ML20202F497

Annual Rept 970101-1231 Il Advance Triga

ML20202F497
Person / Time
Site:	University of Illinois
Issue date:	12/31/1997
From:	Holm R, Bradley Jones ILLINOIS, UNIV. OF, URBANA, IL
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9802190214
Download: ML20202F497 (9)

Text

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University of Illinois DeParime:1 of cotiege or Engineering  ;

'* at Urbana Champaign ""'"""'*"8

.' 214 Nuclear Engineering 217 333 2295 taboratory 217 333 2906 fax 103 south Goodwin Avenue Urbana, IL 618012984 f

Fthruary 16,1998 Docket No. 50-151 1 U.S. Nuclear Regulatory Conunisskm ATTN: Docummt Control Desk Mail Station Pl.137 Washington,DC 20$55 Ikur Sir, SUll1ECT: ANNUAL REPORT:lilinois Advancal TRIGA Reactor License No. R 115 / Docket No. 50-151 The following is writim to wmply with the mjuirunmts of w; tion 6.7 f of the Ttthnical Sptrifications amt the (4Hkhtions of 10CFR$0.59. The outline of the rtiert folkiws the numluni mjumee of wetion 6.7.f of the Ttthnical Srwilications.

Sincerely,

1. Kidiartl L. Ilolm Reactor Administrator s

WWWlbo " A'W llarflay O. Jhs, i [/

Dtpartmmt of car Enghuwing c: Regional Administrator, Region 111. USNRC Nuclear Reactor Conmiittec Annrican Nuchar Insurtes

- File

/GlD ,

Page 1 of 9 9902190214 971231 POR -ADOCK 05000 1 R- p l

STATE OFILLINOIS COUNTY OF CilAMPAIGN

Richard L.11olm, being first duly sworn or, oath, deposes and says that he has affixed his signature to the letter above in his official capacity as Reactor Supervisor, University ofIllinois Nuclear Reactor Laboratory; that in accordance with the provisions of Part 50, Chapter 1 Title .

10 of the Code of Federal Regulations, he is attaching this affidavit; that the f acts set forth in the within letter are true to his best information and belief, Richard L. llolm f ~

Reactor Administrator

=. Subscribed and sworn to before me, a Notary Public, in and for the County of Champaign, State ofIllinois, this ld. day of #d <A . A.D.,1998.

G W2th f ,Aru f /-/4 .Asso Ndtary'Public ofIllincfl- My Commission Expires OFFICIAL' 8EAl.

KATHl.EEN M. DYSART NOTARY PUsLIC, STAtt 0F ILLsOs WY CoMWasCN_ EXPIRES s 19 2000.

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E h ANNUAL REPORT l JANUARY 1,1997 DECEMBER 31,1997 i ILLINOIS ADVANCEDTRIGA  ;

, FACILTTY LICENSE R il5 i

I

1. suestsARY OF OPERATING EXPERIENCE

]  ; A - Summary of Usage _ >

During 1996 the reactor was operated an averaDe of 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per week. Operstbne consisted l of normalirradiations and training

~

CATEGOlR PERCENT OF_ OPERATION -

Research Projects 12.6%

trrediations 50.0 %

Education & Trairdrg 25.8% e Maintenance & Measurements 11.6%

Presently there are two individuals with a Senior Operator License. The facility operates with a ,

40 tour week schedule, a staff of 3.0 full 16me equivalent individuals of which one is a full time '

reactor health physicist.

B. Performance characteristics .

1. Fuel Element length and Diameter Measurements ,

These checks were made on the B and C rings during the month of January. The pulse 3 number at the time of the checks was 11,397. For the eighteen elements in these rings, there was an average increase in the length of about 18.5 mile over the original installed i

measurements. The accuracy of a given measurement is estimated at +5 _

mile. There was no measurable change in the diamotor of the fuel elements checked.

There were 39 pulses in 1997, bringing the total since 1909 to 11,436. For a standard $3.00 pulse, the values for pulse height, reactor potiod and fuel temperature were consistent with  !

those measured in previous years.

2. Readivity Corarol Rods: The measured readivity values hwe not changed significantly due to fusi

!- Insertions and movements. The rotative worth of each rod has maintained approximately the same as previous values.

L Core Readivity: The not loss of reactivity attributed to fuel bumup during the year was $0.25.

This value was determined by a comparison of the cold critical xenon-f;ee control rod position at the beginning and at the end of the year and correcting for core reactivity gained by the Page 3 of 9

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- 1 addnion and movemord of fuel during the year. A certain inaccuracy is inserted here in that -i the rod verth calibratbne are perbrmed in April and October. As the period since the ,

calibration has been perbnned lengthens, the inaccuracy obvbusly increases,

11. TABULATl0N OF ENERGY AND PULSING A. Hours Crtical*. Energy. Pulsing

Hours Crkical = 375 4

Energy (MW hrs) = 216

1. of Pulses = 39

• Because of the type of operstbn, the Hours Crtical time includes the time during continuous pulsed operation between pulses when the roedor is not critical in the normal sense.

