ML20077J393
| ML20077J393 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 08/12/1983 |
| From: | Wilson W WASHINGTON STATE UNIV., PULLMAN, WA |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8308160342 | |
| Download: ML20077J393 (7) | |
Text
..
\\
,.h ',
ANNUAI. REPORT ON THE OPERATION OF THE WASHINGTON STATE UNIVERSITY TRIGA REACTOR Facility license R-76 for the period of July 1, 1982, to June 30, 1983 A.
Narrative Summary of the Year's Operation 1.
Operating Experience The Washingten State University Reactor has accumulated 583 megavatt hours on Core 31-A during the reporting period. A total of 18,901 irradiations for a total of 33,001 samples were performed.
In addition, eight pulses greater than
$1.00 were performed during this 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 results.
B.
Energy and Cumulative Output The quarterly operations summaries are shown in Table I below.
Table I Fiscal Year Summary of Reactor Operations JAS OND JFM AMJ TOTAL Hours of Operation 121 101 226 138 586 Megawatt Hours 118 101 226 138 583 Number of Irradiations 114 80 17106 1601 18901 Number of Sampics Irradiated 3389 1972 23208 4432 33001 Number of Pulses greater than $1.00 2
4 9
2 8
The cumulative energy output since criticality of the TRICA core since 1967 is 478 megawatt days. The mixed core of FLIP.and-Standard fuels installed in 1976 has accumulated 217 megawatt days.
8308160342'830812 gDRADOCK 05000027
~
PDR i
4 1
.o
- C.
Emergency Shutdowns and Inadvertant Scrams During the reporting period, no emergency shutdowns occurred.
The causes of the two inadvertant scrams which occurred during the reporting period are given in Table 11 below.
Table II Inadvertant Scrams 4
Number Cause 1
Period Scram; Period Spike--no apparent cause.
1 Reactor Scram; complete loss of building power.
g D.
Major Maintenance Operations 4
There were no items in this category for this reporting period.
All maintenance conducted was routine planned maintenance.
E.
Changes, Tests and Experiments Carried Out Under 10 CFR 50.59 There were no items in this category for this reporting period.
F.
1.
Radioactive Liquid Release During the reporting period.gthe aveyage release concentration was 9.66 x 10 u Ci/cm. This yielded a total of 2292 microcuries released in a toal of 48,795 gallons of liquid effluent. The monthly releases are shown in Table III below.
Table 111 Radioactive Liquid Releases Quantity Concentratgon Percent
- Volume 1
Month UCi UCi/cm MPC Gallons July 0.28 1.61 x 10-4.0 4655 August 0.22 1.24 x 10 3.1 4650
-9 September 0.09 4.77 x 10
-1.2 4727 October No Release November 0.154 8.85 x 10 '
2.2 4604
-5 i
December 1224.51 5.87 x 10 2.0 #1.
5510
. January No Release
-5 February 1064.4 1.84 x 10 20.4 #2 15,259
-8 March 1.52 8.64 x 10 21.6 4654 April No Release
-8 May 0.89 4'.197 x 10 12.4' 4737 June No Release-
- Release limit'of 410 x 10 UCi/cm* for unknown mixture used
-7 in all releases unless otherwise noted.-
Lt
- l
o
~3-33 NOTE #1: Major activity determined to be from PA and Er 10 CFR 20, Table 1, Col.11 limits are so f ollows:
~3 3
PA 4 x 10 uCi/cm l
~3 3
Er 3 x 10 u Ci/cm
~3 3 x 10 uCi/ml used in calculating MPC.
133 10 CFR 20 NLTE #2: Major activity determined to g from Bg Table 1, Col. 11 limit is 9.0 x 10 uCi/cm 2.
Radioacdtive Casecus Release During the reporting period, no significant quantity of any gaseous or particulate material with a half-life greater than eight days was released.
The average montMy concentration of Argon-M was M x g
3 10 uCi/cm Thjsyieldedatotalof3.57Curiesreleased 13 in 6.68 x 10 cm of air. The monthly releases are summarized below in Table IV.
Table IV Monthly Argon-41 Releases Concentration Percent MPC BeforeDi}ution (Note #1)
Quantity Month uCi/cm After Dilution mci
-8 J uly 1.47 x 10 0.15 83.48
~8 0.34 192.84 August 3.40 x 10~
0.19 103.68 September 1.89 x 10 a
October 2.54 x 10 0.25 144.19
~8 November 7.90 x 10 0.79 432.00
~8 December 3.18 x 10 0.32 180.35
-8 January 7.08 x 10 0.71 401.31 February 1.31 x 10_,
1.31 669.31 1.01 571.39 March 1.01 x 10~
0.85 462.24 April 8.46 x 10_8 May 5.26 x 10_3 0.53 298.20 June 5.45 x 10,
0.05 29.81
~8 NOTE #1: brsed on 10 CFR 20 limit of 4.0 x 10 UCi/ml (Table
~3 II, Col. F, and a dilution factor g 4.0 x 10 (SAR 6.4.2) for an After Jilution Limit of 1.0 x 10 uCi/ml.
