ML042530151
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{{#Wiki_filter:M Washington State University Nuclear Radiation Center PO Box 641300 Pullman, WA 99164-1300 509-335-8641 FAX 509-335-4433 August 27, 2004 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Re: Docket No. 50-27; Facility License R-76
Dear Sir:
In accordance with the Technical Specifications for Facility License R-76 and the provisions of 10 CFR 50.59, paragraph (6), the attached Annual Report prepared by Stephanie L. Sharp, Reactor Supervisor of the WSU facility, is hereby submitted. The report covers the period July 1, 2003 to June 30, 2004. Sincerely, Gerald E. Tripard Director GET/pw Enclosure cc: S.L. Sharp Office of Nuclear Reactor Regulation American Nuclear Insurers AM0
$ Washington State University Nuclear Radiation Center PO Box 641300 Pullman, WA 99164-1300 509-335-8641 FAX 509-335-4433 August 27, 2004 Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Re: Docket No. 50-27; Facility License R-76
Dear Sir:
In accordance with the Technical Specifications for Facility License R-76 and the provisions of 10 CFR 50.59, paragraph (6), the attached Annual Report prepared by Stephanie L. Sharp, Reactor Supervisor of the WSU facility, is hereby submitted. The report covers the period July 1, 2003 to June 30, 2004. Sincerely, Gerald E. Tripard Director GET/pw Enclosure cc: S.L. Sharp American Nuclear Insurers /U.S. NRC, Document Control Desk
A ANNUAL REPORT ON THE OPERATION OF THE WASHINGTON STATE UNIVERSITY TRIGA REACTOR Facility License R-76 for the Reporting Period of July 1, 2003 to June 30, 2004 A. Narrative Summary of the Year's Operation I. Operating Experience The Washington State University Reactor has accumulated 1405 Megawatt hours on cores 33-X and 34-A during the reporting period. A total of 470 samples were irradiated, for a total of 7937.6 user-hours. In addition, 8 pulses greater than $1.00 of reactivity addition were performed during this reporting period. The quarterly operations summaries are shown in Table I Section B. II. Changes In Facility Design, Performance Characteristics, and Operating Procedures Related to Reactor Safety. The reactor facility has made several upgrades during the reporting period including a core configuration change, the installation of new irradiation facilities, and the reinstallation of a beamport. None of the changes were 50.59 type modifications, and were all performed according to appropriate procedure.
- m.
All surveillance tests and requirements were performed and completed within the prescribed time period. The NRC inspection of the week of June 7 found that some shipping papers had been incorrectly prepared. The program used to prepare these papers has since been corrected. B. Energy and Cumulative Output The quarterly operations summaries are given in Table I. TABLE I Fiscal Year Summary of Reactor Operations J-A-S O-N-D J-F-M A-M-J TOTALS Hours of Operation 195.43 542.25 594.07 324.55 1656.3 Megawatt Hours 187.81 458.17 448.57 310.86 1405.41 No of Sample Irradiations' 15 31 17 33 96 No. of Samples 79 100 40 150 369 No. of Iridium Cans Irradiated 18 18 27 22 85 No. of Silicon Cans Irradiated 1 3 6 6 16 User Hours 980.4 1488.8 3102.5 2365.9 7937.6 No. Pulses > $1.00 0 4 0 4 8
2 'This table has been modified for clarity. Numbers of Samples and Sample Irradiations do not include Iridium and Silicon data. Those data are listed in individual format. User hours denotes the total user hours, including Iridium and Silicon. The cumulative energy output since criticality of the TRIGA core since 1967 is 1016 Megawatt Days, The mixed core of FLIP and Standard fuels installed in 1976 has accumulated 750 Megawatt Days. C. Emergency Shutdowns and Inadvertent Scrams There were no emergency shutdowns that occurred during the reporting period. The dates and causes of the 14 inadvertent SCRAMS are listed in Table II. TABLE II Inadvertent SCRAMS 7/17/03 Short period. Blade pulled too quickly by trainee. 8/5/03 Short period. Log-N channel pegged high. 12/23/03 Short period. Noise in Log-N channel. 1/30/04 Short period. Log-N channel pegged high. 2/2/04 High Radiation on bridge. Sample re-shielded. 2/26/04 Short period. Blade pulled too quickly. 318/04 Scram due to BNCT system being turned off. 3/16/04 Power failure. 3/16/04 Power failure. 3/16/04 Power failure. 3/17/04 Power failure. 3/18/04 Power failure. 4/16/04 Log-N channel pegged high. 5/18/04 Manual SCRAM due to fire alarm in building. D. Major Maintenance All routine planned maintenance items were completed within the reporting period. Additionally, several modifications/improvements to the facility were made, including a core configuration change, the addition of several new irradiation facilities, and the re-installation of a beamport tube. The core was re-configured to ensure that the maximum flux was available at the west face of the reactor, for use in BNCT experiments. A new iridium irradiation facility was made to hang from the reactor core support structure, providing a facility to expose iridium to the highest flux available. This facility is movable, so it can be easily removed from the reactor core face to facilitate BNCT operations. This facility was installed by divers in the reactor pool while the core was de-fueled.
