ML24089A242
| ML24089A242 | |
| Person / Time | |
|---|---|
| Site: | Purdue University |
| Issue date: | 03/29/2024 |
| From: | Miller T Purdue University Research Reactor |
| To: | Cindy Montgomery Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML24089A242 (1) | |
Text
School of Nuclear Engineering l 516 Northwestern Ave l West Lafayette, IN, 47906 l 765-494-5739 l ne@purdue.edu l www.purdue.edu/NE March 29, 2024 Cindy Montgomery U.S. NRC One White Flint North 11555 Rockville Pike Rockville, MD 20852 RE:
Submission of 2023 Annual Report for PUR-1, Docket Number 50-182
Dear Ms. Montgomery:
Enclosed please find one copy of the Annual Report for the Purdue University Research Reactor, PUR-1, for the operating year 2023.
Should you have any questions or require further information, please contact me at 765.494.5764, or by e-mail at mill1833@purdue.edu.
I declare under penalty of perjury that the foregoing is true and correct. Executed on March 29, 2024.
- Regards, True Miller PUR-1, Reactor Supervisor
Page 2 of 7 REPORT ON REACTOR OPERATIONS For the Period January 1, 2023, to December 31, 2023 PURDUE UNIVERSITY REACTOR-1 (PUR-1)
Facility Docket No. 50-182 PURDUE UNIVERSITY West Lafayette, Indiana 47907 March 2024 Prepared by True Miller, Reactor Supervisor
Page 3 of 7
- 1. INTRODUCTION This report is submitted to meet the requirements set forth in the Technical Specifications of the Purdue University Reactor (PUR-1) and 10 CFR 50.59 for the period January 1, 2023, to December 31, 2023.
During the reporting period of 2023, multiple experiments and projects were performed, a moderate level of teaching activity and a high level of operator training was performed. No individuals obtained an RO license; however, 5 individuals took an RO exam and a sixth individual their SRO exam and were awaiting results at the end of this period.
There were 1711 visitors across 325 groups to the facility including Purdue facilities staff, students, general tours, and VIPs.
- 2. PLANT DESIGN AND OPERATIONAL CHANGES 2.1 Facility Design Changes No major facility design changes were performed in 2023. The water processing and operator console RAM both suffered a memory card failure and were repaired with like for like parts. No operations took place while these were out of operation. Additionally, the CAM malfunctioned and was sent in for repair and replacement of its background geiger detector. During this time a backup CAM, with the same functionality, was placed in the reactor room. Legacy experimental equipment was also removed from the pool which consisted of a detector holding device on a traversing platform which has not been in use for decades. Lastly, during operations on November 4th, the stainless-steel wire holding up the PuBe startup source broke, dropping the source to the bottom of the source tube.
The source was then retrieved, the stainless-steel wire replaced, like for like, and the source and source motor reinstalled.
2.2 Performance Characteristics The overall status of the PUR-1 facility was sustained satisfactorily during the reporting period.
The facility maintained all required surveillance. Monthly surveillances of process water showed no fission product contamination, thereby verifying fuel integrity.
Page 4 of 7 2.3 Changes in Operating Procedures Concerning Safety of Facility Operations No new operating procedures concerning the safety of the facility operations were enacted during this period.
2.4 Results of Surveillance Tests and Inspections 2.4.1 Reactivity Limits The reactivity worth measurements and visual inspection of the control rods were last performed during February of 2022 and are planned for February of 2024.
During this time control rod maintenance and control rod worth measurements were performed. The rod worths of both SS1 and SS2 matched previous historical data satisfactorily and ensures satisfactory shutdown and reactivity limits. The rod drop times were measured May 11th of 2023; both were well under the required 1 second time limit.
2.4.2 Reactor Safety Systems The reactor safety systems were checked prior to every startup as is required by the prestart procedure.
2.4.3 Primary Coolant System During the checks the conductivity of the primary coolant was measured, and the values never exceeded 3 micromhos/cm.
