ML22242A306
| ML22242A306 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 08/30/2022 |
| From: | Hines C Washington State Univ |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML22242A306 (16) | |
Text
NuclearScienceCenter
POBox641300,Pullman,WA991641300l5093358641lnsc.wsu.edulor.nsc@wsu.edu
August 30, 2022 Document Control Desk U.S. Nuclear Regulatory Commission Washington DC, 20555
Reference:
Washington State University Modified TRIGA Reactor License No. R-76; Docket No.50-027
Subject:
2022 Annual Report for the WSU Nuclear Science Center The annual report for the WSU reactor facility is hereby submitted. The report covers the operating period from July 1, 2021 through June 30, 2022.
Respectfully Submitted, C. Corey Hines Director Enclosure cc:
Hillary Bennett, Reactor Supervisor, Nuclear Science Center WA Department of Health, Office of Radiation Protection
ANNUAL OPERATIONS REPORT 2022 WASHINGTON STATE UNIVERSITY TRIGA REACTOR FACILITY LICENSE R-76 FOR THE REPORTING PERIOD JULY 1, 2021 TO JUNE 30, 2022 NUCLEAR SCIENCE CENTER l Washington State University, Pullman, WA
2022 Annual Report Washington State University Nuclear Science Center TABLE OF CONTENTS
- 1.
NARRATIVE
SUMMARY
OF OPERATION FOR FISCAL YEAR 2022................ 2
- 2.
ENERGY AND CUMULATIVE OUTPUT............................................................... 2
- 3.
EMERGENCY SHUTDOWNS AND INADVERTENT SCRAMS........................... 3
- 4.
MAJOR MAINTENANCE....................................................................................... 3
- 5.
CHANGES, TESTS, AND EXPERIMENTS PERFORMED UNDER 10 CFR 50.59 CRITERIA.............................................................................................................. 4
- 6.
RADIOACTIVE EFFLUENT DISCHARGES.......................................................... 5
- 7.
PERSONNEL AND VISITOR RADIATION DOSES.............................................. 6
- 8.
REACTOR FACILITY RADIATION AND CONTAMINATION LEVELS................. 8
- 9.
ENVIRONMENTAL MONITORING PROGRAM................................................. 11
2022 Annual Report Washington State University Nuclear Science Center Page 2 of 14
- 1.
Narrative Summary of Operation for Fiscal Year 2022 A.
Operating Experience Core 35A has accumulated 14,297 MWH from beginning of life (BOL) through June 30, 2022. During the reporting period of July 1, 2021 to June 30, 2022, a total of 1196 samples were irradiated, for 6149 user-hours. Additionally, 9 pulses greater than $1.00 of reactivity addition were performed during the reporting period. The quarterly operations summaries are shown in Table I.
B.
Changes in Facility Design, Performance Characteristics, and Operating Procedures Related to Reactor Safety.
No changes in facility design, performance characteristics, or operating procedures related to reactor safety were made.
C.
Results of Surveillance Tests and Requirements surveillance tests and requirements were performed and completed within the prescribed time period.
- 2.
Energy and Cumulative Output The quarterly operations summaries are given in Table I. The cumulative energy output since the 1967 TRIGA fuel core was put into service is 1,825 megawatt days (MWD). The mixed Standard Fuel and 30/20 LEU Fuel Core 35A installed in 2008 has accumulated 595 MWD.
Table I.
Fiscal Year 2022 Summary of Reactor Operation1 Q3 2021 Q4 2021 Q1 2022 Q2 2022 Totals Hours of Operation 256 188 94 446 985 Megawatt Hours 200 133 68 361 761 Sample Irradiations 104 44 31 83 262 Samples 539 198 111 348 1196 External Irradiations 21 16 13 31 81 Pulses > $1.00 1
2 0
6 9
User Hours 1524 1192 482 2951 6149 1 Number of samples and sample irradiations do not include external client irradiations. User hours denotes the total user hours, including external client irradiations.
2022 Annual Report Washington State University Nuclear Science Center Page 3 of 14
- 3.
Emergency Shutdowns and Inadvertent Scrams During the reporting period, there were no emergency shutdowns.
The dates and causes of the eight inadvertent scrams are listed in Table II. No scrams were due to exceeding the limiting safety system setting or safety limit.