I Ill. REACTOR SCRAMS There were 337 unplanned scrams and no emergency shutdowns durity this time period. These scrams were attributed to instrument Malfunctbn (131), Operator / Operator Trainee Enor (1) and Extemal Causes (5). This is down a bit from 1996 due to less frequent operation of the reactor.

The majority of these scrams are due to probiome with the General Atomico digital control '

console.

Insenanent hianunctioni131)

NPP 1000 Percent Power (3]1_ This is a power level scram required by Technical Specifications.

It occurs when the signal exceeds about 108% of rated power. This scram occuned due to noise spikes.

CSC/DAC Watchdog scram (125) : This scram is required by the Technical Speed 6 cations.

These scrams occuned due to the Control System Console screen locking up and thus causing the watchdog circuit to time out and initiate a scram. The initiation of this scram has various -

manifestations with little pattom to assist troubleshooting. Various methods have been tried to reduce the frequency of these scrams with little success.

Database Time-out (3): This scram is not required by Technical Specifications. This scram occurs if for some reason the CSC computer cannot talk to ks database. This scram usually occurs in conjunction with a CSC/DAC watchdog scram.

External Causee (6)

Electrical Noise (3): Two (2) high tank level scrams and one (1) low tank level scram occuned due to a noise problem in the relay circuit. Subsequent cleaning and replacement of a relay seems to have resolved this problem.

Loss of Electrical Power (2);Two (2) scrams occurred due to loss of electrical power to the console.

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. _ Operator Error L1)

Primary Flow Scram {1);One (1) scram was caused by ne orimary flow prior to attempting to take reactor power greater than 1.0 MW. The operator was conducting a laboratory exercise in natural circulation that requires the reactor to be taken close to 1 MW and had a power spike due to rod movement that caused power to momentarity exceed 1 MW and hence cause a scram. .

IV. MAINTENANCE lt is estimated that about 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> were spent on maintenance related activities. These hours ,

account for time spent carrying out repairs and scheduled surveillance activities. The signifcant items of maintenance are given below.  ;

NM 1000 Troubleshooting: The NM-1000 has a considerable amount of noise in the output that varlous methods have been tried to correct with little success.

Console Lockup Troubleshootino: The control console locks up with great regularity causing reactor scrams. Troubleshooting continues in this area but is hobbled by the design of the system and availability of support.

Fast Transient Rod Failure; In December of 1996 the Fast Transient Rod failed due to a breakage of the connecting lod that passes through the dashpot assembly. Upon removal of the rod it was also found to have a wear spot on the upper section of the borated graphite portion of the rod that had wom through the cladding. This necessitated construction of a new control rod.

Construction of the new tod and testing necessitated a shutdown for the month of January.

V. CONDITIONS UNDER SECTION 50.59 OF 10CFR50 in 1997 three analysis were perfomed under the auspices of a 50.59 review.

Utilization of a relay on_the_ output of the NM 1000 for the 1 kW interiock This interlock was installed to bypass the CSC software when it was determined that the interiock did not perform as expected under all possible conditions.

Replacement of the NP 1000 and NPP 1000 hardwired bargraph displays The NP/NPP 1000 bargraph displays are to be replaced with identical bargraphs with the exception that the new displays will also have a numeric display.

Replacement of the Fast Transient Rod lower section - (see maintenance section above) A new Fast Transient Rod was constructed to replace the damaged one.

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VI. RELEASE OF RADIOACTIVE MATERIAL A. Gasoous Effluents

1) car

& The average concentration released via the Exhaust Stack was 4.0 E.8pCL/mt.

b. The total activity reloased was 1,705 mCl or 1.7 Cl.

c. The range of monthly activity rcleased was 9 to 407 mCl.

2) 4.j The estimated release of "H (Tritium) to the Reactor Building atmosphere (and consequently out the Exhaust Stack) from the evaporation of water in the TRIGA and Bulk Shloiding Facility (BSF)

Tanks was $24 pCl. This was based on the measuro of the activhy of $H in the TRIGA tank (BSF makeup water is supplied from the TRIGA tank) multiplied by the total volume of makebp water additions since the tanks were last sampled (yearly) and was calculated as follows: concentration of the TRIGA tank (2.0 E4pCl/ml) multiplied by the evaporative loss volume (2.62 E' ml) equals

$24 pCl. The Average Concentration released via the Exhaust Stack is calculated as follows:

assume an average stack flow of 1200 fpm

• 2 ft' = 2400 ft'/ min

• 2.83 E* ml/ft' = 0.792 E' ml/ min

• 5.250 E' min /yr = 3.57 E" milyr. Then, 524 pCl estimated release divided by 3.57 E" ml

= 1.47 E*" pCi/ml Average Concentration.

