at least two control rod guide tubes.

~

Abso: ting maerial: en mass: J5~ / grams - l t

7. Transfer the source from the AGN reactor to the transfer container using a remote handling i

~

tool and secure container. Wipe the source while transferring to container. Also wipe and survey the location of the reactor containing the source. Record data below.

. Survey Instrument: /M/NW AT O Serial Number: */74 Calibration Date: _A %4usim MkW -

Backg[round/#[ \ hurceWine paartorWine [a,/dz Are:rfGreg l r,

Gross Counts '

Net Counts N I

Radiation level @ contact at source locati n: mr/hr Gamma Spevbuscopy (Attach spectrum): M f par. // >f (4 #fer # m ;c 4 ,

Instrument:

Peaks:

Comments: f

8. Place lid on and secure neutron source container. Perform external radiation survey of container. Mark container with radiation hazard signs and label with source activity. Store in MEB 1205-A (Irradiation Facility Room). ,

External radiation survey of container:

Survey Instmment: Y,1 f o e e < ^ YfD P-Serial Number: _ /7 ? .

Calibration Date: 6 Tel, Sr9 -_*,7*

9t'vlta pt ;ft2f/1I/47/89  %:

ddbO Maximum dose rate @ sontact:b@" mr/hr ~ 644) N (T6 mv/h( mdfdaftd. Maximum dose rate @3 fdst: 7# mr/hr {

• 9. pl e secure top cover plate of reactor. G Surveys Performed by:  ;

y Date: I~/8 67 1

Procedure reviewed and approvedolfWhalf caci 6f'Saf ty Comm* e by:

AGN Reactor Supervisor: MM Date: N YA 9 M 7 ff G /

H16

Annendix C:

Parts Transferred To Other Reactor Licenses ' I l

i The following are a set of pictures of the AGN-20lM's parts that have been transferred to other reactor's licenses. The fonns that these pictures are on, contain a brief I description, a summary of the radiological survey, and the specific reactor license that these l parts are being transferred to, ,

l All survey results are located in Appendix G.

l I

1 i

l

)

I l

1 C1 m - -- g

MMITERSITY or IUTAE l

Mechanical Engineering Department s 3209 MEB 8 Salt Lake City, UT 84112 WCl. EAR EWWMMO Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June b': 1993 From: AGN De Enhsloning Staff

Subject:

Part Status and Location Part

Description:

1 y-4 -. Part #28 - Rod Drive 7 Pan #29 - Rod Drive

f. ,

p E I

3 d .. ?

i-i

';f fj  ; j j

~

y - f f-  ?

ba - U:Mdk.

1 Radiological Survey Results: '

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached.

HP Technician: Sltuu @ S lqAP Date: G/n bI 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 . .

-7,f, f, y g[3,7%)

Reactor Superviso - -

Date:

a

W3EVERSITY or WTAE Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 wucma or,m amo Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Dechsfioning Staff

Subject:

Part Status and Location Part

Description:

ggg , Part #87 - Reactor Console 1s.3 -

q !l

~

't l- ..

.)

o

.h.

1 i

Radiological Survey Results:

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No centadnation was detected: survey results are attached.

HP Technician: ba# T.Na3 Date: G [so /43 Part Disposal (or Transfer):

The reactor console shown here was 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. ,

, j , j, p

. &, i < . ,

7 Reactor Supervisor: ,

Date: /93-G3

i I

WUITRESITY es WTAE Mecht.nical Engineering Depr.iiment 3209 MEB i 8 Salt Lake City, UT 84112  !

- -,_ Memorandum l lTo: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Decommissioning Staff  !

Subject:

Part Status and Location l

Port

Description:

j Pan #17 - Graphite Reflector from  !'

Top of Core Tank Pan #21 - Graphite Reflector from Bottom of Core Tank Part #19 -Graphite Reflector Side Plate from Core Tank .

Pan #20 - Graphite Reflector Side l Plate from Core Tank 1 Pan #s 61,62,63,64,66,67,68,69 -

Graphite Plugs for Access Port Pan #s 42,43,44,45,46,47,48,49, '

"n .

50,51,52,53,54,55,56,57 - )

s y ; D, . __ Lead Shielding Plugs in Access Port  ;

J ts . b ,j%;J s.

- :z..

g%

Y" I

l i

Radiological Survey Results:

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached.

HP Technician: S u lt l N Date: 3h93 Part Disposal (or Transfer):

The graphite reflectors from both the top and bottom of the core tank, the graphite reflector side plates from the re tank, the graphite plugs for the access port and the lead shielding plugs in the access p ave been tra sfe from License No. R-25, Docket No. 50-72, to UUNEL's TRIG. Li . n R- 2 , ocket No. 50-407.

Reactor Supervisor: I,L Date: k!.?d k m

1

D21IYERSITY DE UTAE Mechanical Engineering Department i s 3209 MEB 1 8 Salt Lake City, UT 84112

,(

wuci.ua swomazuno Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGNhmmissioning Staff

Subject:

Part Status and Location Part

Description:

Part #65 - Cadmium Foil

- s .

g [ - ..

y. 9

, ,*f a Y  %

' (( ., ' *7S. ..

< r.c . 's  %,

'e if, t%DYytr@ x { >gf .

'p,'"n' 2y. ;.

. f 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: b dDi'lblf Date: C / R ['t 7 l

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:. -

l d'

.)

ate:

3*/fM G5

I UNIYERSITT er UTAE Mechanical Engineering Department s 3209 MEB s 8 Salt Lake City, UT 84112 wuci.e4a nuomismo Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN %rfpissioning Staff lSu'ujc;! Part Status and Location Part

Description:

Part #74 - Main Graphite Reflector

-u _

i _d i j

_4 3n

'O i s h S

i; .y y .,

Y ,. ;.

l l

r; '

b Radiological Survey Results:

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected. Survey results are attached.

HP Technician; b u M F41c d Date: 6 bt/4 7 Part Disposal (or Transfer):

The main graphite reflector shown here were trans' erred from License No. R-25, Docket No. 50-72, to UUNEL's TRIGA License No. R-126 Docket No.50-407.

% i Reactor Supervisorbv[ .

c__

Date:

b (M j

l l l murvaustry l

or WTAE I

! l l Mechanical Engineering Department  !

3209 MEB O Salt Lake City, UT 84112

=ctum suommma Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Dechfhjoning Staff

Subject:

Part Status and Location i Part

Description:

Pan #30 - Rod Drive Part #31 - Rod Drive 4

/

d .'

~

s. ~;f

& 'aj "f

fi -3

\

l A!

I i j

I l

Radiological Survey Results:

)

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No I contamination was detected: survey results are attached.

HP Technician: b . uf R'%d Date: C/R b ^

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.

N Reactor Supervisoy i '- - - Date: #

(37

wervaas Tr er WTAE Mechanical Engineering Department 3209 MEB O Salt Lake City, UT 84112

=com ammmma Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Dghissioning Staff

Subject:

Part Status and Location Part

Description:

Pan #70 - Aluminum Sleeve for Access Pon ffffag$ws.c

V  !

Pan #71 - Aluminum Sleeve for 4 Access Pon Ih.

Part #72 - Aluminum Sleeve for 2" Mg,;

~ ; f, j.. Access Pon WW ' -

Pan #73 - Aluminum Sleeve for s

4 Access Port e, .. WN

,?^ ,

r: .

4

, m

. .,,1 ;

i "

-t -

1

/y  ;  ;

q. .

j u 'x w.u Radiological Survey Results:

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached.

HP Technician: h , , svR liafi Date: (db [i 7 Part Disposal (or Transfer):

The four aluminum sleeves for access pons 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.

Date: b 86 fM Reactor Superviso G8

1. fttTIESITY or ETAE Mechanical Engineering Department 3209 MEB 8 Salt Lake City, UT 84112 wuctaa anomisamo Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN (Dhmissioning Staff

Subject:

Part Status and Location Part

Description:

Part #75 - Lead Shielding Ring Part #76 - Lead Shielding Ring Pan #77 - Lead Shielding Ring Part #78 - Lead Shielding Ring

_"'. _E Part #79 - Lead Shielding Ring q

g n \

i.

I  ::I x

l . 4;:

L 4 l

l l

l Radiological Survey Results: <

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No l contamination was detected: survey results are attached.

HP Technician: ht2IGh [ Date: 6/TC /#/ 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.

s Reactor Supervisap TA - Date: $C!O-Ga

)

Annendix D:

Parts To Be Disnosed Of As Radiolonical Waste The following are a set of pictures of the AGN-20lM's parts that have been set aside to be disposed of as radiological waste. The fomis that these pictures are on contain a brief description, a summary of the radiological survey, and the method of disposal of the parts.

All survey results are located in Appendix G.

1 l

i l

I)I l

l

-= . _ . - - . .- _ - . . .

ftNITRESITY l or UTAE Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 metum immumma Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Decopishning Staff

Subject:

Part Status and Location Part

Description:

- . Generated Decommissioning Waste

(

[

l i

<; }

. . . .y h tr . \4 I F .% i L

• w ;

I 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. l l

l HP Technician: DM d' Yik/O Date: 7 /'b i 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 approved procedures outlined in the Radiation Safety Manual. j N,

Reactor Supervisor: b -I -

Date: $// /i[5--

D2

L

WNIVERSITY j or UT&N Mechanical Engineering Department 3209 h1EB e Salt Lake City, UT 84112 i wei.au xmmiramo Memorandum To

D.M. Slaughter, Reactor Supervi.sor Date: June 8,1993 From: AGN D hissioning Staff

Subject:

Part Status and Location Part

Description:

Part #2 - Safety Rod Guide Tubes s Quantity-2 3 Part #9 - Control Rod Guide Tubes j Quantity-2 L

x1, _

5 C , --

,_h:.,2

'~

% ,p pf t L w= ,

.6% ,

$' 'L i h, 'c , -I

! ( i I.

h!. -' AI.

Radiological Survey Results:

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. Alpha contamination was detected on both pans at .07nCi from U-235 and U-238. Survey results are attached.

HP Technician: (dtwt'lMed Date: 3/f /ri 7 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 m the Radiation Safety Manual.

Reactor Supervisor:

l

~. l! - -

I Date:

n;y 4. "v D3

MNIVERSITT cr WTAR Mechanical Engineering Department 3209 MEB O Salt Lake City, UT 84112 L

mcma nzmmmo Memorandun To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN DecofnA.[ishioningv Staff

Subject:

Part Status and Location Part

Description:

Pan #6 - AGN Screws & other parts Pan #7 - AGN Screws & other pans Pan #8 - Core Suppon Pan #13 - Core Support Pan #83 - AGN Screws & other

. Pans

" ., ,w,%

+ '

. rq pa '

[* jfi -k n , s_. 4 W 4

Il a i u*

4 e

i 14 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 .1nCi, and pan 13 at

.134nCi. All parts were contaminated with U-235 and U-238 isotopes. Survey results are l attached.

HP Technician: Gruc8 %8 Date: v IF /47 Part Disposal (or Transfer): l The aforementioned pans were segregated, packaged and labeled by the AGN ,

Decommissioning Staff, prior to collection for disposal by the Radiological Health '

Depanment, under approved procedures outlined in the Radiation Safety Manual.

N Reactor Supervisor: [ ' ~ ~ -

Date: 7N '

• 1 D4

l mnrvsas Tr er WTAE Mechanical Engineering Department 3209 MEB 8 Salt Lake City, UT 84112 wcma smmmma Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Dec m ssioning Staff

Subject:

Part Status and Location Part

Description:

q q Part #18 - Core Can o

i h k:  ;

l I

h, : .

I f' \

. Lt I

.. }

=-

.,' 'ya er m_. 3 L- _

Radiological Survey Results:

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: Th tuff'OtM/ Date: ~f /h42 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 Marmal. '

. (, ,

Reactor Supervisor: l- 'V Date:

A D5

l RAIYERSITY l or

!WTAE Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 m __ Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco {m ssfoning Staff

Subject:

Part Status and Location Part

Description:

Part #80 - Vacuum Cylinder for Core Gas Sampling

! '- t .

b hij f 1 i  ! p .

. p'h wf s f -

'I

\  : A

~$

.A . fgC_

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: Duu88Mc8 Date: ~J /NT'r 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 approved procedures outlined in the Radiation Safety Manual.

T Reactor Supervisor: -

[ I l #\*

{'- '

Date: '/

~,

' ' ~

D6

IIB M f 7 E M S I T Y er WTAE Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 1

wuctau amminmo Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 l l

From: AGN Decongshoning Staff

Subject:

Part Status and Location Part

Description:

Part #1 - Safety Control Rod #2 l l

Part #5 - Safety Control Rod #2 and Spring Assembly Part #10 - Safety Control Rod #1 and i Spring Assembly l Pan #11 - Course Rod and Spring Assembly Part #12 - Fine Control Rod and

y. g Spring Assembly T- j -,-

![ Ic g.

w-

..2 -

L e.

.,i-

a. .

f,,

.r

, h-- x Radiological Survey Results:

Alpha, Beta, and Gamma contamination surveys were conducted on these parts.

Contamination is specified as follows: Pan I showed alpha contamination at .272nCi, Pan 5 had alpha at .075nCi, Pan #11 alpha contamination at .12 and Part #12 showed alpha contamination at .04nCi. Survey results are attached.

HP Technician: Th q Mlct8 1 Date: V/r/47 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 approved procedures outlined in the Radiation Safety Manual.

N .

]{\.

p ,,i l Reactor Supervisor: e -c -

Date: ' --

D7

MDIYE3SI77 SF

! WTAE Mechanical Engineering Department 3209 MEB 8 Salt Lake City, UT 84112 l .co m _ 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, I 39,40,41,81,82

- Wooden Access Port Plugs kW 7 De

'h r$

l

_g,- .

8 . ,

l ~7 uB' ' s m j. ,

.c i..

w h M;h-[I A- h s

~

5-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 results are attached.

HP Technician: htm LFhlf Date: 7 /J /"/ >

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 approved procedures outlined in the Radiation Safety Manual.

i ' /

Reactor Supervisor: ~ - 'l -k6/ - Date: %/ "- '/ ,

D8

WWIVERSITY j er lWTAE Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 mm. . Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Decomfihing Staff

Subject:

Part Status and Location Part

Description:

Part #4 - Paint Chips from Thermal Column s

~

l $

-l

< ..- i' t #

i i i L

a :-

. . .L 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. Survey results are attached.

HP Technician: hudMt8 Date: 7 [T /07 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 approved procedures outlined in the Radiation Safety Manual.

Tl\! /,i \  : ,, " '/, ",

Reactor Supervisor: N Date:

D9

Anoendix E:

Parts To Be Disnosed Of As Unrestricted Waste The following are a set of pictures of the AGN-20lM'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.

All survey results are located in Appendix G.

l El

WClIEYERSITY es WTAE Mechanical Engineering Department 3209 MEB l 8 Salt Lake City, UT 84112 mcua mmmmmo Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco fhning Staff

Subject:

Part Status and Location Part

Description:

Part #22 -Interior Steel Thermal s; . Column g-* Part #23 - Exterior Steel Thermal N I Column e w "

Part #24 - Top of Thermal Column Cover Plate Part #25 - Bottom of Thermal Column Cover Plate 9 , y -.

q Radiological Survey Results:

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached.

HP Technician: h O! 3dev N Date: 7 b !4 ?

, Part Disposal (or Transfer):

The aforementioned parts were disposed of through non-contaminated waste.

l Reactor Supervisor: y ,

Date: 34 E2

UUtYER$1TY or UTAE Mechanical Engineering Department 3209 MEB 8 Salt Lake City, UT 84112 wcma ammasaw Memorandum

!To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco ioning Staff

Subject:

Part Status and Location Part

Description:

Part # 27 - Pon Covers and Glory Hole Covers With "O" Ring and Bolts

>y:

. -f & ..

() t<

i

! se eum ,A 0 3

i

1 c

,/, c L

i Radiological Survey Results-Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: suney results are attached.

HP Technician: hua8/TR// Date: '+ b &

Part Disposal (or Transfer):

The port and glory hole covers as well as the "O" ring and bolts were disposed of through non-contaminated waste.

f Reactor Supervisor: i i ate: #

E3

ItalIYERSITY es UTAE Mechanical Engineering Department s 3209 MEB

/

O Salt Lake City, UT 84112 L

wucma womaamo Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 l

From: AGN Dectfgjsioning Staff

Subject:

Part Status and Location Part

Description:

l Part #58 - Aluminum Fuse Support i Part #59 - Alignment Pins Part #60 - Polyethelane Rod

,f.'

,,, lA.

ls

{ sa h'

' ',% r \ . '

y ,. ( -

Y  :.:.r, 'e .<{

w/ -

.. m 4 Radiological Survey Results:

Alpha, Beta, and Gamma contamination surveys were conducted on these parts. No contamination was detected: survey results are attached.

HP Technician: h u d0C7 h N Date: 3 /'l / M Part Disposal (or Transfer):

The parts listed above were disposed of through non-contaminated waste.

I

\ \

Reactor Supervisor: -- .

k ate:

H E4

NNtYansITY or UTAE Mechanical Engineering Department 3209 MEB e Salt Lake City, UT 84112 metan ammiamo Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Deco skoning Staff

Subject:

Part Status and Location Part

Description:

Part #13 "O" Ring for Core Tank

- Part #14 - Core Tank Cover (upper)

Part #15 - Com Tank Cover (lower)

Part #16 - Polyethelane Disk Part #84 - Control Rod Support Plate r

f' ,,g, f su r'

l,.

lG"

f. l

) ,

f k- " .g _ .fk Radiological Survey Results:

Alpha, Beta, and Gamma contamination surveys were conducted on these pans. No contamination was detected: survey results are attached.

HP Technician: Tho1171l1b Date: 7 /9 kJ 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.

Reactor Supervisor: i =- -- Pfate: / k E5

9338YERSITY er WTAE Mechanical Engineering Department x 3209 MEB 8 Salt Lake City, UT 84112 mcua ammma.o Memorandum To: D.M. Slaughter, Reactor Supervisor Date: June 8,1993 From: AGN Decom [ning Staff

Subject:

Part Status and Location Part

Description:

Part #86 - Main Reactor Tank lW ,

16^ 4

, . w;. l 3 >;p;

.I 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: Dlu PCi%ll' Date: I/h f4 Part Disposal (or Transfer):

The main reactor tank was disposed of through non-contaminated waste.

Reactor Supervisor' -

~

ate: 3

/r M

E6

I t

Annendix F:

Fuel Shinment 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 laboratory to the DOE at Oak Ridge Tennessee.

This section is broken into three subsections, they are:

1) Fuel Transfer Check Lists

2) FuelTransfer Forms

3) FuelTransferCorrespondence List This break down is designed to show clearly the tracking, procedures, and correspondence  ;

necessary for the transport of the AGN-20lM's fuel. .

4 i

F1 i

4

1. Fuel Transfer Check' Lists l- The following forms NEI,110, NEL-117, and NEL-118, are listed in this section.

These forms dennonstrate 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

'1

'I F2 l-

Fonn N11-110 AGN Fuel Shipment Document Control The following documents pertaming to the shipment of the special nuclear material (SNM) from the AGN-210M training reactor (NRC License No. R-25) will be maintained on fil: for a minimum 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

1. 3. DOE 7A, Type A Qualificanon (Mound Report) .

' 4. NRC Approval of QA Program for AGN Fuel Shipment NRC-Approved QA Program for AGN Fuel Shipment

6. Y-12 Plant Authorization To Ship

7. Form NEL-111, Primary Container IAading Procedure and QA Checklist: UU-AGN-1/1 r d/ 8. Form NEL-112, Primary Container leading Procedure and QA Checklist: UU-AGN-2/1 v Y9. Form NEL-113, Primary Container IAading Procedure and QA Checklist: UU-AGN-3/1

0. Form NEL-114, Shipping Container Imading Procedure and QA Checklist: UU-AGN-1

11. Form NEL-115, Shipping Container loading Procedure and QA Checklist: UU-AGN-2

y. Form NEL-116, Shipping Container Loading Procedure and QA Checklist: UU-AGN-3

, . Form NEL-117, Hazardous Material Shipment Checklist and Transfer

[ 14 Form NEL-118, Hazardous Material Shipment Checklist and Transfer 7

15. . Shipping Papers -

6. DOF/NRC Form 741, Nuclear Material Transaction Report l

l Form reviewed and app ed b :

Director, UUNEL: # Date: _O N Radiation Safety .

.//[M2 AS6 Date: 21r/T/ ~

Reactor Administrator: d// f - Date: 2 - F ~~ 7/ ,

1 F3

Form NEL-117 AGN Fuel Shipment Hazardous Material Shipment Checklist and Transfer Date: 1/_f f/ Shipment No.: ZWW - FZF - 1 Shipping Container Identification and

Description:

UU-AGN-1 and UU-AGN-2 (two nackanesh USA DOT 7A. Tyne A fDOT Snee.17H.

