ML20006E824

Annual Operating Rept for 1989. W/900214 Ltr

ML20006E824
Person / Time
Site:	05000072
Issue date:	12/31/1989
From:	Gehmlich D, Sandquist G UTAH, UNIV. OF, SALT LAKE CITY, UT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9002260393
Download: ML20006E824 (9)

Text

l,9 2 , . ,

THE UNIVERSITY c .

orUTAH i

IL L.

r-t February 14,1990 Document Contml Center U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir / Madam:

- Enclosed you will find a copy of the Annual Operating Re xnt for the University of Utah AGN i 210M Reactor, License R 25, Docket 50 77, for theyerioc January 1,= 1989 through December  !

31,1989. This report fulfills AGN Technical Specification 6.9.1; j If you have any questions concerning the report please contact the staff at the facility.

]

J Sincerely,

,() Y(k ik Dietrich K. Gehmlich ReactorAdministrator 1:

2 P

i Department of Mechanical and Industs'al 1:ngineering

!, MEll 3209 Satt Lake City, Utah Mil 2 /

(M01) 581 G141 1et I -

1.

E, . v  !

j %'.

t, j

1 Annual Operstm' g Report for 1989  :

AGN 201M Reactor No.107 1 University of Utah  !

IJicense R-25 j Docket #5072 i A. FacilityModifarians: '

The AGN reactor has been defueled as permitted by the operatin g license in I neparation for final darammissioning activities. The fuelis being storec in approved  !

ocked fuel sm p pits pending return to DOE (fuel owner) and subacquent transfer to the Y-12 scrap p ant in Oak Ridge, Tennessee. The radium- 'um neutron source was removed from the reactor and transferred to the Unive

• of Utah Radiological  !

L Health Department for disposal. Fusther decommissioning vities will be deferred until the final Decommissioning Plan has been approved by the Res: tor Safety Com-  :

mittee (RSC) and submitted to NRC. A summary of the darammissioning activities completed to date has been presented in a memorandum to the RSC which is included j in the Appendix.

B. Results of Tests and Inspections:

Surveillance of the reactor has continued despite decommissioni activities.

Inspections included monthly visual inspections and monitoring of radia on 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 smce February,1985, and since we are presently preparing to decommission the reactor, none of the operational surveillance activities enuiwd in AGN Technical L Specifications Section 4 are required as provided in Section 4.0. However, i surveillance for retention of radioactive matena s is being performed.

Detailed surveys of reactor csrp.cr.ts during darammissioning activities required to I permit core defueling have demonstrated no activated materials or leakage of fission j' 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.

1' l C. CorrectiveMaintenance:

L l None L D. Energy Produced:

Since February 1985 - none E. Unscheduled Shutdowns:

None i 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.

,.,<i..

i

' University of Utah AGN 201M Reactor

? i 1989 AnnualOperating Rgxirt l

page 2 2.The RSC has reviewed and approved the fallowing preliminary plans and ,

procedures for decommissioning the AGN reactor:  ;

(a) radiation survey procedure for reactor sig.ts j (b) radiation survey record forms  !

(c) detailed reactor diammannbly procedure (d) dismantling and disposalplan o (c) thermal column remcwal procedure l (f) Ra Be neutron source removal pacedure, and l l (g) reactorcare removalprocedure l

1

l. 3. The RSC is cunently comprised of the following members: 1 Dietrich K. Geh nlich - Reactor Administrator .!

Gary M. Sandquist - Director, UUNEL and AGN Reactor Supervisor

, Keith J. Schlager - Radiation Safety Officer b Kevan C. Crawford b

James M. Byrne  !

Vern C. Rogers j John S. Bennion t-  !

G. Summary of Changes Reportable under 10 CFR 50.59:

L The Emergency Plan and Physical (Facility) Security Plan for the AGN reactor which 1 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 1 reviewed and audited in view of the University's intention to umsiidssion the AGN. l

' 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 i reactor and it being stored in approved locked fuel storage pits pending transfer to l DOE. Periodic inventory and surveillance of the fuel is being performed.

H. ReportableOccurrences:

None j' Report submitted by: 1

/ /

.d qu' r du isor

)

l 0 I

1 I

l i

.c,,...-. .

t. ,,- 3 Ushersley of Utah AON 201M Reactor i 1989 AnnualOperating Report page 3 ,

I 1

1 1

1 i

l I

i 4

Appendix A:  ;

RSC Memorandum: Summary of AGN Reactor Decommissioning Activities ..