Monthly samples of the primary coolant were collected and analyzed by personnel from Radiological and Environmental Management for gross alpha and beta activity. No activity which would indicate failure of the fuel plates was identified in the samples.
2.4.4 Confinement No operation or fuel handling was performed while the air pressure was below -
0.05 inches of water.
Page 5 of 7 The air system isolation was tested on both January 13th and July 17th, 2023, correct operation of the louvres was observed for both inspections. The Condensate Valve was also inspected at this time and operated satisfactorily.
2.4.5 Experiments Three experiments were performed in 2023. The first experiment was the irradiation of pet food samples for Hills Pet Nutrition INC to determine the iodine concentration of their feedstock. The second experiment was the irradiation of several microchips to determine the effects of combined gamma and neutron irradiation on their performance. The third experiment performed in 2023 was the installation and testing of an axial moderator displacement rod used in testing of PUR-1s digital twin and cybersecurity research.
2.5 Changes, Tests and Experiments Requiring Commission Authorization No changes were made to the facility Technical Specification and no tests or experiments were performed in 2023 which required commission authorization.
2.6 Changes in Facility Staff PUR-1 Level-1: Interim Dean of Engineering Dr. Mark Lundstrom, stepped down from his role as Interim Dean on April 1, 2023 Dr. Arvind Raman is serving as Dean as of April 1, 2023, and is the acting Level-1 of PUR-1
- 3. POWER GENERATION There were 107 total runs in 2023 which generated an indicated value of 467.28 kWh of thermal heat. The total operations time was 209.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> giving an average indicated power level of 2227.26 Watts.
The total core energy produced is approximately 1225.22 kWh since current fuel loading installed in 2007.
Page 6 of 7
- 4. UNSCHEDULED SHUTDOWNS There were three unscheduled shutdowns in 2023. All three unscheduled shutdowns were due to false electrical signals from the PLC to the RCS caused by loose wire connections. A high-power SCRAM would be indicated on the console but none of the four channels indicated a power above or even near 10kW, additionally no indication of a high-power SCRAM were indicated on the console confirming it to be a false signal from the PLC.
- 5. MAINTENANCE The HEPA filter for the room supply and exhaust air was checked upon during normal maintenance checks quarterly. Filters were replaced as needed.
The water processing and console RAM both had their memory units replaced. Following the reinstallation of the repaired RAMs the detectors were calibrated by REM staff and their alarm setpoints tested. The CAM was sent in for repairs and had its background Geiger detector replaced. The CAM was calibrated by REM after reinstallation and its alarm checkpoints tested.
The PuBe startup source wire broke during operations and was disassembled, replaced with a new wire, and reinstalled.
- 6. RADIOACTIVE EFFLUENT RELEASES a) Liquid Effluent No liquid radioactive effluent was released to the environs.
b) Airborne Waste Other than the Ar-41 amounts listed below, no measurable amount of radioactive effluent was released to the environs beyond our effective control, as measured at or prior to the point of such release.
Month Ar-41 Released (uCi)
January 0.0 February 166.7 March 45.4 April 0.0 May 0.0 June 143.8 July 16.9 August 22.5 September 738.9 October 201.6 November 53.8
Page 7 of 7 December 178.9 Total 1568.4 c) Solid Waste On 11/21/2023, Purdues REM department picked up one 40-gallon trash bag (5.35 cubic feet) of low-level solid waste from the designated blue waste barrel. This waste contained potentially contaminated gloves, paper, tape, and other disposable lab materials. Radiation measurements of the waste showed no discernable radiation levels above background. The total activity disposed of was determined to be 10 uCi of Co-60.
- 7. OCCUPATIONAL PERSONNEL RADIATION EXPOSURE No radiation exposures greater than 25% of the appropriate limits of 10 CFR 20 were received during the reporting period.
- 8. ENVIRONMENTAL SURVEYS PERFORMED OUTSIDE THE FACILITY There were no additional environmental surveys performed outside the facility beyond license and regulatory requirements.