55-enllon steel drumsh Gross Weicht: 751bs. each nackage Contents: .

UN2918: Radioactive Material Fissile. n.o.s.

Carrier: T.5.m.T '

Vehicle No.: df 'I 7 4 # 447I4I Driver: A,b L . b', d '

Current Chauffeur's(icense: 447J6/470 Chak: Commente .

Review Of Physical Security Plan: 7 Medical Certificate: 7 Special State Permits: T To be obtained by driver Carrier Certificate ofInsurance: /

Driver Logs: 7 Placards:

Exclusive UseInstructions:

4/ ,

Emergency ResponseInstructions: /

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.: 33 W7 /4 V ,

Comments: 44oVT Add D'"-

Final Inspection: II Ads lle Ub Date/ Time: 2/f!T/,!jleop, Material Transfer: -

Material Released By: o [ (;~

• Date/ rime: 8'M8/"/6004 Material Receiv fN Date/ Time: '/IM 8Nk Campus Security acd/boedM Direc o L: .

Date: E 8 Radiation Safety Offi I I [ID - - Date: 1/f/9/

Reactor Administrator: - ,-

/ ,/b. -I Date: 'r + Y F4 i

.+ 7, . - .

Form NEL-II8 l AGN Fuel Shipment Hazardous Material Shipment Checklist and Transfer  :

Date: 2- 9/ Shipment No.: ZWW - FZF - 2 g Shipping Container Identification and

Description:

UU.AGN-3 (one nackaneh USA DOT 7A. Tyne A (DOT Snee.17H. SS-callon steel drumh Gross Weight: 751bs.

Contents: .

UN2918: Radioactive Material. Fissile. n.o.s.

Carrier:  % - J/d. #f,he 1,rl fs 847- '

Vehicle No.: _2 V 5~ / WPMP -

• Driver: b4 C# - (Tm s Current Chauffeur's License: #. c - 2 / 7 /0~/

Checg: Commentr Review Of Physical Security Plan: /

MedicalCenificate: /

Special State Permits: / To be obir.ed by driver Carrier Cenificate ofInsurance-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: /

C_onsignee Notified and Authorized to Receive Shipment- [-

Vehicle Seal No.: ?W70 LM Av Comments:  ? 42.VT ki d- Aer Final Inspection:

Material Transfer:

,- I ,, /./I -

/

AfD Date/ rime:

f/, Stew Material Released B M,M /

Datemme: 6h 8['/6@#52 Material Received B /I Md b < o Date/ Time #-OS #7/ Mkfl8#

Campus Security c .

Ow AMt/

Fonn reviewed and a ed b -

Director, UUNEL: .

Date: N N

_. Radiation Safety O /$m - Date: 2 r-/4/

Reactor Administrator: /

w/[# Date: 2-%9/

F5

4

~ 2. Fuel Transfer Forms  !

The following fonns are included in this section, Uranium Scrap Declaration ID-90 .

1, DOFJNRC FORM 741 Nuclear Materials Transactions Report, correction to DOE /NRC FORM 741, and the Bill Of Lading of the fuel shipment.

l

+

i I

i F6

RECeiCD

' United States Department of Energy REaut T NO.  ;

Oak Ridge Operations Office RE00EST FOR URANIUM SCRAP DISPOSITION nrT'O 4 1940 l SECTION 1 * (70 SE CEMPLETED BT SCRAP EENERATOR) '

1 N (1) PREPARE IN OUADRUPLET; RETAIN 4TN COPT AND FORWARD TNE OR!C!NAL AND 2 SM908ARWDMDMAvfRR THE SCRAP GENERATING CONTRACT.

(AN ADDITIONAL COPY SNouLD SE PREPARED & FORWARDED T 5

OWR TME GENERATING St ACCOUNTASILITY STATION WNEN DIFFERENT FROM TME .CONTRACTING *

• FFICE NAVING JURISDICTICa OF j

T (2) 1718 IMPERATIVE TNAT A C3p*LETE AND CONC!$E DES *R!PTION CF TME 53AP BE FURN!SMED V!TN EACM RECUEST. l R- AND oR*6580 sRJs1 at UTIL12ED FDR THIS PugPDst. FORMS CR i!EC e U BT DECLARAfich NUMBER IN BLOCE 3 DN, Tuls FORM. COtPLETED FORMS OR*658C Am CR*6580 SNCULD BE ATTACME f C FORM 04 6588, URAN!UM 3 CRAP SMIPP]NG DATA, SMOULD Alt 0 BE COMPLETED AND i lT ATTACMED OR*d5Bt. TO TN!s REQUEST FCRM. ANY EMBER OF SCRAP DECLARAT10Ns MAY BE MADE ST UTIL (3) IF A NEGATIVE STATEMENT 151NDICATED FOR ITEM A BELOW, CIVE FULL DETAILS ON REVERSE $110F THIS FORM.

l I

,W l1.TO: 2. FROM: ,

U. S. Department of Energy University of Utah l DAc RIDet oPERAfl0Ns OFFICE Pest CFF::I sex E- Dept. o? Mechanical Engineering 1

DAc RID:E. TENNEss!E snst 14EB 3209 ATTN! CENTRAL SCHP MHCEMENT OFFrCE Salt Lake City, UT 84112

3. DECLARAT10N NtstsER: ATTAcaED; l

. ID-90-1

4. : CRAP is AvA!LAsLE FOR IMMEDiATE cEuvERT TO A REn0aCess YES0R. a NO i

' 5.TxE DATE RE0utRED sN!Po!C DATA Aff DETAILES ON FORM CR 65EB VNICH j l

April 27, 1990 6. slCuTuRE OF REcufsTOR 7. n ! Ae TITLE l SECTION M[

11

• CONCURRENCE OF CDCNIZANT DOE OPEIAT!ONS OFFICE U i er i Reactor Assist. F THE AC CES31PflVE AC ALL CTNER DATA CN ACCURACT. ATTA3[D FORM $ CR 6588, OR*658C, OR*6580 NAVE BEEN CH l C8 TPE URAN!Uw $CR18 TE:s OFFIC! HEREIT CERT;FIES Tui CSVER BY TN!! R!:UEST.

~

DOE MAS THE FINANCIAL RESPON3131LITY FOR THE RECDVERT AND l

1. DATE

2. st- ATURE

3. Def CPERAT!DNs Crr:CE S-/O-90 a

[g SDtM Branch

!!CTION A , Idaho Operations Office I

!!!

• FCR UST l' THE CSMO IN REPLTINC TO CO3!ZANT ER0A OPERAT!dNS OFFICES SIIGHILY IRP.ADIATED MATE I AI.

The urar.ium scrap described in Scra Oak P.idge Y-12 Plant for recovery. p Declaration No. ID-90-1 should be shirped to the Y-12 should receive the material in Project No.

F-0E-0221-05C. Please call ItLxie Bop' p at PTS 626-2506

, Courtesy copy of the 7h1 document should be sent to John Millerfor an authorization

, ORO-C fMO . to ship.

CC: A. King, T-12 D. Bopp, T-12 DATE l' 'ah

, $1GNATURE John H A

ller Ak TITLE ORO-CSIO 3RM OR-658A (REY. 3/78)

F7

y l

-. .:.:=

United States Departinent of Eliergy SNiPr Nc MElwoo CODES Oak Ridge operations office .

URAtIIUM SCRAP SIIIPPING DATA ^ ~ C0'*E"C'^E "'Ci t ("'"E' E 5CO*Il '

B - CtttMERCIAL VfMICl[ (LIL) ,

C - COVERNMENI vtNICt[ (ARM (O ESCORT)

D - Oliff t MEIM005 (SPICIFf IN REMARKS)

DECLARATION NO. SMIPPING COSIS FRCPI PRESEN! LOCAll0N of AN0/OR SHIPPING NUMBit Of SHlrMFNis SCRAP 30: 141HutR OF SillPPING TOIAL NO. TRAMSPORT SCRAP LOT leo.

MEllED REuplRi o CONIAINERS/SNilHINI INDEX LNiliS/SNIPMENT ERVIN, IN. CODE DAC RIDGI, TN. WESifRtY, R.I. FISSILE 11 ftSSitE lit ilSSitE il flSSitt til FISSitE il FIS$ltE Ill 10-90-1 $250 D l

4 REMARKS 0 = Commercial Carrier miut on-650in ,(sissf 3/7 i) - -

United Statas Department of En:rgy .

Oak Ridge Op;raticns Offica 1. LOCATION OF SCRAP RIS: 2. g ,g rip nor .

namr a t v nr ut ah w saur 1 or i URANIUM SCRAP DECLARATION 3. SECURITY CLASSIFICATION OF SCRAP t1 UNCLASSIFIED o

4. SulPflMS CtlllTAluft DATA (LOADfD)

CONFIDENTIAL BY a SHAPE o COMPOSITION

$4 SIAL

5. PainAar (tukER) CoulatwER SATA TTPE SECURIIT G4015 UT IDENTIrl- 4. SCRAP C(BE, Samt CoWTENT & CrutaATING PeoJECT IRAWit CCDE Stat 30 TYPE WEIGHT (GRA8tS)

(POUNOS) CAil0N 30. CooE CROSS AllSI GRAMS \ UT. 1 GRAMS 1ARE NET UU-N21 1 P Cree URAkitM U-235 U 235 l PROJECT 200 Max 20481 3 1 _ IRSIDES 20474 " m4 148.7* 19.5 29.0 492.3* " g g {no 20475 " "

96.0 492.3* "

UU-AGi-2 F 200 Max 20470 3 20442 " m4 148.7* 19.5 29.0 20476 "

492.3* "

96.0 UU-AQ1-3 P 200 Max 20478 3 20473 " W4 297.4* 19.5 58*0 n n n

" n 20469 a n u o 20386 "

20395 "

a 18.5 "

3.6 n n n 20391 "

a u at r

20387 " n n

• n a n

" u 20393 *

• n n 20389 " '

n n n n 20394 "

n a n n 20390 "

n n j 20388 " n n Ir a n n l

n I

20392 "

n n n n 20396 "

a n i " .n n 20385 n o n n I

C2WTAIIEEAS TOTAL WEIGNT i l 3 CON TAINERS TOTAL *Et vi-21 1 5 totAt u AvenAct

~ to At u.!35 "!ljgplimg SHIPPING CONTAINER TYPE CODE ;JC 3380.8* 19.'i l oof u (55 cat > PRIMARY CONTAINER TYPE CODE I 659.?

• d dM I

A i or etASvit soitte 7. REMARKS cor a (tle gat > s 1 ( *thlailated valiins

)cor-eetsssAtt 2 or eta $ tic soitte c a  !

iloofsi(110 CAL) PLA$ tic sAs on uuAcPinc 3

F = 6J or 1711 IY71* spec. - 55 gal. steel D

a 2 SEAlf014EI AL CAN i dnuns with ) Irw rn.

not-Sp (Seecerr is stoct 73 e 4 g l otra (SPECity su stoCr r) a 3 ce tAecte Sirro MTAL CAN e

etwa (sPEClry la stoCr r)

$ (

a FORM-OR-658C (REY. 3/78) _

l CSM0tt0TfN0!W*^4R MiRM193f MMill:M

i . - . . - - - - -

United States Department of En:rgy -. -

Oak Ridga Operations Office DECLARATION NO. .

l iib 90-1 DESCRIPTION OF DECLARED URANIUM SCRAP I 1

) SHIPPING CONL , SHEET 0F PRIMARY CONT. -

1 SERIAL NO. I. D. NO. '

I SCRAP DESCRIPTION W-N21-1 3- AGN Reactor core fuel disks: right-circulier cylinders of 25.6 m diarreter. Fbel is 19.5% enriched (U2 urticlest horrrsjencoiinty dispersed in inlyethylene.

L, #20481: 1 cm thick, total disk mass = 652 g

1. 20474: 4 m thick, total disk mss = 2157 g l

1. 20475: 4 m thick, total disk mss = 2164 g W-MN-2 3- N21 Reactor core fuel disks: sane description as alzwe.

l #20470: 1 cm thick, total disk mss = 657 g l

1. 20442: 4 cm thick, total disk mss = 2051 g

1. 20476: 4 m thick, total disk mass = 2065 g

{ W-MN-3 3- AGN Reactor core fuel disks: sime description as alove.

1. 20-178: 2 cm thick, total disk mass = 1267 g I!20473: 2 cm thick, total disk rrnss = 1269 g 3

o #20469: 2 m thick, total disk rruss = L273 9 I 12- N71 Safety arxl contiol rod fuel disks: right-circular cylirvier of 4.7 cm dia-I meter and 4 m high, each disk is 79 9 aml is 19.5% enricini 10 inrticles horogeneously dispersed in polynthylene. 2

1. 20386 #20395 #20391

, #20387 #20393 #20389 l #20394 #20390 #20388 -

'#20392 #20396 #20385 ,

I I

t l

8 instauctions: tw MCtanAsion anmoEn snow su tw ween miser mAm ConwEn or inns rosa REMARKS i suaine se = sane ameEn As snar snown om tw ComeEscoe me rann on-65ec. tu snireins gD AND IIIG toRMettimtf touTAIMRs sNOULD M LIstE9 IM IM sAME sEGUENCE As LisIED IN On-658C. TIIE CORREsPoN-IIIE scaAP MsCalPiloti passi 3DEWile? ALL KNoWII CoNsTITuturs of NAME AllD gs enEuni am ms inmiteT tu remCn Dimusions or at itEns orma me roeEns CM R0d 3.q ,R01gggNO "}" $ y$.$ j g"" $gg 3 Il'g"ks

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Correction Of DOE /NRC FORM 741

.The Following corrections need to be made to DOE /NRC FORM 741 Nos. ZWW-FZF-1 & ZWW FZF-2.

Corrections to ZWW FZF 1:

(1) Block 22. TOTAL GROSS WEIGHT: Add" 150 lb. ".

(2) Block 24. Item D. NO.OFITEMS: Add " 2 ".

(3) Block 24. Item M. GROSS WEIGliT: Change from " < 200 lb. " to " 150 lb. "

Corrections to ZWW-FZF-2:

(4) Block 22. TOTAL GROSS WEIGliT: Add" 75 lb. ".

(5) Block 24. Item D. NO. OF ITEMS: Add " 1 ".

(6) Block 24. Item M. GROSS WEIGHT: Change from " < 100 lb. " to " 75 lb. ".

I l

l F13

r un nca r are uncu,va cucnuttmaco uvevuvu.a or sw u ar s l FIRE OR EX SURE CALL TOLL-FREE b800-424-9300 DAY OR NIGHT l a .a = - : "*' *' * **ae - - .ad = =' "= oava* ** *' twas. '* Shipper's No. N e .ery ., eu,a . aae ta. ,*up.rvy a n.d h.*em. .nd . me. nee. a.ey 9.e ones ., e e .i 4CD971 Carrier's No. [

'Bri-&nte Etzr 'Ihmsit 2/5/91 [

SCAC Date l (NAME OF CARRIER) ll i TO: Martin Marietta Energy Systems pgog: Ihiversity of Utah Mr1=r W=adig 1A..hty .

Consignee for U.S. IIE Shipper dir U.S. IIE Y-12 Plare, P.O. Ibit 2009 1205 Merrill E=ia.=rir= mildie= i Street Street - - -

t Ouk thige, 'IN 37831 Shlt Ide'CLty, Ur 84112 D:stination ll,'

Zip Zip On. . gin a-o,1-ese,1-w.u-u,;.z& z,1,cs,14.0,1-vu,1.uu,1,,co,1-cr.,1-4,ng_iv, vehicle Route: I,'DD,I-255,I-64,I-57,I-26,I-65,I-Mi5,I KLhea 2: IfM4 ut. Number  !

ne y LA8Et3 RE00mEO

. is e s.o.i 1 IK} EnrHnartive Material, Pimrite, n.o.s.

l l then 20k) daa; l

10.8 hNr=ce4ve Yellow 111

• l P=Hgve Elaami requind; #/ L r.lp Irder S );

l Fimrila Gama 111: Z17.2 l

1.5 g LMD4; jppipy)P/////g U-ZD, 5/U.3 g LMN, Sealk.E.51p; ua wr 7A, Type A (wl Spec 12).

Notes: 1. In Gese at L a y, Ikziversity of Uts: Ih11re  : 48 ti I Tnarruct diansa to y I'.==nrwurf hla @ list czt Mrleer(hlctor ) 361-79 Call List. %.

2. h rm ade benun&r h for U.S. of meny, and tt e actm total b---- a >m chaqpes to the carrier (s) the corsigner cr crrutigiee are I r==i.onahla to, and are to 1.=LL- d by, 6-4 I 3. Isetar of Instnetions l b-l 4. Wrrrig,, Fis=ilr> Nm IdE Stipment.

l l Ib Not Iced More Ihan 1 R::lege per Vetricle.

5. See #tated Seet.

Rernit C.O.D. to: C.O.D. FEE:

Address: g't n n Prepaid City: State: Zip: UUu Amt: $ Collect s I

" ~ .Z.c.='"a,*v.'*11

.. FREIGHT CHARGES

w. .n,*i,7.,",.a0.,*illl".',,"*.'71*d,%".'",."**"J'.'.,L"f%"

PREPAID COLLECT

]

"J.S"'", ""..".J ": *.*:ll" ,O "."'.""' '.".:"00". *::' .*,J"1.* a* *t". ."*,1"L"l"ll;,'ll~43::".'" " "."',='4" *,::"."." "",,,"ll"':"" :".",,0 *

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=

. _.-- _ . = . .. -_ =.- -.= m.,4 : .m -

a .mu s .-

SPECIAL INSTRUCTIONS: M 30,M: .M O YEs h 880 - FURNgED eV CARRIER a iuusi; .- ontvEns ssGNATURE: '

,- r / ,f,.,y, Q_

SHIPPER /4tu/D/ T/A//rMN - /////t bs26/Md CARRIER: h J / ,' 7"/ T- '

PER: ' ~ / / / W- //'t ud PER- D. ,// /

DATE/ 6 M/f WW~ b// # .'~ T DATE: O/ :/5 -1/

FORM # 9-BLS-C(3 PLY) nry vos F14

r un neer ir Lntuia tutnut.wita u. avirwu dr.u tour,.

, FIT.E OR EXPOSURE CALL TOLL-FREE 1-800-424-9300 DAY OR NIGHT THIS MEMORANDUM .o 2w

. : i,- -,

Shipper's No.

.,,,,.--...-sat,= .

ev e - a=,e - -.

Carrier's No.

Tri-State Motor Transit SCAC Date (NAME OF CARRIER)

TO: Nrtin Marietta BwEy Sy*==, Inc. FROM: Utd of kah Mr_laar Nv==,,tg IM-. Lay Consignee for U.S. IIE Shipper fr U.S.

Y-12 Plant, P.O. am 2009 E M D"""*8 "'#'E Street Street Drstination Oak Ridge, W .' 37831 Zip Origin Salt Ide CLty, Ur 84112 Zip 1644mi . - J-o,1-o+a-w.tw/,sba= / 1-a,1ui,W 1'wd-=:D.4-o+, Vehicle _%4/448141 Route: T,57,I-24,I-45,I-215,I-40,%*a S Number

$ N 1

2 X) h44n=+4ve &tsial Fimile, n.o.a.

(M2918 (Raa. ---lih); kight: 11CB.4 1 Ikmdm endi err *=*r, I Biriched Urardna (lees tien 2(E); M1M 3:tal fhrih; l 11.1 act endt - "

l P M=r+4ve Fleettlr=r; b+4,=r+4ve regidred; TM#dkFYellw III lahalm aqh#

MMlW/L=Ti ft #/19//w.t 1

• r 25; Fimila Classendi III; mnminer; 221 g U-235,/Md4/

55.7 ZE anA l I 1.7 g n.234 M /////'/gg/ Seal }bs, s-511 and m 72:

WA IDI 7A, Type A (wr Spec ITd).

Ntes: 1. In One of L.-som,y, Gac thiverstty at mIice 1eputmeni e (801) 561-79 %.

I Instru-t M---.: :-< to rispansible lista d on b.] ear >= +rr Odl Lie-

2. h=raisim hereunder for U.S. LamLaut of berg '. and the e=1 total l vmormimm Umga, pai4 to the enrrier(s) bt the cm danne or mnsign e are l a=4gnah1. to, arx! are to $e W . J by, thel6 _.

l 3. I*rar cf Imw. f ms .

l 4. Wrning - Pimile Class I Shir=mt. l Ib ex. Iced Rae 'Ihnn 2 per Veldcle.

5. See Attached Sbeet.

Remit C.O.D. to:

Address:

C.O.D. FEE:

pnn Prepaid City: State: Zip: u u sJ Amt: $ Coitect s

"** ~

'

• Z.c.u.