?

i 1

l I

1 I

\

1 i

i

)

e i.

1 J

1 I

l I

I e

i

..f i

i l '

1 4

1

, i a

m __ .-__.__.-.-m___._.__________.____.__-._.___m- -

- - - w .-. -, -- +-- er -v *'

fI

,:. u. .+ . .

t h

MEMORANDUM j To: Reacta Safety Co nmittee (RSC) q Prom- JohnBennion M -

Date: September 27, 11 9 I

Report of AGN Reactor Du-- - Moning Activities p

Subject:

i The following summarizes AGN d~ammissioning activities completed to date, those in progress, and those that will be accomplished in the future. De RSC hu previously approved several l1 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 recorded. i 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 surveyco 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 ,

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 sheeting on the reactor room floor. At this time wipes were taken from the underside of the thermal column and the interior cavity of the AGN structure immaAiately 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 e poxy 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 i scraped off and placed in a ziy-lock ba,g for further analysis. Analysis of the wipes showed no indication of fission products, Fuel, cr ot ser 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 inserted into the core through the guide tubes of the rods and locked in place to l ensure that ko rt we.s less than 0.8 as required by AGN Technical Specifications. The fueled - -

3 l portions of the rods were detached from the drive assemblies and scaled in plastic after wiping the exterior surfaces. No evidence of fission products or other radioactive leaca ge or contammation ,

. was observed. The fueled rods were then secured in the Middle Fuel Storage Pit. De control and r safety rod drives were su:veyed 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 l paraffin lined shipping container. This task was accomplished under the supervision of Gary Sandquist, AGN Reactor Supervisor, and Bob Hoffman, alternate Radiation Safety Officer. nc

,c Reecear Sasty f%==isse Memoranden Report of AON Reactor E--:-:=='"'; Aedvides

A September 27,1989 page 2 source was stored on the lower floor of the reactor room behind the 1RIGA teactor tank. A cave made from concrete block surrounding the source container was constructed to reduce exposuit from the source until transfer from UUNEL occurred. The source was leak tested by the Radiological Health Department on August 23,1989; no eviis.cc ofleakage was observed. De source was transferred to Radiological Hcalth and removed from UUNEL on August 31,1989 for final 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 alow the pressure in the core tank and the '

c mamber to oc uilibrate. The gas sample was counted using the Nal(11) detector; no detectable activity was o > served. A gamma spectrum of the sample using the intrinsic gerinanium detector showed no evidence of any fission products. Defueling occurred on August 18,1989, under the -

direction of Dr. Sandquist. De core tank can was hoisted out of the reactor structure and pNod 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 operated throuJhout the procedure to collect airbome particulates for analysis of radioactivity. De hermetical y-scaled core can was opened and its contents were carefully removed, surveyed, and inventoried. De fuel discs were placed into two storage containers (one half of the core in each) with blocks of borated parafrm 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 cwp,cnts for both fixed and removable alpha activity as well as beta and gamma activity and the decontamination of contaminated components is still in progress. All fuel has been surveyed, weighed, and sealed in plastic and is being stored in the Fuel Stora ge Pit pending the return of the fuel to its owner, U.S. DOE. A letter requesting assistance in the retum of the fuel has been sent to the DOE Idaho Operations Offlee. 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 final version of the Decommissioning Plan to the Nuclear Regulatory Commission. Other important tasks remaining to be completed are:

1. Sample, analyze, v i drain the water shield,

2. Complete transfet W fuel to Oak Ridge,

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

4. Submit Request for License Termination to NRC.

d me  %

, , y -

1 1 I

1 i

i i

29 August 1989

~

Mr. Keith R. Brown U.S. Department of Energy Idaho Operations Office j c/o EO&G Idaho i

P.O. Box 1625 i IdahoFalls,ID 83415

{

Dear Keith:

1 As you know, the University of Utah is in the process of d~=missioning its AGN 201 M  !

Nuclear Reactor, License R 25. The purpose of this letter is to req uest assistance from the U.S. I DOE Idaho Operations Office in the return of DOE owned fuel from W reactor core and rernovalof that fuel from the reactor site. It is our usderstanding that DOE will provide the shi pping container l for transport of the fuel to Oak Ridge, Tennessee for final disposition and will provide some I 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 fuel follows.