3) Summary of Gasoous Effluents Released A Summary of all gaseous effluents for 1997 (Sections 1+2 above)is shown in the following table, which includes for each isotope; the total activity releasod, the average concentration, the 10 CFR 20, Appendix B, Table 2 limit, and the fraction of the limit released. The sum of the fractions for all isotopes released is listed at the end of the table.

Isotope Total Cl Ave Conc. (pCl/ml) App. B Table 2 limit Ave. Conc. Ilimit

Ar 1.7 4.6 E4 2.0 E4

• 0.023

• H 2.30 E'* 1.47 E " 4.0 E4 0.368 E

• Sumai 0.023 < 1.0

• Ar-41 Concentration Limit is specified by the facility Technical Specificatkms.

B. Liquid l Effluent

1) Wasto Water discharged to the municipal sanitary sewer system Wasto Water is collected in the Reactor Building Retention Tank. When the Tank becomes full it is pumped over to a Holdup Tank. The water passes through a coarse and a fine filter assembly on route to the Holdup Tank where it is then samplod The water is discharged from the Holdup Tank into the municipal sanitary sewer system when the soluble activity results are satisfactory and it is verified that no insoluble activity is present, if insoluble activity is detected before the discharge then the contents of the Holdup Tank can be recirculated through a 0.4 micron process filter until the insoluble activity has been removed and it is verified that no insoluble activity is present.

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. The Average Concentration of all soluble beta-gamma activity roleased in 1997 was 7.6 E4 p CVml. This is well below the 10 CFR 20, App. B, Table 3, ' Releases to Sewers' limit of 9.0 E* p CVml for the rnost restrictive isotope not known to be absent. *Cs. The Average Concentration

• H released concurrently with the ateve was 7.4 E4pCvrnt. This is well below the 10 CFR 20

' release to sewer

• limit of 1.0 E4 pCVml for 'H.

Vll. ENVIRONMENTAL SURVEYS Continuous Radiation Monitoring utilizing Thermoluminescent Dosimeters (TLDs) supplied by a vendor (Landauat, Inc.) was conducted at the Site Boundary and in the surrcunding Environs. -

A. Site Boundary The site boundary is established at the Reactor Building Walls with extensions at the fence around the Cooling Towers and the perimeter of the roof over the Mechanica Equipment Room.

This is also defined as the boundary between the Restricted and Unrestricted Areas. The average annual dose at this perimeter was 101 mrem with a range of 10 trRem to 320 mrem.

However, pursuant to 10 CFR 20.1302 (b)(1) an Annual Site Boundary Dose Calculation for Members of the Public, based on Occupancy Time, was performed. The highest calculated dose at the site boundary for 1997 was 0.9 mrem for the Year. These calculations are maintained and updated in the files of the Reactor Health Physicist.

B. Surrounding Environs The Environs and University Owned Buildings in near proximity to the Reactor Building were monitored. The average done recorded was 22 mrem with many locations equal to or less than the Lower Limit of Detection (LLD = 10 mrem / Quarter). The highest location reading for 1997 was 80 mRom for the year.

Vill. PERSONNEL RADIATION EXPOSURE AND SURVEYS WITHIN THE FACILITY A. Personnel Exposure 1)Whole Body A total of 7 individuals who were assigned Film Badges at the facility received a neasurable Whole Body exposure (LLD = 10 mrem / month). There were 4 full time empbyees working 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week, and 2 students working 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> / week. All others averaged less than 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> / week in the facility. The badoas are read by Landauer, Inc.! a National Voluntary Laboratory Accreditation Pmgram (NVLAP) accredited Dosimetry Vendor. The tables and explanations below outline the Whole Body Dose received by all 7 individuals who received a measurable exposure.

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Whole Body Exposure (mRom) Number of indiviouais .

. 10 to' 100 6

> 100 to 250 1 i

> 250 0 Total 7  :

i ManRom Total: 0.300 Averene: 56 mRom  ;

i Summary: The highest irufivklual Nie Body Exposures was 140 mRom. This exposure was received by the Reactor Health Phyoloist. All of this exposure was recolved as a result of handling: radioisotopes and preparing them for shipment, redweste, and/or experimental devices. ,

2) Extremity Exposure  !

1' A total of 8 inc.lviduals who were assigrwd Finger Rings at the facility rooelved a measurable Extremily Exposure rLLD = 10 mRom/ month).