'*1.L *"*=*EIlf.i,IO,,".L'*.* '"n, ,."1" . - - - - . . ~ - - . - - - -

,*. '.**i. .E OF,."**,"'**.,".' FREIGHT CHARGES

==cd vm e a.,

a. PREPAID COLLECT

[3 o "Etr.,::::".J' =':= *."."J."".: :"."'.:." ~ =a.. u  :;':"':t . ,3

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g""._'.*.'5;g" ., ,,, :"f L":'t".',*.ll*;J."".'::'=ll l' O'."."-"',*"""TJ",*"..':l',;l"* * ..

': :::.:=r.":r-- .  ::=- .. _  :, :: m.m u.m RAmmCIIE 7**'"""~ a2e1:113aoW SPECIAL INSTRUCTIONS- >e O Yts CINo-runNISH Y CARN

- e omrvens $1GNATUnt: M ,,

SHIPPER: /h /tP/ 5/7/ ff /f,'W + ~ &C A/V //W CARRIER: 'T . . nT.u.

PER- d V/Y --r:~o W,o d EY"-~ - PER- ~7__ 41 1 is."h DATE /C VNA/f8// - /c m 4'6 7 DATE: -Of *~/9/ r FORM # 9 BLS-C(3 PLY) nev une f.bWfk FIS

t

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. H. Miller -  !

Oak Ridge Operations Office l

CSMO P.O. Box 2001 l Oak Ridge, TN 37831 M. A. Thom EG&G Idaho, Inc.

P.O. Box 1625 Idaho Falls, ID 83415-3126 P

Adolphus King Martin Marietta Energy Systems, Inc.

P.O. Box 2009 Oak Ridge, TN 37831-8169 Bob Berry EG&G Idaho, Inc. 1 P.O. Box 1625 Idaho Falls, ID 83415-4113 I A. J. Vinnola, Jr.

EG&G Idaho, Inc.

Fuel Manager P.O. Box 1625 Idaho Falls, ID 83415-7112 F16

h' A'onendix G:

L Survey R'esults L

L The following are the results of the surveys conducted during the decommissioning of the

' AGN-201M 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 Smveys.

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, it should be noted that there are inconsistencies from section to section in the presentation of this data. An effort has been made to transpose the original hand written data into typed form so that it is more clear to the reader. The typed data has added to it infom1ation that should make the data more easily understood.

l'

'l G1

=

i

1. Preliminarv Defueline Survey. .

Prior to the defueling of the AGN reactor a survey of the reactor exterior and of the '

immediate vicinity was perfonned. This survey's purpose was to insure exposure to the l decommissioning staff was as low as possible, and to identify any potential problem areas. No removable or fixed contamination was found. The detector used was capable of alpha, beta, and i gamma detection. The potential presents of alpha contamination is extremely improbable on the exteriorof the AGN. j l

I I

G2

RADIOLOGICAL HEALTH DEPARTMENT Mail code os40s 100 Orson Spencer ham, Univers#y of Utah Toha b n to" To: DATE: 5!I7)E9 FROM: 0k&w kib

SUBJECT:

Md b tu nC on Ideln OfRoe:

• • '*"' T kan surnyed 4-ke e,e+e c ien- a S +ke- AGM

"' 5 reacher- asing both dtrcef me. tera 3aJmiPo em AM h4.Ve hd yto tv._ptoV MI4- CobvE t W AM ON -

-w M 5* Yt S thedtAde_s -4 b hlbor' im med hhe.(1 Jurrowwcdin7 i g 4 m + ka O - S eipes w e la.k a m -f%. 4cp , s/ des em s. ad b w. wkde A r u .t - su r e 4 o er<- ~4 int Ext. 7485

~

2 h k n % h I c o r'. T c d S o Stw veyed + k co S I md whanisw ad .AJ +kem Cree o& exhl m.kmidb. f%-4ke. Sucocy I med a TBm-3 3etye compc l p os2332, wla ct ho n

• • errIl e N oc k,3ertmA- c9-36 (e medium e> sert 1 c.3 en;doD C eypv. 2.2'/.

-r m _- _ _ _ _ _ --w _ ---,.+_____.__.__m_____.._______.____-__.___._=___u_.

2. Concrete' Block Surveys L

Concrete Block Surveillance:

The dismantling of the AGN's concrete block wall began in early 1987, and ended in early 1988. Attached at the beginning of these survey's are the Concrete Block Surveillance Procedures for the approved decommissioning plan. Following these procedures are copies of the original pallet surveys. It must be noted that prior to the pallet surveys each block was individually l

surveyed on all six faces as outlined in the procedures. After the individual survey the block was placed on the pallets for the pallet surveys. No documentation was made of the individual block surveys.

1 Concrete Block Release Guidelines:

The release limit of 250 cpm gross was instituted as an administrative control that allowed efficient identification of the contaminated blocks. This limit was established by doubling the l' expected average background count (125 cpm), thus a release limit of 250 cprn gross was established. The efficiencies for the concrete block survey meters (TBM-3S) ranged from 20% to 27% as noted in Appendix H. To show compliance with NRC guidelines an example is as t l follows. As sample calculation, during the survey on March 25,1988 the background count was 50 cpm. If a count of 250 cpm gross was found, a corresponding net count of 200 cpm would exist for this background. Using the detector with the lowest efticiency (20%) the dom would be found to be 1000 dpnV100 cm2. Thus the 2000 dpm/100 cm2limit is set to be conservative by a factor of two.

l Concrete Block Documentation Clarification:

Some of the concrete block survey pages have notes added to the sides. Several of these notes involve the background of the facility and specifically the cave background. The cave was a concrete block enclosure used to house inadiated materials from the TRIGA 100 kW facility.

When the cave was used to house samples from the TRIGA addition background surveys were performed to determine if background from the cave would interfere with the pallet suiveys. Also during these surveys some inconsistency exists for the determination of the background. This is addressed as follows.

All counts gross.

Date.

Background:

Readinps: Comments:

1/25/87 90-110 cpm 100-120 cpm 43-130 dpnV100 cm2 1/29/87 100 cpm 100 cpm 0 dpm/100 cm2 G4 i

l

Disc

Background:

Readings: Comments:

11/9/87 140 cpm ' 190-230 cpm 217-391 dpm/100 cm2 .  ;

11/11/87 150 cpm 180-220 cpm 130-304 dpm/100 cm2 -

11/12/87 80 cpm 120-180 cpm - 174-435 dpm/100 cm2 two pages 11/13/87- 80-100 cpm 100-160 cpm 87-349 dpm/100 cm2 wo t pages ,

11/16/87 60-100 cpm 100-170 cpm f 182-500 dpm/100 cm2 ourpages 11/18/87 100 cpm 120-160 cpm 87-261 dpm/100 cm2 11/20/87 100 cpm 100-180 cpm 0-364'dpm/100 cm2 11/28/87 80-140 cpm 80-180 cpm 0-455 dpm/100 cm2 two pages I 1/27/88 90 cpm 100-130 cpm .43-174 dpm/100 cm2.

3/2/88 80 cpm 120 cpm - 174 dpm/100 cm 2  ;

3/25/88 50-70 cpm _70-110 cpm 100-300 dpm/100 cm2 three pages -

Note that some of the data extends on to multiple pages. The calculations for dpm/100_cm2 i are based on net counts utilizing the lowest background count data. Also for the counts on 11/16/87 two different detectors were used. To simplify calculations and to remain conservative the detector with the lower efficiency was used for all results on that day.

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University of Utah Nuclear Engineering Laboratory q AGN-20lM Decommissioning Project q Concrete Block Surveillance Procedure .

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Intmduction l

This report details the procedure to be followed during the removal of the l

concrete block used as shielding for the University of Utah Nuclear Engineering i Laboratory (UUNEL) AGN-20lM nuclear reactor. De removal of the block is a necessary first step in the decommissioning process of the AGN reactor.

Surveillance of the block is uired to preclude the release of potentially contaminated material from 'Ihis procedure has been developed by the staff of UUNEL in collaboration with and the approval of the University of Utah  !

Radiological Health Dep-ius.t (UURHD) following guidelines established by the '

U.S. Nuclear Regulatory Commission.

, hferv Cor.M. m:nne l i

The removal of the concrete block requires transferring the block from its  !

present location onto wooden pallets while monitoring the block to assure l

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 concem. Carelessness, horse-play, and unsafe >rocedure 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 perrmssion and/or presence of UUNEL staff. Furthermore, the TRIGA reactor tank will be covered with plastic sheeting whenever blocks are 2noved to prevent contamination of TRIGA tank water by concrete dust.

General Pmcedure The block will be monitored with portable survey meters, vir Technical Associates Model TBM-3S " friskers." Readings will be made such that the bottom surface of the detector is 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 i-survey portion of the procedure per shift. De 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 comprised of 15 blocks com metly arranged. The first stage of the survey involves passing the frisker over 15 > locks (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 w -

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I 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 m, volves 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 loadmg 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 coverloaded lets to prevent accidental contamination. A radiation safety l technician from 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 doorlocated 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 rescaled 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.

Accentable Activity Umik The criterion for the rejection of concrete block as contaminated material as recommended by the Radiological Health Dep-buent is a measurable count rate in excess of twice the average area background count rate on the day of measurement.

'Ihe average area background in the vicinity of the present location of the block runs between 100 to 150 cm on the TBM-3S. Blocks exceeding a count rate of 250 cpm on any surface will 3e 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 Disnosition Once the blocks have been surveyed, and only those at or below the acceptable activity limit have been transfened onto pallets, they will be subjected to a final survey to be performed by UURHD. Followmg approval by UURHD that the block meet the criteria of acceptability, the block will be transfened to the University of Utah Broad Form License No. UT18-00001. The block will subsequently be released from UUNEL to a preapproved contactor for fmal disposition.

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3. AGN Water Survev l l

Prior to the draining of the AGN's water shield a sample of the AGN's water was taken to determine if there was any contamination or activation. The instrument used was an High Purity Germanium Crystal Detector.

)

AGN Water Sample 1/9/89 Instrument used High Purity Ge Crystal Background 46764 cpm Water 1 - 47278 cpm gross 2 - 46025 cpm gross 3 - 46732 cpm gross Average of counts 2-4: 46388 cpm gross 4 - 46407 cpm gross Background 1) 45834 epm, 2) 46246 cpm .

1 Average of Backgrounds of counts 1 and 2: 46040 cpm net counts = 348 cpm Activity = 348 = 0.56 nCi/l 533 Note that the activity is derived by dividing the net count rate by an experimentally determined l conversion factor (533 cpm /nCi/l) based upon sample geometry, energy, and detector efficiency.

Surveyed by John S. Bennion.

i Analysis of AGN Shielding Water September 22, 1989 Counted sample of water from AGN tank on HPGe detector for 30 minutes. No j observable photo peaks besides Co-60 and Mn-54 background and K-40. Sample was taken on 9/2/89 and counted the same day.

i i

Surveyed by John S. Bennion.

i G28

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4. Thermal Column survey Prior to the removal of the fuel from the AGN reactor the thermal column was removed.

1 What follows is a copy of the report issued from the University of Utah's Radiological Health

- Department. No contamination was detected.

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UNIVERSITY

" UTAH Memorandum 26 February'1990 To: Gary Sandquist, Director

• Nuclear Engineering Laboratory From: Byron Hardy, Health Physicist ,

Radiological Health Re 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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I Radiological llealth Department 100 Orson Spencer Hall Salt Lake (i v Utah 84112 (8(kg - -6141

1

--i

5. Fuel Surveys -

Along with the removal of the fuel from the AGN reactor the Ra-Be neutron source was j also removed. What follows are a chronologically based set of surveys documenting the process of removing first the source and then the fuel from the reactor. The survey results of source and E ,

fuel surveys were used not as disposal criteria but rather as exposure data. The source and the fuel . .I were considered respectively as radioactive waste or as special nuclear material. The Re-Be

. neutron source was sent to RAMP Inc. for ultimate disposal at the U.S. Ecological site in Beatty  !

Nevada. The fuel was removed to Manin Marietta Energy Systems at Oak Ridge National Laboratory. The following surveys are photocopies of the completed original survey fonns and  ;

irwrites of the hand written data and notes made during these surveys. l l

1 1

l 4

l G31

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LNVERSfTY 55I5h,,,,

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G32 l

j

l Ra Be Neutron Source 1

I l 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 corner to provide shielding. Concrete blocks were placed around container to prevent access to the hot spot where surface radiation dose is approx.120 mR/hr. Radiation levels were as follows:

1 Max surface dose of concrete shield: 3 mR/hr Max dose at three feet: Not perfonned ,

Max dose on tope surface of shield: 2 mR/hr I The movement of the source was recorded by the EPA's PIC detector. Before movement the reading was approx.16 pR/hr. (Normal background is approx. 9.8 - 10.4 R/hr) Transfer of the container by crane 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 more shielding as the line of sight to the detector must pass through the foundation, ground, etc. When transferred behind the tank, the PIC reading was back to nonnal.

Leak Tested 8/22/89 - Nolan Smith RHD  :

i Surveyed by John S. Bennion.

1 G33

Fount NEL 101 RSC Appnyval:5/25/88 i AGN COMPONENT RADIATION SURVEY RECORD PORM ,

Survey Form #:

Survey Location AGN Ranctor. Nuclame Eneineerinr 12h Survey Date: BMY/S/

TIEM SURVEY SURVEY GRGSS PE!T NET

- ' - fa '-i NO. GENERALDESCRFIl0N INSTR (J) TYPE (4) spat epm 100aus a S Y Tomi M'

-/ , 3[" A D /6 '"YAr # #

I 3 D i,

AtWc5 28311 4 1aodqw

• r I 3 WA Sv3 99g 724 %/e,s,;< uupug i 2

W4 fwX bi%

1. ,20 39r ,,2. D /b'"Ad<o8/1  :

2. <i 3 f) AVf44 Jt#P/l %3fo<hes.

2 ei WA rov 3 496 7M &/uk sarrac<. I

$sd-I Su d d<Sk.

3 wto79I .2. D /6*^Y4<B,1 l 3 3 'O 22989 82')bI 3 T M10 chw-3 3 hlA b61 (23 %c N"" ukh:,u1&u DETECTOR USED: REMARKS: i

)

(1) Back -.J countag rase m /20f At 613 (location) was: $

_ cpm = dpm = nwen/hr.

(2) Backgrond conting rate for this instrument was:

cpm = dpm. The 11D at 95% conrulence level was:

net dpm = net pCi. No wipes wipes showed agenovable contamination above the L1b, except from the following hams:

<r AA q r . = Sctw A7 huhyc2* * #4 *d (J) SurveyInstrument Codes: .

TAGM = Technical Associates portable G-M with pancake pmbe (thin window):

Serial #: . 667/A9 Calitration Date: . L/z3/89 Osher:blg% t%bA 19 # 7150 c J , 7/zo181 N.L a-udd. iu.4d 43-1 pfwosz (4) SurveyType Codes:

D = Direa Survey over the entire surfeos of she object.

WA = 100-300 can2 wipe counted with an alpha detector.

WG = 100-300 can2 wipe counted with a portable G-M.

WL = 100 300 cun2 wipe counted with a liquid scintillation counterH(3 ).

WGS = 100 300 cm2 wipe counted with a gamma spectrometer.

SURVEY PERPORMED BY:

( >

(ut

% Nm .i  ;

RscAppuvat:sassa .

AGN COMPONENT RADIATION SURVEY RECORD PORM i Survey Form #:

Survey Lx:ation AGN Rame ear. Nuctaar Enair=4ne 1 mh Survey Dese: Eu20/M9 T111M i SURVEY SURVEY GROSS PET - - -

fa _'a NO. GENERALDESCRD710N INSTR (3) TYPE (4) cpm cpn a 8 100em y _ Total j S H-1 but 015 k 4 x n grn .2- O h ~R/4r R1

" \

if 5 O ATf36 ;XISo 3&2'10 d{n 4 T WA n .o Tu 74 ItolW"4Aitusu.

5 Core h S*- D- D o't ~t/w Rif i 5

• 3 D S1,c27 Slo 71 801co dem C 9 WA b ,i 663 9tr3 %"-4. ux w daex.

DETECIOR USED: REMARKS:

I (1) Backgrmaul conaiung rate at 1 (taranan) was: '

cpm =

@= W.

(2) Backgrund counting rase for this instrument was: i cpm = - _ dpm. The llD at 95% conradence level was:

net dpm = {

net pCi. No wipes wipes showed removable contasn' a m above the 11D, except hem the followag isams: I (J) SurveyInstnanent Codes: .

TAGM = Techmcal Associanas portable G-M with pancake probe (thin window):

Serial #: Calibration Date:

Other.

(4) Survey Type Codes:

D = Dr' ect Swvey over the entire surface of the objem.

WA = 100 300 cm2 wipe counted with an alpha detector.

WG = 100 300 cm2 wipe counted with a portable G-M.

WL = 100-300 cm2 wipe counaed with a liquid scian1=rian couniar H (3 ).

WGS = 100 300 con 2 wipe counted with a gamma specuometer.

{

SURVEY PERPORMED BY: C /b> ~  !

od -

Poem neb 101 Rsc Appsoval:5/25/ss AGN COMPONENT RADIATION SURVEY RECORD PORM Survey Location Smvey Form #:

AGN Reactor. Nirkar Eneineerine 12h. Survey Date: a#f/89 TIEM SURVEY SURVEY GROSS )ET NET h menAm= (a ==h)

NO. GENERALDESCRD910N INSTR (J) TYPE (4) cpm cpra 100 cm2 a A y Total 52-2 fu'l Disk-I g ao393 c2/ D /r '"f/w g,1 I ^

3 D .2 H G 25i3( 38080 &

I 3 h/A //.2'/ ///7 /b/6 Du6h sw/au 3 SR-2 Twlt>l%

at .2c389 2. D

/5 "'#kw 6(Y

1. 3 D J/611 ;t/8sd Shf3odem 2- 3 WA N7 STt) 787 di nh4h safe ~e.-

St% *2. Fwr.X Ont 3 :5.ao3N 2 D

/6 " Ytw 9Ifr 3 0 3 2sta nyx 37c2o dem 3

3 MA 15) 9 12. 767 b/ea44 wtact DETECIDR USED: REMARKS:

(1) Back,v-.d r " -: rate at /Ao C /L4 EM (location) was:

cpm = dpm = mrem /hr.

(2) Background counting rate for this instrumet was:

cpm = - dprn. The 11D at 95% confidece level was:

nel dpm =

net pCi. No wipes wipes showed removable contammation above the 11D. except from the following items:

t1 hu & n n d

$,'t htt>gd c.7 cpn e 2. tu2/tw (3) Survcy L.;,w. . Codes:

TAGM = Technical Associates portable G-M with pancake pmbe (thin window):

Serial #:

Calibration Date:-

Othee: .2 > La<d k Mc 3* lS o'~dd l9 4 ~Fisc ea), 7/zg/M (4) Survey Type Codes: &Qldn'hjnLi>L p]ulcl y)-l 20' th?c2.1.CL.

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.

WL = 100-300 cm2 wipe counted with a liquid scimillation counter H (3 ).

WGS = 100 300 cm2 wipe counted with a samma spectrometer.

SURVEYPERFORMED BY: Iv /2h~M. Om j _

(nt -

l

Form NEL.101 Rsc Appovat:5/25/ss AGN COMPONENT RADIATION SURVEY RECORD IURM Savey Form #:

Survey Location AGN Reactor. Nuclear En eineerine i mh Survey Date: B/zf/M ITEM SURVEY SURVEY GROSS Mr NETden mremhur (e ==fM NO. GENERALDESCRFIlON INSTR (3) TYPE (4) cpn cpm 100cm2 a 8 y Total )

59-2 FwJd ex5 t

'/ we aoato 2- D /f **d//w /9 n' l

j tl

• D Affl0 2/483 30'YIOdem 3 1 8/ 3 h/A /.232 /2.2f D7 3 @/s.64.wfvu.c Coaa M Fuk M f g 2cwS .2 D 16 '"'Vtw Sir f 3 D AV739 3473A 9573ocipe l

( "

3 WA int ytty L49 ~4""/evhh wr6u twa M M Ont sj h 4 aoM2 R D /6 '*7/w S/7 h 3 D .2.1290 22283 3i.9eo </gm h 3 WA 487 V8o 649 4 /c W o w dart DETECIDR USED: REMARKS:

(1) Background murnas rate at (locarian) was:

cpm = dpm = mremk.

(2) Background counting rate for this instrumena was:

cpm = dpm. The 11.D at 95% mafhe level was:

net dpm = nei pCi. No wipes wipes showed renovable contaminarv=i above the 11D. except from the following items:

(3) SurveyInstrument Codes:

TAGM = Technical Associates portable G-M with pancake probe (thin window):

Serial #: Calibration Date:

Other:

(4) Survey Type Codes.

D = Direcs Survey over the entire surface of the object.

WA = 100-300 an2 wipe counted with an alpha detector.

WG = 100-300 cm2 wipe counted with a portable G.M.

WL = 100 300 am2 wipe counted with a liquid scintillation counter (3H).

