ML050960498
| ML050960498 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 03/31/2005 |
| From: | Vasbinder D University of Buffalo |
| To: | Document Control Desk, NRC/FSME |
| References | |
| Download: ML050960498 (12) | |
Text
University at Buffalo The State University of New York Occupational and Enviromental Safety Services March 31, 2005 Docket 50-57 License R-77 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington D.C. 20555
Dear Sir or Madam:
Enclosed please find two copies of the 2004 Annual Facility Technical Report for the Buffalo Materials Research Center at the State University of New York at Buffalo. This report is submitted pursuant to Facility Technical Specification Requirement 15.1.
If you have any questions or wish further information, please contact me at (716) 829-3301.
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David R. Vasbinder Director, Buffalo Materials Research Center Cc: Daniel Hughes, Project Manager USNRC Steve Holmes, USNRC Inspector Region 1 Joseph Raab, Kevin Thompson, Mike Dupre, Jeff Slawson, Mark Adams, Harry Miller, Director Environment, Health, and Safety Chairman Reactor Decommissioning Safety Committee Associate Vice President for University Facilities Radiation Safety Officer Reactor Engineer Operations Manager OCRs Buffalo Materials Research Center 2004 A&VRepenr Ave., Buffalo, NY 14215-1034 Tel: (716) 829-3301 Fax: (716) 829-2704 Page I
TIjA University at Buffalo The State University of New York Occupational and Enviromental Safety Services ANNUAL TECHNICAL REPORT STATE UNIVERSITY OF NEW YORK AT BUFFALO BUFFALO MATERIALS RESEARCH CENTER License R-77 Docket 50-57 Calendar Year 2004 Submitted by:
David R. Vasbinder Director March31, 2005 Buffalo Materials Research Center 2004 AAMA2aporr Ave., Buffalo, NY 14215-1034 Tel: (716) 829-3301 Fax: (716) 829-2704 Page 2
TABLE OF CONTENTS Pag
- 1. Introduction.............................................................................................
4
- 2. Major Maintenance...................................................... 4
- 3. 10 CFR 50.59 Reviews or Changes......................................... 4
- 4. Radioactive Effluents...................................
.. 4
- 5. Environmental Radiation Surveys.......................................
5
- 6. Radiation Exposures.....................................................
5
- 7. Radiation and Contamination Surveys..................................
6
- 8. Miscellaneous............................................ 0.
6 Table 2 - Waste Tank Release to Sanitary Sewer............................ 8 Table 2 - Waste Tank Release to Sanitary Sewer...................
.................. 9 Table 3 - Waste Tank Release to Sanitary Sewer...................
....... 10 Table 4 - 2004 Cumulative Summary of Environmental Radiation Dose Equivalent
................................................ 11 Table 5 - 2004 Whole Body Dose Equivalent Summary..................... 12 Table 6 - 2004 Extremity Dose Equivalent Summary................................... 12 Buffalo Materials Research Center 2004 Annual Report Page 3
- 1. INTRODUCTION This report is submitted to the United States Nuclear Regulatory Commission (NRC) pursuant to section 15.1 of Appendix A, of the Technical Specifications (License R-77) for the Buffalo Materials Research Center (BMRC) located at the State University of New York at Buffalo. It summarizes changes to the facility, major maintenance activities, surveillance tests and inspections, radiation surveys, and radioactive effluents for the 2004 calendar year. The facility remained in Possession Only License status throughout the year. All required surveillance was completed.
- 2. MAJOR MAINTENANCE Many routine maintenance activities were undertaken in the B.M.R.C. However, there were no maintenance activities undertaken in 2004 that would qualify as major maintenance.
- 3. 10CFR 50.59 CHANGES There were no 50.59 reviews performed during the 2004 calendar year.
- 4. RADIOACTIVE EFFLUENTS 4.1 Controlled Discharges to the Sanitary Sewer There were three controlled discharges to the sanitary sewer system in 2004. The total volume of water released was 89,200 liters, containing a total of approximately 0.043 millicuries of radioactivity. All three releases were made from the 10,000 gallon above ground waste storage tank (referred to as 10K Tank). Tables 1, 2, and 3 contain the discharge information specific to the releases including comparisons to the monthly average concentration in 10 CFR Part 20, Appendix B, Table 3 "Releases to Sewers" and the sum of the fractions.