Table II.
Inadvertent Scrams Date Description 7/13/2021 Electrical Short on the bridge caused a console fuse to blow.
12/7/2021 Trainee inadvertently took mode selector switch to test.
12/23/2021 Pulse High Power SCRAM when firing the pulse rod for pulse no. 1415. The cause was traced to the J4 connector on the pulse channel being lose. Fuel temp was monitored and did not exceed the limiting safety system setting or safety limit.
3/4/2022 Manual SCRAM initiated due to miscommunication about pool water conductivity reading to the SRO. Conductivity was within technical specification limits.
3/10/2022 Linear High-Power Scram caused during power reduction, RO lowered power to ~1kW, as read on the 10kW scale of the NMP-1000 Channel. RO pressed 1kW range button, then auto range, which caused the channel reading to spike and initiated the high-power scram. TS maximum licensed power level was not exceeded, and fuel temperature was observed to stay within normal operating range as the SCRAM was caused by exceeding the 120% SCRAM setpoint of the lowest scale on the channel and not the 1MW scale.
4/12/2022 Manual scram due to RO dropping a tool in the east pool. The tool did not go near the reactor core.
4/29/2022 A trainee pulled an experiment in C8 while at 1 MW, causing a Pulse High Power SCRAM. TS maximum licensed power level was not exceeded, and fuel temperature was observed to stay within normal operating range.
6/15/2022 Pulse High Power SCRAM when firing the pulse rod for pulse no. 1421. Power levels and fuel temperature were monitored and did not exceed the tech spec values. Connections were checked and the problem could not be replicated.
- 4.
Major Maintenance Although they are not part of routine preventative maintenance, the below listed items were performed.
9/15/2021: Flow rate meter for the purification loop was not reading properly. It was replaced with one of the same make and model.
11/02/2021: The Bridge Speed controller was found to have a failing relay. It was replaced with a like-for-like part. The maximum speed was set to the required 1Ft/8Sec.
12/9/2022: The Lovejoy connector on the secondary pump for the cooling system failed and was replaced.
2022 Annual Report Washington State University Nuclear Science Center Page 4 of 14 12/16/2022: The east gutter inlet valve was found to be inoperable and was replaced with a new 316 stainless steel ball valve. The west gutter inlet valve was also replaced.
1/17/2022: The valve on the west sump was replaced with a stainless steel ball valve and the flange on the pool return hose was replaced with the proper connecting part for the purpose.
From 1/10/2022 to 2/23/2022 the reactor pool liner was replaced according to 50.59-109-2022.
2/3/2022: An air leak was found in the line for the pulse rod air supply. The copper piping where it connected to the air hose was damaged and could not be repaired.
The air hose was hooked directly into the regulator.
2/28/2022: The lower limit switch did not actuate when the pulse rod was air scrammed during the checkout but would when the rod was lowered with the drive. The connecting rod was found to be rubbing against the inside of the hold down tube and the system was realigned and lubricated.
3/28/2022: The east sump valve was replaced with a stainless-steel ball valve.
6/1/2022: The readout for control element 5 was found to be reading one inch when fully inserted. The chain driven mechanism was found to have skipped and was re-zeroed.
6/24/2022: The EGM amplifier failed and was replaced with a like for like part. The amplifier settings were set based on the previous amplifier settings and then adjusted using the method in the manual. The EGM was then calibrated as per procedure.
- 5.
Changes, Tests, and Experiments Performed Under 10 CFR 50.59 Criteria A total of three (3) proposed changes to the facility were reviewed during the 2021-2022 year. All of the proposals were screened with the 10 CFR 50.59 requirements and found to screen out, thus allowing the changes to be made. The following changes were made to the facility under 50.59 criteria:
- 1) The east and west pool gutter valves were replaced with 316 stainless steel ball valves. The previously installed valves were not fit for the purpose, installed backwards, and the east one had failed closed.
- 2) The east and west pool sump valves as well as the flange for the return hose were replaced with 316 stainless steel replacements. This was an upgrade over previously installed parts.
- 3) The reactor pool liner was replaced with an industry standard liner: InstaCote SE FR polyurea coating system. The pool was drained one half at a time for the replacement.