WGS = 100 300 cm2 wipe counted with a gamma spectrometer.

SURVEY PERFORMED BY: ^

a.

s l Pasm NEL let RSCAppseval:S/25/ss AON COMPONENT RADIATION SURVEY RECORD 10RM i i

Survey Form #:

Survey Location AGN Raeear. Nelaae Eneinaarine I ah Survey Date: E M /69 m!M SURVEY- SURVEY OROSS .Mir HEIAga "

ta " 1 -

l NO. GENERAL meren' DON INSTR (J) . TYPE (4) cpn spa 100 m2 a 8 y Total i (jmixa W4 ruaKINSL 7 s aom .2. D /.f *%i g/7 i

.i 7 0 3 X109b 40% &l5SD denn

] 3 WA 764 75 7 ti x & / M w (s w ]

8 a=m #&C E=f O'5 A

.2o38r 2 D /6 *b 8/I  :

6 n 3 O aMiz add yo480c4>m b

3 WA {pD bY %D c&/dv't. WhtLL

[

DElliC10R USED: REMARKS:

1 (1) Background counung ras a (locanon)was:

cpm = dpsa= areenthr.

(2) Background comung ress for this instrument was:

cpm = dyra. The 11D at 95% cenrulence level was:

met 4:n = net pCi. No wipes wipes showed removable contani=adan above lhe LID, except from the following hams:

l l

l (J)SurveyInstrument Codes: l TAGM = Technical Associates portable G-M with peneaks pobe (thin window):

Serial #: Calibration Dese:

Other:

(4)SwveyType Codes: 1 D = Direct Swvey over the entire surface of the objem. '

WA = 100-300 con 2 wipe counted with an alphs h.

- WO = 100-300 an2 wipe counced with a postable G-M.

WL = 100 300 an2 wipe counted with a liquid scintillation couniar (3H). j WOS = 100 300 an2 wipe counted with a genma spectromesar. i SURVEY PERFORMED BY: -

. . MD2 - -

• e l

n,. . - . . , . ~ , . - , , _ _ . - - _ - . . - y y,,

.f k

AGN Core Surveys (Fuel):

~ August 24-25,1989

1. Core Fuse j 2.. Safety Rod #1 (SRI) -

' 3. Safety Rod #2 (SR2) _

4.~ Coarse Rod #3 (CR3)  :

August 24, 1989  ;

PART: Core Fuse #20110. Weight: 6.8 g Instruments:

Ludlum, a # PRO 21524, scalar # 33640 '

eff. Pu-239 = 69.5%

i a background = 8 cpm; TBM - 3S # 087129 ,

. p,y = 0.02 mR/hr Results:

fixed alpha 72104,40069 cpm gross ,

removable 691,639,682 cpm gross

,y 12 mR/hr @ contact Instruments used on all SR1, SR2, AND CR3 pans below:

Ludlum, a # PRO 21524, scalar # 33640 eff. Pu-239 = 69.5% l a background = 7,8 cpm;  ;

Ludlum #7950, Model 19 p,y background 0.02 mR/hr calibrated 7/28/89 ,

Removed in order below PARTS: SR1 #20386 Weight: 79 g  !

SRI #20395 Weight: 79 g SR1 #20391 Weight: 79 g SR1 #20387 Weight: 79 g G40

Results:

SR1 #20386 removable a 509,488,513 cpm = 724 dpm (entire surface) fixed a 28925,27884 cpm = 41620 dpm p,7- 18 mR/hr @ contact

.I SRI #20395 -

removable a 496,526,491 = 726 dpm (entire surface) fixed a 25263,24435 = 36350 dpm i

,7- 16 mR/hr @ contact l SR1 #20391 .

removable a 658,610,625 = 910 dpm (entire surface) fixed a 24885,21093 = 35810 dpm p,y- 16 mR/hr @ contact SRI #20387 removable a 735,784,797 = 1111 dpm (entire surface) fixed a 225224,25052, = 36290 dpm -

,7- 16 mR/hr @ contact August 25, 1989 i l

Removed in order below PARTS: SR2 #20393 Weight: 79 g  ;

SR2 #20389 Weight: 79 g SR2 #20394 Weight: 79 g SR2 #20390 Weight: 79 g 4 Results:

. SR2 #20393 removable a 1109,1118,1146 = 1618 dpm (entire surface) fixed a 20618,26465 = 38080 dpm p,y- 15 mR/hr max. @ contact l SR2 #20389  ;

removable a 547,558,536, = 787 dpm (entire surface) i fixed a 25391,18350 = 36530 dpm

,y- 15 mR/hr max. @ contact G41

SR2 #20394 removable a 976,974,866 = 1350 dpm (entire surface) fixed a 24669,26145 = 37620 dpm

,y- 16 mR?ir max. @ contact SR2 #20390 removable a 1195,1261,1241 = 1773 dpm (entire surface) fixed a 21440,21540 = 30990 dpm

,y- 15 mR/hr max. @ contact Removed in order below PARTS: CR3 #20388 Weight: 79 g CR3 #20392 Weight: 79 g CR3 #20396 Weight: 79 g CR3 #20385 Weight: 79 g Results:

CR3 #20388 removable a 455,456,443 = 649 dpm (entire smface) fixed a 24831,24647 = 35730 dpm

,7- 16 mR/hr max. @ contact CR3 #20392 removable a 463,513,486 = 701 dpm (er. tire surface) fixed a 25650,18930 = 36910 dpm p,y- 16 mR/hr max. @ contact CR3 #20396 removable a 4759,778,756 = 1100 dpm (entire surface) fixed a 30960,27225 = 44550 dpm

,y- 15 mR/hr max. @ contact CR3 #20385 removable a 665,661,614, = 930 dpm (entire surface) fixed a 28134,25690 = 40480 dpm

,y- 16 mR/hr max. @ contact Surveyed by John S. Bennion.

G42

FounNEL 101 RSC Approvat: 5/25/88 AGN COMPONENT RADIATION SURVEY RECORD PORM Surveylocation Survey Form #:

AGN Reactor. Nucle Eneineerine I A Survey Date: F / * //<-f ITEM SURVEY SURVEY GROSS ET NET h mramh= UB == fan =)

NO. GENERALDESCRIPDON INS 11t(J) TYPE (4) cpra epn 8 100an2 y 7 Total i F;ss d n Ptc[z Them D & ~ 4 'A p ,T'

/ " "

Lu M D J2. ,2., C ox l WA tJ- o o ox nue oisk A 4 .:.cvn- QM/N O IY 'M/2rin f') 9 ml 2

Ludl.ue D M111 M%7 34%c

,2

~

O m M/A E 9/ 69

'Ra.% unsk S j/ 4 #19 e/w/ i) /T m/Ub k A 3 t' l u ,. L a n 1T45^7 17653 4 250

'3 *! 't WA M bo kg DETECTOR USED. REMARKS:

(1) Backgi-id counting rate at /h 6 'i #R T (location)was:

cpm = dpm = mran/hr.

(2) Backgromd comtmg rate for this instrument was:

cpm = dpm. The 11D at 95% confidence level was:

net dpm =

net pCi. No wipes wipes showed removable contamination atm .he 11D, except from the following items:

7pcf ?

E.MW .

Dior ond/h <t s>< c / evd//

h cfn Lstell.LLm l e (3)SurveyIsa ..eiis Codes: f cp TAGM = Technical Associates portable G-M with pancake probe (thin window):

Serial #: 68 7 / A 1 Calibration Date: / /2s /O 0:ha: 1.ad h.weJ RD2R.2 ta.t1 :y sca.(u

• 5fL:yo <<&h&d .

(4) SurveyTypeE;*hCodes: C o-2 A -71/243 (4AbA.( 7//B/&J

/

D = Direct Survey over the entire surface of the object.

WA = 100-300 cm2 wipe counted with an alpha detector.

WG = 100-300 cen2 wipe counted with a portable G-M. ~

WL = 100-300 can2 wipe counted with a liquid scintillation counta H (3 ).

WGS = 100 300 cm2 wipe counted with a gamma spectrometer.

SURVEY PERFORMED BY:

f M . dLh "

e

\ -

(14

Fann NBL 101 i RSC Appsovel.S/25/B0 AGN COMPONENT RADIATJON SURVEY RECORD PORM Survey I_m'iaa Survey Form #:

AGN Raa< tor. Na< la- EneL=i..e 1 sh Survey Date: _ A /ac /#v IfliM SURVEY 1

NO. GENERALDESCRIPI1ON SURVEY GROSS M!r - g --

• ---ta a -)

INS 11t(J) TYPE (4) cpn opa 100an4 a 8 y _ Total FeuJL Dost 4 e h ugg blm O D /V *nd4 DN

'l 't bec0wn D Mit? .2cw3 3772o Ll l'

n/A 71 in 10 9 Ftu.X Q< 5 t 5 d 2e w a E l> U Y D /S *~^Ys l>lY T 'i Ldim D /3707 I3703 A37o v

\ f WA h C6 /O h tt) !)i$l<

b & Mdl 7 E"l)lixY D / f "I*ll1 f],1

'b O LAW D VM7 Y%V3 7Li30 V

WA 4D M8 '72 I DETECTOR USED: REMARKS.

(1)hackgrond comung rate at d's 6 8 3 /2o5 (w=) was:

cpm = dpm = mrandr.

(2) Background ==tinr. rese for esis instrwnant was:

cpm = dpm. The II.D at 95% confidence level was:

met dpm =

net pCl. No wipes wipes showed removable contarmnemon above the llD, encept from the foBowmg isams:

(3) Survey Instrument Codes. ~

TAGM = Technical Associanas portable G-M with pancake probe (thin window):

Serial #:

Calibration Dase:

Olher:

(4)SwveyType Codes:

D = Direct Savoy over the entire surface of she object.

WA = 100 300 cm2 wipe counted with an alphe detector.

WG = 100-300 an2 wipe counted with a panable G-M.

WL = 100 300 cr,2 wipe counced with a liquid scintillation counter H (3 ).

WOS = 100-300 cen2 wipe counted with a gamma spectrometer.

SURVEYPERPORMEDBY: -

/A u 3 o.

j G4I '

=

I Form NEL 101 Rsc Appsoval:5/25/88 i

' AGN COMPONENT RADIATION SURVEY RECORD FORM l

Survey Fonn #:

Surveylocation AGN Reactor. Nuclear Engineerine T 2h. Survey Date: A/Bo/N/

HEM SURVEY . SURVEY GROSS NFT NET A - mremh= (8 mwfami NO. GENERALDESCRFHON INSTR (J) TYPE (4) cpm cpm 100 an2 a 8 y Total l

FwA. Dis k- . -

7 Eba&d D w =4 7g i4.*nA Sir 9 Luklum D 6t3% (1330 Iv'jc'lo 9

WA fu HB 266 8 Fsud /)isk-al. M 18 Lhw L'ra. D i4 wiUL 5,1

[2> Lwll&r D 4&l.24 4L170 73iro 1

B WA sto s,k iver 4 F1al' Ossi-st .n J ro Shul.<At D /3' wIWL f{f 9 4 W/uue O Vo W) Veifr f8rro

@ */

WA 198 19 4 c26%

DETECIDR USED: REMARKS:

(1) Background - aq rate at (location) was:

cpm = dpm = mran/hr.

(2) Background cosmting rase for this instrument was:

cpm = dpm. The 11D at 95% conf"xlence level was:

net dpm = net pCi. No wipes wipes showed renovaNe contamination above the 11D, except from the following items:

(3)SurveyInstrument Codes:

TAGM = Technical Associates portable G-M with pancake probe (thin window):

Scris! #: Calitration Date:

Other:

(4) Survey Type Codes:

D = Direct Survey over the entire surfam of the object.

WA = 100-300 cm2 wipe counted with an alpha detector.

WG = 100-300 crn2 wipe counted with a portable G-M.

WL = 100-300 cm2 wipe counted with a liquid scintillation courter 1(3 {).

2

_ WGS = 100-300 an wipe counted with a gamma qmmeter. ,

SURVEY PERFORMED BY: ( -

D+ M o x -

l a4 -

FannNBL.101 RSCAppnwal:5/25/88 AGN COMPONENT RADIATION SURVEY RECORD FORM t

Survey Form #:

SurveyImation AGN Reactcr. Nuclame Engineerine I mh. Survey Date: __ A /k /r9 HEM SURVEY SURVEY GROSS Petr NET h NO. GENERALDESCRIPDON n __" --(a mwf M INSTR (3) TYPE (4) cpm cpn 100ca 2 a 8 y Total ,

FvA.N f)H K lD 21. yo uei bhN O. D lY ^^Y4 $f/

to 4 Lwlk D . 43/2L 43/n M67 lO P WA lD- 18$ Sc} '

lh$W s vtuiH n (o O < !v'n A '

4

// / Led O 60 6 77

//

NA /'7 /A /8 DETECIDR USED: REMARKS:

(1) Back -.d w mg rue at (locanan) was:

cpm = dpm = aram/hr.

(2) Background counting rase for this insaumont was:

cpm = dpm. The LLD at 95% conrulence leve1 was:

met dpm =

net pCi. No wipes wipes showed removable contaminanon above the LID, except from the following isams:

(3) SurveyInstrument Codes:

TAGM = Technical Associates ponable G-M with pancake probe (thin window):

Serial #:

Calibration Date:

Other:

(4) Swvey Type Codes:

D = Direct Swvey over the entire surface of the object.

WA = 100-300 cm2 wipe counted with an alpha detector.

WO = 100-300 cm2 wipe counted wlah a portable G-M.

WL = 100 300 cm2 wipe counted with a liquid scintillation counter H (3 ).

WGS = 100-300 cm2 wipe counted with a gamma spectmmeser.

1 l

SURVEYPERPORMED BY:

C4N v .d O 4 m _

aA -

f:.

AGN Fuel Surveys '

August 30,.1989 histruments used on Fission Plate Fuel Disks, and Polyethylene Disk parts below:

Ludlum, a # PRO 21524, scalar # 33640 eff. Pu-239 = 69.5% -

a background =. 4-5 cpm; Eberline Ion Chamber, Model RO-2A , #1263

,7 background 0.01-0.02 mR/hr calibrated 7/28/89 PARTS: Fission Plate - Weight: 2506 g

1. 20475 Weight: 2164 g

1. 20471 Weight: 2157 g

1. 20476 Weight: 2065 g ,

1. 20442 Weight: 2051 g

1. 20469 Weight: 1273 g

1. 20473 Weight: 1269 g

1. 20478 Weight: 1267 g

1. 20470 Weight: 657 g I

1. 20481 Weight: 652 g l Poly. Disk Weight: 473 g I Results: l Fission Plate no serial number:

Max. p,y@ contact = 8 mR/hr fixed a = 2 epm gross = 0 net removable u = 0 net i Fuel Disk #20475

,7 = 14 mR/hr,15 mR/hr fixed a 15994,23948 = 34460 dpm removable a 27,48 = 69 dpm/100 cm2

' Fuel Disk #20471

, y 15 mR/hr max. @ contact fixed a 13765,17549 = 25250 dpm removable a 57,71 = 102 dpm/100 cm2 G47

)

-l l

Fuel Disk #20476

, y 14 mR/hr max. @ contact fixed cx 26215,15619 = 37720 dpm removabie a76,65 = 109 dpm/100 cm2 Fuel Disk #20442 I

, y 15 mR/hr max. @ contact fixed a 9085,18328 = 26370 dpm l

removable a 78,45 = 112 dpm/100 cm2 Fuct Disk #20469

, y 15 mR/hr max, @ contact ,

fixed a 53049,34284 = 76330 dpm I

removable a 501,402 = 721 dpm/100 cm2' Fuel Disk #20473

, y 14 mR/hr max. @ contact fixed a 46848,75819 = 109090 dpm removable a 461,602 = 866 dpm/100 cm2  ;

Fuel Disk #20478 p, y 14 mR/hr max. @ contact l fixed a 51117,41131 = 73550 dpm removable cx 754,406 = 1085 dpm/100 cm2 l Fuel Disk #20470

, y 13 mR/hr max. @ contact fixed a 40024,40694 = 58550 dpm removable a 197,199 = 286 dpm/100 cm2 -

Fuel Disk #20481

, y 14 mR/hr max. @ contact >

fixed a 43894,42357 = 63157 dpm t removable a 173,211 = 304 dpm/100 cm2  ;

Polyethylene disc

, y 0.03,0.02 mR/hr @ contact fixed a 0 net,47 net,3 net,55 cpm removable a 9 net,18 net,10 net Surveyed by John S. Bennion.

f G48 i i

. . . , , . . - , - +-,

1 I'

Inspection of AGN Fuel ~ j L, June - 15,1990 -l l

Instrument:

Eberline E-5008 Geiger Counter, SN 1015 I i

Calibrated 12/18/89 All containers secure Radiation levels at surfxe of containers:

Black can: 0.2 mR/hr max.

Bottom core: 1.5 mR/hr max. l l 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 ,

@ l foot Beta shield closed: 0.2 mR/hr  !

Beta shield open: 4.0 mR/hr Surveyed by John S. Bennion.

l I

1 I

l l

l G49

6. Core Component Surveys 1

After the removal of the fuel from the reactor the core components were surveyed. These surveys were perfonned to detennine if contamination existed from contact with the fuel. Also these surveys provided information for remediation of the contaminated parts. In the course of ,

these surveys the parts of the core in contact with the fuel were found to be contaminated. l Decontamination of these parts was perfonned for the eventual transfer of these parts to North i Texas State University. When the transfer was terminated these parts were disposed of as radioactive waste through the University of Utah's Radiological Health. The following surveys are photocopies of the completed original survey fonns and rewrites of the hand written data and notes made during these surveys.

4 l

G50

s a. ...+a a ._, -a,, .ez..x . u l

1

.. Core Fuel. Component Survey

. Sept _ ember - 7, L 1989 -

l

.- Survey Instruments:

TBM-3S #087129 U 1 Contamination Meter Calibrated 6/23M

Background:

40 - 60 cpm = 0.015 - 0.02 mR/hr -

Ludlum Model 19 #7950, pR Meter Calibrated 7/28/89

Background:

0.012 mR/hr-Eberline Model RO-2A #1263, Ion Chamber l Calibrated 7/28/89 Ludlum, a # PRO 21524, scalar # 33640 eff. Pu-239 = 69.5%

a background = 6 cpm,4 cpm,3 cpm; Average Background 4 cpm .

AGN Core Can Extemal Surface ,

, y 0.03 mR/hr exposure rate, TBM-3S  ;

fixed a: 8 cpm gross / entire surface 6 dpm/ entire surface, Ludlum j l

Removable a (Ludlum)- i l

Core Can Exterior gross -DPM -l 1 top 6 cpm,2 cpm net 3 dpm/100-300 cm2 8 bottom 3 cpm < MDA 9 middle 11 cpm 10 dpm/100 cm2 2 top 5 cpm 1 dpm/100 cm2 10 middle 7 cpm 4 dpm/100 cm2 5 bottom 4 cpm < MDA -

3 top 5 cpm 1 dpm/100 cm2 11 middle 4 cpm <MDA 4 top 10 cpm 9 dpnv100 cm2 12 middle 12 cpm 12 dpm/100 cm2 l 1

6 bottom 6 cpm 3 dpm/100 cm2 inside of glory hole 10 cpm gross 9 dpm/ entire inside surface 1

G51 l

Bottom Flange e ,y. 0.03 mR/hr gross max. on contact, TBM-3S removable a: 12 cpm gross = 12 dpm/ flange surface, Ludlum Top Flange

,y: 0.03 mR/hr gross max. on contact, TBM-3S removable a: 10 cpm gross = 9 dpnVflange surface, Ludlum Internal Core Can Surveys: ,

Background check a: 7 cpm,3 cpm,7 cpm,8 cpm, = average bk 6 cpm, Ludlum Core Can Interior:

p,yTop half: 0.01 mR/hr max, on contact, gross, TBM-3S p,7 Bottom half: 0.025 mR/hr max. on contact, gross, TBM-3S fixed a: N/A, Ludlum detector to large to fit.  !