3.
Radioactive Solid Waste Disposal For waste generated by the Nuclear Radiation Center during the reporting period, one shipment was made to the U.S.
Ecology Company of Richland, Washington, for disposal. A total of 0.5 m Curies in a volume of 7.5 cubic feet was packaged in a 55-gallon drum for shipment. The shipment is tabulated below in Table V.
a.
+
Table V W.S.U., N.R.C. Solid Radioactive Waste Disposal Date Volume in Cubic Feet Activity in m Curies 7/7/82 7.5 0.50 G.
Personnel and Visitors Radiation Exposure The average quarterly exposures of reactor personnel are shown in Table VI below. The maximum quarterly exposure for an individual was 110 millirem.
A total of 1862 individual visitors and non-Nuclear Radiation Center staff experimenters visited the Center during the reporting period. As determined by pocket dosimeter, the average individual exposure was 3.91 millirem with a maximum exposure of 48 millirem.
A total of 36 group-type tours visited the Nuclear Radiation Center during the reporting period consisting of 417 individuals.
As determined by pocket dosimeter, the average group exposure was 3.78 millirem with a maximum exposure of 23 millirem.
Table VI Average Quarterly Reactor Staff Exposure (in millirems)
Jul-Aug-Sep Oct-Nov-Dec Jan-Feb-Mar Apr-May-Jun*
38 65 63 35
- Average for April and May. June film badge results not available from vendor at the time this report was prepared.
11.
Reactor Facility Radiation Levels The routine area radiation surveys in reactor operating areas had an average of 0.65 mrem /hr. The highest average was 4.26 mrem /hr. which occurred in a locked radiation source storage area. The lowest average level was 0.02 mrem /hr. which was found in the reactor shop area. The average level in the reactor l
control room was 0.04 mrem /hr.
l
[
Routine surveys for removal contamination in reagtor operatigg l
areas resulted in an average value of 5.52 x 10 uCi/100 cm l
vhich was found on the platform where experimenters stand to i
insert and remov samples frog the reactor. The lowest average 5
value, 1.63 x 10 UCi/100 cm, was the floor.of the reactor console room.
t q
e,
l 1.
Environmental Monitoring Program The environmental monitoring program uses thermoluminescent dosimeters (TLD's) at locations in and around the reactor facility. The water saaples taken in the vicinity of Washington State University are anlayzed for gross beta / gamma activity.
The quarterly exposures near the Nuclear Radiation Center are listed in Table V11. Normal ambient gamma radiation levels for this area (80 mile radius) average 240 UR/ day as reported in the 18th Annual Report of the Environmental Radiation Program by the Office of Environmental Health Programs, Washington State Department of Social and Health Services.
The values observed indicate there is no significant effect on the environmental radiation levels by reactor operations.
Table VII Environmental Radiation Levels in the Vicinity of the WSU Nuclear Reactor *
~~~
Exposure in UR/ day Yearly J-A-S 0-N-D J-F-M A-M-J Median 164 158 234 185
- From sampling stations located within 50-500 meters of the Nuclear Radiation Center.
- April, May, June data not available from TLD vendor at the time this report was prepared.
Quarterly exposure rates at readily accessible locations at the reactor facility are listed in Table VIII. Again, no significant effect on the environment radiation levels by' reactor operation was observed.
Table V111 Exposure Rates Adjacent to the WSU Reactor
- Exposures in UR/ day Yearly JAS OND JFM AMJ Median Building Entrance 285 185 185 218 E. Lower Loading Dock 141 217-225 194 E. Pool Room Door 3011 1435 940 1482
[
Storage Shed 228 196 192 205 N. Side of_ Building 130 196 _ 212 179 l
W. Beam Room Door ~
141 141 l252 178 W. Side of Building 120
-196 225 180
o
- From sample stations located less than 50 meters of the Nuclear Radiation Center.
- April, May, June data not available from the TLD vendor at the time this report was prepared.
The environmental water sampling and counting is performed by the Washington State University Radiation Safety Office.
In June 1982, the low-level beta-gamma counting system used by the campus Radiation Office ceased to function. Recently, a new counting system was purchased and the water samples are presently being analyzed.
4 h
f t
k I
uL -.1 -
- ~ ^ WA'SHINGTON STATE UNIVERSITY PULLMAN, WASHINGTON 991H NUCLEAR RADIATION CENTER August 12, 1983 Director, Division of Reactor Licensing U.S. Nuclear Regulatory Commission Re: Docket No. 50-27 Washington, D, C.
20545 Facility License R-76
SUBJECT:
Annual
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 W.S.U.
facility is hereby submitted. The report covers the period from July 1, 1982 to June 30, 1983.
Sincerely, 7 F.9%
W. E. Wilson Associate Director WEW:efm enclosure cc: John C. Sheppard, Chairman Reactor Safeguards Committee C. J. Nyman, Dean of the Graduate School N.R.C. - Region V, Office of Inspection and Enforcement American Nuclear Insurers J. A. Neidiger go2e Ifo u
--