ML20117K904
| ML20117K904 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 06/30/1996 |
| From: | Tripard G WASHINGTON STATE UNIV., PULLMAN, WA |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9609120227 | |
| Download: ML20117K904 (8) | |
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] Washington StateUniversity E Nuclear Radiation Center Pullman, WA 991641300
, 509-335-8641 FAX 509-335 4433 August 30,1996 Document Control Desk U.S. Nuclear Regulatory Commission Washington,DC 20555 l
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 i CFR 50.59, paragraph (6), the attached Annual Report prepared by Jerry A. Neidiger, Reactor i' Supervisor of the WSU facility, is hereby submitted. The report covers the period July 1,1995 to June 30,1996.
Sincerely, Gerald E.Tripard Director GET/pw Enclosure cc: J.A. Neidiger NRC, Region IV, Office of Regional Adminstrator American NuclearInsurers JET)k 4
9609120227 960630 i PDR ADOCK 05000027 R PDR
ANNUAL REPORT ON TIIE OPERATION OF THE WASIIINGTON STATE UNIVERSITY TRIGA REACTOR Facility License R-76 for the Reporting Period of l July 1,1995 to June 30,1996 l
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A. Narrative Summary of the Year's Operation
- 1. Operating Experience l
The Washington State University Reactor has accumulated 396 Megawatt hours on Core 33-X hours during the reponing period. A total of 170 irradiatiens for a total of 4832 samples were performed. In addition,11 pulses greater than $1.00 of reactivity addition were performed during this reponing period. The quarterly operations summaries are shown in Table 1, section B.
- 2. There wen: no changes in design, performance characteristics, or procedures that related to reactor safety during the reporting period.
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- 3. All smveillance tests and requirements wen: performed and completed within the prescribed time period. The results of all inspections revealed no abnomialities.
i B. Energy and Cumulative Output l l
The quarterly operations summaries are given in Table I.
l TABLLI I
J A-S O-N D J F-M A-M-J TOTALS
, Hours of Operation 109 85 110 150 454 I I Megawatt Hours 86 73 102 135 396 No. of Irradiations 34 30 47 59 170 l No. of Samples Irradiated 2015 1665 801 1351 4832 l No. Pulses > $1.00 0 7 2 2 11 l
l The cumulative energy output since criticality of the TRIGA core since 1967 is 759 Megawatt Days, The mixed core of FLIP and Standard fuels installed in 1976 has accumulated 493 Megawatt Days.
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. C.' Emergency Shutdowns and inadvertent Scrams There were no emergency shutdowns that occurred during the reporting period. The dates and causes of the 6 inadvertent SCR AMS are listed in Table 11..
TABLE II Inadvertent SCRAMS j l
DATE CAUSE 10/16/95 Loss of building / site power.
! 11/18/95 Log Power Channel Loss of H.V. - No other indication. Possible line power )
i fluctuations due to high winds.
l 11/14/95 Loss on Control Console Power. - Power CB inadvertently cycled.
01/03/96 Seismometer bumped by worker in Control Room.
04/18/96 Loss of building / site power.
04/18/96 No Indication - Possible power line transients.
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1 D. Major Maintenance 09/19/95: Pulse Rod mechanism support plate penetration opening enlarged to allow removal of
, drive without disassembly of lower limit switches.
All other major maintenance performed was routine planned maintenance items.
E. Changes, Tests and Experiments Performed Under 10 CFR 50.59 Criteria There were two items performed and documented under 10 CFR 50.59 criteria during the reporting period:
11/16/95. Approval to install a remote Reactor Manual SCRAM button in the Beam Port Room (Rm.2).(Related to the BNCP project).
i 12/14/95: Replacement mechanical pulse rod air low air pressure alarm with combination digital air
! pressure display / low pressure alarm unit mounted in Reactor Console.
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. F.* Radioactive Effluent Discharges I
- 1. Radioactive 1.iquid Releases A total of 1.81 microcuries was released in 224,748 liters of liquid during the reporting period.
The releases are listed in Table 111..