Removable a (Ludlum):

Core Can Interior gross DPM j I

1 top 5 cpm <MDA 2 middle 6 cpm < MDA 2 top 8 cpm 3 dpm/100 cm2 10 middle 3 cpm diDA ,

12 middle 12 cpm 9 dpm/100 cni2 4 top 4 cpm < MDA 3 top 5 cpm 1 dpm/100 cm2 11 middle 4 cpm <MDA 7 bottom 6 cpm d1DA 6 bottom 2 cpm d1DA 8 bottom 4 cpm diDA 5 bottom 8 cpm 3 dpm/100 cm2 Bottom Flange (interior wipe):

Removable a: 6 cpm gross <MDA, Ludlum Top Flange (interior wipe):

Removable a: 13 cpm gross 10 dpm / entire surface, Ludlum a background check: 10 cpm,2 cpm,7 cpm,4 cpm, = Average bk 6 cpm, Ludlum G52

Bottom Cover Plate:

p, y inside - 0.02 mR/hr max on contact gross, TBM-3S p,7: outside - 0.025 mR/hr max on contact gross, TBM-3S fixed a: inside - 8 cpm gross 3 dpm/ entire surface, Ludlum fixed a: (entire surface) outside - 6 cpm gross <MDA, Ludlum removable a: inside - 12 cpm gross 9 dpnVentire surface, Ludlum removable a: outside - 3 cpm gross <MDA, Ludlum Top Cover Plate:

, y inside - 0.03 mR/hr max on contact gross, TBM-3S

,7: outside - 0.03 mR/hr max on contact gross, TBM-3S fixed a: inside - 4 cpm gross <MDA, Ludlum fixed a: outside - 5 cpm gross <MDA, Ludlum removable a: inside - 7 cpm gross 1 dpnV300 cm2, Ludlum removable a: outside - 3 cpm gross I dpnV300 cm2, Ludlum Control and Safety Rod Guide Tubes:

SR1 extemal surveys:

,7: 0.03 mR/hr max on contact gross, TBM-3S fixed a: 5 cpm gross <MDA, Ludlum removable a: 6 cpm gross <MDA, Ludlum SRI internal surveys:

p,7: N/A, TBM-3S detector to large to fit.

fixed a: N/A, Ludlum detector to large to fit.

removable a: 4 cpm gross <MDA, Ludlum CR external surveys:

p, y: 0.04 mR/hr max on contact gross, TBM-3S fixed a: 10 cpm gross 6 dpm/ entire surface, Ludlum removable a: 4 cpm gross <MDA, Ludlum CR internal surveys:

, y N/A, TBM-3S detector to large to fit.

fixed a: N/A, Ludlum detector to large to fit.

removable a: 7 cpm gross 1 dpm/ entire surface, Ludlum a background check: 6 cpm,4 cpm,7 cpm,10 cpm, = Average bk 7 cpm, Ludlum G53

SR2 external surveys:

, y 0.03 mR/hr max on contact gross, TBM-3S fixed a: 6 cpm gross <MDA, Ludlum -

removable a: 14 cpm gross 10 dpnVentire surface, Ludlum SR2 internal surveys:  :

, y. N/A, TBM-3S detector to large to fit. l fixed a: N/A, Ludlum detector to large to fit. 1 removable a: 9 cpm gross 13 dpm/ entire sudace, Ludlum FR external surveys: l p, y. 0.04 mR/hr max on contact gross, TBM-3S l fixed a: 10 cpm gross 4 dpm/ entire surface, Ludlum removable a: 6 cpm gross <MDA, Ludlum )

FR intemal surveys:

p, y. N/A. TBM-3S detector to large to fit.

fixed a: N/A, Ludlum detector to large to fit.

removable a: 7 cpm gross <MDA, Ludlum Thimble: )

, y 0.05 mR/hr, TBM-3S l fixed a: 69 cpm / entire surface 89 dpm/ entire surface , Ludlum removable a: 69 cpm gross 89 dpm/ entire surface, Ludlum i Control and Safety Rods:

SR1 Fuel Cladding external surveys:

p, y 0.03 mR/hr max on contact gross, TBM-3S fixed a: 4 cpm gross <MDA, Ludlum removable a: 11 cpm gross 7 dpm/ entire surface, Ludlum SRI internal surveys:

, y. N/A, TBM-3S detector to large to fit.  ;

fixed a: N/A, Ludlum detector to large to fit.

removable a: 90 cpm 119 dpm/ entire surface, Ludlum l SR1 Spring:

, y. 0.03 mR/hr max on contact gross, TBM-3S fixed a: 14 cpm gross 10 dpm, Ludlum removable a: 40 cpm gross 47 dpm, Ludlum SRI End Plug:

, y 0.03 mR/hr max on contact gross, TBM-3S G54

1 i

I fixed a: 3 cpm gross <MDA, Ludlum

! removable a: 8 cpm gross 1 dpm/ entire surface, Ludlum ,

1 SR1 Washer: I

, y 0.03 mR/hr max on contact gross, TBM-3S lI fixed a: 5 cpm gross diDA, Ludlum removable a: 6 cpm gross <MDA, Ludlum l SR2 Fuel Cladding extemal surveys:

, y. 0.03 mR/hr max on contact gross, TBM-3S  ;

fixed a: 5 cpm gross <MDA, Ludlum  ;

removable a: 6 cpm gross <MDA, Ludlum 1

a background ebeck: 3 cpm,4 cpm,5 cpm,7 cpm, average bk 5 cpm, Ludlum i

SR2 internal surveys:

, y. N/A, TBM-2S detector to large to fit.

fixed a: N/A, Lud'.um detector to large to fit.

removable a: 96 cpm gross 131 epm /inside surface, Ludlum SR2 Washer:

p, y 0.02 mR/hr max, TBM-3S .

l fixed a: 3 cpm gross diDA, Ludlum removable a: 5 cpm gross <MDA, Ludlum i SR2 Graphite:

l , y 0.04 mR/hr max on contact gross, TBM-3S fixed a: 12 cpm gross 10 dpm/outside surface, Ludlum j removable a: 12 cpm gross 10 dpm/ outer surface, Ludlum l SR2 Spring:

p, y 0.02 mR/hr max on contact gross, TBM-3S fixed a: not counted (may injure detector), Ludlum removable a: 9 cpm gross 6 dpm/ outer surface, Ludlum SR2 End Plug:

, y 0.02 mR/hr max on contact gross, TBM-3S fixed a: 4 cpm gross <MDA, Ludlum removable a: 5 cpm gross <MDA, Ludlum Surveyed by John S. Bennion.

1 G55

AGN Fuel Components Decontamination September 12, 1989 Instruments Used:

Ludlum, a # PRO 21524, scalar # 33640 eff. Pu-239 = 69.5%

a background = 2 cpm,5 cpm,3 cpm; Average Background 3 cpm All wipes approx.100 cm 2 TBM-3S #087129, GM Contamination Meter Calibrated 6/23/89

Background:

0.03 mR/hr AGN poly dise:

,y. 0.04 mR/hr, TBM-3S removable a (inscribed side): 19 cpm, Ludlum removable n (non inscribed side): 12 cpm, Ludlum fixed a (inscribed side): 40 cpm, Ludlum Washed with micro solution:

fixed a (inscribed side): 6 cpm, Ludlum fixed a (non-inscribed side): 6 cpm, Ludlum AGN graphite reflector #8 removable a: 7 cpm, Ludlum After wiping with acetone: 5 cpm, Ludlum p,y < MDA, TBM-3S AGN graphite reflector #6 removable a: 5 epm, Ludlum After wiping with acetone: 7 cpm, Ludlum p,y. < MDA, TBM-3S i

AGN graphite reflector removable a: 6 cpm, Ludlum After wiping with acetone: 8 cpm, Ludlum

,y < MDA, TBM-3S l

l Background check: 6,3,6,6 cpm: average bk 5 cpm, Ludlum l G56

AGN graphite #5 removable a: 3 cpm, Ludlum -

After wiping with acetone: 6 cpm, Ludlum

,y < MDA, TBM-3S AGN graphite #4 removable a: 3 cpm, Ludlum After wiping with acetone: 3 cpm, Ludlum

,y. < MDA, TBM-3S AGN graphite #3 removable a: 9 cpm, Ludlum After wiping with acetone: 4 cpm, Ludlum p,y < MDA, TBM-3S AGN graphite #2 removable a: 5 cpm, Ludlum After wiping with acetone: 7 cpm, Ludlum l

,y. < MDA, TBM-3S

)

AGN graphite #1 removable a: 11 cpm, Ludlum After wiping with acetone: 6 cpm, Ludlum

,y. < MDA, TBM-3S ,

i October 4,1989 Instruments Used:

Ludlum, Model 43-1, a # PRO 21524, scalar # 33640, alpha probe eff. Pu-239 = 69.5%

a background = 3 cpm,4 cpm,4 cpm; Average Background 4 cpm Xetex , Model 318-A2 w/ ext 6 M Probe, # 11964/021819 a background = 0 - I cps Calibrated 7/13/89 TBM-3S, #087129, GM Contamination Meter Calibrated 6/23/89

Background:

0.025 mR/hr G57

Results:

Control Rod 1 - Identified 9/7/89 - 130 cpm removable a contamination:

exterior surface: 5 cpm,4 cpm gross = 1 cpm net, Ludlum l

L interior decontaminated by Byron L. Hardy (DLH)

Interior count rate: less than detectable (<1 cps), Xetex p,y. < MDA, TBM-3S l Fuse Suppon - Identified 9/7/89 - U-235 approx. 90 dpm removable:

l Decontaminated by Bryon L. Hardy l removable a: 2 cpm gross < MDA, Ludlum fixed a: 14 cpm gross, Ludlum l p,y 0.04 mR/hr gross = 0.015 mR/hr max on contact, TBM-3S 2nd Decontamination fixed a: 8 cpm gross over surface, Ludlum removable a: 5 cpm gross, Ludlum p,y. 05 mR/hr max gross, TBM-3S 3rd Decontamination - soak in dilute HNO3 p,y. 05 mR/hr max gross - non removable TBM-3S Control Rod 2 - identified - 9/7/89120 dpm removable a:

Decontaminated by Byron L. Hardy interior:

removable a: 5 cpm gross = 1 cpm net, Ludlum fixed a: 2 cps max, Xetex l 2nd Decontamination by Bryon L. Hardy fixed a: less than detectable with Xetex removable a: 6 epm gross, Ludlum j exterior:

l fixed a: 3 epm gross, Ludlum i

removable a: 2 cpm gross, Ludlum p,y < MDA, TBM-3S Couse Rod:

l interior:

removable a: 8 cpm gross, Ludlum fixed a: < MDA (<1 cps), Xetex p,y. < MDA, TBM-3S exterior:

l removable a: No value given.

G58

November . 21,1989 ~

. Instruments Used-Ludlum, Model 43-1, a # PRO 21524, scalar # 33640, alpha probe ,

eff. Pu-239 = 69.5%' l a background = 4 cpm,3 cpm,4 cpm;' Average Background 4 cpm , -

Xetex , Model 318-A2 w/ ext 6 M Probe, # 11964/021819. .

, y background = 0 - I cps Calibrated 7/13/89 j Fine Rod: .

sealed in plastic, with no detectable contamination:

4 polyethylene discs 1 graphite disc l l

1 spring 1 fastening plug Coarse Rod:

cladding:

interior a: 5,6,7 cpm gross, Ludlum exterior removable a: 11,6,5 cpm, Ludlum interior ,y: 2 cps max,Xetex exterior p,y: 1 cps max, Xetex Spring removable a: 5,2,5 cpm gross, Ludlum p,y. max 1 cps, Xetex fixed a: 5,4,4 cpm gross, Ludlum j Washer removable a: 3,7,4 cpm gross, Ludlum

,y: O cps, Xetex fixed a: 4,3,5 cpm gross, Ludlum Graphite removable a: 2,6,6 cpm gross, Ludlum

,y. I cps max, Xetex fixed a: 5,7,4 cpm, Ludlum G59

4.

End Cap  ;

removable a: 4,5,6 cpm gross, Ludlum l

,y. O cps, Xetex .l fixed a: 6,5,3 cpm gross, Ludlum j Course Rod Sealed in Plastic. l

~ November 22,1989 ,

Background a: 6,- 2,4 ave. bk 4 cpm, Ludlum, ,y. 0-l' cps, Xetex i SRl:

Graphite:  ;

i

,y. I cps max gross, Xetex removable a: 4,4 cpm gross, Ludlum fixed a: 4,5 cpm gross, Ludlum Spring: >

p,y: 1 cps max gross, Xetex removable a: 4,3 cpm gross, Ludlum l fixed a: 4,4 cpm gross, Ludlum Washer: l

,y. O cps, Xetex removable a: 2,5,6 cpm gross, Ludlum i

fixed a:

l End Cap:

,y: O cps, Xetex ,

. removable a: 6,4 cpm gross, Ludlum fixed a: 2,5 cpm gross, Ludlum Cladding:

external removable a: 7,4,4 cpm gross / entire surface, Ludlum internal removable a: 5,5 cpm gross / entire surface, Ludlum

,7 int. & ext.: max reading 1 cps gross, Xetex fixed a ext: 4,5 cpm gross, Ludlum SRI Components Sealed in Plastic.

G60

i Core Reflector: ,

Bottom: i removable n (entire surface): .14,13,12 cpm gross, Ludlum  ;

Top:  ;

removable a (entire surface): 12,7,9 cpm gross, Ludlum i o

Bottom (surface adjacent to fuel only):

removable a: 10,9,16 cpm gross, Ludlum SR2: .!

i Cladding:  ;

external removable a: 4,4 cpm gross / entire surface, Ludlum  :

internal removable a: 64,70,46 cpm gross / entire surface, Ludlum l

,y: No value given.

fixed a ext: No value given.  !

November 24,1989 [l i

background a: 4,4,5 cpm, average bk 4 cpm, Ludlum ,y: 0-1 cps, Xetex '  ;

SR2 Cladding Sealed in Plastic-will either dispose or decontaminated waste, End cap, graphite, -  ;

washer- previously sealed in plastic i spnng:

.l p,y. O cps, Xetex 1 removable a: 4,5 cpm gross, Ludlum  !

fixed a: 5,3 cpm gross, Ludlum  :

Spring was sealed in plastic. '

Aluminum Core Support (approx.14" long, hollow):

removable a: 15,10 cpm gross, Ludlum Contaminated-sealed in plastic.

Screws, miscellaneous hardwood sealed in plastic.

Surveyed by John S. Bennion.

G61

Form NEL-101 RSC Approval:5/25/88 AGN REACIOR DECOMMISSIONING & DISASSEMBLY AGN COMPONENT RADIATION SURVEY RECORD FORM Survey Form #

Surveylocation AGN Reactor. Nuclear Enaineerine Iih. Survey Date r- # -B9 NET ITEM mpeur(e surf ca NO. GENERALDESCRIPTION SURVEJ SURV(Y INSTR GROSS (3) TYPE NETluu (4) M 'cym 4 cm2 y 8 n Total 1 See %.k G P'Pt. SPe n oA e mea o

7. *a l', F PL SPC < mu < moA o 5 n

& F Pt spe ' ~ PA l ~oA o 4 <<

/GFPC SPt 'mok < m oA o 5 >>

M Pc S pc i,.w A s ~ ca o 5 or r E'PC S PC. i moa <ma4 o f or

& FPe SPc. '*> M < *"M o 8 to fa, G PC Cak e ,., O A a ses pth e ey .. /,', F Pd E Pt_ e ,,, o A emn4 o

_1o

/sPfd GPe z. o+r0 4 t s*w 4 o oi 6 FRL SPc t m o4 & m 04 e '

tz i- (., F Pt. sPe. &nsuA nM o DETECf0R COUNTING YIELD USED: REMARKS f/,

kry [ g[f.,bf_ P gf50 vo/rg a ,> ~ c c a = i kJoUef.e m ,m o.a.s e s ,,, e A.W. y .,.J co;- (, cl A) *11.0 c/w (1) Background counting rate at (3) Survey L=m .ca Co:les:

was epm = 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) 5 background radiation levels. Exceptions:

(, AS , p/w pn,forteM c,s rer-

. (4) Survey Type c',wi,e D = Diret Survey over the entire surface of the object.

(2) Background counting rate for this instrument SG = 100-300 cm2 wipe counted with a portable GM.

was cpm = dpn. 'Ihe SL = 100-300 cm2 wipe counted with a liquid LLD at 95% confidencelevel was net scintination counter (3H).

dpm = net pCi. No wipes above the SGS = 100-300 cm2 wipe counted with a gamma LLD, except from the foBowing items: spectrometer.

S PC soo-toocm a,;fe cwnrulws k r Q' (reforwd esustrc SURVEY PERFORMEDBY:

[MI'I'ett d G62

~ Form NEL.101 RSC Appeval:5/25/88 1 1

AGN REACIVR DECOMMISSIONING & DISASSEMBLY AGN COMPONENT RAEiATION SURVEY RECORD PORM i

Surveylocation Survey Form #

AGN R**, ear. Nn< ta- Rad = is I* Survey Date NET nsu -n ^- ta _ __)

SURVEY SURVEY GROSS NET _dma_. ,

NO. GENERALDESCRFnON INS 11t(3) TYPE (4) qpm syn 100cm2 y 8 a Total 15 See L k. iCp?* S R2 <- m D 4 4 m a 4 e l

1. 4 " - a i 4 ,,, o A u o e

_ ,g or u .. t m os sm M o  !

/(, # 4 "

4 #t D ) d re:Mo

!? GFPC Sit s m eA ' * *A- o

_ts or "

im os smat o e

'or ti i<

s.rnoA 4moAe n * ** **

tm4 a.ma4 e

_ti N ** U I 4.oe4 94 4.M 94 e N yi k hPk Sk ***1b4 AniDA O n 11 fo Ff( G $l* 4 *** D 4 4 **t a d e DETECTOR COUN11NG YIELD USED:  !

REMARKS: g ,7fggg I

)lp flese & Ibv$bt'c osoc.s- @ l A V Asume l$s tons B q)c ours't- 18' Cy (1) Background counting rase at (J)SurveyInstnanent Codes.

was cym =

TAGM = Technical Associates portable GM with dpm = mRendir. pancake probe (thin window).

Direct radiation levels from the (area. Serial #

item (s)) surveyed (were, were not) s background radiation levels. Exceptions 6FPe - G=r FIN fr*P"'8" # 0"*"'-

(4)SurveyType Codes:

(2) Background counting rate for this instrurnent D = Dirct Survey over the entire saface of the object. 4 was SG = 100-300 cm2 wipe coursed with a ponable GM. '

epm = dpm. The SL = 100-300 cm2 wipe counted with a liquid LLD at 95% confidencelevel was - net dpm = not pCi. No wipes above the scintillationcounter(3H).

SGS = 100-300 cm2 wipe counted with a gamma LLD,except from the foBowing items: speccomener.  ;

SPC,

• J 4,  !

t**-SeaC*@ 'vag s a t a ,/ is e m ga.s Clo.o ro rso C-o v r rt r-SkelS et '

j SURVEY PERFORMEDBY: _

hW/L  %

i G63

i l

Notes From The Back of Form NEL-101 I t

hcm General Description 1 Lead Shield East 100 cm2 T.C. out/ Fuel in  ;

2. Lead Shield West 100 cm2 T.C. out/ Fuel in j

.3' 2 Lead Shield North 100 cm T.C. out/ Fuel in

-4 Lead Shield South 100 cm2 T.C. out/ Fuel in >

5 Bottom of AGN Thennal Column,just after removal of T.C., fuel, and source in '

6 Sidewall of Thermal Core Receptacle. East Fuel in, Thermal Core out ,

7 Sidewall of Thennal Core Receptacle West Fuel in Thennal Core out 8 Sidewall of Thennal Core Receptacle, Nonh Fuel in, Thennal 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, Thennal Core out, Fuel in 12 Graphite Reflector Rim East, Thermal Core out, Fuel in '

13 Graphite Reflector Rim West, Thermal Core out, Fuel in  ;

14 Fuel Cover, Thermal Core out, Fuel in  ;

15 Ra-Be Source in corejust after removed 5/4/89 16 Control Rod 1 (CRI) Fuel Element 17 Control Rod 2 (CR2) Fuel Element 18 Fine Control Rod Wipe i

Spring Assay Wipe (CR2) 19 20 Course Control Red Spring Assay Wipe ,

21 CR1 Spring Assay Wipe 1 22 Fine Control Rod Spring Assay Wipe 23 Course Control Rod Fuel Wipe Surveyed by John S. Bennion.

i G64

.,, ~ _ _ _ _,

-1 1

7. Second Facility Survey Prior to resuming decommissioning activities on the AGN reactor a survey of the reactor exterior and of the immediate vicinity'was performed. This survey's purpose was to insure exposure to the decommissioning staff was as low as possible, and to identify any potential

_ problem areas. No removable or fixed contamination was found. The 'detectors used were capable

. of alpha, beta, and gamma detection. The potential presents of alpha contamination is extremely improbable on the exterior of the AGN or the surrounding facility area.

l t

t i

ass a

i -

AGN DECOMM8SSIONfNG i

RPR 50C. CONTAMINATION WIPE TEST RESULTS User: %dge M4 -

'h' Group i: im Date: 3/I T/9 7 Task #: *^

Bldg / Room (s): 1260 E #EU Isotopes used: "H Ad* bc- O *k m 1

COUNTING INSTR 1 MENT DATA l Model, serial f: LS- 7 Co t' -" N i"7 Prograin/ Setup: 7-1 Preset: I minutes or -

counts Units of Readout: c M^

0 sta attached Counting Channel: Ill I21 I31

/

or entered here: Background b OTi [

Isotope: I4 Efficiency: C C'l ~

Expected Net Response to 1 RCL: b(' \

Isotope: f Effsetency: o td --

c '. c I' /

Expected Net Response to 1 RCL: IN MIPE TEST COUKTING RESULTS

[A] Enter "100" for a 100 cut wipe or "300" for a 300 cat ,gp,, I

[B) het response in each channel in same units se recorded above.

i If the not response in any channel exceeds that expected for 1.RCL of any isotope:

lC; enter the Itkely nuc1tde and l

', D, enter the multiple of the RCL.