2022 Annual Report Washington State University Nuclear Science Center Page 5 of 14
- 6.
Radioactive Effluent Discharges A.
Radioactive Liquid Effluent Releases The liquid effluent releases for the facility during the reporting period are provided in Table III.
Table III.
Monthly Liquid Effluent Releases Month Volume (gallons)
July 2021 0
August 0
September 0
October 0
November 0
December 0
January 2022 280 February 0
March 4290 April 0
May 4728 June 0
Approximately 9298 gallons of liquid effluents were released from the storage tank during the reporting period. Prior to discharge, a sample of the liquid in the tank was analyzed using gamma spectroscopy and liquid scintillation counting. The January gamma spectroscopy report indicated an activity of 0.12
µCi. The two March gamma spectroscopy reports indicated an activity of 0.17
µCi and 0.76 µCi. The May gamma spectroscopy report indicated an activity of 0.09 µCi. A total of activity of 1.14 µCi was released as liquid effluent during the reporting period.
B.
Radioactive Gaseous Effluent Release During the reporting period, no emission of a measurable quantity of gaseous or particulate material with a half-life greater than eight days was detected. The measured argon-41 out of the common exhaust stack did not exceed 20% of the effluent release limit. A total of 2.24 Ci of argon-41 was released, with an average argon-41 concentration of 1.13 x 10-10 µCi/mL of air, after environmental dilution. The argon-41 release and the pool water analysis is used in the 2022 Annual Report for Radioactive Air Emission License (RAEL-004), stack number 7. Per COMPLY v1.7, the reactor facility (stack 7) complies at level 4 with an effective dose equivalent of 3.1 x 10-3 mrem/yr. The monthly releases from Ar-41 are summarized in Table IV.
2022 Annual Report Washington State University Nuclear Science Center Page 6 of 14 Table IV.
Monthly Argon-41 Releases2 Month Quantity (Ci)
Conc. After Dilution (µCi/mL)
% of DAC Limit July 2021 3.2E-01 2.0E-10 6.3E-03 August 8.2E-02 4.9E-11 1.6E-03 September 2.3E-01 1.4E-10 4.7E-03 October 2.9E-01 1.7E-10 5.8E-03 November 1.5E-01 9.2E-11 3.1E-03 December 1.6E-01 9.7E-11 3.2E-03 January 2022 1.7E-01 1.0E-10 3.4E-03 February 7.4E-02 4.7E-11 1.6E-03 March 1.0E-01 6.0E-11 2.0E-03 April 2.1E-01 1.3E-10 4.3E-03 May 2.5E-01 1.5E-10 4.9E-03 June 2.0E-01 1.2E-10 4.0E-03 C.
Radioactive Solid Waste Disposal During the reporting period, 1.59E+02 mCi in 10 cubic feet of non-compacted solid waste was transferred to the WSU Radiation Safety Office for packaging and disposal.
- 7.
Personnel and Visitor Radiation Doses The quarterly doses of the WSU Nuclear Science Center reactor staff and experimenters are given in Table V. The maximum quarterly dose to a reactor staff member was 92 mrem, whole body. A total of 667 individual persons visited the Nuclear Science Center during the reporting period, of which 335 entered a controlled access area (CAA).3 A total of 14 group tours, consisting of 75 individuals, visited the center during the reporting period, also entering a CAA. All but one of the doses were less than or equal to 0.2 mrem as determined by digital pocket dosimeters. The one outlier was a visitor who received a total dose of 0.5 mrem during an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
2 Quantity released based on 4500 CFM effluent of ventilation system in AUTO mode of operation. Concentration after dilution is based on 10 CFR 20 effluent release limit of 1.0 x 10-8 µCi/mL for Ar-41 (Table 2, Col.1), and a dilution factor of 3.4 x 10-3 (WSU Technical Specifications 3.5.2). DAC limits are based on 10 CFR 20 derived air concentration limit of 3.0 x 10-6 µCi/mL for Ar-41 (Table 1, Col. 3) and a dilution factor of 3.4 x 10-3.
3 A controlled access area is an area in the building where radioactive materials are used or stored and is a part of the licensed reactor facility.
