ML20137P443

Us Geological Survey Triga Reactor Annual Rept,1985

ML20137P443
Person / Time
Site:	U.S. Geological Survey
Issue date:	12/31/1985
From:	Rusling D INTERIOR, DEPT. OF, GEOLOGICAL SURVEY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NUDOCS 8602050106
Download: ML20137P443 (8)

Text

- -

4 U.S. GEOLOGICAL SURVEY TRIGA REACTOR ANNUAL REPORT JANUARY 1,1985 - DECEMER 31, 1985 NRC LICENSE H0. R-113 - DOCKET NO. 50-274 I. Administrative Changes No administrative changes.

II. Operating Experience The prime function of the Geological Survey TRIGA Reactor (GSTR) for the year 1985 continued to be the provision of neutrons for the various research programs being conducted by the U.S. Geological Survey. Irradiations were also performed for other Government agencies and educational institutions.

A listing of irradiations performed during the year 1985 is given below:

Organization Samp1es (1985)

Geologic Division (Denver) 9055 Geologic Division (Reston) 1882 Geologic Division (Menlo Park) 137

University of Georgia 28 Rensselear Polytechnic Institute 22 Brigham Young University 6 Colorado College 26 University of Utah 1 Oregon State University 28

, University of Maine 6 Louisiana State University 2 University of Southern California 1 Colorado School of Mines 2 Colorado Division of Wildlife 393 Total 11,589 The operation of the reactor has been normal. The primary activities are listed below.

A. Thermal power calibrations at 50KW were performed in January, March, May, July, August, September, and Novemer.

B. Fuel element measurements were made in January.

C. The rotary specimen rack was replaced with a new unit modified to permit samples to be unloaded pnetriatically. (See Section VI) g p

8602050106 851231 PCR ADOCK 05000274 R PDR \j

D. No Class II experiments were approved during 1985.

E. During the report period, 200 daily checklists and 12 monthly checklists were completed in conpliance with Technical Specifications requirements for surveillance of the reactor facility.s F. Tours of the reactor f acility were provided to groups during the year. Some of the major groups visiting the facility were affiliated with:

Colorado School of Mines Colorado Cbilege Western State College Rennett High khool Republic of China (Uranium Research Institute)

Department of Labor Case Western Reserve University Colorado State University Highlands High School

, thiversity of Colorado Denver area High Schools (Public and Private)

Approximately 300 visitors were admitted to the facility during the year.

III. Tabulation of Energy Generated Megawatt Time Reactor Number of Pbnth Hours Was Critical Pul ses January 1985 65.706 97 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br /> 07 minutes 0 Fd)ruary 1985 58.230 69 hours7.986111e-4 days <br />0.0192 hours <br />1.140873e-4 weeks <br />2.62545e-5 months <br /> 45 minutes 0 March 1985 79.107 98 hours0.00113 days <br />0.0272 hours <br />1.62037e-4 weeks <br />3.7289e-5 months <br /> 05 minutes 0

April 1985 108 543 118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br /> 15 minutes 0 May 1985 95.569 106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br /> 32 minutes 0 June 1985 66.128 81 hours9.375e-4 days <br />0.0225 hours <br />1.339286e-4 weeks <br />3.08205e-5 months <br /> 06 minutes 0 July 1985 108.808 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> 46 minutes 0 August 1985 73 474 93 hours0.00108 days <br />0.0258 hours <br />1.537698e-4 weeks <br />3.53865e-5 months <br /> 22 minutes 0 September 1985 98.237 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> 40 minutes 0

[ October 1985 95 S46 102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br /> 23 minutes 0 November 1985 57.168 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> 08 minutes 0 Deced)er 1985 94.668 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> 21 minutes 0 1001.784 1159 hours0.0134 days <br />0.322 hours <br />0.00192 weeks <br />4.409995e-4 months <br /> 30 minutes 0