[A] .s

[B] [C] [D]

ling Ob.iect or location Arga _ Net > Channel Resoonse likely Multiple

,(gL}, Ill I21 I31 Isotone of RCL 1 l <' + ** M 's l'- O M /

2 c u m ,w..5 % <,..,\ d 1. ; c4 c' l 3 w I2 N -

cP c,+ L O

1205-E

.g. va s -

o- c.,. _,

1

@ Co s AGN c.o. ,

O

"~ - " -

c,a 1205 cu -

E.F c.e ,.

enums SURVEY METER (S) USED: ~

.LUDLUM MICRO-R SERIAL *12911

@ results (VIPE attached)LOCATIONS CAllBRATED 3/8/93 1205-A 41 RECT READINGS IN rr.R/hr A.A. TBM-3S SERIAL 8093127 gy kq,J : O c ' '. a t L CAllBRATED 7/28/92 G6 _

EXIT

- =. . .

. J P) V E qaups r eaups c 2

ont 6 j 7 005

' kb' l207-6 20 Ha 11  ;

42 Ha  !

j 4 ELT 4.63 MIN ELT 16.40 MIN f CH 1 3lUl0 #' '

2.00 CfN CH 1 8.00 CPM 99.99 2Fx. ,

70.50 2rx ST 1 00 MIN CH 2

.ST. 1.00 MIN CH 2

'13.00 CPN i5.00 CPM 55.38 2ai 51.60 '2tx t a WPa r 3 samps F

• y DOS A 809 17 28.Hs ..

27 Hs ELT 6.88 MfN ELT. 18.65 Mis CN 1 CH 1 7.00 CPN 3 0'0 dPN 75.42 2Fi _

99.99 2Fi

, C' A L 780 MEM ST 1 00 min . ST 1 00 MfM CH 2 CH 2 ',

'1 8'.'0 0 C P N

',,9 ,

47.11 2at i3 00 CPN 55.38 2ri CNT CH H12 1 T I ME'S( eaup F 4 SCR NO s a ws: r g 40C e' n t 9 808 NO 13 CALC 4 5 'Hs PST 1 , . ,

. ELT 9'.25 Mfy 33 Hs 1.00 MIN ELT CH 1 CH 1 21.00 MIN

,2.00 2FX CH 1 O 'l 4.00 CPN 7.00 CPM

)

99,99 2FE  !

. 317 U.. -.

75.42 2ax I CH 2 ST 1 00 MIN ST 2.00 2rX 1.00 MIN 397 L CH 2 CH 2 655 u . 17.00 CPM 18.00 CPM AB.47 2Fi 47.11 2's ,

t aMPt r 5 tsuntv t

'*** 'O NR O 6 0 Ha ELT 11.50 MIN, 21 Hs ELT., 2 37 MIN- CH 1 CH I 12'.00 CPM 6.00,CH 57.66 2ax ST 1.00 MIN 81.33 2aK ST 1.00 MIN CH 2 "2 -

18.00 CPM' 35.'00 CPN

• 51.60 2ax G68

1 l

8. AGN Comoonent Surveys Upon resuming decommissioning activities on the AGN reactor the remaining components were surveyed. These surveys were performed to determine if any contamination still existed on these parts, and if any of the parts might have picked up new contamination from the long storage period in the TRIGA Facility. In the course of these surveys the parts from the pervious administration that had been sealed in plastic due to contamination from contact with the fuel were not resurveyed in detail. These pans remained sealed to reduce exposure to decommissioning personnel and were disposed of as radioactive waste through the University of Utah's Radiological Health Department. The following surveys are preliminary in form. The purpose of these surveys are to identify pans to be released as non-contaminated waste. These selected parts were then re surveyed in much more detail for release as unrestricted waste. The unrestricted waste surveys are in the next section of this appendix. No contamination was detected.

4 i

a M

E G69

b Part # Direct Counting Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludium Model Beckman LS-7000 2200 (197M) (7700259) 3 1 0.02 mR/hr Sealed Scaled Safety Rod #2 (Empty) 0.02 mR/hr Course and Fine Control Rod Thimbles 2 Sealed Sealed 3 0.02 mR/hr 0 OA) "O" Ring Core Can Top Plate 4 0.02 mR/hr Sealed . Scaled Paint Chips from Thermal Column 5 0.02 mR/hr Sealed Sealed Safety Rod #2 Parts -

6 0.02 mR/hr Sealed Sealed Core Can Assembly Bolts and Spring ,

7 0.02 mR/nr Sealed Sealed Assembly Bolts And Washers (Com Can) 8 0.02 mR/hr Sealed Scaled Com Suppon Rod 9 0.02 mR/hr Sealed Sealed Quantity-2 Safety Rod Thimbles 10 0.02 mR/hr Sealed Sealed Safety #1 with Parts 11 0.02 mR!hr Scaled Scaled Course Control with Parts 12 0.02 mR/hr Scaled Sealed Fine Control Rod with Parts -

0 13 0.02 mR/hr Sealed Sealed Core Support

$ 14 0.02 mR/hr 0 OA) Core Can Top Plate

< 15 0.02 mR/hr 0 OM Core Can Bottom Plate

'6

. 0.02 mR/hr 0 OA) Polyethylene Disk i

s7 0.02 mR/hr 0 OA) Graphite Reflector for Interior Core Can 1el 0.02 mR/hr Sealed Sealed Aluminum Core Can 19 0.02 mR/hr 0 OA) Graphite Reflector Plate

) 20 0.02 mR/hr 1(0) - 04) Graphite Reflector Plate 21 0.02 mR/hr 0 0/4 - Graphite Reflector (Bottom Interior Core Can)

22 0.02 mR/hr 0 OA) Interior Thermal Column 23 0.02 mR/hr 0 OA) Extemal Thermal Column 24 0.02 mR/hr 0 OA) Top Thennal Column Cover plate 25 0.02 mR/hr 1(0) OA) Bottom Thermal Column Cover plate 26 0.02 mR/hr 0 OA) Socket and Wrench 27 0.02 mR/hr 0 OA) Glory Hole /Pon Covers Assembly with Covers 28 0.02 mR/hr 0 OA) Rod Drive i

29 0.02 mR/hr 2(0) OA) Rod Drive - 1 30 0.02 mR/hr 0 OA) Rod Drive 31 0.02 mR/hr 0 OA) Rod Drive 4

,i Part # Direct Counting Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludlum Model Beckman LS-7000 2200 (19788) (7700259) 32 0.02 mR/hr O Oh Wood Plug in Access Port 33 0.02 mR/hr 0 OA) Wood Plug in Access Port 34 0.02 mR/hr O OA) Wood Plug in Access Port 35 0.02 mR/hr 0 OM Wood Plug in Access Port 36 0.02 mR/hr 0 OA) Wood Plug in Access Port 37 0.02 mR/hr 2(0) 0A) Wood Plug in Access Port 38 0.02 mR/hr 0 OA) Wood Plug in Access Port 39 0.02 mR/hr 0 OA) Wood Plug in Access Port 40 0.02 mR/hr 0 OA) Wood Plug in Access Port ~

41 0.02 mR/hr 0 OA) Wood Plug in Access Port 42 0.02 mR/hr 0 OA) Lead Plug in Access Port 43 0.02 mR/hr 0 OA) Lead Plug in Access Port 44 0.02 mR/hr O OA) Lead Plug in Access Port C 45 0.02 mR/hr 0 OA) Lead Plug in Access Port j 46 0.02 mR/hr 0 OA) Lead Plug in Access Port 47 0.02 mR/hr 0 OA) Lead Plug in Access Port 48 0.02 mR/hr 0 OA) Lead Plug in Access Port 49 0.02 mR/hr 0 OA) Lead Plug in Access Port 50 0.02 mR/hr 0 OA) Lead Plug in Access Port 51 0.02 mR/hr 0 OA) Lead Plug in Access Port 52 0.02 mR/hr 0 OA) Lead Plug in Access Port '

53 0.02 mR/hr 0 OA) Lead Plug in Access Port -

l 54 0.02 mR/hr 0 OA) Lead Plug in Access Pon 55 0.02 mR/hr 0 OA) - Lead Plug in Access Port l

56 0.02 mR/hr 0 OA) Lead Plug in Access Port 57 0.02 mR/hr O OA) Lead Plug in Access Port 58 0.02 mR/hr 0 OA) Aluminum Fuse Support 59 0.02 mR/hr 0 OA) Alignment Screws 60 0.02 mR/hr 0 OA) Polyethylene Rod 61 0.02 mR/hr 0 OA) Graphite Plug in Access Pon 62 0.02 mR/hr 0 OA) Graphite Plug in Access Pon 63 0.02 mR/hr 0 OA)- Graphite Plug in Access Port

.. . . . - . . . - . . .. .- . . . -- - - _ . . ~ . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - - _ _ _ . - - _ _ _ _ _ _ _ _ - - _ .

Part # Direct Counting Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludlum Model Heckman LS-7000 2200 (19788) (7700259) 64 0.02 mR/hr 0 OA) Graphite Plug in Access Pon 65 0.02 mR/hr 0 O/0 Cadmium Plug 66 0.02 mR/hr 0 OA) Graphite Plug in Access Port 67 0.02 mR/hr 0 OA) Graphite Plug in Access Pon 68 0.02 mR/hr 0 O/0 Graphite Plug in Access Port 69 0.02 mR/hr 0 OA) Graphite Plug in Access Port 70 0.02 mR/hr 0 OA) Aluminum Access Port Sleeve 71 0.02 mR/hr O OA) Aluminum Access Port Sleeve 72 0.02 mR/hr 0 OA) Aluminum Access Port Sleeve 73 0.02 mR/hr 0 OA) Aluminum Access Port Sleeve 74 0.02 mR/hr 2(0) OA) Graphite Redector Columi:

75 0.02 mR/hr O OA) Bottom Lead Shield Ring 76 0.02 mR/hr 0 OA) Bottom Lead Shield Ring w/ Access l'ons O 77 0.02 mR/hr 1(0) OA) Top Lead Shield Ring w/ Access Pens d 78 0.02 mR/hr O OA) Top Lead Shield Ring 79 0.02 mR/hr O OA) Bottom Lead Shield Plate 80 0.02 mR/hr 0 OA) Fission Gas Canister 81 0.02 mR/hr 0 OA) Wood Plug in Access Port 82 0.02 mR/hr O OA) Wood Piug in Access Port 83 0.02 mR/hr 0 OA) Associated Core Assembly Bolts 84 0.02 mR/hr 0 OA) Control Rod Support Plate 85 0.02 mR/hr O OA) Cadmium Disks 86 0.02 mR/hr See Page G77 See Page G77 Main Reactor Tank 87 0.02 mR/hr O OA) Reactor Console

7 I

9. Unrestricted Comnonent Survev  :

The objective of these surveys are to demonstrate that all pans below meet NRC guidelines y for the release as non-contaminated waste. The NRC will perform confirmation surveys on these i parts prior to their release. These selected parts are surveyed in detail for release as unrestricted l waste. One part had a very small amount of counts,27 cpm net. This part was decontaminated.

No other contamination was detected. These part . are being held on site in room 1205E. i i

t i

[

l s

G73

Parts to be released as unrestricted waste.

4 Com Can Cover, Top Part # 14 Direct Counting Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludium Model Beckman LS-7000 2200 (197M) (7700259) ,

A 0.02 mR/hr 0 OM exterior B 0.02 mR/hr 0 OM interior Core Can Cover, Bottom t

Part # 15 Direct Counting- Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludlum Model Beckman LS-7000 2200 (197M) (7700259) ,

A 0.02 mR/hr 0 OM exterior B 0.02 mR/hr 1(0) OS interior O

2 Polyethylene Disk 3

Part # 16 Direct Counting . Net Alpha cpm Net LSC cpm . Description l TBM-3S (093127). Ludlum Model Beckman LS-7000  !

2200 (197M) -(7700259)

A 0.02 mR/hr 0 OM Opposite Disk Sides -

B 0.02 mR/hr 0 OM Opposite Disk Sides

, Thermal Column Interior (22) And Exterior (23) l Part # Direct Counting . Net Alpha cpm Net LSC cpm Description 22/23 TBM-3S (093127) Ludium Model Beckman LS-7000 2200 (197M) (7700259)

A 0.02 mR/hr 0 OM 1/4 of Wall, Interior (22)

B 0.02 mR/hr 0 ]i- OM 1/4 of Wall, Interior (22)  ;

C 0.02 mR/hr 0 OM 1/4 of Wall, Interior (22) - '

D 0.02 mR/hr 0 OM 1/4 of Wall, Interior (22)

E 0.02 mR/hr 0 OM Interior Floor (22) -  !

___- . . . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , . . _ . . - - . _ . ~ - _ _ . _ _ . ~ . _ . _ , _ _ _

F

Part #

1 22/23 Direct Counting Net Alpha cpm Net LSC cpm Description

. TBM-3S (093127) Ludlum Model Beckman LS-7000 2200 (197M) (7700259)

F 0.02 mR/hr 0 OA) 1/4 of Wall, Exterior (23) t G 0.02 mR/hr 0 OA) 1/4 of Wall. Exterior (23)

H 0.02 mR/hr O OA) 1/4 of Wall, Exterior (23) 1 0.02 mR/hr 0 OA) 1/4 of Wall. Exterior (23)

J 0.02 mR/hr 0 OA) Exterior Floor (23)

Thermal Column Cover Plate i Part # Direct Counting Net Alpha cpm Net LSC cpm Description 24/25 TBM-3S (093127) Ludium Model Beckman LS-7000  ;

2200 (197M) - (7700259)

A O.02 mR/hr O OA) Top (24)

, , B 0.02 mR/hr 0 OA) Bottom (25)

Access Port And Glory Hole Parts Part # 27 Direct Counting Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludium Model - Beckman LS-7000 2200 (19788) (7700259)

A 0.02 mR/hr 0 OA) Access Pon Sleeve B 0.02 mR/hr 0 OA) Access Pon Sleeve C 0.02 mR/hr O OA) Access Pon Sleeve  !

D 0.02 mR/hr O OA) Access Port Sleeve E 0.02 mR/hr - 0 OA) Access Pon Sleeve F 0.02 mR/hr 0 OA) Access Pon Sleeve G 0.02 mR/hr 0 OA) Access Pon Sleeve H 0.02 mR/hr 0 04) Access Port Sleeve 1 0.02 mR/hr 0 OA) Access Port Cover J 0.02 mR/hr 0 04) Access Port Cover K 0.02 mR/hr 0 OA) Access Port Cover L 0.02 mR/hr 0 OA) Access Port Cover i

Part # 27 Direct Counting Net Alpha cpm Net LSC cpm Description TIIM-3S (093127) Ludlum Model lleckman LS-7000 2200 (19788) (7700259)

M O.02 mR/hr 0 OA) Access Port Cover N O.02 mR/hr 0 OA) Access Port Cover O O.02 mlVhr 0 OA) Access Port Cover P O.02 mR/hr 0 OA) Access Port Cover Q O.02 mR/hr O OA) Access Port And Glory Hole "O"-Rings R O.02 mR/hr 0 0/0 Glorv tiole Sleeve S 0.02 mR/hr 0 OA) Glorv llole Cover T 0.02 mR/hr 0 UA) Glory Hole Cover U O.02 mR/hr 0 OA) Glorv liole Sleeve V 0.02 mR/hr 0 OA) Associated Bolts And Nuts Alignment Screws O

g Part # 59 Direct Counting Net Alpha epm Net LSC cpm Description TBM-3S (093127) LudIum Model Beckman LS-7000 2200 (19788) (7700259)

A O.02 mR/hr O OA) Core Can Alignment Screw B 0.02 mR/hr O OA) Core Can Alignment Screw Part #'s Direct Counting Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludtum Model Beckman LS-7000 2200 (19788) (7700259) 3 0.02 mR/hr 0 OA) Core Can "O"-Ring 58 0.02 mR/hr 1(0) OA) Aluminum Fuse Support 60 0.02 mR/hr O OA) Polyethylene Rod

Control Rod Support Plate Part # 84 Direct Counting Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludlum Model Beckman LS-7000 2200 (197M) (7700259)

A 0.02 mR/hr 0 OA) Interior Side With Rods - i B 0.02 mR/hr 0 OA) Exterior Side

, Reactor Main Tank  ;

5 Part # 86 Direct Counting Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludlum Model Beckman LS-7000 2200 (197M) (7700259)

A 0.02 mR/hr 0 OA) 1/4 Base Plate, Interior Of Bottom Section '

B 0.02 mR/hr 0 OA) 1/4 Base Plate, Interior Of Bottom Section ,

C 0.02 mR/hr 0 OA) 1/4 Base Plate, interior Of Bottom Section '

D 0.02 mR/hr 0 OA) 1/4 Base Plate, Interior Of Bottom Section

[' E F

0.02 mR/hr 1(0) OA) 1/4 Wall. Interior Of Bottom Section 1/4 Wall, Interior Of Bottom Section 9 0.02 mR/hr 1(0) OA) i G 0.02 mR/hr 0 OA) 1/4 Wall, Interior Of Bottom Section 11 0.02 mR/hr 0 OA) 1/4 Wall, Interior Of Bottom Section I 1 0.02 mR/hr 0 OA) 1/4 Rod Drive Cylinder Plus Ceiling J 0.02 mR/hr 0 OA) 1/4 Rod Drive Cylinder Plus Ceiling 4

K 0.02 mR/hr 0 OA) 1/4 Rod Drive Cylinder Plus Ceiling L 0.02 mR/hr O OA) 1/4 Rod Drive Cylinder Plus Ceiling i M 0.02 mR/hr -0 3/O 1/8 Base Plate

• L N 0.02 mR/hr 0 OA) Bottom Section Door Both Sides

, O 0.02 mR/hr 0 OA) 1/8 Bottom Section

! P 0.02 mR/hr 0 OA) 1/8 Bottom Part Of Big Cylinder Q 0.02 mR/hr 0 OA) 1/8 Bottom Of Big Cylinder Wall Q1 0.02 mR/hr 0 OA) Top Access Pon On Temperature Gage Side Q2 0.02 mR/hr 1(0) 0/0 Top Access Pon On Temperature Gage Side R 0.02 mR/hr 0 OA) 1/8 Top Of Big Cylinder Wall R1 0.02 mR/hr 0 OA) Bottom Access Port, Temperature Gage Side R2 0.02 mR/hr 1(0) OA) - Bottom Access Port. Temperature Gage Side

- - - - . . - ~ - . ~ - - -- ---- - - - - . , _ _ - - _ _ - - - _ _ _ _ - - _ . . ~ . - . . -___ ;- - L . - - , _ . - _ - - - - - -- -- ..

Part # 86 Direct Counting Net Alpha cpm Net LSC cpm Description TBM-3S (093127) Ludlum Model Beckman LS-7000 2200 (19788) (7700259)

S 0.02 mR/hr 0 OA) 1/8 Base Plate T 0.02 mR/hr 0 OA) 1/8 Bottom Section U 0.02 mR/hr 0 OA) 1/8 Bottom Part Of Big Cylinder V 0.02 mR/hr 0 OA) 1/8 Bottom Of Big Cylinder Walt W 0.02 mR/hr 0 OA) 1/8 Top Of Big Cylinder Wall X 0.02 mR/hr 1(0) OA) 1/8 Base Plate Y 0.02 mR/hr 0 OA) 1/8 Bottom Section Z 0.02 mR/hr 0 OA) 1/8 Bottom Part Of Big Cylinder AA 0.02 mR/hr 0 OA) 1/8 Bottom Of Big Cylinder Wall 1/8 Top Of Big Cylinder Wall

~

BB 0.02 mR/hr 0 OA) bbl 0.02 mR/hr 0 2A) Glory Hole CC 0.02 mR/hr 0 OA) 1/8 B ise Plate DD 0.02 mR/hr 0 OA) 1/8 Bottom Section O EE 0.02 mR/hr 0 OA) 1/8 Bottom Part Of Big Cylinder y FF 0.02 mR/hr 0 OA) 1/8 Bottom Of Big Cylinder Wall GG 0.02 mR/hr U OA) 1/8 Top Of Big Cylinder Wall HH 0.02 mR/hr ') OA) 1/8 Base Plate 11 0.02 mR/hr 0 OA) 1/8 Bottom Section And Part Of Big Cylinder ,

. JJ 0.02 mR/hr 1(0) OA) Bottom Section Door Both Sides KK 0.02 mR/hr 0 OA) 1/8 Bottom Of Big Cylinder Wall KKI 0.02 mR/hr 0 OA) Bottom Access Port -

KK2 0.02 mR/hr 0 OA) Bottom Access Pon -i LL 0.02 mR/hr 0 OA) 1/8 Top Of Big Cylinder Wall LLI 0.02 mR/hr 0 OA) Top Access Pon LL2 0.02 mR/hr 0 OA) Top Access Pon MM 0.02 mR/hr 0 27A) 1/8 Base Plate NN 0.02 mR/hr 0 OA) 1/8 Bottom Section 00 0.02 mR/hr 0 OA) 1/8 Bottom Part Of Big Cylinder

, PP 0.02 mR/hr 0 OA) 1/8 Bottom Of Big Cylinder Wall QQ 0.02 mR/hr 0 OA) 1/8 Top Of Big Cylinder Wall RR 0.02 mR/hr 0 OA) 1/8 Base Plate-SS 0.02 mR/hr 0 OA) 1/8 Bottom Section

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i l

I Annendix H:

I

..-Survev Instrument Data The following survey instruments were used during the decommissioning process of the~ t AGN 201M reactor. i 1

Liquid Scintillation Counter.