4.2 Airborne Releases No airborne radioactive releases, other than natural background resulting from radon and its daughter products, were made during 2004. The sensitivities of the air effluent monitors (based on the injection of a known quantity of Kr-85 gas) were not performed.
A sensitivity (pCilcc/cpm) of the building air system will be conducted prior to moving reactor fuel.
Buffalo Materials Research Center 2004 Annual Report Page 4
- 5. ENVIRONMENTAL RADIOLOGICAL SURVEYS 5.1 Routine Surveys The direct radiation levels outside the BMRC reactor building are routinely monitored adjacent to the "truck door" access area and on the roof of the liquid waste holding tank vault.
Global Dosimetry Solutions dosimeters are used to monitor integrated radiation levels in seven exterior areas around the facility. These dosimeters are replaced with a new badge every month and the previous month's sent to the dosimetry vendor for processing. The vendor is NVLAP certified. The minimum photon sensitivity for the dosimeter is 5 mrem. Table 4 lists the cumulative summary of the environmental radiation dose equivalent around the facility. The maximum cumulative annual deep dose equivalent reading was 16 mrem on the dosimeter (# 2116) located on the roof of the vault containing the above ground waste holding tank.
Semi-annual "tell-tale" samples are drawn and analyzed from the sampling well tubes adjacent to the underground liquid waste holding tanks (Tank #1). These analyses detected no radioactivity in excess of background levels.
- 6. RADIATION EXPOSURES 6.1 External Dosimetry Dosimetry records were maintained for a total of eight staff members and other authorized facility entrants. Film dosimeters provide X, beta, and gamma exposure monitoring. Thermoluminescent dosimeter (TLD) rings are used to measure extremity dose for selected personnel. Also, a TLD for neutron detection is available when necessary. All dosimeters are processed by Global Dosimetry Solutions, a NVLAP certified vendor. These dosimeters are replaced on a bimonthly basis.
The film dosimeters have a minimum sensitivity of 10 mrem for both beta and photon radiation. A separate neutron sensitive dosimeter (with a minimum sensitivity of 20 mrem per monitoring period) is available and is worn by personnel during manipulations involving the reactor fuel or plutonium - beryllium (PuBe) sources.
Buffalo Materials Research Center 2004 Annual Report Page 5
During 2004 no monitored individual received a measurable whole body deep dose equivalent. The maximum extremity shallow dose equivalent to an individual was 0.105 rem. This individual received measurable extremity dose performing fuel pre-shipment activities.
University Police Department officers perform routine security tours of the building. The patrol officers wear a University Police dosimeter pack when they perform these walkthroughs. These dosimeters did not record any dose equivalent during 2004.
Four visitor dosimeter packs are also available. These dosimeters are issued to visitors who may need to enter into areas requiring exposure monitoring. None of these visitor dosimeters recorded any measurable dose equivalent in 2004.
Tables 5 and 6 provide summaries of personnel whole body and extremity dose for calendar year 2004.
- 7. RADIATION AND CONTAMINATION SURVEYS 7.1 Exit Monitoring Exit monitoring is required as part of each egress from the reactor containment building and other radioactive materials areas within the BMRC. These surveys occasionally detect radioactive contamination, allowing rapid correction of contamination problems.
7.2 Routine Surveys The BMRC staff performs monthly radiation and contamination surveys of the BMRC building. BMRC contamination action levels are 30 dpm/100 cm2 beta for personal items, 200 dpm/l00 cm2 beta, otherwise. In calendar year 2005, no contamination was detected in excess of action levels by these surveys on items, surfaces, or areas not labeled or restricted as contaminated.
- 8. MISCELLANEOUS
- The Reactor Decommissioning Safety Committee convened three times during calendar year 2004. This meets the annual requirement in Facility Technical Specifications for a minimum of two committee meetings.
Buffalo Materials Research Center 2004 Annual Report Page 6
- As per periodic requirement, the average annual flow rate through the sanitary sewer system from the facility was measured via flow measurements and the updated dilution factor applied.
Buffalo Materials Research Center 2004 Annual Report Page 7
University at Buffalo Buffalo Materials Research Center Table 1 -- Waste Tank Release to Sanitary Sewer Release Number:
From:
Month:
2004-01 10K Tank February Amount Released:
Date of Release:
7850 gal.