The AGN reactor, Serial No.107, was a uired from Aerojet General Nucleonics in September, 1957 through a grant from the Atomic rgy Commission. De reactor was operated from j January,1958 through February,1985 primarily in conjunedon with a nuclear reactor laboratory course offered once each year for traimng reactor operators and conducting basic experiments in reactor physics. In November,1961, a construccon 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.- De facility opeinting license was amended in January, I 1962 authorizing operation of the reactor at its new site. Following the assembly of a 24 inch thick l shield from concrete block around the reactor in 1969, another heense amendment was granted 1 1

which authorized operation of AGN at power levels up to 5 watts, up from the original license limit -

L of 100 milliwatts. '!he AGN has not been operated since 19 February 1985 but has been maintained in standby status pending decommissioning. A uring the twenty seven years of j operation, less than one kilowatt hour of thermal energy was generated. Defueling of the reactor i core occurred on 18 August IW/. At that time, all fuel discs were surveyed for contamination, placed in containers and secured in a fuel stcrage pit with fuel discs which had been remoW carlier  :

from the control and safety rods. I l-De AGN core consists of nine homogeneously dispersed polyethylene / uranium dioxide fuel discs,  !

twelve polyethyleneNO2fuel discs from the control and safety rods, and one polystyreneNO2C0!c fuse. The fuel is enriched to twenty percent with a total uranium-235 content of approximately 663  ;

,4 grams. In addition to fuel fmm the reactos core, a fission plate, which has not been arradiated and is L

stillin its original shi L 31 grams of U 235. pping All fuel container, is owned by was E. a uired At this time, with the original the University AGN of Utah fuel and co Nuclear L

Engmeering Laboratory would like to retain possession of both the fission plate and the core fuse L for possible use in future experiments. A summary description of the fuel is attached and includes a I

+

r

g. s . , j

~ ,

Keith R. Brown 29 August 1989 N2 i l

l 1

+

1 o

description of each piece of fuel, its identificatloc number, approximate mass, and nom:od U.235 content. 1 p 1 The information contained in this letter is not intended to be exhaustive, since it serves merely to initiate the process by which the AGN fuel is retumed to DOE. Catainly, further information will

!' he required and questions will need to be answered before fue! transfer may take place. Therefore, please contact us at your earliest convenience with additional instructions to expedite these L proceedings. A detailed bud pared and submitted when additionalmformationis recei gtWe ofappreciate fuel transfer costs will be yourefforts and

[ in this matter.

1 Sincerely yours,

[ i f hW

/ ..

i V

4 L

r w

M O~ -

Sm.n v g r.n.,.t. Nu == u d.1 r, 'A(1N De h. ifrf. I Lu= R-is .

i. , -

Rancant Care FuelDiscs .

Rigin<arcular cyhnder 25.6an chameter of various th Fabricated hem 20% annched 00 2Powder and ]

- polyethylent-Fuel Specirgetions:

UO2 Pd U 235 enrichment .19.510.5%

Particle size.15i10 pm Polyethylene powdw Parucle siae.100pm Purity. commercial i

i

__ldentificadonNo. Thicimee Dise M=== Nnminal U-235 Maec i e 1. 20481 1cm 652 g 29 g t l

2. 20470 1cm 657g 29 g  ;

3. 20478 2cm 1267 g 58 g i

4. 20473 2cm 1269g 58 g

5. 20469 2cm 1273 g 58 g  ;

i-

6. 20442 4cm 2051 g 96 g  ;

7. 20476 4cm 2065 g 96 g '

8, 20474 4cm 2157 g 96 , i

9. 20475 4cm 2164 g %g Safety and Contml Rod Fuel Discs Right-circular cylinder 4.7<m diameter,4 cm h!gh. Fabricated from 20% enriched UO2 Powder and polyethene.

Fuel Specifications: Same as above Identification No.- Dine Mane Nnminal U 235 Mass

1. 20386 79 g 3.6g'

2. 20395 79 g 3.6g

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. l 20394 79 g 3.6g~

8. 20390 79 g 3.6 g

9. 20388 79 g - 3.6 g .

10. 20392 79 g 3.6 g

11. 20396- 79 g 3.6g i

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 UO 2 powder -

and polystyrene.

Identification No. Fuse Mass Nominal U-235 Mass  ;

- 1. 20110 6.8g 0.40 g i Fission Plate Aluminum clad fission plate. Fuelis 20% enriched UO2 with polyethylene.

Identification No. _Platehiass Nominal U-235 Mcss

1. none 2506 g 30.75 g L

}

?. - . - . ._. -. .