ML20011F493

Forwards Annual Operating Rept for 1989.

ML20011F493
Person / Time
Site:	05000072
Issue date:	02/14/1990
From:	Gehmlich D UTAH, UNIV. OF, SALT LAKE CITY, UT
To:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NUDOCS 9003060123
Download: ML20011F493 (1)

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February 14,1990 Robert D. Martin, Administrator

. U.S. Nuclear Regulatory Commission Refon IV 61:. Ryan Plaza Drive, Suite 1000 -

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Dear Mr. Martin:

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L Enclosed you will find a copy of the Annual Operating Re for the University of Utah AGN

. 20lM Reactor, License R-25 Docket 50-72, for the ; January 1,1989 through December -

31,1989. 'Ihis report fulfills AGN Technical Specification 6.9.1. .

. If you have any questions conceming the report please contact the staff at the facility. H l

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1 L Sincerely. .-

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LA Dietrich K. Gehmlich '

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g-Annual Operating Report for 1989 i AGN 20lM Reactor No.107 University of Utah -

License R 25 Docket #50 72 A. FacilityModifications:

t The AGN reactor has been defueled as permitted by the operating license in mpamtion for final decommissioning activities. The fuel is being stored in approved

.ocked fuel storage pits pending return to DOE (fuel owner) and subsequent transfer to .

the Y-12 scrap plant in Oak Ridge, Tennessee. The radium-berylhum neutron source was removed from the reactor and transferred to the University of Utah Radiological Health Department for disposal. Further decommissioning activities will be deferred until the final Decommissioning Plan has been approved by the Reactor Safety Com-mittee (RSC) and submitted to NRC. A summary of the decommissioning activities completed to date has been presented in a memorandum to the RSC which is included in the Appendix.

B. Results of Tests and Inspections:

Surveillance of the reactor has continued despite decommissioning- activities.

Inspections included monthly visual inspections and monitoring of radiation levels in the vicinity of the reactor and the periodic sampling and analysis of shielding water to determine the presence of any radioactive materials above background. These in-spections showed no evidence of water leakage, excessive corrosion, release of fission products,or unusual radiation levels. Because the AGN reactor has not been operated since February,1985, and since we are presently preparing to decommission the reactor, none of the operational smveillance activities enumerated in AGN Technical Specifications Section 4 are required as provided in Section 4.0. However, surveillance for retention of radioactive materials is being performed.-

Detailed surveys of reactor components during decommissioning activities required to permit core defueling have demonstrated no activated materials or leakage of fission products. With the exception of a few internal surfaces of the core in direct contact with fuel material, no evidence of contamination has been observed.

C. CorrectiveMaintenance:

None D. Energy Produced:

Since February 1985 - none E. Unscheduled Shutdowns:

None F. Reactor Safety Committee Action:

1. Personnel radiation exposures and radiation surveys were reviewed and approved.

All exposures and surveys have been within nominal background levels.

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_ o- . Univenity of Utah AGN 20lM Reactor

.' 1989 Annual Operating Report

page 2

2. The RSC has reviewed and approved the following preliminary plans and pmcedures for decommissioning the AGN mactor:

(a) radiation survey procedure for reactor components (b) radiation survey record forms l- (c) detailed reactor disassembly procedure (d) dismantling and disposal plan L

L- g (c) thermal column removal procedure -

(f) Ra Be neutmn source removal procedure, and -

- (g) reactorcore removal procedure

3. The RSC is currently comprised of the following members:

Dietrich K. Gehmlich - Reactor Administrator Gary M. Sandquist - Director, UUNEL and AGN Reactor Supervisor '

' Keith J. Schlager - Radiation Safety Officer Kevan C. Crawford L James M. Byrne ,

Vern C. Rogers John S. Bennion G. Summary of Changes Reportable under 10 CFR 50.59

The Emergency Plan and Physical (Facility) Security Plan for the AGN reactor which L is incorporated in the general plans for both the AGN (R-25) and the TRIGA (R-126) reactors have been reviewed, audited, and modified by the RSC to permit the timely decommissioning of the AGN reactor. The Techmcal Specifications have been reviewed and audited in view of the University's intention to decommission the AGN.

