ML20211G330
| ML20211G330 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 06/30/1999 |
| From: | Tripard G WASHINGTON STATE UNIV., PULLMAN, WA |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9908310225 | |
| Download: ML20211G330 (9) | |
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Washington StateUniversity.
Nuclear Radiation Center P O Box 641300 Pullman, WA 991641300 l 509 335-8641 FAX 509-335-4433 August 26,1999 I
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 Jerry A. Neidiger, Reactor i Supervisor of the WSU facility, is hereby submitted. The report covers the period July 1,1998 to l June 30,1999.
Sincerely, a4 Gerald E. Tripard i Director l i
GET/pw Enclosure cc: J.A. Neidiger !
Office of Nuclear Reactor Regulation American NuclearInsurers i
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AogO 3 9908310225 990630 PDR ADOCK 05000027
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[ Washington StateUniversity M Nuclear Radiation Center P O B< x 641300 Pullman. WA 991641300 509-335-8641 FAX 509-335-4433
- August 26,1999 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 Jerry A. Neidiger, Reactor Supervisor of the WSU facility, is hereby submitted. The report covers the period July 1,1998 to June 30,1999.
Sincerely,
&dA 0 Gerald E. Tripard Director GET/pw Enclosure cc: J.A. Neidiger American Nuclear Insurers U.S. NRC, Document Control Desk l
ANNUAL REPORT ON THE OPERATION OF THE WASHINGTON STATE UNIVERSITY TRIGA REACTOR Facility License R-76 for the Reporting Period of July 1,1998 to June 30,1999 A. Narrative Summary of the Year's Operation .
1 I. Operating Experience The Washington State University Reactor has accumulated 1180 Megawatt hours on Core 33-X hours during the reporting period. A total of 833 irradiations for a total of 5913 samples were performed. In addition,11 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.
There were no changes in design, performance characteristics, or procedures that related to reactor safety during the reporting period.
III. All surveillance tests and requirements were performed and completed within the prescribed time period. The results of all inspections revealed no abnormalities.
B. Energy and Cumulative Output The quarterly operations summaries are given in Table I.
TABLEI Fiscal Year Summary of Reactor Operations .
I J-A-S O-N-D J-F-M A-M-J TOTALS j Hours of 0peration 344 268 231 418 1261 Megawatt Hours 306 247 221 406 1180 No. ofIrradiations 281 227 72 253 833 No. of Samples Irradiated 2318 1280 1190 1125 5913 No. Pulses > $1.00 1 6 0 4 11 l
The cumulative energy output since criticality of the TRIGA core since 1967 is 841 Megawatt Days, i The mixed core of FLIP and Standard fuels installed in 1976 has accumulated 575 Megawatt Days. J L
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C. -
Emergency Shatdowns and Inadvertent Scrams There were no emergency shutdowns that occurred during the reporting period. The dates a nd causes of the 14 inadvertent SCRAMS are listed in Table II.
TABLE II Inadvertent SCRAMS DATE CAUSE 07/09/98 Log-N High Voltage Failure - HV in spec. No other indication.
08/04/98 Log-N High Voltage Failure - No other indication. l 09/24/98 Reactor Scram at full power - No other indication. )
12/02/98 Pulse rod and control blades dropped - No other indication.
12/02/98 SCRAM - No other indication. Weather stormy with high winds.
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j 12/02/98 SCRAM - No other indicatioru Weather stormy with high winds )
12/02/98 SCRAM - No other indication. Weather stormy with high winds. j 12/02/98 SCRAM - Control Power key switch inadvertently de-energized. '
12/21/98 SCRAM at 80% power. Logic Element lit. No other indication.
12/21/98 SCRAM at 80% power. Logic Element lit. No other indication.
12/21/98 SCRAM at 80% power. Logic Element lit. No other indication.
12/21/98 SCRAM at 80% power. Logic Element lit. No other indication.
12/21/98 SCRAM at 80% power. Logic Element lit. No other indication.
12/21/98 SCRAM at 80% power. Logic Element lit. No other indication. *
- Logic Element opto-isolator IC replaced 12/22/98. No further spurious SCRAMS D. Major Maintenance I All other major maintenance performed was routine planned maintenance items.
E. Changes, Tests and Experiments preformed Under 10 CFR 50.59 Criteria There was one major modification that began during the reporting period that was documented under 10 CFR 50.59 criteria; the replacement of the reactor pool cooling system heat exchanger, primary and secondary pumps, and the cooling tower.
