ML20151M650
| ML20151M650 | |
| Person / Time | |
|---|---|
| Site: | 05000076 |
| Issue date: | 06/30/1988 |
| From: | Wilson W WASHINGTON STATE UNIV., PULLMAN, WA |
| To: | NRC |
| References | |
| NUDOCS 8808050264 | |
| Download: ML20151M650 (8) | |
Text
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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, 1987 to June 30, 1988 A.
Narrative Summary of the Year's Ooeration 1.
Operating Experience The Washington State University Reactor has-accumulated 499 Megawatt hours on Core 31 A during the reporting' period.
A core change was performed in' February, 1988 to Core 32-A.
Core 32-A has accumulated 246 Megawatt hours during the reporting period for a total of 745 Megawatt hours of operation during the reporting period. A total of 7356 irradiations for a total of 36,862 samples were performed.
In addition, 12 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 safet', during the reporting period. A core change was performed Febcuary 8, 1988 to Core 32 A.
Measured core parameters upon complecion of core change were within expected values.
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 Cumulative Outout The quarterly operations summaries are given in Table I below.
TABLE I Fiscal Year Summary of Reactor Operations J-A-S O N-D J-F-M A-M J TOTAIS Hours of Operation 192 241 208 159 800 Megawatt Hours 192 227 172 154 745 No. of Irradiations 4121 1123 909 1203 7356 No. of Samples Irradiated 15037 9529 7.249 5047 36862 No. Pulses > $1.00 0
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4 12 The cumulative energy output since criticality of the TRIGA core since 1967 is 605 Megawatt Days, The mixed core of FLIP and Standard fuels installed in 1976 has accumulated 344 Megawatt Days.
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8808050264 880630 PDR ADOCK 05000076 R
2 C.
Emercency Shutdowns and Inadvertent Scrams During the reporting period,1 emergency shutdown was performed due to a false fire alarm, which occurred on 06/20/88.
The causes of the 3 inadvertent scrams that occurred during the reporting period are given-in Table II below.
TABLE II Inadvertent Scrams DATE CAUSE 02/03/88 Blade Disengagement due to power line transient.
02/12/88 Short Period during control rod calibration rod pull.
04/07/88 High Power Trip due to sample removal spiking detector.
D.
Maior Maintenance All maintenance performed during the reporting period was routine scheduled preventive maintenance.
E.
Chances. Tests and Exceriments Performed Under 10 CFR 50.59 Crf teria One modification was conducted and documented under 10 CFR 50.59 criteria during the raporting period.
The Pool Room (Rm 201) ventilation system was modified which consisted of installation of a steam heat coil in the Pool Room supply duct and removal of the Pool Room north and east wall unit vents.
The removal of the north wall vent constituted a change in the ventilation system drawing in Section 3 Fig. 3.2-1, page 3-8 of the facility's Safety Analysis Report.
The vent removal does not constitute a change in the Facility's Technical Specifications.
F.
Radioactive Effluent Discharees 1.
Radioactive Liquid Releases Duringthereportingperigd, the average release concentration of liquid waste was 1.52x10' microcuries per milliliter.
This yielded a total of 1.12 microcuries released in 73,074 liters of liquid.
The monthly re) eases are listed in Table III on page 3.
3 TABLE III Radioactive Liquid Releases
- Quantity, Concentration,
- Volume, I
Month uCi-uCi/ml Percent MPC Liters Jul.
None Aug.
None Sep.
None Oct.
.3.10x10-2 1.70x10*9 1.7 18,170' Nov.
None Dec.
None Jan.
None Feb.
4.50x10*1 2.44x10 8
-24.0 18,439 Mar.
4.40x10*1 2.40x10 8
,24.0 18,258 Apr.
' None May.
2.00x10*1 1.10x10 8
- 11.0 ~
18,207-Jun.
None 1 Based on a release limit of 1.00x10*7 uCi/mi 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 that eight days was-released.
During the reporting period, at no time'did-the release exceed 20% of MPC for Argon 41.
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The average monthly concentration of Argon 41 released was 1.22x{g'cc i
uCi/cc.
This yielded a total of 8.16 Curies released in 6.70x10 of ai-The monthly releases are summarized in Table IV on page 4.
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4 TABLE IV Monthly Argon-41 Releases 1
Concentration Before Percent MPC Quantity Month Dilution, uCi/cc After Dilution mci Jul.
1.13x10'7 1.13 643 Aug.
1.16x10*7 1.16 660 Sep.
1.68x10*7 1,68 925 Oct.
1.55x10'7 1.55 882 Nov.
1.41x10*7 1.41 776 Dec.
1.26x10~7 1.26 717 Jan.
1.56x10~7 1.56 887 7
Feb.
1.07x10 8 1.07 580
'8.57x10'7 Mar.
0.86 488 Apr.
1.09x10'8 1.09 600 May.
9.26x10 8 0.93 527 Jun.
8.60x10' 0.86 473 1
dilutionfactorgf4.0x10'{4.0x10-8 Based on 10 CFR 20 limit o uCi/cc (Table II, Col. I), and a (S.A.R. 6.4.2) for an gfter dilution limit of 1.0x10' uCi/cc. (20s of limit is 2.0x10' uCi/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 of 0.32 mil 11 curies in 7.5 compacted cubic feet was shipped in one 55 gallon drum.
The shipment is tabulated below in Table V below.