As provided by AGN Technical Specification 4.0, certain surveillance activities have been discontinued since the reactor is not operational. Fuel has been removed from the reactor and is being stored in approved locked fuel storage pits pending transfer to -

DOE. Periodic inventory and surveillance of the fuel is being performed.

H. Reportable Occurmnces:

-None Report submitted by:

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University of Utah AGN 201M Reactor i;E * ' -

1989 Antiual Operating Report

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Appendix A:

RSC Memorandum: Summary of AGN Reactor Decommissioning Activities ,

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MEMORANDUM To: Reactor Safety Co nmittee (RSC) l-From: John Bennion /6 Date: September 27, 89

Subject:

Report of AGN Reactor Decommissioning Activities The following summarizes AGN decommissioning activities completed to date, those in progress, and those that will be accomplished in the future. The RSC has previously approved several .

documents pertaining to this effort including the detailed disassembly procedure, procedure for the removal of the Ra-Be neutron source, the defueling procedure (both control and safety rods and the reactor core), as well as the radiation survey procedure and the forms on which those surveys are L recorded.

The first major decommissioning project involved the surveillance and disposal of the concrete shielding block originally surrounding the AGN reactor. More than 2700 blocks were carefully surveyed for contamination or radioactivity in excess of background levels and loaded onto pallets for transfer from UUNEL. On March 25,1988, nearly six months after the project was started, all blocks designated for disposal had been surveyed and transferred to a contractor for ultimate disposition following a independent final survey conducted by the Radiological Health Department.

None of the blocks was found to be contaminated or exhibit activity in excess of background.

In April,1989, water from the thermal column was sampled for radioactivity content. Analysis l showed no detectable concentrations of any radionuclides (except for naturally-occurring K-40).

Approximately 254 liters of this water was siphoned to the sanitary sewer for disposal. The '

thermal column was then removed from the reactor structure using the overhead crane and placed on plastic shecting on the reactor room floor. At this time wipes were taken from the underside of i the thermal column and the interior cavity of the AGN structure immediately above the core tank can. Borated paraffin was placed over the Ra-Be neutron source upon lifting the thermal column to reduced the neutron dose to personnel. The lead brick layer at the bottom of the thermal column was removed. Each brick was surveyed for radioactivity, but no contaminated brick was found.

The remaining water in the thermal column was filtered, analyzed, and discharged to the sewer.

The epoxy lining of the column began to blister and peel as soon as the top of the AGN was unsealed. Upon removal of the lead brick and water from the column, the remaining epoxy was

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scraped off and placed in a zip-lock bag for further analysis. Analysis of the wipes showed no indication of fission products, fuel, or other radioisotopes. In addition, no activity was detected in the epoxylining.

The control and safety rods were removed from the reactor on May 2,1989. A total of 35 grams of cadmium was insened into the core through the guide tubes of the rods and locked in place to ensure that km was less than 0.8 as required by AGN Technical Specifications. The fueled i portions of the rods were detached from the drive assemblies and sealed in plastic after wiping the

exterior surfaces. No evidence of fission products or other radioactive leakage or contamination was observed. The fueled rods were then secured in the Middle Fuel Storage Pit. The control and safety rod drives were surveyed and found to be free of contamination.

On May 5,1989, the 10 mci Ra-Be neutron source was removed from the reactor and placed in a paraffin-lined shipping container. This task was accomplished under the supervision of Gary Sandquist, AGN Reactor Supervisor, and Bob Hoffraan, alternate Radiation Safety Officer. The l

f Reactor Saety Committee Memorandum Repan of AGN Reactor D-mdssioning Activities

.. Septersber 27; 1989.

page 2 -

source was stored on the lower floor of the reactor room behind the TRIGA reactor tank. A cave '

made from concrete block surrounding the source container was constructed to reduce exposure from the source until transfer from UUNEL occurred. The source was leak tested by the Radiological Health Department on August 23,1989; no evidence ofleakage was observed. The source was transferred to Radiological Health and removed from UUNEL on August 31,1989 for -

fmal disposition.