2022 Annual Report Washington State University Nuclear Science Center Page 7 of 14 Table V.
Quarterly Reactor and Experimenter Staff Dose4 (mrem)
Badge No.
Q3 2021 Q4 2021 Q1 2022 Q2 2022 706 18 30 24 22 1330 19 25 25 1204 22 20 10921 92 28 22 55 12176 48 29 23 23 1368 23 24 23 1360 18 24 21 705 37 8
28 1352 18 23 1340 26 26 27 1222 22 1401 10 11975 62 42 40 29 1428 8
33 1335 19 29 28 1327 20 28 24 12216 30 28 24 9
3150 5
3151 5
1278 16 9
701 34 29 42 45 1160 27 25 19 22 11937 41 1203 21 12 12212 28 30 38 26 8141 28 28 26 23 698 63 51 18 47 1166 38 27 24 6145 5
12207 39 28 25 10 704 54 31 24 39 3135 12 3149 5
1206 21 22 703 28 25 23 9
1329 19 28 21 12030 75 28 1282 16 4 -- denotes data not available either due to departure from the facility or new personnel starting at the facility. An M denotes that the dosimeter reading was less than or equal to the background radiation level for that quarter.
2022 Annual Report Washington State University Nuclear Science Center Page 8 of 14 11965 70 49 28 1207 25 12 1397 11 1400 5
1399 2
1328 19 27 26
- 8.
Reactor Facility Radiation and Contamination Levels The limit of quantification (LOQ) for building removable contamination determination survey samples as measured by liquid scintillation assay is 9.09 x 10-8 Ci/cm2; the survey sample data that was collected for removable contamination determination were averaged over one year. Routine building surveys showed average levels of removable activity to be less than the LOQ for all non-CAAs save for the Rm. 101 Shipping Bench, which was 9.4 x 10-8 uCi/cm2.
2022 Annual Report Washington State University Nuclear Science Center Page 9 of 14 Table VI.
Average Removable Contamination for Weekly Monitoring in CAAs and Non-CAAs5 Location Measured Activity Above LOQ (µCi/cm2) 201B M
201A M
201 Reactor Bridge Steps M
201 Sample Drop Tube M
201 Reactor Bridge South M
201 Reactor Bridge North M
201 Experimenter Platform 9.6E-08 201 Laboratory Benches M
201 Floor South M
201-C Heat Exchanger Floor M
201 Floor North M
106 Ion Exchanger Pit M
101-A Purification Pump Pit M
101 Doorway M
101 Sample Preparation Bench M
101 Sample Drop Hood #2 M
101 Hood #1 M
101 Hood #2 M
101 Hood #3 M
101 Hood #4 M
101 Shipment Bench 9.4E-08 RAM Storage Safe M
101 Island M
101 North lab Bench M
B21 Panoramic Irradiator M
B21 Floor M
2 South Floor M
2 Thermal Column M
2 Thermal Column Floor M
2 North Floor M
2 Cave Floor West M
2 Cave Floor East M
The results for the routine area radiation surveys of the building in CAAs and non-CAAs are given in Table VII. The highest average dose rate for a single location in a CAA was 24.84 mrem/hr, which occurred in Room 2 East Cave. This value is less than the limit for CAAs. The lowest average dose rate in a CAA was 0.04 mrem/hr (a 5 Bolded text indicates a non-CAA. Regular text indicates a CAA. M indicates the value is below the LOQ value of 9.09 x 10-8 Ci/cm2.
2022 Annual Report Washington State University Nuclear Science Center Page 10 of 14 level considered background), which occurred in Room 201A and Room 201C HX.
The average dose rate in the radiochemistry sample hoods (a non-CAA) was 0.05 mrem/hr. The East and West cave are secured storage areas that are designed to house radioactive sources, and provide shielding. The space is posted as a high radiation area. Personnel do not typically work in this area and it is locked when not in use.
Table VII.