F. Radioactive Emment Discharges I. Radioactive Liquid Releases A total of 54.27 microcuries was released in 2,073,495 liters ofliquid during the reporting period. The releases are listed in Table III on Page 3.
3 TABLE III l Radioactive Liquid Releases l Quantity Release Release WSU Sewer Total Dilut. Sewer Date uCi Concen. Volume Volume Volume Concen. % MPC l uCi/ml Liters Liters Liters uCi/ml 08/l1/98 1.15 2.72x10* 422,973 480,000 902,973 1.27x10* 0.60 '
09/01/98 1.65 6.16x10* 267,440 480,000 747,440 1.54x10* 7.70 '
09/17/98 1.63 9.95x10* 16,335 480,000 4 % ,335 3.28x10* 16.42 '
09/23/98 10.08 5.42x10* 18,620 480,000 498,620 2.02x10* - 0.05 3
10/02/98 8.49 3.71x10* 22,812 480,000 502,812 1.69x10" 0.04 2
10/16/98 2.58 1.38x10* 18,708 480,000 498,708 5.17x10* 0.01 2
11/16/98 4.46 1.68x10* ~26,513 480,000 506,513 8.81x10* 0.02 3
12/04/98 0.61 8.37x10" 72,377 480,000 522,377 1.10x10* 5.52 '
12/31/98 1.95 1.54x10* 126,786 480,000 606,786 3.21x10* 16.07 '
04/16/99 1.29 1.09x10* 117,590 480,000 597,590 2.16x10* 10.79 '
05/07/99 1.77 1.72x10* 103,130 480,000 583,130 3.04x10* 15.18 '
05/18/99 4.55 1.95x10* 233,382 480,000 713,382 6.38x10* 31.89 '
05/28/99 2.28 4.00x10* 57,019 480,000 537,019 4.25x10* 0.01 3
i 06/08/99 0.013 6.45x10* 20,269 480,000 500,269 2.60x10-" 0.13 ' !
06 17/99 7.10 1.93x10* 367,718 480,000 847,718 8.38x10* 41.88 '
3-06/29/99 4.67 2.57x10* 181,823 480,000 661,823 7.06x10* 0.02
' Based on a release limit of 2.0x10* uCi/ml for unknown mixture,10 CFR 20, Table 3.
' Isotope found to be K". Release limit is 4.0x10* uCi/ml,10 CFR 20, Table 3
- 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 7.87 Curies of Argon-41 was released in 5.86x10" cc of air, which yields an average concentration of Argon-41 of 1.341x10# uCi/cc. The monthly releases are summarized in Table IV on Page 4.
. 4 TABLE IV I Monthly Argon-41 Releases Conc. Before % Release Limit % DAC Limit Quantity rnCi -
Month Dilution, uCi/ml Before Dilution ' Before Dilution
- Jul. 97 8.08x10** 3.23 0.01 551 Aug. 97 1.41x10*7 5.64 0.02 725 Sep. 97 1.98x10*7 7.92 0.03 991 Oct. 97 7.60x10** 3.04 0.01 343 Nov. 97 1.33x10*7 5.32 0.02 642 Dec. 97 1.09x10*7 4.36 0.01 598 Jan. 98 1.03x10*7 4.12 0.01 566 Feb. 98 1.11x10*7 4.44 0.01 413 Mar. 98 1.02x10*7 4.08 0.01 476 Apr. 98 1.31x10*7 5.24 0.02 719 May. 98 1.69x10*7 6.76 0.02 765 Jun. 98 1.53x10*7 6.12 0.02 1083
' Based on 10 CFR 20 efBuent release limit of1.0x10-8 uCi/ml for 41 Ar (Table 2, Col.1), and a dilution factor of 4.0x10-3 (S.A.R. 6.4.2) for a before dilution limit of 2.5x10-6 uCi/cc. (20% oflimit is 5.0x10-7 uCi/ml).
2 Based on 10 CFR 20 DAC limit of 3.0x10-6 uCi/ml for 41 Ar (Table 1, Col. 3) and a dilution factor of 4.0x10-3 for a before dilution DAC limit of 7.5x10-4 uCi/ml.
- 3. Radioactive Solid Waste Disposal During the reporting period, the following solid waste was transferred to the Campus Radiation Safety OfBce for packaging arJ disposal.
50.41 millicuries in 67 cubic feet of non-compacted solid waste.