A core gas sample was obtained in preparation of defueling the reactor by connecting the core tank spigot to an evacuated chamber and opening the spigot to a. low the pressure in the core tank and the chamber to ec uilibrate. The gas sample was counted using the Nal(TI) detector; no detectable activity was o sserved. A gamma spectrum of the sample using the intrinsic r,crmanium detector showed no evidence of any fission products. Defueling occurred on August 18,1989, under the

. direction of Dr. Sandquist. 'Ihe core tank can was hoisted out of the reactor structure and placed on  ;

plastic sheeting spread over the floor of the reactor room to contain a possible release of radioactive -

material. Strict procedures were followed to minimize any contamination of the area or personnel.

In addition, a high-volume air sampler was opemted throughout the procedure to collect airborne particulates for analysis of radioactivity. The hermetically sealed core can was opened and its I

contents were carefully removed, surveyed, and inventoried. The fuel discs were placed into two i storage containers (one half of the core in each) with blocks of borated paraffin to reduce further the reactivity of the fuel. The containers were then secured in the Fuel Storage Pit. Subsequent detailed surveys of each piece of fuel and all core components for both fixed and removable alpha activity as well as beta and gamma activity and the decont~nination of contaminated components is ,

still in progress. All fuel has been surveyed, weighed, e. ' tealed in plastic and is being stored in.

the Fuel Storage Pit pending the return of the fuel to its . ner, U.S. DOE A letter requesting assistance in the return of the fuel has been sent to the doc Idaho Operations Office. We are presently waiting for instructions for transfer of the fuel to the repository at Oak Ridge, Tennessee.

The next major task to be completed is the submittal of the fm' al version of the Decommissioning  ;

Plan to the Nuclear Regulatory Commission. Other important tasks remaining to be completed are:  ;

1. Sample, analyze, and drain the water shield,

2. Complete transfer of fuel to Oak Ridge,

3. Complete and document all surveillances of AGN reactor components and structures and decontaminate contaminated components as necessary,' and

4. Submit Request for License Termination to NRC.

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29 August 1989 Mr. Keith R. Brown U.S. Depanment of Energy Idaho Operations Office c/o EG&G Idaho P.O. Box 1625 Idaho Falls,ID 83415

Dear Keith:

As you know, the University of Utah is in the process of decommissioning its AGN 201 M Nuclear Reactor, License R-25. The purpose of this letter is to request assistance from the U.S.

DOE Idaho Operations Office in the return of DOE owned fuel from the reactor core and removal of that fuel from the reactor site. It is our understanding that DOE will provide the shipping container for transport of the fuel to Oak Ridge, Tennessee for final disposition and will provide some financial assistance to aid in this endeavor. The University, of course, will ensure compliance with

' all state, local, and federal regulations and will be res;x>nsible for the actual transfer of the fuel. A brief history of the reactor and a description of the fue l follows.

The AGN reactor, Serial No.107, was acquired from Aerojet General Nucleonics in September, 1957 through a grant from the Atomic Energy Commission. The reactor was operated from January,1958 through February,1985 primarily in conjunction with a nuclear reactor laboratory course offered once each year for training reactor operators and conducting basic experiments in reactor physics. In November,1961, a construction permit was issued which authorized the relocation of the reactor from its original site in the Fuels Technology Building to the newly constructed Merrill Engineering Building. The facility operating license was amended in January, 1962 authorizing operation of the reactor at its new site. Following the assembly of a 24-inch-thick shield from concrete block around the reactor in 1969, another license amendment was granted which authorized operation of AGN at power levels up to 5 watts, up from the original license limit of 100 milliwatts. The AGN has not been operated since 19 February 1985 but has been maintained in standby status pending decommissioning. During the twenty-seven years of operation,less than one kilowatt hour of thermal energy was generated. Defueling of the reactor core occurred on 18 August 1989. At that time, all fuel discs were surveyed for contamination, placed in containers and secured in a fuel storage pit with fuel discs which had been removed earlier from the control and safety rods.