I V. thscheduled Shutdowns

1. Period Scram - while connecting-scope to console Serial #330

2. Linear Scram - noise spike Serial #331

3. Manual Scram - lost area monitor power and underpressure in reactor room Serial #332

4. Mnaual Scram - underpressure less than 0.1" water Serial #333

5. Linear S ram - physical shock to console Serial #334

6. Linear Scram - noise spike Serial #335

7. Linear Scram - noise spike Serial #336

8. Linear Scram - noise spike Serial #337 9 Linear Scram - noise spike Serial #338 10 Linear Scram - noise spike Serial #339

11. Linear Scram - while adjusting linear chamber Serial #340

12. Manual Scram " Rabbit failed to leave reactor" signal - pnematic system Serial #341

13. Linear Scram - operator error Serial #342 14 Manual Scram - lost program on CTD for pnematic

, system Serial #343 i 15 Manual ecram - lost program on CTD Serial #344

16. Manual Scram - lost program on CTO Serial #345

17. Linear Scram - noise spike Serial #346

18. Linear Scram - noise spike Serial #347 19 Linear Scram - noise spike Serial #348 20 Linear Scram - noise spike Serial 8349

21. Loss of building power Serial #350

22. Loss of building power Serial #351

23. Period Scram - noise on log channel Serial #352 24 Manual Scram " Rabbit failed to leave reactor" signal - pnematic system Serial #353 i

25. Loss of building power Serial #354

26. Linear Scram - physical shock to chanber Serial #355

27. Manual Scram " Rabbit failed to leave reactor" signal - penunatic system Serial #356

28. Manual Scram - lost program on CTD Serial #357 V. Major Maintenance Operations

1. A new motor was installed on main exhaust system in reactor room.

2. The demineralizer resing was changed once during the year.

3. In stalled new CIC in linear channel.

VI. Summary of 10 CFR 50.59 Changes The existing rotary specimen rack (lazy Susan) was replaced in Novenber.

The new unit was modified to allow the samples to be unloaded pneunatically. The new unit was designed and manufactured by GA Tech-nologies, Inc. The major modifications consist (d of 1.) adding an air supply line to the drive side of the housing, and 2.) adding a second load tube, offset three positions from the standard load tube. The seco.:d load tube was added to permit the use of the sample container that is used in our pneunatic system. The container is smaller than the conventional TRIGA tube, procedures for the removal and installation of the lazy susans were furnished by GA Technologies.

The replacement of the rack was reviewad by the Reactor Operations Committee in its meeting of February 27-28,1984 The Committee found that the operations of the modified rack will not increase the probability of occurrence or the consequences of an accident or i malfunction of equipment important to safety previously evaluated in the l Safety Malysis Report, and it will not create the possibility for an accident or malfunction of a different type than previously evaluated in the Safety Malysis Report. The margin of safety as defined in the basis for any technical specification is not reduced.

The Cbmmittee concluded the change did not involve an unreviewed safety question and would constitute a 10 CFR 50.59 change.

l l

i

a O .

VII. Radioactivity Releases A. Listed below are the total amounts of radioactive gaseous effluents released to the environs beyond the effective control of the reactor facility.

License (R-113) 10 CFR 20 Argon-41 Allowable Tritium (HTO) Allowable Month (curies) (curies) (curies) (curies)

January 1985 0.53 5 .8 12.5 x 10-5 0.25 February 1985 5 0.35 5.8 0.25 March 1985 0.68 5 .8 13.2 7 .1 xx 10 10-5 025 April 1985 0.90 5.8 14.4 x 10-5 0.25 May 1985 0.97 5 .8 21.5 x 10-5 025 June 1985 0.60 5.8 13.4 x 10-5 0.25 July 1965 0.95 5 .8 19.2 x 10-5 0.25 August 1985 5 1.06 5.8 0.25 Septenber 1985 0.93 5 .8 11.6 x 10 5 0.25 October 1985 1.32 5.8 7.3 x 10 5 0.25 Novenber 1985 1.34 5 .8 8.1 9.3 xx 10 10-5 0.25 Decenber 1985 1.30 5.8 14.7 x 10-5 0.25 Total 10.93 70.0 1.52 x 10-3 3.00

% of allowable 22.4% 0.05%

(Note #1: The argon activities reported are integrated values obtained from the facility's gaseous stack monitor. Calculated values have been substituted for measured values in the few instances when the monitoring system was down for maintenance or repair) .