3 E. Changes, Tests and Experiments per'irmed Under 10 CFR 50.59 Criteria There have been no changes to the facility made under 10 CFR 50.59 criteria within the reporting period. F. Radioactive Effluent Discharges I. Radioactive Liquid Releases A total of 13.7 microcuries was released in 670 gallons of liquid during the reporting period. The releases are listed in Table m. TABLE III Radioactive Liquid Releases Date Nuclide Activity (pCi/ml) Release Limit Percent of Release Limit 11/12/2003 6Sc 8.64e-8 1.OOe4 0.09 51Cr 1.81e-7 5.00e-3 0.00 54_Mn 2.11e-10 3.OOe-4 0.00 5_Co 3.05e-9 6.OOe4 0.00 58Co 7.21e-7 2.OOe-4 0.36 "Co l.Ole-8 3.00e-5 0.03 ______1.36e-7 5.OOe4 0.03 J 92 r 5.41e-8 l.OOe4 0.05 Total Activity Released in 670 fW 3 water: 13.7 pCi
- 2.
Radioactive Gaseous Release During the reporting period, no significant quantity of any gaseous or particulate material with a half-life greater that eight days was released. During the reporting period, at no time did the Argon-41 release exceed 20% of the Effluent Release Limit. A total of 9.97 Curies of Argon41 was released, with an average concentration of Argon41 of 1.511 x 1007 uCi/cc. The monthly releases are summarized in Table IV on Page 4.
4 b 0 TAB3LE IV: Monthly Argon-41 Releases Conc. Before % Release Limit % DAC Limit Quantity mCi Month Dilution, uCi/ml Before Dilution 1 Before Dilution 2 Jul. 03 1.935 x 10-7.74 A0.0258 1064 Aug. 03 7.494x 104 3.00 0.0100 412 Sep. 03 8.791 x 10-3.52 0.0116 483 Oct. 03 2.078x 107 8.31 0.0277 1143 Nov. 03 1.177x10-7 4.71 0.0157 647 Dec. 03 1.883 x 10' 7.53 0.0251 1036 Jan. 04 1.218 x I0O-4.87 0.0163 670 Feb. 04 1.273 x 10-7 5.09 0.0170 700 Mar. 04 3.137x 107 12.55 0.0418 1725 Apr. 04 1.454x 107 5.81 0.0194 800 May. 04 9.843 x 10 3.94 0.0131 541 Jun. 04 1.365 x 10 7 5.46 0.0182 751 'Based on 10 CFR 20 effluent release limit of 1.Ox1O-8 uCi/ml for 4lAr (Table 2, Col.1), and a dilution factor of 4.0xl 0-3 (S.A.R. 6.4.2) for a before dilution limit of 2.5xI 0-6 uCi/cc. (20% of limit is 5.Ox1O-7 uCi/ml). 2 Based on 10 CFR 20 DAC limit of 3.OxlO-6 uCi/ml for 41Ar (Table 1, Col. 3) and a dilutiofi factor of 4.Ox1O-3 for a before dilution DAC limit of 7.5xl0-4 uCi/ml.
- 3.