2.98E+07 ml 2/17/04 Monthly Percent Nuclide Tank Limit Release of Monthly (ACi/ml)
(AiCi/ml)
(gCi/nmi)
Limit Co-60 2.39E-07 3E-05 1.2E-08 4.1E-02 Ag-108m 2.29E-07 9E-05 1.2E-08 1.3E-02 Sr-90 2.17E-07 5E-06 1.1E-08 2.2E-01 Y-90 2.17E-07 7E-05 1.E-08 1.6E-02 Unidentified 2.36E-10 2E-08 9.5E-13 4.8E-03 Beta TOTAL 9.02E-07 giCi/ml Total of Limit Released:
Total of Activity Released:
Year to Date Activity Released 0.29 %
26.91 gCi 26.91 tiCi Buffalo Materials Research Center 2004 Annual Report Page 8
University at Buffalo Buffalo Materials Research Center Table 2 -- Waste Tank Release to Sanitary Sewer Release Number:
From:
Month:
2004-02 10K Tank -
May Amount Released:
Date of Release:
7800 gal.
2.96E+07 ml 5/28/04 Monthly Percent Nuclide Tank Limit Release of Monthly (Ci/ml)
(AlCi/ml)
(iRCi/ml)
Limit Co-60 6.65E-08 3E-05 3.4E-09 1.LE-02 Sr-90 5.66E-08 5E-06 2.9E-09 5.8E-02 Y-90 5.66E-08 7E-05 2.9E-09 4.1E-03 Unidentified 8.98E-08 2E-08 4.6E-09 2.3E+01 Beta TOTAL 2.7E-7 o
tCi/ml Total of Limit Released:
Total of Activity Released:
Year to Date Activity Released 23.11 %
7.99 pCi 34.90 gCi Buffalo Materials Research Center 2004 Annual Report Page 9
University at Buffalo Buffalo Materials Research Center Table 3 -- Waste Tank Release to Sanitary Sewer Release Number:
From:
Month:
2004-03 10K Tank November Amount Released:
Date of Release:
78500 gal.
2.98+07 ml 12/6/04 Monthly Percent Nuclide Tank Limit Release of Monthly (p.Ci/ml)
(IPCi/ml)
(j+/-Ci/ml)
Limit Unidentified 2.90E-07 l 2E-08 5.OE-09 2.5E+O1 Beta TOTAL 2.90E-07 gCi/rnl Total of Limit Released:
Total of Activity Released:
Year to Date Activity Released 24.98 %
8.66 IlCi 43.56 ligi Buffalo Materials Research Center 2004 Annual Report Page 10
University at Buffalo Buffalo Materials Research Center Table 4 -- 2004 Cumulative Summary of Environmental Radiation Dose Equivalent (mrem)
A B
C D
E IF G
l Monthly 0
F Monitoring 2
2 m
_3 Peio N
2 o
<o CD> M c
y M
e
,o Penad O
a c
O -
(O CD LL January 0
0 0
0 0
O 0
13 February 0
0 0
0 0
0 5
11 March 0
0 0
0 1
0 2
14 April 0
0 0
0 0
0 0
16 May 0
0 0
5 1
0 0
9 June 0
0 0
2 0
0 0
16 July 0
0 0
0 4
N/A 2
14 Auqust 0
0 0
0 0
N/A 1
11 September 0
0 0
0 0
N/A 0
11 October 0
0 0
0 0
N/A 0
15 November 0
0 0
2 1
N/A 2
11 December 0
0 1
1 1
N/A 4
16 Total 0
0 1
10 8
0 16 Dose equivalent reported is subtracted from control average.
F 1
l (Removed 7104)
Buffalo Materials Research Center 2004 Annual Report Page I I
University at Buffalo Buffalo Materials Research Center Table 5 -- 2003 Whole Body Deep Dose Equivalent Summary Deep Dose Equivalent BMRC University Visitor Fuel (rem)
Staff Police Handler Dosimeter None 8
1 4
2 Measurable 0.OO1 to.010 0
0 0
0 0.Oll to.100 0
0 0
0
>0.100 O
0 0
0 Table 6 -- 2003 Extremity Shallow Dose Equivalent Summary Extremity Shallow Dose BMRC (rem)
Staff None 4
Measurable
.OlOto O.100 4
>0.100 0
Buffalo Materials Research Center 2004 Annual Report Page 12