TABLE V W.S.U., N.R.C. Solid Radioactive Waste Disposal Date Volume in Cubic Feet Activity in Millicuries 11/17/87 7.5 0.32
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Personnel and Visitor Radiation Exeosures j
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 1
reactor staff member and who routinely prepares irradiated samples for shipment and calibrates radiation survey meters, was 100 millirem, whole body.
A total of 1360 non-Nuclear Radiation Center staff or experimenter individuals visited the Center during the reporting period, out of which 612 enter posted Radiation Areas. As determined by digital pocket dosimeter and an exposure recorded, the average individual exposure was
<1.0 millirem with a maximum exposure of 7 millirem.
A total of 23 group tours, consisting of 227 individuals, visited the Center during the reporting period. As determined by digital pocket dosimeter and an exposure recorded, the average group exposure was <0.1 millirem with a maximum of 0.4 millirem.
TABLE VI Average Quarterly Reactor and Experimenter Staff Exposure (in millirem) 1 Jul-Aug-Sep Oct Nov Dec Jan Feb-Mar Apr May Jun
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20 14 22 16 1 June's film badge results not available from the vendor at the time this report was prepared.
H.
Reactor Facilitv Radiation and Contamination Levels Thergutinearearadiationsurveysofthebuildinginnon-reactorvital had an average dose level of 0.03 mR/Hr., while routinely accessible areas reactor vital areas had an average dose level of 0.18 mR/Hr. The highest average dose level in a routinely accessible reactor vital area was 0.33 mR/Hr., which occurred in Room 201, the reactor Pool Room.
The lowest average dose in a routinely accessible reactor vital area was 0.02 mR/Hr.,
which occurred in Room 201A, the reactor shop area.
The average dose in the reactor control room was 0.03 mR/Hr.
The average dose in the radiochemictry sample hoods was 0.50 mR/Hr.
The highest average on site dose level was 3.8 mR/Hr. which occurred in Room 2A, Cave Room, which is a locked storage area where radioactive material and sources are stored.
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Routigebuildingsurveysforremovable,contaminatigninnon-reactorvital areas had an average level of 2.4x10' uCi/
levelinthereactorvitalareaswas4.9x10'}00cm,whigetheaverage uCi/100 cm. The h average value in the reactor vital areas was 14.2x10'5 uC1/100cm{ghest which was found on the platform froa which experimenters insert and withdraw samples from the areaswas4.5x10'geactor.
Thglowestaveragevalueinthereactorvital uC1/100 cm which was in Room 201B, the reactor control
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room floor.
The average level of remov cion in the radiochemistrysamplehoodswas5.9x10'gblecontami uC1/100 cm 1 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.
I.
Environmental Monitorine Procram The environmental monitoring program uses thermoluminescent dosimeters (TLD's) at locations both near and at distances around the reactor building facility. The quarterly exposures in the vicinity of the Nuclear Radiation Center are listed in Table VII below.
The average ambient gamma radiation levels for this area (80 mile radius) is 91 mrem /yr., (249 uR/ day) as reported in the 24nd Annual Report of the-Environmental Radiation Program, Washington State Department of Social and Health Services.
f The values observed indicate there is no significant effect on the environment radiation levels due to reactor operation.
TABLE VII Environmental Radiation Levels in the Vicinity of the Nuclear Radiation Center 1 (Exposure in uR/ day)
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2 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr-May Jun Median i
184 195 221 200 j
1 For sampling stations located 50 meters or greater from the Nuclear Radiation Center.
2 Apr May Jun TLD data not available from TLD vendor at the time this report was prepared.
Quarterly exposures at readily accessible locations at the reactor facility are listed in Table VIII on page 7.
No significant effect on the environmental radiation levels by reactor operation was noted.
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7 TABLE VIII Environmental Radiation Levels Adjgcent to the Nuclear Radiation Center (Exposure in uR/ day) 2 Location Jul-Aug Sep Oct Nov Dec Jan-Feb Mar Apr May Jun Median S. Bldg. Entrance 113 113 275 167 E. Loading Dock 121 122 176 140 Pool Room E. Door 283 282 784 450 Storage Shed 282 283 569 378 Building N. Side 104 105 235 148 Beam Room W. Door 117 118 235 157 Building W. Side 126 126 294 182 Building W. Roof Badges Lost 235 235 Building E. Roof 93 94 137 108 1 For sampling stations located less that 50 meters of the Nuclear Radiation Center.
2 Apr May Jun TLD 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 of the reporting period, the average background radiation level for sampling points 400 meters or greater from the facility was 187 uR/ day.
The average radiation level at the closest extended occupied area 380 meters away was 176 uR/ day, which yields a ratio of 5.8%, indicating no significant exposure level above natural background.
For the four quarters of calendar year 1986, the average background radiation level was 200 uR/ day, while the exposure to the same closest offsite area was 182 uR/ day.
This yields a ratio of expasure to background of -9.2%, again indicating no significant exposure above natural background.
,o f' Washington State University Nuclear Radiation Center, Pullman, Washington 09164-1300 / 509 33S-8641 July 25, 1988 Director, Division of Reactor Licensing U. S. Nuclear Regulatory Commission MS Pl-137 Washington, DC 20555 Re:
Docket No. 50-27; Facility License R-76 Dedr 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, 1987 to June 30, 1988.
Sincerely, hk 69Vd3 W.
E. Wilson Associate Director Enclosure cci Gary Collins, Chair, Reactor Safeguards Committee R.
V.
Smith, Vice Provost for Research N.R.C.,
Region V, Office of Inspection & Enforcement J.
A.
Neidiger American Nuclear Insurers WEW: crc 1
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