Radioactive Solid Waste Disposal During the reporting period, the following solid waste was transferred to the Campus' Radiation Safety Office for packaging and disposal. 0.02 millicuries in 14 cubic feet of non-compacted solid waste. 82.5 millicuries in 7.5 cubic feet, (1 - 7.5 cuft barrel), of non-compacted solid waste. G. Personnel and Visitor Radiation Exposures The quarterly exposures of selected Nuclear Radiation Center reactor staff and experimenters who routinely utilize the W.S.U. reactor are given in Table V on Page 5. The maximum quarterly exposure of a reactor staff member was 34 millirem, whole body. A total of 2372 individual persons visited the Nuclear Radiation Center during the reporting period, of which 564 entered a Restricted Area. All exposures as determined by digital pocket dosimeter were less than I millirem.
3 A total of 30 group tours, consisting of 354 individuals, visited the Center-during the reporting period. As determined by digital pocket dosimeter, all exposures were less than 1 millirem. TABLE V Quarterly Reactor and Experimenter Staff Exposure (in millirem) Badge No. Jul-Aug-Sep 03 Oct-Nov-Dec 03 Jan-Feb-Mar 04 Apr-May-Jun 04 6 6 18 5 6296 1 22 24 20 4045 3 4 3504 1 5855 9 12 8 4 6834 31 31 34 29 5723 1 _4 1 The "-" denotes a dosimeter reading that is less than or equal to the background radiation level for that quarter. H. Reactor Facility Radiation and Contamination Levels The routine area radiation surveys of the building in non-reactor vital areas' had an average dose level of 0.240mRAIr., while routinely accessible reactor vital areas had an average dose level of 0.182 mnR/Hr. The highest average dose level in a routinely accessible reactor vital area was 0.68 mR/Hr., which occurred in Room 201, Reactor Pool Room, on the reactor bridge. The lowest average dose in a routinely accessible reactor vital area was 0.03 mR/Hr., which occurred in Room 201B, the Reactor Console area. The average dose in the radiochemistry sample hoods was 0.09 mR/Hr. The highest average on site dose level was 12.0 mR/Hr. which occurred in Room 101-A, Purification Pump Room, which is accessible only through a floor hatch, and is adjacent to the reactor pool. Routine building surveys for removable contamination in non-reactor vital areas' had an average level of 8.98 x 10407pCill00 cm2, while the average level in the reactor vital areas was 6.03 x 1047 [Ci/100 cm2. The highest average value in the reactor vital areas was 2.03 x 106 pCi/100 cm2 which was found on the heat exchanger pit floor. The lowest average value in the reactor vital areas was 3.13 xl007 pCi/I 00 cm2 which was in Room 201, the Reactor Bridge, north side. The average level of removable contamination in the radiochemistry hoods was 1.46 xl04 pCi/100 cm2. 'A non-reactor vital area is an area in the building where radioactive materials are used or stored but which is not a part of the Licensed reactor facility.
6 7 Environmental Monitoring Program The environmental monitoring program uses thermoluminecent dosimeters (TLD's) at locations both near and at distances around the reactor facility building. The quarterly exposures in the vicinity of the Nuclear Radiation Center are listed in Table VI. The average ambient gamma radiation levels for this area (80 mile radius) is 243 pRem/day as reported in the 30th Annual Report of the Environmental Radiation Program, Washington State Department of Health, Environmental Health Program, Table A-12, Page 131. The values observed indicate there is no significant effect on the environmental radiation levels due to reactor operation. TABLE VI Environmental Radiation Levels in the Vicinity of the Nuclear Radiation Center1 (Exposure in pRem/day) Jul-Aug-Sep 02 Oct-Nov-Dec 02 Jan-Feb-Mar 033 Average 186.5 113.3 101.8 133.8 698.92 474.72 494.42 . 556.0 sampling stations located 25 meters or greater from the Nuclear Radiation Center. D attached to "Decorative" granite display on Compton Union Building Mall approximately 1300 3ters from the Nuclear Radiation Center. ,terly exposures at locations adjacent to the reactor facility are listed in Table VII on Page 7. No >ficant effect on the environmental radiation levels by reactor operation was noted.}}