(Note #2: The trititsn concentrations are estimates based on the amount of water lost by evaporation from the reactor times the concentration of tritium a s HT0) .

8. No radioactive liquid effluents were released from the reactor facility during the year 1985.

C. No radioactive waste was shipped for burial during 1985.

The total amount of radioactive waste released from the reactor facility

! during 1985 is estimated to be approximately 11.0 mci.

( Not e: The principal radioactive waste generated at the reactor facility is the demineralizer resin - used resin with small quantities of rinse water is solidified with Portland cement prior to release in 55-gallon drtsns) .

I l

l

{

VIII. Radiation Monitoring A. Our program to monitor and control radiation exposures included the four major elements below during the operating year 1985.

1. Eighteen area monitors (17 gammas,1 neutron) located throughout the Nuclear Science Building. To provide a background signal, a small check source is attached to the scintillation detector. High alarm set points range from 2 mr/hr to 50 mr/hr. High level alarms have been infrequent and are documented in appropriate Log Rooks.

2. One Continuous Air Monitor (CAM) sampling the air in the reactor b ay . An equilib riun concentration of 3.0 x 10-8 present for two minutes will result in an increase of 500 cpm above background.

There are two alarm set points. A low-level alarm is set at 3,000 cpm, and the high level alarm is set at 10,000 cpm.

Reactor bay air is sampled during all reactor operations. The fixed particulate air filter is changed and counted daily on a Gamma Products Ga020 Low Level counting system. The charcoal filter, fitted behind the air filter, is changed and counted weekly . In all instances, final sample calculations show less than MPC (10 CFR Part 20, Appendix B, Table II) concentrations for all isotopes in question in the reactor bay.

3. Contamination wipe surveys and radiation surveys with portable survey instranents are performed at least once each month. All portable instroments are calibrated with a certified 3-curie Cs-137 source and wipes are counted on a Gamma Products G4020 Low Level counting system.

Wipe surveys have shown the reactor area remains free of tactile contamination except for intermittent low level activity on work table tops and the sample storage caves. Instrument surveys indicate no fixed areas of contamination and radiation leaking at outside wall surfaces have been less than 0.5 mr/hr at our maximum power level. The maximum count for a wipe (beta +

gamma /100 cd) was 1130 pCi on a storage cave. No alpha contamination was detected.

4 Personnel, X and gamma, beta and neutron film badges are assigned to all permanent occupants of the Nuclear Science Building.

CaSO 4 :Dy dosimeters have been used at four outdoor environmental stations. Reactor facility visitors are issued L 49 self-reading dosimeters.

These monitoring results are categorized below:

Rem - 1985 Gamma Reta Neut ron Reactor Staff I Whole Body Cumulative Dose for Calendar Year Highest 0.030 0.000 0.000 Hands Cumulative 00se for Calendar Year Highest 1.360 0.000 0 .000 Reactor Experimenters Whole Body Cumulative Dose for Calendar Year Highest 0.000 0.000 0.000 Hands Cumulative Dose for Calendar Year Highest 0.060 0.000 0.000 Reactor Visitors All readings were less than 1.0 mrem.

Fnvironmental Stations Rem 1985 Exhaust Stack 0.0930 l

West 0.0014 Southwest 0.0000 i Sou theast 0.0000 IX. Environmental Monitoring Pursuant to reactor operating procedures, soil and water sa@les are collected every second year. No samples were collected in 1985.

i i

a G' 4.','>s, ,

.-l'

'F-M 151 United States Department of the Interior GFOI.OGKL\l. SU RVEY 424 H O X 3 046 M .S -

' DENVER FEDERAL CENTER

" DENVER, COI.ORADO 80225 l\ Rt P1i ktlies Ifa Janaary 24, 1986' License No. R-113 Docket No. 50-274

, Administrator Region IV U..S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 The enclosed annual report of the U. S. Geological Survey TRIGA reactor, including a description of 50.59 changes, is submitted in accordance with 10 CFR 50.59(b). l f Sincerely, 44 o

' DONALD RUSLING Reactor Supervisor Enclosure 1

i 4

l l

I

@o