ManRom Total: 27.830 HosJth Physicist: 26.440 A, vorage of othws : 0.326 i Summary: In July 1997 the Roador Health Physicist received a relatively high Extremity  :

Exposure (25.5 Rom; The accompanying his Scdy dose received during the same evolution was 24 mRom (DDE) Nthough the Extremity Exposure was higher than ant 6cipated for the evolution perbrmed a significant dose was expected. No regulatory or administrative levels were  ;

exceeded, and the cause of the exposure is fairty well understood. Details of the ALARA review are available and on file but too lengthy to be included with this annual summary.

3) Skin Dose There were no sigrncant deviations between the Shallow Dose and Deep Dose reported by the l vendor for any personnel, j 4)intomal Exposure  ;

There were no incidents or events that required investigation or assessment of intomal exposure.

Contamination levels are acceptably low and areas few(see B. below). There were no evolutions perbrmed or events that occurred which caused, or could have caused, the presence of Airbome Radioactivity,  ;

5) Visitor Exposures [

All recorded exposures for Visitors were o mRom by Elodronic Pocket Dosimeter (EPD).

B. Contamination Surveys

' Smear surveys from various locations around the laboratory were taken Routinely; weekly, monthly, and quarterty as appropriate to the crea of concem; and Specifically; to assess experimental devices, tools and equipment, potentially contamirated areas, or to evaluate Page 8 of 9 F

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adverso trends. The terrovablo contaminatien was determined by counting the smoais on an

. Eberline BC-4 Beta Countor, RM 14/HP 210T, and/or a SAC 4 Scintillation Alpha Counter. ,

The maximum gross Bota/ Gamma Contamination was usuall/ found in the two posted contamination areas where irradiated sample containers are handled. T here were ((XXXXD samplos irtadiated and handlod during tho year. In the samplo unloading bin (1.6 ft') the average tomovable activity was 23K dpm/100 cm' with a high of 148K dpm/100 cm'. This area was immodlatory decontaminated when iomovablo activity exceeded 100K dpm/100 cm'. In the sample preparation area (5 ft') the average removable activity was 4,900 dpm/100 cm' with a high of 57K dpm/100 cm'. The balance of the posted contamination area, the reactor bridge (11.5 ft ). had average tomovable activity of 34b dpmf100 cm'. Smears from other areas of the 5

laboratory, within the restricted aree, were less than 870 dpm/100 cm'. In the Control Room and other clean areas, outside the iestricted area, the maximum detectable contamination was loss than or equal to a Minimum Detoctable Activity (MDA)of 89 dpm/100 cm'.

Routino surveys for Alpha Contamination were allloss than or equal to a MDA of 14 dpnV100 cm' Total contaminated surface area = 18 ft2 IX. NUCLEAR REACTOR COMMITTEE Dr. David Millor (Illinois Power Company and Adjunct Assistant Professor of Nuclear Engineering) continuod as Chairman of the Nucioar Reactor Comrnittee for the 19971998 Academic Yost.

The following members remained on the Committee: Mr. Daniel Hang (Professor Emeritus of Nuclear Engineering), Dr. Bront Hous n (Assistant Professor of Nuclear Engincoring). Dr. Erik Wiener (/asistant Professor of Nuclear Engineering), Mr. David Schoror (Carnpus Radiation Safety Officer). Mr. Rich Holm (Reactor Administrator), and Mr. Mark Kaczor (Roactor Health Physicist and ex officio member). Dr. De Wu(Nuclear Engineering Visiting Resident Scientist)left the University and resigned from the committee.

The committee held 0 mootings during the calendar year. Major top;cs reviewed weh duactor Operations, Surveillancos, and Hoalth Physics Procedures and Activities; NRC Annual Report, inspection Report, and a Notice of Violation; Bionnial Reviolon of the Emergency Plan and implementing Procedures: 50.59 Reviews for .1) Utillzation of a relay on the output of the NM-1000 to perform the function of the 1 kW Interlock for transient rod firing that bypasses the CSC software, and 2) Replaconwnt of the NP 1000 and NPP 1000 hardwired bargraph displays on the reactor control consolo; Safety Evaluations and Amendments for egeriments, such as, "Mo Production Project. and Study of Mouse Erpholeukomla Cells; Reports on Reactor Committee Audit of Operations, Poor Review Audit of Operations, Operations Quartecty Reports, Annual Review of the Radiation Protection and ALARA Programs, the Emergency Plan Drill Critique, a Temporary Deviation from Normal Operating Procedures with regard to ti e NM 1000. Decreased Primary System Suction Pressure Troubleshooting C* "telines, and Untir oly Expiraton of an SRO license.

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