13.38 millicuries in 30 cubic feet, (4 - 7.5 cuft barrels), of non-compacted solid waste.
5.25 millicuries in 200 cubic feet of reactor grade graphite.
i 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 70 millirem, whole body.
A total of 2,240 individual persons visited the Nuclear Radiation Center during the reporting period, of which 1,205 entered a Restricted Area. All exposures as determined by digital pocket dosimeter were less than 1 nullirem.
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A total of 19 group tours, consisting of 246 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 98 Oct-Nov-Dec 98 Jan-Feb-Mar 99 Apr-May-Jun 99 1 60 30 31 23 2 70 40 54 35 3 50 40 36 22 4' 0 0 36 0 5 0 0 32 1 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 vitd areas had an average dose level of 0.03 mR/Hr. The highest average dose level in a routinely accessible reactor vital area was 0.40 mR/Hr., which occurred in Room 201, Reactor Pool Room, north-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 Room was 0.03 mR/Hr.
The average dose in the radiochemistry sample hoods was 0.25 mR/Hr. The highest average on site dose level was 81 mR/Hr. which occurred in Room 2A, Cave Room, which is a locked storage area where radioactive material and radioactive sources are stored.
Routine buildingsurveys for mmovable contamination in non-reactor vital areas' had an average levelof1.8x10 uCi/100cm2, while the average level in the reactor vital areas was 3.4x10*
uCi/100cm2. The highest average value in the reactor vital areas was 2.1x10* uCi/100cm2 which was found on the platform where experimenters stand to insert and withdraw their samples from the reactor. The lowest average value in the reactor vital areas was 1.15x10#
uCi/100cm2 which was in Room 201B, the Reactor Control Room Floor. The average level of removable contamination in the radiochemistry hoods was 6.2x10" uCi/100cm2.
' 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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. 6 L Environmental Monitoring Program l The environmental monitoring program uses thermaluminecent dosimeters (TLD's) at locatic ns 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 VI. The average ambient gamma radiation levels for this area (80 mile radius) is 243 uRem/ day as reported in the 30th Annual Report of the Environmental Radiation Program, Washington State Department of Health, Environmental Heahh Program, Table A-12, page 131.
The values observed indicate there is no significan: effect on the environment radiation levels due to reactor operation.
TABLE VI Environmental Radiation Levels in the Vicinity of the Nuclear Radiation Center '
(Exposure in uRem/ day)
Jul-Aug-Sep 98 Oct-Nov-Dec 98 Jan-Feb-Mar 99 Apr-May-Jun 99 Median 154 165 141 143 151 725 764 733 missing 741'
' For sampling stations located 25 meters or greater from the Nuclear Radiation Center.
2 TLD attached to " Decorative" granite display on Compton Union Building Mall approximately 1300 {
meters from the Nuclear Radiation Center. J Quarterly exposures at locations at the reactor facility are listed in Table VII on Page 7. No significant effect on the environmental radiation levels by reactor operation was noted.
. 7 TABLE VII Environmental Radiation Levels Adjacent to the Nuclear Radiation Center '
(Exposure in uR/ day)
Location Jul-Aug-Sep Oct-Nov-Dec Jan-Feb-Mar Apr-May-Jun Median i
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E. Loading Dock 140 130 126 110 127 l Rad. Storage Shed 236 250 184 264 234 l Rx Rm W. Secr. Gate 253 261 195 187 224 l Cooling Tower Fence 180 272 253 253 240 i Liquid Waste Tank missing 239 230 231 233 Building Roof West 174 163 149 154 160 Building W. Side 219 217 207 165 202 Rx. Room Exh. Vent 135 141 126 121 131 I 2
Rx. Room W. Vent 674 674 575 835 690 Pool Room E. Vent 461 500 414 495 468 Building Roof East 146 141 126 132 136 S. Bldg. Entrance 281 261 230 209 245
' For sampling stations located less that 25 meters from the Nuclear Radiation Center, i
' Pool Room West Vent. TLD on roof, directly above reactor core.
BOLD print locations indicate areas that are readily accessible by the public..
Technical Specifications ALARA effluent releases in 3.12(2) specify annual radiation exposures at the j 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 radiation level for sampling points 400 meters or greater from the facility was 144 uR/ day, while the average total radiation level at the closest extended occupied area 930 meters away was 148 uR/ day.
This yields a ratio of 2.78%, indicating no significant exposure level above natural background.
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