The AGN core consists of nine homogeneously-dispersed polyethylene /uraniurn dioxide fuel discs, twelve polyethylene /UO2 fuel discs from the control and safety rods, and one polystyrene /UO2core

{ fuse. The fuel is enriched to twenty percent with a total uranium-235 content of approximately 663 grams. In addition to fuel from the reactor core, a fission plate, which has not been inadiated and is still in its original shipping container, was acquired with the original AGN fuel and contains nearly 31 grams of U 235. All fuel is owned by DOE. At this time, the University of Utah Nuclear Engineering Laboratory would like to retam possession of both the fission plate and the core fuse for possible use in future experiments. A summary description of the fuel is attached and includes a

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.. 'o c Keith R. Brown 29 August 1,989 -

page 2 description of each piece of fuel, its identification numeer, approximate mass, and nominal U 235 content.

'Ihe information contained in this letter h not intended to be exhaustive, since it serves merely to .

initiate the process by which the AGN fuel 12 returned to DOE.' Certainly, further information will be required and questions will need to be answc-d before fuel transfer may take place. Therefore, please contact us at your earliest convenience wSh additional instructions to expedite these

. proceedings, . A detailed budget of fuel transfer costs veill be prepared and submitted when

. additional mformation is received. We appreciate your efforts and a:sistance in this matter.

Sincerely yours.,

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-[& Summarv of Snecial Nuciaar Mnemial imm AGN Danctor Serial No: 107. Limnne R-25

• . Reacto Core Fuel Disen _

Right<ircular cylinder 25.6<m diameter of various thicknesses. Fabricated imm 20% enriched UO2Powder and

- polyethylene.

Fuel Specifications:

UO2 Powder.

. U 235 enrichment - 19.510.5%

Particle size- 15110 pm Polyethylene powder Particle size 100 pm Purity commercial Identification Noc . Thickness Dise Mass Nominal U-235 Mass

1. 20481. Icm 652 g 29 g

2. 20470 1cm 657 g 29 g

3. -20478 2cm 1267 g 58 g

4. 20473 2cm 1269 g 58 g

5. 20469 2cm 1273 g 58 g

6. 20442 4cm 2051 g 96 g

7. 20476 4cm 2M5g 96 g

8. 20474 4cm 2157 g 96 g

9. 20475 4cm 2164 g 96 g Safety and Control Rod Fuel Discs Right-circular cylinder 4.7 cm diameter,4-cm high. Fabricated from 20% enriched UO2 powder and polyethene.

Fuel Specifications: Same as above Identification No. Dise Mass Nominal U-235 Mass

1. -20386 79 g 3.6 g

2. 20395 79 g 3.6 g

3. 20391 79 g 3.6 g

4. 20387 79 g 3.6 g

5. 20393 79 g 3.6 g

-6. 20389 79 g 3.6 g 7, 20394 79 g 3.6 g

8. 20390 79 g 3.6 g

9. 20388 79 g 3.6 g

10. 20392 79 g 3.6g

11. 20396 79 g 3.6 g

12. - 20385 79 g 3.6 g Core Fuse Small, right circular cylinder,2.2 cm diameter,0.9-cm high. Fabricated from 20% enriched UO2 Powder and polystyrene.

Identification No. Fuse Mass Nominal U-235 Mass

1. 20110 6.8 g 0.40 g Fission Plate Aluminum clad fission plate. Fuel is 20% enriched UO2 with polyethylene.

Identification No. Plate Mass Nominal U-235 Mass

1. none 2506 g 30.75 g

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