TAllLE Ill -
Radioactive 1.iquid Releases i
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Quantity Tank Release Tank Release Time
- Sewer Conc %*
Date uCi/mi Voi, Liters Vol., Liters firs. uCi/mi MPC l
l 07/24/95 0.81 9.69x10* 83,799 5.0 6.31 x 10^" 3.2
! 09/28/95 0.27 10,615 2.5 2.1 1.43x10[ 4.18x10 [
11/15/95 0.04 18,804 2.0 8.02x10~ 0.4 12/14/95 0.12 2.16x10[
6.45x10 18,333 2.0 2.41x104 " 1.2 02/03/96 0.16 8.69x10
- 19,059 2.0 3.21x104 " 1.6 03/04/96 0.17 8.87x10j 18,946 2.0 2.41x10 0.7 05/28/96 0.24 1.30x10 18,691 2.0 4.81x10] 2.4
") Time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is used if miease time is not measured. Average release time is 4-6 hours.
- Based on a release limit of 2.0x10' uCi/ml for unknown mixture,10 CFR 20, Table 3. ,
- 2. Radioactive Gaseous Release i 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.
I o l A total of 4.03 Curies of Argon-41 was releasef in 5.86x10 cc of air, which yields an average monthly concentration of Argon-41 of 6.88x10 uCi/cc. The monthly releases are summarized in Table IV.
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l TABLEIV Monthly Argon-41 Releases Conc. Before % Release Limit'" % DAC Limit' ' Quantity Month Dilution, uCi/mi Before Dilution Hefore Dilution mci Jul.(l995) 7.84x10) 3.14 0.01 392 Aug. 6.58x10 2.6 0.01 329 Sep. 4.17x 10, 1.6 0.01
, 204 Oct. 6.96x 10, 2.78 0.01 208 Nov. 7.20x10 2.8 0.01 352 Dec. 4.91x10, 1.96 0.01 245 Jan.(1996) 5.63x10, 2.25 0.01 281 Feb. 5.73x10 2.2 0.01 259 Mar. 5.50x 10* 2.20 0.01 286 Apr. 1.66x10 6.64 0.02 812 May 7.18x10, 2.87 0.02 351 Jun. 6.44x10 2.58 0.01 315 l
. Based on 10 CFR 20 efflue a dilution factor(S.A.R. of 4.0x}0,nt 6.4.2) for a before release dilution limitlimit of uCi/cc.
of 2.5x10 1.0x10 u (20% oflimit is 5.0x10 uCi/ml).
Based on 10 CFR 20 DAC limit of 3.0x10 uCi/ml for"Ar (Table 1, Col. 3) and a l 3
dilution factor of 4.0x10 for a before dilution DAC limit of 7.5x10-4 uCi/ml.
- 3. Radioactive Solid Waste Disposal During the reporting period the following waste was transferred to the Campus Radiation Safety Office for packaging and disposal:
- 1. Twenty four (.24) cubic feet (29 boxes) of non-compacted solid waste for a total of 0.042 millicuries of activity.
- 2. One (1) 55 gallon drum of compacted, dewatered ion exchanger spent resin containing 0.002 millicuries of activity.
G. Personnel and Visitor Radiation Exposures The average quanerly exposures of Nuclear Radiation Center reactor staff and experimenters who routinely utilize the W.S.U. reactor are given in Table V. The maximum quarterly exposure of a reactor staff member was 20 millirem, whole body.
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5 A total of 2208 non-Nuclear Radiation Center staff or routine facility user individuals visited the Center i during the reponing period. out of which 978 enter Restricted Areas. As determined by digital pocket dosimeter and an exposure recorded, the average individual exposure was <l.0 millirem.
A total of 19 group tours, consisting of 206 individuals, visited the Center during the reponing period.
As determined by digital pocket dosimeter and an exposure recorded, the average group exposure was
<l.0 millirem.
l TAlllE V Average Quartely Reactor and Experimenter Exppsures (in millirem )
l Jul-Aug-Sep Oct-Nov-Dec Jan Feb-Mar Apr-May-Jun l
10 10 20 10 l m l June's film badge results not available from the vendor at the time this mport was prepared.
l l Note: 10 mR minimum exposure mported by vendor.