Make: Beckman LS-7000 Serial Number: 7700259

Background:

Ch.1 = 916 cpm / Ch. 2 = 1718 cpm Efficiencies: (wipes) H-3 = .03 / C-14 = .04 / P-32 = .60 / I-125 = .35 Calibration Date: Calibrated monthly .

Instrument Used: Preliminary Defueling (console wipes), Facility Survey, AGN 1 Components, Unrestricted Release i

Windowless Gas Flow Proportional Counter. i Make: Ludlum Model 2200 scalar Serial Number: 19788

Background:

0-5 cpm i

l Efficiencies: (wipes) alpha = .35 Calibration Date: 5/21f)3 Instrument Used: Core Components , AGN Components, Unrestricted Release Thin Window G-M.

Make: Technical AssociatesTBM-3S Serial Number: 093127

Background:

50120 cpm Efficiencies: C-14 = .05 / P-32 = .27 Calibration Date: 7/28/92,7/26/93 Instrument Used: AGN Components, Unrestricted Release III

l 1 .

a 1hin Window G M.

Make: Technical AssociatesTBM-3S Serial Number: 087129- l

~

Background:

60-150 cpm :

Efficiencies: C-14 = .04 / P-32 = .23 ,

Calibrat6n Date: 12/22/88 (blocks),6/23/89 (defueling) . -

~

c. Instrument Used: Concrete Blocks, Defueling, Core Components i

Thin Window G-M.'

Make: Technical AssociatesTBM-3S

. Serial Number: 066164

Background:

70-140 cpm  ;

Efficiencies: Cl-36 = .22 Calibration Date: 6/25/87 I Instrument Used: Concrete Blocks Thin Window G-M. .

Make: Technical AssociatesTBM-3S Serial Number: 092332

Background:

50 cpm (blocks) .  !

. Efficiencies: Cl-36 = " ]

Calibration Date: 12/22/88  ;

Instrument Used: Preliminary Defueling, Concrete Blocks ,

i Alpha Scintillation j Make: Ludlum43-1 PRO #02132 Serial Number: 33640

Background:

0-1 cpm

~ Efficiencies: alpha 31%

Calibration Date:

Instrument Used: Defueling, Core Components H2 '

!E High Purity Ge Crystal Make: EG&G ORTEC Serial Number: 25-P-K72

Background:

less than 0.01 nCi Efficiencies: Varies with energy Calibration Date: at each use Instrument Used: AGN Shield Water Survey GM Probe:

Make: Xetex, Model 318-A2 w/ ext. 6 M Probe Serial Number: 11964 /021819

Background:

0-1 cps Efficiencies: C-14 = 7%, Cl-36 = 25%, P-32 = 26%

Calibration Date: 7/13/89 Instrument Used: Defueling, Core Components EPA Detectors: The following detectors are calibrated with a 10 mci Cs-137 source by the EPA.

These detectors are rotated out every year and are no longer on site.

Micro R Meter Make: Ludlum Model 19 )

Serial Number: 7950

Background:

0.03 mR/hr l Efficiencies: Exposure rate within 10% on all usable scales.

Calibration Date: 7/28/89, with NIST sources Instrument Used: Defueling, Core Components i

Ion Chamber Make: Eberline Serial Number: 289  ;

Background:

0.03 mR/hr Efficiencies: Exposure rate within 10% on all usable scales.

I Calibration Date: 1/22/89 Instrument Used: Defueling II3

.v.  ;

< lon Chamber Make: Eberline E-5008

, 4 Serial Number: 1015 w I

Background:

0.03 mR/hr Efficiencies: Exposure rate within 10% on all usable scales.

Calibration Date: 12/18/89 L--

Instrument Used: Defueling H.

?

Ion Chamber Make: Eberline RO-2A Serial Number: 1263

Background:

0.01 to 0.02 mR/hr Efficiencies: Exposure rate within 10% on all usable scales.

Calibration Date: -7/28/89 Instrument Used: Defueling, Core Components 1

l Pressurized Ion Chamber ]

Make: Victoreen450P ,

Serial Number: 172' Background. 0.01 mR/hr Efficiencies: Exposure rate within 10%.

Calibration Date: 2/6/89 Instmment Used: Defueling l

l l

11 4

4 I

i Annendix I:

Survey Oneration And Site ".ala i This section of the report details the methodologies, objectives, and procedures used in the decommissioning of the AGN-201M reactor. This section is broken down into the same sub .-  ;

sections as are listed in Appendix G as follows:

General Site Characteristics I Preliminary Defueling Surveys.

Concrete Block Surveys. )

AGN Water Survey.  !

Thennal Column Survey. i The Fuel Surveys.  !

The Core Component Surveys.

Facility Suivey For Continued Deconunissioning Activities. .

AGN Component Surveys. l The Surveys For Parts To Be Released For Unrestricted Use.

This arrangement insures that there is a solid match between the data and the specific -j methodologies used to acquire it. Each of these sub-sections is further broken down into the l following areas:

Objectives Expected Contaminants Instrument Type -

Instrument Caliv.ation Instrument Procedures Survey Procedures Primary Contaminates ,

Exposure Rates Contamination Guidelines Calculations _

i This arrangement, of the procedures and decisions used to gather the data in Appendix G, will give all the relevant infonnation needed to show compliance with NRC regulations and the quality control system used in perfonning the decommissioning surveys.

I1

General Site Characteristics:- .

L Site History: The University of Utah's AGN-20lM reactor went initial criticality 12 September 1957. From this time until July 1%9 the reactor operated at a reactor power level of 100 mWatts for about 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> per year, generating about 2 Watt-hours per year of energy. In July 1969 the reactors power level was increased to 5 Watts. Operating at 5 Watts required the construction of a large 18 inch thick concrete block wall. After July 1969 the reactor produced about 16.4 Watt-hours per year. The reactor was finally shut down on 19 February 1985, and the reactor has not operated since.

Site Radiological Status: The AGN-20lM was a polyethylene moderated, graphite reflected, water shielded core. The core consisted of nine uranium oxide impregnated polyethylene disks enriched to less than 20% U-235. Safety and Course rods contained the same fuel material  !

sealed in aluminum capsules. Reactivity increased as the rods were inserted in to the core. On 18 August 1989 the stanup source was removed and the reactor was defueled. The stanup source and  ;

fuel have since been n moved from the site. Only parts in direct contact with the fuel showed any contamination. No activation was seen anywhere on the site. Parts that showed non-remotable -

contamination were sealed in plastic. These parts have since been disposed of through Radiological Health as radioactive waste. All Remaining parts have been classified as Radiological Waste, Pans to be Transferred to other licenses, and Unrestricted Waste. Parts designated as Radiological Waste have been disposed of through Radiological Health as Radiological Waste.

Parts Transferred to other licenses either remain on site under the TRIGA License or have been transferred to Idaho State's Reactor License. All parts that were not contaminated were designated as Unrestricted Waste and remain on site pending the NRC's final survey, at which time these parts will be released to a landfill or scrap metal facility.

12 l

_ _ ~. _ _

= ,

l Preliminary . Defueling Surveys: .

Objectives: Determine radiological contaminates that might effect defueling smveys.

Expected Contaminants: No contaminants are expected on the exterior of the reactor.

Inside the core can some contamination from the fuel is possible.

Instrument Type: A GM contamination Meter (TBM-3S #092332) was used for direct metering. A Liquid Scintillation Counter (Beckman LS 7000

1. 7700259) was used for removable contamination survey.

Instrument Calibration: The GM meter's efficiency was detennined with Cl-36 a medium beta emitter for an efficiency of 22%. The LSC is calibrated monthly and has experimentally detennined efficiencies of 4%, and 3% for C-14 and H-3 with respectively.

Instrument Procedures: Battery checks on all the survey meter (s) used were perfomied prior to the start of surveys. The GM contamination meter was held one inch from all surveyed surfaces. All wipes counted by the LSC were 100 cm2 in area.

Survey

Description:

The top, sides, and control rod area of the reactor were both directly surveyed and wiped for contamination. Also the floor surrounding the reactor was directly surveyed.

Primary Contaminates: No contaminants were found.

Exposure Rates: Only backgrcund radiation levels were detected.

Contamination Guidelines: Any counts exceeding background required >

remediation.

Calculations: NA.

13

Concrete Block Surveys:

Objectives: Determine if concrete blocks can be released from facility as non-contaminated.

Expected Contaminants: No contaminants are expected on the concrete blocks, and activation is not a possible radiation source. i Instrument Type: GM contamination Meters (TBM-3S's, #087129, #066164,

1. 092332) were used for direct metering.

Instrument Calibration: The GM meter's efficiencies were determined with P- .

32, (#087129) and Cl-36 (#066164, #092332). P-32 and Cl-36 are high  !

and medium beta emitters mspectively. These detectors had efficiencies of ;

23%,22%, and 22% respectively.

Instrument Procedures: Battery checks on all the survey. meter (s) used were perfonned prior to the start of surveys. The GM contamination meters were held one inch from all surveyed surfaces.

Survey

Description:

The individual blocks were individually surveyed on all six faces )

and then placed on pallets. The blocks were then surveyed. Next the blocks were - l rotated to face the opposite side up and surveyed again on the top face.  !

Primary Contaminates: No contaminants were found.  ;

Exposure Rates: Count rates varied from 0 cpm net to 100 cpm net.

Contamination Guidelines: Any counts exceeding 250 cpm gross required -

remediation. j Calculations: The release limit of 250 cpm gross was instituted as an administrative control that allowed efficient identification of the contaminated blocks. This limit was established by doubling the expected average background count (125 cpm), thus a release limit of 250 cpm gross  ;

was established. The efficiencies for these detectors (TBM-3S) ranged I from 20% to 27% as noted in Appendix H. As an example calculation, I I

during the survey on March 25,1988 the background count was 50 cpm. If I

a count of 250 cpm gross or 200 cpm net was found, this experimentally detennined efficiencies of 4%, and 3% would correspond to 1000 dpm/100 cm2 using the detector with the lowest efficiency (20%). Thus the 2000 dpm/100 cm2 limit is set to be conservative by a factor of two.

14 )

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AGN Water Survey:

Objectives: Determine if the AGN's shield water can be released from facility as non-contaminated.

Expected Contaminants: No contaminants are expected in the AGN's shield water.

Instrument Type: HPGe was used for a measurement of water sample from the j reactor. ,

f Instrument Calibration: The HPGe is calibrated prior to every measurement.

Instrument Procedures: Several background counts are made with the HPGe and are averaged together for a total background count as listed in Appendix G. The water sample is then counted. several times and averaged for a gross -

count.

. Survey

Description:

A water sample was collected from the AGN's water shield and placed in a special beaker for measurement.

I Primary Contaminates: An activity of .56 nCi/l was found in the sample.

Exposure Rates: The exposure rate not applicable to HPGe.

Contamination Guidelines: Release criteria for the AGN's shield water followed the guidelines as stated in 10 CFR 20 Subpart K 20.2003 Disposal j by release into sanitary sewerage, j Calculations: The background count average was subtracted from the sample  !

l count average, and then divided by an experimentally determined factor. '

\

This experimental detennined factor is 533 counts

• liters / nCi, that results in j a nCi/ liter result. j i

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Thermal Column Survey: '

Objectives: Determine if the AGN's Thermal Column had any residual contamination. l Expected Contaminants: No contaminants are expected in the AGN's Thermal Column.

Instrinnent Type: GM contamination Meter, TBM-3S was used for direct ,

metering.

Instrument Calibration: A TBM-3S's from Appendix H was used for this survey but the survey information does not exist, and we can not identify which TBM-3S was used.

Instrument Procedures: Battery checks on all the survey meter (s) used were ,

performed prior to the start of surveys. The GM contamination meters were held one inch from all surveyed surfaces.

Survey

Description:

The individuallead bricks were individually surveyed on all six faces. Then the entire interior and exterior of the Thermal Column was surveyed.

Primary Contaminates: No contaminants were found.

Exposure Rates: The exposure rate was at background.

Contamination Guidelines: Any exposure rate above background requires (

remediation. No exposure rates exceeded background.

Calculations: NA.

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The Fuel Surveys:

L. Objectives: Determine ifleakage from the AGN's fuel was a contamination concern, and to determine the decommissioning personnel's exposure risk from the fuel.

Expected Contaminants: Contaminants are expected on the AGN's fuel, cladding, and core can. This contamination results from contact with the fuel itself. The fuel was uranium oxide enriched to almost 20% impregnated in polyethylene disks. The expected contaminants are uranium 235, and fission products.

Instrument Type: Alpha Scintillation (Ludlum 43-1 # PRO 02132) for removable alpha contamination. A GM contamination Meter (TBM-3S

1. 087129) was used for direct metering. An Ion Chamber (Eberline RO-2A

1. 1263), a Micro R Meter (Ludlum model 19 #7950), and a GM Meter (Eberline E-5008 #1015) were used for exposure rates.

Instrument Calibration: The Alpha Scintillation (Ludlum 43-1 # PRO 02132) had an efficiency of 31% for alpha contamination. The GM contamination Meter (TBM-3S #087129) had an efficiency of 4% and 23% for C-14 and P-32 betas respectively. The lon Chamber (Eberline RO-2A #1263), the Micro R Meter (Ludlum model 19 #7950), and the Geiger Counter (Eberline E-5008 #1015) were calibrated with in 10% on all usable scales for exposure rates.

Instrument Procedures: Battery checks on all the survey meter (s) used were perfonned prior to the start of surveys. All survey meters were held one inch from all surveyed surfaces. All wipes counted by alpha scintillation were 100 to 300 cm2 in area.

Survey

Description:

The fuel disks were individually surveyed on both sides by direct measurement and wipes were perfonned on both sides.

Primary Contaminates: The Primary contaminants found were alpha emitters from the -

fuel itself. The contaminants were uranium 235, and fission products.

Exposure Rates: The maximum exposure rate was at 120 mR/hr from the Ra-Be sourre. The exposure rate from the fuel averaged at 16 mR/hr.

Contamination Guidelines: No remediation was performed on the fuel. The fuel was shipped to Oak Ridge for proper disposal.

Calculations: NA.

l 17

]

The Core Component Surveys:

Objectives: Detennine if leakage from the AGN's fuel on to the core components was a contamination concern, and to detennine if remediation effons on core components are successful.

Expected Contaminants: Contaminants are expected on the AGN's, cladding, and core components. This contamination results from contact from the fuel itself. The fuel was uranium oxide enriched to almost 20% impregnated in polyethylene disks. The expected contaminants are uranium 235, transuranics, and fission products.

Instrument Type: Alpha Scintillation (Ludlum 43-1 # PRO 02132) for removable alpha contamination. A GM contamination Meter (TBM-3S

1. 087129) were used for direct metering. An lon Chamber (Eberline RO-2A

1. 1263) was used for direct metering. An GM Meter with an alpha probe attachment (Xetex Model 318-A2 #11964/#021819) was used for direct intemal measumments where the Ludlum would not reach. A Gas Flow Proportional Counter (Ludlum Model 2200 #19788) was used to count mmovable contamination.

Instrument Calibration: The Alpha Scintillation (Ludlum 43-1 # PRO 02132) had an efficiency of 31% for alpha contamination. The GM contamination Meter (TBM-3S #087129) had an efficiency of 4% and 23% for C-14 and P-32 betas respectively. An Ion Chamber (Eberline RO-2A #1263) was calibrated with in 10% on all usable scales. The Gas Flow Proportional Counter (Ludlum Model 2200 #19788) had an efficiency of 35% for alpha contamination.

Instrument Procedures: Battery checks on all the survey meter (s) used were perfonned prior to the start of surveys. All survey meters were held one inch from all surveyed surfaces. All wipes counted by Alpha Scintillation and Gas Flow Proportional Counter were 100 to 300 cm2 in ama.

Survey

Description:

The core components were individually surveyed by both direct measurement and wipes. The wipes were perfomled on both the interior and exterior of the parts. Dimet metering of the interior of some parts was not possible due to the size of probes used.

Primary Contaminates: The Primary contaminants found were alpha emitters from contact with the fuel itself. The contaminants were uranium 235, and fission products.

18 j l

a l:

Exposure Rates: The exposure rate was at background.

l Contamination Guidelines: Extensive remediation was performed on the core '

. components to remove the contamination. The level of contamination was  !

reduced to near background, < 20 dpm/100 cm 2 . All parts from the core j

were disposed of as radioactive waste when it was decided that the reactor -

would be disposed of rather than transferred to a new facility.

' Calculations: NA. i t

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Facility Survey For Continued Decommissioning Activities:

l Oh,icctives: Determine radiological contaminates that might effect defueling surveys.

l Expected Contaminants: No contaminants are expected on the exterior of the reactor.

Inside the core can some fuel contamination is possible.

l Instrument Type: A GM contamination Meter (TBM-3S #093127) was used for direct metering. A Liquid Scintillation Counter (Beckman LS 7000

1. 7700259) was used for removable contamination survey.

Instrument Calibration: The GM meter's efficiencies were determined with C-14 and P-32 beta emitters for efficiencies of 5% and 27% respectively. The  !

l LSC is calibrated monthly and has experimentally determined efficiencies of l 4%, and 3% for C-14 and H-3 with respectively.

Instrument Procedures: Battery checks on all the survey meter (s) used were performed prior to the start of surveys. The GM contamination meter was held one inch from all surveyed surfaces. All wipes counted by the LSC were 100 to 300 cm2 ni area.

Survey

Description:

The top, sides, and control rod area of the reactor were both directly surveyed and wiped for contamination. Also the floor surrounding the reactor was directly surveyed.

Primary Contaminates: No contaminants were found.

Exposure Rates: Only background radiation levels were found.

Contamination Guidelines: Any counts exceeding background required remediation.

Calculations: NA. ,

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I-AGN Component Surveys:

Objectives: Determine if all remaining parts of the AGN have any contamination or activity that would restrict there release from the laboratory.

Expected Contaminants: No contaminants are expected due to previous remediation in the core component surveys.

Instrument Type: A GM contamination Meter (TBM-3S #087129) was used for dimet metering. A Gas Flow Proportional Counter (Ludlum Model 2200

1. 19788) was used to count for removable alpha contamination. A Liquid -

Scintillation Counter (Beckman LS 7000 #7700259) was used for beta removable contamination.

Instrument Calibration: The GM contamination Meter (TBM-3S #093127) had an efficiency of 5% and 27% for C-14 and P-32 betas respectively. The Gas Flow Proportional Counter (Ludlum Model 2200 #19788) had an efficiency of 35% for alpha contamination. The LSC is calibrated monthly and has experimentally determined er ciencies of 4%, and 3% for C-14 and H-3 with respectively.

Instrument Procedures: Battery checks on all the survey meter (s) used were performed prior to the start of surveys. All survey meters were held one inch from all suiveyed surfaces. All wipes counted by Alpha Scintillation and Gas Flow Proportional Counter were 100 to 300 cm2 in area.

Survey

Description:

The core components were individually surveyed by both direct measurement and wipes. The wipes were performed on both interior and exterior of the pans.

Primary Contaminates: No contaminants were found.

Exposure Rates: The exposure rate was at background.

Contamination Guidelines: All parts from the core were disposed of as radioactive waste when it was decided that the reactor would be disposed of rather than transferred. Any parts that could not be properly characterized due to fonn (i.e. wood, paint chips etc.) or showed any counts above background were disposed of as radioactive waste.

Calculations: NA.

Ill

The Surveys For Parts To Be Released For Unrestricted Use:

Objectives: To confirm that all remaining parts of the AGN have no contamination or activity that would restrict there release from the laboratory and be in compliance with all NRC guidelines.

Expected Contaminants: No contaminants are expected due to previous experience with the component surveys.

