ML20214J665
| ML20214J665 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 06/30/1986 |
| From: | Wilson W WASHINGTON STATE UNIV., PULLMAN, WA |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8608150122 | |
| Download: ML20214J665 (8) | |
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ANNUAL REPORT ON THE OPERATION OF THE WASHINGTON STATE UNIVERSITY TRIGA REACTOR Facility License R-76 for the Reporting Period of July 1, 1985 to June 30, 1986 A. Narrative Summary of the Year's Operation
- 1. Operating Experience The Washington State University Reactor has accumulated 619 Megawatt hours on Core 31-A during the reporting period. A total of 8974 irradiations for a total of 27,036 samples were performed. In addition, 26 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.
- 2. There were no changes in design, performance characteristics, or operating procedures that related to reactor safety during the reporting period.
- 3. All surveillance tests and requirements were performed and completed within the prescribed time period. The results of all inspections revealed no abnormalities and were within expected values.
B. Energy and Cummulative Output The quarterly operations summaries are given in Table I below.
Table I Fiscal Year Summary of Reactor Operations J-A-S 0-N-D J-F-M A-M-J TOTALS i
Hours of Operation 135 144 213 152 644 Megawatt Hours 135 123 213 148 619 -
No. of Irradiations 1992 1677 3161 2144 8974 No. of Samples Irradiated 7130 5036 8705 6165 27036 No. of Pulses > $1.00 0 23 0 3 26 The cummulative energy output since criticality of the TRIGA core since 1967 is 549 Megawatt Days. The mixed core of FLIP and Standard fuels installed in 1976 has accumulated 288 Megawatt Days.
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2 C. Emergency Shutdowns and Inadvertent Scrams During the reporting period, no emergency shutdowns occurred. The causes of the six inadvertent scrams that occurred during the reporting period are given in Table II below.
Table II Inadvertent Scrams Date Cause 09/05/85 Period spike during startup.
09/12/85 High Power Trip, Safety Ch. #1 during startup while ad 10/08/85 Pu se usting)#1
(#3 Rod CIC drop Compensating
- No other indication.Voltage.
10/29/85 High Power Trip, Safety Ch. #1 at 10% power while ad;usting #1 CIC Compensating Voltage.
05/03/86 Blade drop - Loss of building power.
05/20/86 Blade drop - Loss of building power.
D. Major Maintenance A TRIGA FLIP Instrumented Fuel Rod with three defective thermocouples was removed and replaced with a spare FLIP Instrumented Fuel Rod from storage on 03/17/86.
E. Changes, Tests and Experiments Performed Under 10 CFR 50.59 Criteria No changes, tests or experiments were carried cut under 10 CFR 50.59 criteria during the reporting period.
F. Radioactive Effluents Discharges
- 1. Radioactive Liquid Release During the reporting period, the average release concentration of liquid waste was 5.51E-10 microcuries per milliliter. This yeilded a total of 0.038 microcuries released in a total of 18,713 gallons of liquid. The monthly releases are listed in Table III on page 3.
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3-Table III Radioactive Liquid Releases Quantity Concentration Percent Volumne Month uCi uCi/ml MPC* Gallons Jul. No Release - -
Aug. No Release - -
Sep. No Release - -
Oct. No Release - -
Nov. No Release -. -
Dec. No Release - -
Jan. 0.015 8.58E-10 0.9 4700 Feb. No Release - -
Mar. 0.006 4.01E-10 0.4 4152 Apr. No Release - -
May. 0.006 3.23E-10 0.3 5231 Jun. 0.011 6.22E-10 0.6 4630 Based on a release limit of 1.0E-7 uCi/ml for unknown mixture found in Technical Specifications 6.10, paragraph 5, page 36,
- 2. Radioactive Gaseous Release During the reporting period, no significant quantity of any gaseous or particulate material with a half life greater than eight days was released.
During the reporting period, at no time did the release exceed 20%
of MPC for Argon-41.
The average monthly concentration of Argon-41 released was 1.07E-7 uti/cc. This yielded a total of 7.2 Curies released in 6.7E+13 cc of air. The monthly releases are summarized in Table IV on page 4.
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c-4 Table IV Monthly Argon-41 Releases Concentration Before Dilution Percent MPC* Quantity Month uCi/cc After Dilution mci Jul. 1.12E-7 1.12 635 Aug. 1.07E-7 1.07 607 Sep. 1.62E-7 1.62 889 Oct. 1.30E-7 1.30 -737 Nov. 3.48E-8 0.35 191 Dec. 9.73E-8 0.98 552 Jan. 1.43E-7 1.43 811 Feb. 9.79E-8 0.98 501 Mar. 1.25E-7 1.25 709 Apr. 9.21E-8 0.92 505 May. 1.02E-7 1.02 578 Jun. 8.21E-8 0.82 450 Based on 10 CFR 20 limit of 4.0E-8 uCi/cc (Table II, Col. I), and a dilution factor of 4.0E-3 (S.A.R. 6.4.2) for an after dilution limit of 1.0E-5 uti/cc. (20% of limit is 2.0E-6 uti/cc).
- 3. Radioactive Solid Waste Disposal for waste generated by the Nuclear Radiation Center during the reporting period, one shipment was made to U.S. Ecology Company in Richland, Washington for disposal. An estimated total of 10 microcuries in 7.5 compacted cubic feet was shipped in one 55 gallon drum. The shipment is tabulated in Table V below.
Table V W.S.U., N.R.C. Solid Radioactive Waste Disposal Date Volume in Cubic Feet Activity in Millicuries 07/11/85 7.5 0.01
5 G. Personnel and Visitor Radiation Exposures The average quarterly exposures of Nuclear Radiation Center reactor staff and experimenters who routinely utilize the W.S.U. reactor are given in Table VI below. The maximum quarterly exposure of one individual, who is a reactor staff member, was 120 millirem, whole body.