Average Radiation Dose Rates for Weekly Monitoring in CAAs and Non CAAs6 Location Average Dose Rate (mrem/hr)
Room 201 B 0.05 Room 201 A 0.04 Room 201 Bridge 0.48 Room 201 Benches 0.12 Room 201 South 0.77 Room 201 East 0.43 Room 201 C Heat Exchanger 0.04 Room 201 North 0.19 Room 106 Ion Exchanger Pit 0.98 Room 101 A Purification Pit 0.62 Sample Storage 0.15 Room 101 Doorway 0.04 Room 101 Sample Prep Bench 0.04 Room 101 Sample Drop Hood 0.05 Room 101 Shipping Bench 0.05 Room 101 Hood 1 0.05 Room 101 Hood 2 0.08 Room 101 Hood 3 0.04 Room 101 Hood 4 0.04 Room B21 Panoramic Irradiator 0.04 Room 2 South 0.18 Room 2 Thermal Column 0.05 Room 2 North 0.25 Room 2 West Cave 2.26 Room 2 East Cave 24.84 6 Bolded text indicates a non-CAA. Regular text indicates a CAA. M indicates the value is below the LOQ value of 9.09 x 10-8 Ci/cm2.
2022 Annual Report Washington State University Nuclear Science Center Page 11 of 14
- 9.
Environmental Monitoring Program The environmental monitoring program is used to determine the offsite background radiation levels; thermoluminescent dosimeters (TLDs) are used to make the measurements. The offsite radiation monitoring program is required by the Technical Specifications. The TLDs that are used for offsite monitoring are designated as TLD numbers 3, 7, 9, 15 through 35, and 39 through 44. The average background radiation level is then compared to the nearest occupied dwelling.
Average quarterly dose rates for offsite locations are listed in Table VIII and are used to calculate the Technical Specification threshold of 20% above the background radiation level and compared to the limiting values which are listed in Table XI. The average environmental radiation levels for the closest offsite point of extended occupancy is listed in Table X. Table IX shows the quarterly environmental radiation levels for those TLDs located at onsite locations. The onsite locations are not required to be compared to background radiation levels.
The closest offsite points of extended occupancy are compared in Figure 1 to both the background radiation levels and the 20% above background radiation levels. The ALARA effluent release limits in Technical Specification 3.5.2(3) specify that annual radiation exposure due to reactor operation, at the closest offsite extended occupancy, shall not, on an annual basis, exceed the average offsite background radiation by more than 20%. For the reporting period, the average background radiation dose rate for off-site locations was 0.35 mrem/day, while the average radiation dose rate at the closest extended occupancy area 600 meters away was 0.32 mrem/day. This result indicates that no exposure level above normal background radiation were found, and that no dose levels exceeded Technical Specifications requirements for an offsite area of extended occupancy.
2022 Annual Report Washington State University Nuclear Science Center Page 12 of 14 Table VIII.
Environmental Radiation Levels at Offsite Locations7,8 Location Q3 2021 Q4 2021 Q1 2022 Q2 2022 Average Fence E of NSC 0.33 0.32 0.37 0.34 0.34 Fence, N of Rad Waste Shed 0.36 0.35 0.37 0.41 0.37 Fence directly N Rad Waste Shed 0.48 0.48 0.52 0.46 0.48 S NSC, on parking lot fence 0.30 0.30 0.35 0.29 0.31 Fence S Roundtop Dr, 10th pole W of pole C14 0.36 0.60 0.33 0.35 0.41 Telephone pole C12 0.37 0.34 0.35 0.35 0.36 Telephone pole near golf course gate 0.37 0.33 0.40 0.33 0.36 E across fairway on pine tree 0.36 0.32 0.37 0.34 0.35 Maple tree #54 along driving range 0.34 0.34 0.35 0.30 0.33 NW to fence uphill from driving range 0.36 0.33 0.36 0.34 0.35 Follow fence E to fence corner 0.37 0.34 0.37 0.37 0.36 S to lone spruce tree near water