Instrument Type: A GM contamination Meter (TBM-3S #087129) was used for direct metering. A Gas Flow Proportional Counter (Ludlum Model 2200

1. 19788) was used to count removable alpha contamination. A Liquid Scintillation Counter (Beckman LS 7000 #7700259) was used for beta removable contamination.

Instrument Calibration: The GM contamination Meter (TBM-3S #093127) had an efficiency of 5% and 27% for C-14 and P-32 betas respectively. The Gas Flow Proportional Counter (Ludlum Model 2200 #19788) had an efficiency of 35% for alpha contamination. The LSC is calibrated monthly and has experimentally determined efficiencies of 4%, and 3% for C-14 and H-3 with respectively.

Instrument Procedures: Battery checks on all the survey meter (s) used were perfonned prior to the start of surveys. All survey meters were held one inch from all surveyed surfaces. All wipes counted by Alpha Scintillation and Gas Flow Proportional Counter were 100 to 300 cm2 n i area.

Survey

Description:

All components were individually surveyed by both direct measurement and wipes. The wipes were performed on both interior and exterior of the parts. Large parts were sectioned so that wipes did not exceed 300 cm2 limit. ,

Primary Contaminates: One section of the reactor tank showed a small amount of l contamination. This pan was completely decontaminated. No other contaminants were found.

Exposure Rates: The exposure rate was at background. ll Contamination Guidelines: Any pans that showed any counts above l background were decontaminated.

Calculations: NA.

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y s DOCUMENT REVIEW A

SUMMARY

OF THE DECOMMISSIONING PROCESS OF THE UNIVERSITY OF UTAH AGN-20lM REACTOR NO.107 (DOCKET NO. 050-072)

General Comments

1. The primary contaminants at this site and the applicable exposure rate and surface contamination guidelines are not clearly specified. Survey results should be reported in the same units as the guidelines (dpm/100 cm2) to permit guideline comparison and determination of compliance. The data provided in this report are not sufficient to demonstrate compliance with the NRC surface contamination guidelines. For example:

. A new appendix, Appendix I, will address the primary site contaminates,-

applicable exposure rates, and related surface contamination guidelines.

In general, no contamination in the unsealed parts was expected at this site. Scaled containers listing contamination had been in existence from previous administration's decommissioning activities. The seals on these items were not broken and re surveyed due to the ALARA principle.

These sealed items and their original survey readings were recorded and turned over to Radiological Health for proper characterization and disposal according to the University of Utah's Radiological Disposal Policies. In this report the results are listed as net cpm from 300 cm2 wipes using 2000 dpm/100 cm2 as a release limit. Appendix 11 and I have been updated to express contamination limits in cf.i for all wipes, and exposure rates for the final direct surveys. All results will be listed in this manner unless otherwise specified.

(a) In many cases the report states that the measurement was collected over the entire surface of an item. The NRC guidelines state that surface contamination should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object. Was the entire surface area of the item less than I square meter?

Parts smaller than I square meter will be averaged and updated in this manner.

(b) Background data should be provided. Different surfaces have different backgrounds, such as metal and concrete. Wen: these types of background differences accounted for during the f~ mal survey data calculations? It was not clear how surface activities were calculated from individual measurements.

Background results are given throughout the report. During the concrete block survey, some of the background data and results listed are unclear. These sections will be updated for more clarity.

During the course of the AGN decommissioning, the background readings varied due to a number of reasons. These fluctuations of background results will be explained in the data or section they are associated with.

n a

' 2. In general, it is the opinion of ESS AP that the documentation lacks certain information/ data that are consistent with that provided from similar facilities in which similar types of work have been performed.- A final status report should provide all the necessary information to allow the reader to evaluate the final radiological status of the items / facility in question.

Further detail should be provided for the technical reviewer to evaluate the adequacy of the final status report. This information should include:

. The final report will be updated for a clearer description of the final d!sposition of the AGN facility.

(a) General Information such as a site history and description and the objectives of the survey activities.

Appendix I will be updated with this information.

(b) Methodologies for:

(1) surface scans (2) direct measurements (3) grid block averaging .

(4) miscellaneous sample collection if applicable (drain, vents, residues)

(5) calculations of surface activity measurements and MDA determinations

. Appendix I will be updated wille this information.

(c) Instrument calibration and QC procedures (i.e. routine operational checks)/ operating parameters (including efficiencies, backgrounds, and detection capabilities).

. Instrument calibration, and efficiency information is in Appendix

11. QC procedures, detection capabilities, and operational checks and will be added to Appendix I.

(d) Procedures for evaluating results, relative to guidelines and conditions.

• Appendix I will be updated with this information.

3. Uranium is mentioned as a possible contaminant, and in some cases, only alpha measurements were performed. Measurements of beta activity levels, rather than alpha activity levels, provide a more accurate representation of uranium surface activity, due to conditions of building surfaces, (e.g., dusty, porous, or rough), which may selectively attenuate the alpha activity. Therefore, due to site conditions, it may be more appropriate to use beta activity levels for comparison with the guideline values.

• The Uranium contamination mentioned existed only in the scaled containers that were not opened. These were aluminum parts in the reactor's core can. This contamination comes from direct contact with the fuel. The sections of the final decommissionin report that refer to this type of contamination will be clarified.

4. The quality of data presentation and repon preparation is poor. Although data are provided, it is not clear as to how the data was compared to the NRC surface contamination guidelines.

c I

. Data presentation throughout this report will be presented in more detail  !

and more clearly.

5. The report presents the results, but does not provide a discussion and/or assessment of the data. ESSAP recommends that infonnation be included that discusses the final status of the decommissioned areas.

. The final report will be updated for a clearer description of the final decommissioning of the AGN facility in order to verify compliance with NRC regulations.

6. Figures, when provided, are not drawn to scale or labeled clearly. Figures should also be labeled with the direction and should have a figure title and a legend.

. Figures are copied from the AGN operator's manual. Figure titles and legends will be added for greater clarity.

7. It is not clear from the report which items or rooms / areas are to be released for unrestricted use. Will the AGN Reactor Room (Room 1205-E) be released? _ If so, were there other surveys performed on floors, walls, ceilings, and penetrations into this area?

. No rooms will be released to unrestricted use. The room (1205-E) in which the AGN was operated and decommissioned is under license to the Universities 100 kW TRIGA facility and is a restricted area. Surveys are periodically performed on the facilities walls and floors as specified by the TRIGA facilities license and technical specifications. - Prior to the decommissioning activities of the AGN reactor, a facility survey was performed to determine if there was any significant contamination or source of radiation that would interfere with the decommissioning survey of AGN parts.

8. The last page provided in the repoit had a page number of xxv. Was this intended to be in this report, and, if so, are there other pages that are missing?

No page should have existed with the page number xxv. The new report will contain all correct page numbers.

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l Snecific Comments I.211

'1. Page 1: The first paragraph states that the report is a brief summary of the decommissioning activities that complied with the NRC approved decommissioning plan.

ESSAP would like to review this plan since on Page 3, the licensee states that the plan "contains in detail the steps and procedures that were used to decommission the AGN-201M reactor." This information would be helpful in reviewing the documentation and in preparing a confirmatory / radiological smvey plan.

. A copy of this plan will be attached to the amended final decommissioning report.

Anoendix A;fiulslist and location

2. Page A3: The figure is blurry and difficult to read.

. This figure is a photocopy from the operator's manual. We will submit a better copy in the next report.

Accendix 11; Disassembly orocedures

3. Pages B2-B5: Provide an explanation as to why some of the procedure steps were not performed (marked NA).

. The AGN reactor was already partially disassembled by the previous administration's decommissioning activities. These steps were either unnecessary due to previous decommissioning activities, or unnecessary because the reactor will not be reassembled.

From NEL-103: II. 1. b. 4) Ra Be source previously removed.

II. 1. b. 7) Fuel previously removed.

II. 2. c. 2) Ra.Be source previously removed.

II. 2. c. 4) Fuel previously removed, manually lifted can.

III. 4) Plates previously removed.

III. 6) Part previously removed.

III. 7) Rods previously removed.

III,8) Rods and fuel previously removed.

III.10) Thermal column previously drained.

III.12) Ra.Be source previously removed.

III. 13, 14 ,15 ,16 ,17 ,18, 19) Fuel, rods, and source i previously removed. )

III. 23. a) Reactor will not be reassembled.

III. 24. a) Reactor will not be reassembled.

III. 25. a) Reactor will not be reassembled.

III. 26) Shield water previously drained.

III. 27, 28) Console previously removed.

4. Page B6: This page is missing.

. This page has been added to this report.

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5. Page B7: Provide an explanation as to why Fonn NEL-104 is incomplete; this fonn is the cheek-off list for the defueling procedure.-

4

. . Defueling was conducted by the previous reactor administration. The Form NEL-104 was created under this previous administration. After l conversation with personnel from this administration it was determined  ;

that the form NEL-104 was followed in detail during the defueling.

Unfortunately the completed version of this forrn can not be found. l

6. Page B8: This form should be labeled NEL-106.  !

. The report is correct. This page sh'ould be and is labeled NEL-104 not N E L-106.

7. Page B12: Is an adequate measurement sensitivity achieved for a smear by gamma ,

spectrometry?

i

. The gamma spectrometry is a high purity Ge crystal in a lead, shielded  !

environment. This is the most sensitive instrument that the nuclear engineerin<: laboratory owns with the ability to detect radioactive sources  !

of less then 0.01 nCi. Also, in conjunction with this meter a contamination survey meter (TBM-3S) was used.

8. Page B 13: The handwritten data is difficult to read.

. A cleac copy of this photo-copy will be substituted in the new report.

Anoendix FJ E;Lin m igdisoosed of n unrestricted _wnte

9. There were no survey results attached for these parts (in this section) and the copies of the l pictures (photographs) were poor. P ease desenbe in more detail. the survey procedures i used for the alpha, beta, gamma contamination surveys (See General Comment 2). l 1

. Survey results are listed in Appendix G for all non-contaminated waste that will be released. No final survey results will be added to this section until the NRC confirmation survey's results are completed. Note: The actual release of these items has not taken place, pending a confirmation survey by the NRC.

Aopendix Cn Survey results

10. Pages G3 and G4: It was stated that the exterior of the AGN reactor was surveyed "using both direct metering and swipes and have found no removable contamination." Was any l fixed contamination found? A TBM-3 was used for the surveys for beta contamination, were there any sun'eys performed for alpha contamination? It is recommended that an explanation be provided for the data.

. This survey of the AGN's exterior was performed prior to the decommissioning activities and the actual dismantling of the AGN reactor.

The purpose of this survey was to determine if contamination existed on the exterior of the AGN reactor prior to beginning the decommissioning i process. The TBM-3 detector was used to determme if any fixed l contamination existed. No fixed contamination was found. TBM-3 l l

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i detectors are capable of detecting alpha particles, although their efficiency is low. Alpha contamination'swipas were not performed during this survey. Alpha contamination is an extremely unlikely contaminant on the exterior of the reactor. Page G4 has been removed from the report its data is not relevant to the exterior surveys of the AGN reactor.

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11. Page G7: The licensee states that the first stage of the survey of the concrete block used for ,

shielding involves scanning the surface (one side) of the concrete block (presumably the o side that faced the reactor). If the block was acceptable,it was placed on a pallet with the monitored side face down. The licensee then states that the "second stage of the survey therefore involves passing the frisker over this surface of the block..." It is not clear as to .

which surface the licensee is referring.

. Attached at the beginning of these surveys are the Concrete Block Surveillance Procedures from the approved decommissioning plan.

Subsequent to these procedures are copies of the original pallet surveys.

The block was surveyed on one face and then placed face down where the top face of the block'was surveyed. Additionally, in a conversation with personnel from the previous laboratory administration it was indicated that prior to the pallet surveys, each block was individually surveyed on ,

all six faces. After the individual survey, each block was placed on the pallets for the pallet surveys. No documentation was made of the  ;

individual block surveys.

12. Page G8, third paragraph: The licensee states that " blocks exceeding a count rate of 250 cpm on any surface will be rejected as contaminated material." Background count rates ranged form 60 cpm to 150 cpm. Provide additional information for the justification of using 250 cpm as the " criterion for rejection of concrete block as contaminated material..."

and explain how this information compares to the release guidelines. Has the possibility of activauon of the concrete block and any structural reinforcement bars been considered? ,

. The release limit of 250 cpm gross was instituted as an administrative  !

control that allowed efficient identification of the contaminated blocks.

This limit was figured by doubling the expected average background count (125 cpm), thus a release limit of 250 cpm gross was established.

The efficiencies for these detectors (TBM 3S) ranged from 20% to 27% as noted in Appendix 11. As an example, during the survey on March 25, ,

1988 the background count was 50 cpm. A count of 250 cpm gross or 200 cpm net would then correspond to 1000 dpm/100 cm2 if the detector with the lowest efficiency (20%) was used. Thus the 2000 dpm/100 cm2 limit is set to be conservative by a factor of two.

In response to the second part of the question above, at the power levels produced by the AGN-20lM reactor (5 Watts, 286.55 Watt-hours) acti"ation of any part of the reactor is negligible. This is true even of parts located inside the core.

13. Page G13: Explain the meaning of a " cave" background.

A concrete block cave existed in the lab for temporary storage of activated '

items from the TRIGA Reactor. Each day before the concrete block surveys were performed the cave area was surveyed with the TBM-3S detectors for a background check. By measuring the background level of the cave, it could be determined if the cave's background would interfere r

with the concrete block surveys. Then a decision would be made as to whether the concrete block surveys could be performed or if the cave's background needed to be reduced. Annotations on the pallet survey sheets concerning the cave background were adopted as an administrative control to insure the quality of the surveys. ,

14. Page G21: It is not clear as to why maximum readings are less than the background reading in some cases. . It is also unclear as to why a background reading (with the same instrument on the same day) can vary by a factor of almost two (80 cpm to 150 cpm).

. The average background lisled is 120 cpm. In the case of these surveys, I the normal fluctuation of 140 cpm is not included in the report.  :

Therefore, the background should have read 120140 cpm and hence a needle swing from 80 cpm to 160 cpm on the detection device while counting the concrete blocks is not unreasonable.

15. Page G22: It is unclear as to which background applied to each measurement.

. Again, as in response to question 14, the average background would be  ;

120 cpm with a fluctuation of i40 cpm.

16. Pages G25 - G27: There is no data provided for the " Number Set Aside" column.

. No blocks were set aside. The blanks left should all read zero.

17. Page G26: One of the measurements exceeds twice the background level. On Page G7, the licensee states that the " criterion for the rejection of concrete block as contaminated material ......" is a measurable count rate in excess of twice the average area background count rate on the day of the measurement. It appears that this measurement exceeds the licensee's criteria. Also, is this criterion appropriate (See Specific Comment 12)?

. The rejection crueria of twice background was recommended by the University's Radiological IIcalth. These guidelines were used to establish the actual rejection count rate of 250 cpm gross. This gross count rate is based upon an expected background level of 125 cpm. The criterion for rejection is set at 250 cpm gross as detailed in the response to uestion 12. This is based on a rejection criteria of 2000 dpm/100 cm .

I8. Page G29: It is unclear as to what the data means. Please provide units and more detail on calculations and procedures (See General Comment 2).

. This page is rewritten in the report.

19. Page G32: The data should be provided. Were any alpha measurements perfonned? j i

. No alpha surveys were performed. Alpha contamination is not a probable l contaminant in the thermal column by Process Knowledge. The purpose l of this survey was to assess the radiological hazard of the AGN thermal l column to workers prior to beginning the decommissioning process. This i data no longer exists.

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20. . Page G37: It is unclear how this data can be compared to guidelines.

. These surveys were not compared to guidelines. The purpose of these surveys is to establish exposure levels for the fuel handling personnel, ,

and to determine if leakage or contamination from the fuel existed.

Results from survey data notes will be rewritten for greater clarity.

21. Pages G42 - G44: This data is confusing,i.e. are there 3 individual measurements for i removable contamination or is there only one measurement? How were 3 separate measurements (in epm) converted to one measurement (in dpm)? Explain how this data is compared to guidehnes. Exposure rates are typically measured at im above the surface and not at contact, if compared to the 5 pR/h above background criterion. ,

. These data pages have been rewritten to provide more detail in the results.

The three measurements are averaged together for a gross count. This gross count is then divided by the efficiency of the detector to determine the dpm value.

22. Page G45 - G48: The copied data are difficult to read and understand.

. A cleaner copy of this photo-copy will be substituted in the new report.

23. Page G53: Provide an explanation for the data. There are several data entries that are <

MDA; the MDA should be provided with the data.

. Any count that reads at background or less for gross counts is considered to be below minimum detectable activity (<MDA). This data will be rewritten to better present these results. l

24. Page G55: Provide an explanation as to why beta-gamma fixed measurements were not  :

performed (See General Comment 3).

• In the external surveys, a TBM-3S detector sensitive to 11, y was used to determine exposure levels for the defueling personnel in mR/hr units for i fixed contamination. Internal surveys were conducted exclusively with j wipes for removable contamination because our portable survey instruments were too large to fit in the interior of these tubes.

25. Page G68: All of the net counts for the smears are listed as zero. It appears that an i inappropriate background was used in the calculations since it is expected that there would be a normal distribution above the background, with some positive and some negative values for net counts. Perhaps the background was high and all numbers that were negative were reported as zero.

. The LSC background counts are: Ch.1 = 916 (15 cpm), Ch. 2 = 17i8 cpm (25 cpm). All counts in Ch. I were below 15 cpm, and in Ch. 2 all counts were below 25 cpm. Therefore all net counts were 0. The gross count data is listed on page G68.

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26. Page G70: Provide an explanation for the data presented on this page.

. These are the gross LSC counts for wipes taken on the floor in the room 1205-E prior to beginning the second AGN decommissioning surveys. i Refer to question 25 and to page G66 in the report for more clarity.

27. Pages G72 - G83: There is no consistency in the presentation of the data. For example, the units for the d.irect counting column are reported for each part number while the units for the alpha counts and liquid scintillation counts are reported in the column headings. It is recommended that the table should have a title and that the heading for each column of  ;

data should be provided on each page. Provide an explanation for 0/0 in the LSC colunm.

In the LSC column counts were made for two channels. Parts with no counts listed were sealed in plastic by the previous decommissioning team '

so only p, y counts by direct survey were made. The seals to these parts were not broken. These parts were disposed of through the University of +

Utah's Radiological Health Department in compliance with all state and j federal regulations. These tables have been updated for more clarity.

28. Page G75: For Part #86 the columns labeled " Alpha" and "LSC" reports for the data "see below." These data were not provided.

. The data for. these parts is located later in Appendix G. These parts are to be released as non-contaminated waste, pending the NRC's confirmation surveys. This section of the final decommissioning report will be rewritten for more clarity.

29. Page G79: For Part # 58, and for other parts on some of the following pages, provide an explanation for the data in the alpha column which is listed as 1(0). Also, on Page G82, provide an explanation for Part MM in the "LSC" column where the data is presented as 27/0.

. Any wipe that showed any counts on the alpha counter were recounted to determine if contamination or background was responsible. Both counts are provided. The result of 27 cpm is below the release criteria of 200 dpm/100 cm2 This area has since been decontaminated.

Annendix IL Survey instruments and oneration dala 1

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30. Page Hl: The efficiencies listed for H-3 (0.03) and C-14 (0.04) seem quite low. Typically for liquid scintillation counters, these efficiencies are approximately 40% and 80%,

respectively. Provide an explanation.

The efficiencies listed for the LSC are quite low. The LSC efficiencies '

for aqueous solutions are 30% for H-3 and 40% for C-14. For filter '

paper wipes the efficiencies were experimentally determined by -

Radiological Health staff to be 3% for H-3 and 4% for C-14. The filter paper tends to absorb some of the beta emissions and that results in the lower efficiencies.

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31. Page Hl: The calibration sources used to calibrate the thin-window GM probes were C-14, P-32, and Cl-36. Were these appropriate choices for the possible contaminants of concem? How were the different efficiencies applied to different areas? Was sampling and analysis performed to provide infomiation on the nature of the contaminants?

. The sources used for efficiency checks with the thin window GM probes are NBS traceable sources used by the University of Utah's Radiological Health Department. Sampling prior to defueling did not identify any. t contaminants. These sources were used in the absence of any information on what possible contaminants might exist. Using low, medium, and high energy betas gives a wide spectrum of efficiencies.  ;

32. Page H2: The Micro-R meter, mentioned in the calibration data, is typically calibrated with Cs-137. Due to the energy dependence of this instrument, the response of this instrunent to the gamma energies present should be indicated.

. This was an EPA detector and its calibration data will be added to Appendix H. The instrument was calibrated with Cs 137 to 10% on all usable scales.

33. Page H2: Provide a copy of the calibration data for the EPA calibrated detectors.

• A copy of EPA calibration data will be added to Appendix H.

Ending note: The page numbers of the revised report may not coincide with the page numbers of the previous report due to changes in format and additional information.

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