ML12055A397

Annual Report: Illinois Advanced Triga Reactor

ML12055A397
Person / Time
Site:	University of Illinois
Issue date:	02/02/2012
From:	Holm R, Stubbins J Holm, Blough & Co, University of Illinois
To:	Document Control Desk, NRC/FSME
References
Download: ML12055A397 (5)

Text

February 2, 2012 Docket No. 50-151 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk MS T-8F5 Washington, DC 20555

SUBJECT:

ANNUAL REPORT: Illinois Advanced TRIGA Reactor License No. R-115 / 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 10CFR50.59. 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 2, 2012.

Sincerely, Richard L. Holm 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

ANNUAL REPORT JANUARY 1, 2011-DECEMBER 31, 2011 ILLINOIS ADVANCED TRIGA FACILITY LICENSE R-1 15 I.

SUMMARY

The reactor was in a shutdown SAFSTOR status through September of 2011. In October of 2011 decommissioning of the facility began. Monitoring of the facility is through the use of weekly, monthly and quarterly surveillance checklists performed by the Reactor Administrator and decommissioning contractor. Additional surveillances are performed at other intervals where appropriate.

II. UNSCHEDULED REACTOR SHUTDOWNS Not applicable.

III. MAJOR PREVENTIVE AND CORRECTIVE MAINTENANCE HAVING SAFETY 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)4 1 Ar No longer produced: reactor shutdown, defueled, and in SAFSTOR condition for January -

September. Commenced decommissioning in October.

2) 3H 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 less than 25% of the allowable limit based on previous year's sampling and no further operation to generate a Page 2 of 5

source term.

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 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 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. 7 The average concentration of all soluble beta-gamma activity released in 2011 was 5.6 E8 I Ci/ml. This is well below the 10 CFR 20, App. B, Table 3, "Releases to Sewers" limit of 9.0 E-6 ýtCi/ml for the most restrictive isotope not known to be absent, 134Cs. The average concentration of 3H released concurrently with the above was 1.1 E"7 gCi/ml. This is well below the 10 CFR 20 "release to sewer" limit of 1.0 E2 jCi/ml for 3H.

VI. ENVIRONMENTAL SURVEYS 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 mRem/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 167 mRem with a range of 115 mRem to 384 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 2011 was 1.1 mRem for the Year. These calculations are maintained and updated in the files.

B. Surrounding Environs A background TLD was deployed -100 meters from the Reactor Building. The total annual dose recorded on this monitor was 112 mRem.

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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 Global Dosimetry Solutions, a National Voluntary Laboratory Accreditation Program (NVLAP) accredited Dosimetry Vendor.

Whole Body Exposure (mRem) Number of Individuals 10 to 100 1

>i00to250"' 0"

>250 0 Total 0 ManRem Total: 0.029 rem

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

ManRem Total: 0.026 rem

3) Skin Dose 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-Page 4 of 5

14/HP-210T Beta Counter, and/or a SAC-4 Scintillation Alpha Counter. Contamination surveys performed by the contractor are counted on a Ludlum model 2929 dual scaler.

2 Routine surveys for Alpha Contamination were all< 100 dpm/l100 cm2.

Routine surveys for beta contamination were all < 1000 dpmll00cm.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. William Roy (Illinois State Geological Survey). Dr. Tom Anderson, Associate Director - Occupational Safety and Health at the University Facilities and Services joined the committee in May. Mr. Mark Kaczor left the committee in May.

The committee held 6 meetings during the calendar year. Major topics reviewed were: a) Reactor and Health Physics Surveillances; b) NRC Annual Report; c) Decommissioning plan; d) Reports on - Reactor Committee Audit of Operations, Annual Review of the Radiation Protection and ALARA Programs, and Operations and Health Physics Quarterly Reports. In addition, the Committee reviewed numerous procedures associated with the decommissioning activities.

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