ML060580164

Annual Report: Illinois Advanced Triga Reactor

ML060580164
Person / Time
Site:	University of Illinois
Issue date:	02/06/2005
From:	Holm R, Stubbins J University of Illinois
To:	Document Control Desk, NRC/FSME
References
Download: ML060580164 (5)

Text

UNIVERSITY OF ILLINOIS AT URBANA-CHAMPAIGN College of Engineering 306 Engineering Hall, MC-266 1308 West Green Street Urbana, IL 61801 February 6, 2005 Docket No. 50-151 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555

SUBJECT:

ANNUAL REPORT: Illinois Advanced TRIGA Reactor License No. R-1 15 / Docket No. 50-151 The following is written to comply with the requirements of section 6.8.d of the Technical Specifications and the conditions of IOCFR50.59. The outline of the report follows the numbered sequence of section 6.8.d of the Technical Specifications.

I declare under penalty of perjury that the foregoing is true and correct. Executed on February 6, 2005.

Sincerely, Richard L. Hohm Reactor Administrator James F. Stubbins, Head Department of Nuclear, Plasma and Radiological Engineering c: Nuclear Reactor Committee American Nuclear Insurers File Page 1 of 5

-i ANNUAL REPORT JANUARY 1, 2005-DECEMBER 31, 2005 ILLINOIS ADVANCED TRIGA FACILITY LICENSE R-115 I.

SUMMARY

The reactor was in a shutdown SAFSTOR status for all of 2005. Monitoring of the facility is through the use of weekly, monthly and quarterly surveillance checklists performed by the Reactor Administrator. Additional surveillances are performed at other intervals where appropriate. The checklists created for SAFSTOR have proven to be more than adequate to ensure that the facility is monitored safely.

A site characterization was performed in the summer of 2005 in preparation for development of a decommissioning plan.

II. UNSCHEDULED REACTOR SHUTDOWN'S Not applicable.

1I. MAJOR PREVENTIVE AND CORRECTIVE MAINTENANCE HAVING SAFElY SIGNIFICANCE No major maintenance was performed having safety significance.

IV. CONDITIONS UNDER SECTION 50.59 OF 10CFR50 No 50.59 reviews were performed.

V. RELEASE OF RADIOACTIVE MATERIAL A. Gaseous Effluents

1) 41Ar No longer produced: reactor shutdown, defueled, and in SAFSTOR condition.

2)3H Page 2 of 5

-~A-I The estimated total release of 3H to the Reactor Building atmosphere (and consequently out the Exhaust Stack) from the evaporation of water in the Primary Tank (PT) was 15 c;_Ci. This is based on the measure of the activity of 3H in the PT multiplied by the total volume of makeup water additions since the tanks were last sampled for 3H (yearly). This is calculated as follows:

highest concentration of 3H in the PT or BST (1.0 E-5 gCi/ml) multiplied by the evaporative loss volume (1.5E 6 ml) equals 15 pCi.

The average concentration released via Ihe Exhaust Stack was 1.4 Fl' iKCi/ml calculated as follows: assume an average stack flow of 50 fpm'

• 2 fi

= 100 ft3/ min

• 2.83 E4 ml/ft3 = 2.83 E6 ml/min

• 5.256 E5 min/yr = 1.5 E'2 mi/yr. Then, 15 ttCi (estimated total release) divided by 1.5 E12 ml (the total volume released) = 1.0 E-" tCi/ml average concentration.

' Exhaust Stack Blower secured, flow reduced from 1200 fpnm to 50 fpm.

3) Summary of Gaseous Effluents Released A summary of all gaseous effluents for 2005 (Sections 1+2 above) is shown in the following table, which includes for each isotope: the total activity released; 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 pCi Ave Conc. (pCi/ml)

App. B Table 2 limit Ave. Conc. / limit 41

~

None None 2.0 E 0.000 3H 216 l.0E-"

4.0 E 0.0003 Sum of Fractions =

0.0003(< 1.0)

• Ar-41 concentration limit is specified by the Facility Technical Specifications.

B. Liquid Effluent

1) Waste Water discharged to the municipal sanitary sewer system Waste Water is collected in the Reactor Building Retention Tank. When the rank becomes full it is pumped over to a Holdup Tank. Thle water passes through a coarse and a fine filter assembly on route to the Holdup Tank where it is then sampled. 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.

There were no liquid effluent discharges in 2005 thanks to draining of the BST in 2004.

VI. ENVIRONMENTAL SURVEYS Page 3 of 5

Continuous radiation monitoring utilizing Thermoluminescent Dosimeters (TLDs) supplied by a vendor (ICN Worldwide Dosimetry Service) was conducted at the Site Boundary and in the Surrounding Environs. The Lower Limit of Detection (LLD) for these TLDs = 10 rmRem/Quarter).

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 Mechanical Equipment Room. This is also defined as the boundary between the Restricted and Unrestricted Areas. The average annual dose at this perimeter was 145 mRem with a range of 90 mRem to 413 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 2005 was 1.15 mRem for the Year. These calculations are maintained and updated in the files of the Reactor Health Physicist.

B. Surrounding Environs A background TLD was deployed -100 meters from the Reactor Building. The total annual dose recorded on this monitor was 81 mRem.

VII. PERSONNEL RADIATION EXPOSURE AND SURVEYS WITHIN THE FACILITY A. Personnel Exposure

1) Whole Body One individual was assigned dosimetry at the facility. The dosimetry was provided by ICN Worldwide Dosimetry Service, a National Voluntary Laboratory Accreditation Program (NVLAP) accredited Dosimetry Vendor.

Whole Body Exposure (mRem)

J Number of Individuals 10 to 100 I

> 100 to 250 0

I> >250 10- -

- HY--

_ Total I

0 ManRem Total: 0.047

2) Extremity Exposure One individual was assigned dosimetry at the facility.

ManRem Total: 0.067

3) Skin Dose Page 4 of 5

There were no significant deviations between the Shallow Dose and Deep Dose reported by the vendor for any personnel.

4) Internal Exposure There were no incidents or events that required investigation or assessment of internal exposure.

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

5) Visitor Exposures All recorded exposures for Visitors were 0 mRem by Electronic Pocket Dosimeter (EPD).

B. Contamination Surveys Smear surveys from various locations around the laboratory were taken on a quarterly basis. The removable contamination was determined by counting the smears on an Eberline BC-4 or RM-14/HP-210T Beta Counter, and/or a SAC-4 Scintillation Alpha Counter.

Routine surveys for Alpha Contamination were all < 100 dpm/nl00 cm2.

Routine surveys for beta contamination were all < 1000 dpm/nl00cm 2.

VIII. REACTOR COMMITTEE Dr. Barclay Jones, Professor of Nuclear Engineering continued as the chairman. The following members remained on the Committee: Mr. Daniel Hang (Professor Emeritus of Nuclear Engineering), Mr. David Scherer (Campus Radiation Safety Officer), Mr. Rich Holm (Reactor Administrator), Mr. Mark Kaczor (Reactor Health Physicist - Emeritus), and Dr. Jonathan Nadler (Adjunct Assistant Professor of Nuclear Engineering and former licensed SRO on the facility).

The committee held 2 meetings during the calendar year. Major topics reviewed were: a) Reactor and Health Physics Surveillances; b) NRC Annual Report; c) Site Characterization; d) Reports on -

Reactor Committee Audit of Operations, Annual Review of the Radiation Protection and ALARA Programs, and Operations and Health Physics Quarterly Reports.

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