A total of 1377 individuals and non-Nuclear Radiation Center staff experimenters visited the Center during the reporting period, out of which 501 entered posted radiation areas. As determined by pocket dosimeter and an exposure recorded, the average individual exposure for those entering posted radiation areas was 3.5 millirem with a maximum exposure of 55 millirem.
A total of 33 group tours, consisting of a total of 389 individuals, visited the Nuclear Radiation Center during the reportin aeriod. As determined by digital dosimeter and an expoure recorded,g tie average group exposure was 0.7 millirem with a maximum of 5 millirem.
Table VI Avertje Quartarly Reactor / Experimenter Staff Exposure
( in millirem )
Jul-Aug-Sep Oct-Nov-Dec Jan-Feb-Mar Apr-May ***
42 16.7 22 27.5
- June's film badge results not available from vendor at the time this report was prepared.
H. Reactor Facility Radiation levels The routine area radiation surveys of the building in non-reactor Controlled Access Areas
- had an average level of 0.06 mrem /Hr., while the average level in reactor Controlled Access Areas was 1.0 mrem /Hr.
The highest average in a reactor Controlled Access Area was 4.3 mrem /Hr., which occurred in the beam port room at the thermal column face. The lowest average in a reactor Controlled Access Area was 0.04 mrem /Hr., which occurred in the cooling system pump room. The average level in the reactor control room was also 0.04 mrem /Hr.
- See page 6.
6 Routine building surveys for removable contamination in non-reactor Controlled Access Areas
- had an average value of 6.18E-6 uCi/100 cm2 while the average value in reactor Controlled Access Areas was found to be 24.93E-6 uCi/100 cm2.The highest avera Controlled Access Area was 169.85E-6 uCi/ge value 100 cm2 in was which a reactor found on the platform where experimenters stand to insert and withdraw samples from the reactor. The lowest average value in a reactor Controlled Access Area was 1.63E-6 uCi/100 cm2 which was the cave storage room floor.
non-reactor C.A.A.'s are areas in the building where radioactive materials are used or stored but which are not a part of the reactor facility.
I. Environmental Monitoring Program The environmental monitoring program uses thermoluminescent dosimeters (TLD's) at locations in and around the reactor building facility. The quarterly exposures in the vicinity Nuclear Radiation Center are listed in Table VII below. The average ambient gamma radiation levels for this area (80 mile radius) is 93 mrem /yr., (255 uR/ day) as reported in the 22th Annual Report of the Environmental Radiation Program, Washington State Department of Social and Health Services.
The values observed indicate there is no significant effect on the environment radiation levels by reactor operations.
Table VII Environmental Radiation Levels in the Vicinity of the Nuclear Radiation Center *
(Exposure in uR/ day)
Jul-Aug-Sep Oct-Nov-Dec Jan-Feb-Mar Apr-May-Jun Median 263 69 297 ** 210 For sampling stations located 50 meters or greater from the Nuclear Radiation Center.
- Apr May-Jun data not available from TLD vendor at the time this report was prepared.
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Quarterly exposures at readily accessible locations at the reacter facility are listed in Table VIII below. No significant effect on the environmental radiation levels by reactor operation was noted.
i Table VIII Environmental Radiation Levels Adjacent to the Nuclear Radiation Center
- i (Exposure in uR/ day) 1 Location J-A-S 0-N-D J-F-M A-M-J Median S. Bldg. Entrance 315 152 289 ** 252 E. Lwr. Loading Dock 315 207 278 ** 267 Pool Room E. Door 761 935 1067 ** 921 Storage Shed 370 272 389 ** 344 Building N. Side 304 185 367 ** 285 Beam Room W. Door 293 174 333 ** 267 Building W. Side 326 196 378 ** 300 Building W. Roof 609 696 756 ** 687 Building E. Roof 413 370 467 ** 417 For sampling stations located less than 50 meters of the Nuclear Radiation Center.
- Apr-May-Jun data not available from TLD vendor at the time this report was prepared.
Technical Specifications ALARA effluent releases in 3.12(2) specify annual radiation exposures at the closest offsite extended occupancy shall not, on an annual basis, exceed the average local offsite background radiation level by more than 20%. For the 1st three quarters 4
of the reporting pericd, the average background radiation level for sampling points 400 meters or greater from the facility was 182 uR/ day.
The average radiation level at the closest extended occupied area 380 meters away was 192 uR/ day, which yeilds a ratio of exposure to background of 5.5 %, indicating no significant exposure level above natural background. For the four quarters of calender year 1985, the average background radiation level was 259 uR/ day, while the exposure to the same closest offsite area was 264 uR/ day. This yeilds a ratio of exposure to background of 1.9%, again indicating no significant exposure level above natural background.
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A *gv Washington State University Nuclear Radiation Center, Pullman, Washington 99164-1300 / 509-335 8641 August 4,1986 Director, Division of Reactor Licensing U.S. Nuclear Regulatory Commission Washington, DC 20545 Re: Docket No. 50-27 Facility License R-76
Subject:
Annual Report
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 Jerry A. Neidiger, the Reactor Supervisor of the WSU facility, is hereby submitted. The report covers the period from July 1,1985 to June 30, 1986.
Sincerely, W f WW W.E. Wilson Associate Director -
WEW:mb Enc.
cc: John Sheppard, Chainnan Reactor Safeguards Committee C.J. Nyman, Dean of the Graduate School N.R.C.-Region V, Office of Inspection and Enforcement J.A. Neidiger American Nuclear Insurers
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