hazard 0.34 0.33 0.35 0.34 Roundtop hill park, NW fence corner 0.34 0.30 0.34 0.31 0.32 Deciduous tree edge of 18th green 0.36 0.34 0.39 0.37 0.37 6ft pine tree, 3rd W down cart path from clubhouse 0.36 0.33 0.38 0.36 0.36 3rd to last tree after gap in same line of trees 0.35 0.29 0.32 0.30 0.31 SW to fence along path near 2nd to last tee box at bottom hill 0.37 0.33 0.37 0.38 0.36 Follow fence partway up hill after fence turns S 0.36 0.31 0.34 0.32 0.33 Follow fence, 15th pole E after fence turns W 0.36 0.33 0.33 0.35 0.34 Follow fence about halfway between last TLD and corner 0.39 0.34 0.36 0.36 0.36 Largest bush S of NSC 0.38 0.35 0.34 0.34 0.35 2nd fence S NSC, W end at gate 0.33 0.31 0.33 0.30 0.32 S Fairway Rd, 1st light post on right 0.37 0.33 0.35 0.32 0.34 S Fairway Rd, 2nd light post on right 0.35 0.32 0.35 0.36 0.35 Ellis Way and Hog Lane sign 0.36 0.33 0.33 0.34 0.34 Bottom of radio antenna hill, fence next to shrub left of gate 0.37 0.34 0.34 0.32 0.34 3rd fence S of NSC, SE corner, cow pasture 0.37 0.38 0.33 0.32 0.35 Airport fence W end runway at gate 0.35 0.33 0.35 0.36 0.35 Fence/entry bar E of Jewett Observatory 0.34 0.29 0.35 0.31 0.32 Railing at Terrell Mall / Library 0.29 0.29 7 Offsite defined by the Technical Specification 1.0 and 5.1.1 as any location, which is outside the site boundary. The --
indicates a TLD which was missing.
8 Dose rate in mrem/day.
2022 Annual Report Washington State University Nuclear Science Center Page 13 of 14 Table IX.
Environmental Radiation Levels at Onsite Locations9,10 Location Q3 2021 Q4 2021 Q1 2022 Q2 2022 Average E lower loading dock 0.33 0.31 0.34 0.34 0.33 Pool room truck door fence S end 0.48 0.39 0.47 0.48 0.45 Pool room truck door fence N end 0.52 0.39 0.53 0.63 0.52 E wall rad waste shed 0.36 0.42 0.46 0.48 0.43 N wall rad waste shed 0.44 0.45 0.67 0.55 0.53 Cooling tower fence, NE corner 0.59 0.50 0.57 0.55 0.55 Room 101 window 0.41 0.34 0.45 0.46 0.42 Railing next to upper liquid waste tank 0.39 0.31 0.36 0.33 0.35 Room 2 truck door fence 0.35 0.35 0.37 0.35 0.36 Transformer vault vent louvers 0.37 0.37 0.39 0.38 0.37 NSC main entrance, light fixture 0.42 0.42 0.44 0.36 0.41 NSC roof, pool room vent stack 0.35 0.28 0.35 0.24 0.30 NSC roof, guide wire E end of building 0.34 0.36 0.35 0.28 0.33 NSC roof, E pool room vent support leg 0.57 0.49 0.47 0.63 0.54 NSC roof, air conditioning support leg 0.34 0.26 0.36 0.29 0.31 NSC roof, W pool room vent support leg 0.63 0.46 0.50 0.69 0.57 Table X.
Environmental Radiation Levels for the Closest Offsite Point of Extended Occupancy10 Location Q3 2021 Q4 2021 Q1 2022 Q2 2022 Average Apt complex C, gas meter 0.30 0.33 0.34 0.32 0.32 Apt complex B, gas meter 0.33 0.27 0.34 0.34 0.32 1st fence S apt complex A 0.34 0.29 0.32 0.32 0.32 Table XI.
Background Environmental Radiation Levels10 Description Q3 2021 Q4 2021 Q1 2022 Q2 2022 Average Background radiation levels 0.36 0.34 0.35 0.33 0.35 20% above background radiation levels 0.43 0.41 0.42 0.40 0.41 9 Onsite defined by the Technical Specification 1.0 and 5.1.1 as any location within the site boundary. The -- indicates a TLD which was missing.
10 Dose rate in mrem/day.
2022 Annual Report Washington State University Nuclear Science Center Page 14 of 14 Figure I:
Environmental radiation levels for the closest offsite point of extended occupancy radiation levels as compared to background radiation levels and 20% above background radiation levels.
0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 0.40 0.45 Q3 2021 Q4 2021 Q1 2022 Q2 2022 Average Dose Rate (mrem/day)
Quarter Apartment Complex A Apartment Complex B Apartment Complex C
Background
20% Above Background