ML050670389
| ML050670389 | |
| Person / Time | |
|---|---|
| Site: | University of Illinois |
| Issue date: | 02/23/2005 |
| From: | Holm R, Stubbins J University of Illinois |
| To: | Document Control Desk, NRC/FSME |
| References | |
| Download: ML050670389 (6) | |
Text
Nuclear Reactor Laboratory University of Illinois at Urbana-Champaign Department of Nuclear, Radiological and Plasma Engineering / College of Engineering 214 Nuclear Engineering Laboratory 217-333-775510866 103 South Goodwin Avenue 217-333-2906 fax Urbana, IL 61801-2984 r-holm@uluc.edu ReactorAdminbitrator: Richard L. Holm February 23, 2005 Docket No. 50-151 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555
Dear Sir,
SUBJECT:
ANNUAL REPORT: Illinois Advanced TRIGA Reactor License No. R-I 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 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 23, 2005.
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 4000 f
ANNUAL REPORT JANUARY 1, 2004-DECEMBER 31, 2004 ILLINOIS ADVANCED TRIGA FACILITY LICENSE R-1 15 I.
SUMMARY
The reactor was in a shutdown SAFSTOR status for all of 2004. Monitoring of the facility is through the use of weekly, monthly and quarterly surveillance checklists performed by the Reactor Administrator and Reactor Health Physicist. 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.
During 2004 there were two individuals with a Senior Reactor Operator License, one of which is the reactor health physicist.
In August of 2004 the fuel at the facility was shipped to Idaho and Texas. Subsequent license and technical specification changes have eliminated the need for licensed individuals at the facility. The position of Reactor Health Physicist has also been eliminated.
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 One 50.59 review was performed in 2004 titled "Fuel Follower Control Rod IOCFR50.59 Facility Modification Safety Evaluation".
Description:
In order to ship the Fuel Follower ControlRods (FFCRs) to Idaho they must be cut to shorten them. The rods are approximatelysixty (60) inches long andmust be less thanforty-eight (48) inches to go in the shipping basket and be received in Idaho. The FFCRswill be movedfrom the main TRIGA pool using the transfer cask to a temporarypool on the west bayfloor to be cut. The elements will then be cut using a tool supplied by NAC, Intl. andplaced in a shipping can.
V. RELEASE OF RADIOACTIVE MATERIAL Page 2 of 6
A. Gaseous Effluents No longer produced: reactor shutdown, defueled, and in SAFSTOR condition.
- 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) and the Bulk Shielding Tank (BST) was 216 uCi. This is based on the measure of the activity of 3H in the PT or BST (whichever had the highest concentration of 3H), 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 pCi/ml) multiplied by the evaporative loss volume (2.16 E ml) equals 216 pCi.
The average concentration released via the Exhaust Stack was 1.4 E'0 UCi/ml calculated as follows: assume an average stack flow of 50 fpm'
- 2 ft2 = 100 fW 3/ min
- 2.83 E4 mI/fL3 = 2.83 E6 ml/min
- 5.256 E5 min/yr = 1.5 E12 ml/yr. Then, 216 pCi (estimated total release) divided by 1.5 E'2 ml (the total volume released) = 1.4 E-10 pCi/ml average concentration.
l Exhaust Stack Blower secured, flow reduced from 1200 fpm to 50 fpm.
- 3) Summar of Gaseous Effluents Released A summary of all gaseous effluents for 2004 (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/mil) App. B Table 2 limit Ave. Conc. / limit
_41_AX l None None 2.0 E-6
- 0.000 3H 216 1.4 E-'0 4.0 E8- 0.004 Sum of Fractions = 0.004 (< 1.0)
- Ar-41 concentration limit is specified by the Facility Technical Specifications.
B. Liquid Effluent I) 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 Page 3 of 6
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.
The average concentration of all soluble beta-gamma activity released in 2004 was 6.6 E-8 i Ci/mI. This is well below the 10 CFR 20, App. B, Table 3, "Releases to Sewers" limit of 9.0 E6 pCi/ml for the most restrictive isotope not known to be absent, 13 4 Cs. The average concentration of 3H released concurrently with the above was 1.2 E-5 iCi/ml. This is well below the 10 CFR 20 "release to sewer" limit of 1.0 E2 pCi/mI 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 122 mnRem with a range of 95 mRem to 231 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 2004 was 0.64 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 76 mRem.
VII. PERSONNEL RADIATION EXPOSURE AND SURVEYS WITHIN THE FACILITY A. Personnel Exposure
- 1) Whole Body Two part-time employees (SROs) who were assigned dosimetry at the facility. The dosimetry was provided by ICN Worldwide Dosimetry Service, a National Voluntary Laboratory Accreditation Program (NVLAP) accredited Dosirnetry Vendor.
Whole Body Exposure (mRem) l Number of Individuals 10 to 100 2 Page 4 of 6
> 100 to 250 0
> 250 0 Total 0 ManRem Total: 0.065
- 2) Extremity Exposure Two part-time employees (SROs) were assigned dosimetry at the facility.
ManRem Total: 0.164
- 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 With the exception of the fuel shipment period, all recorded exposures for Visitors were 0 mRem by Electronic Pocket Dosimeter (EPD). During the fuel shipment period the highest EPD reading was 14 mrem. This was received by a contractor also being monitor by a film badge.
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/l 00 cm2.
Routine surveys for beta contamination were all < 1000 dpm/I 00cm2.
VIII. REACTOR COMMITTEE Dr. David Miller (Illinois Power Company and Adjunct Assistant Professor of Nuclear Engineering) resigned as Chairman of the Nuclear Reactor Committee. Dr. Brent Heuser also resigned from the committee. Dr. Barclay Jones, Professor of Nuclear Engineering joined the committee as the new Page 5 of 6
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), and Dr. Jonathan Nadler (Adjunct Assistant Professor of Nuclear Engineering and former licensed SRO on the facility).
The committee held 3 meetings during the calendar year. Major topics reviewed were: a) Reactor Operations and Health Physics Surveillances; b) NRC Annual Report; c)Fuel shipping preparations and procedures; d) Post 9/11 Security; e) 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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