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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 0.02 mR/Hr., while routinely accessible reactor vital areas had an average dose level of 0.03 mR/Hr. The j highest average dose level in a routinely accessible reactor vital area was 0.2 mR/Hr., which occurred in Room 201, Reactor Pool Room, South side. The lowest average dose in a routinely accessible reactor vital area was 0.02 mR/Hr., which occurred in Room 201 A, the Reactor Shop area. The average dose in the Reactor Control R00m was 0.015 mR/Hr. The average dose in the radiochemistry sample hoods was
, 0.08 mR/Hr. The highest average on site dose level was 8.0 mR/Hr. which occurred in Room 2A, Cave l Room, which is a locked storage area where radioactive material and radioactive sources are stored.
Routine 9 building surveys for removable contamination in non-reactor vital aeas* had an gverage 3.6x10 uCi/cm2, while the average level in the reactor vital areas was 6.32x10 uCi/cm ' The highest average value in the reactor vital areas was 6.24x10-5 uCi/cm2 which was found on the platform where experimenters stand to insert and wjthdraw their samples from the reactor. The lowest average value in the reactor vital areas was 1.63x10 uCi/cm2which was in Room 201, the Reactor Room Floor. The average level of removable contamination in the radiochemisuy sample hoods was 6.03x10^ uCi/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.
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. , I. Environmental Monitoring Program The environmental monitoring program uses thennoluminescent 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 am listed in Table VI. The average ambient gamma radiation levels for this area (80) mile radius)is 243 uRem/ day as reported in the 30* Annual Report of the Environmental Radiation Program, Washington State Department ofIIcalth, Environmental llcalth Program, Table A-12, page 131.
The values observed indicate there is no significant effect on the environment radiation levels due to reactor operation.
TABLE VI Environmental Radiation Levels in theg, Vicinity of the Nuclear Radiation Center (Exposure in uR/ Day)
Jul-Aug-Sep Oct-Nov Dec Jan Feb-Mar Apr-May-Jun Median i
198 161 176 171 177 768<2' 703 793 767 740 0)
For sampling stations located 25 meters or gmater from the Nuclear Radiation Center.
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TLD attached to " Decorative" granite display on Compton Union Building Mall approximately 1300 meters from the Nuclear Radiation Center.
Quarterly exposures at locations at the reactor facility are listed in Table Vll. No significant effect on the environmental radiation levels by reactor operation was noted.
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7 TAllLE VII Environmental Radiation Levels Adgi, cent i
to the Nuclear Radiation Center (Exposure m uR/ day) l 1A> cation Jul-Aug-Sep Oct-Nov-Dec Jan-Feb-Mar A pr-May-Jun Median l
Rad. Storage Shed 223 220 207 209 215 RdnOLSecLOate 195 231 221 219 217 Conting TowenEence 205 198 256 233 223 LILimuling_D_ock 232 264 220 221 234 Liould Wasic_ Tank 214 165 195 209 196 l Building Roof West 179 187 163 134 160 1 Duildine WJiic l 232 209 233 133 202 l Pool Room Exh. Vegt, 152 143 163 134 148 I Pool Room W. Vent 330 297 407 378 353 l Pool Room E. Vent 268 264 293 290 279 Building Roof East 214 154 152 134 164 S. Bldg. Entrancs 214 231 213 244 226 l -
l For sampling stations located less that 25 meters from the Nuclear Radiation Center.
! Pool Room West Vent. TLD on roof, directly above reactor core.
l l l Underlined locations indicate areas that are r viily accessible.
Technical Specifications 3.12(2) ALARA effluent releases specify annual radiation exposures at the l closest off-site extended occupancy shall not, on an annual basis, exceed the average local off-site l background radiation level by more than 20%. For the reporting period, the average total background l radiation level for sampling points 400 meters or greater from the facility was 157 uR/ day, while the l average total radiation level at the closest extended occupied area 930 meters away was 170 uR/ day. This l yields a ratio of 8%, indicating no significant exposure level above natural background.
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