ML102780397
| ML102780397 | |
| Person / Time | |
|---|---|
| Site: | University of Maryland |
| Issue date: | 09/29/2010 |
| From: | Al-Sheikhly M Univ of Maryland - College Park |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML102780397 (20) | |
Text
UNIVERSITY OF
(' Building 090 College Park, Maryland 20742-2115 301.405.5207 TEL 301.314.2029 FAX DEPARTMENT OF MATERIALS SCIENCE AND ENGINEERING September 29, 2010 Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555-0001
Reference:
Annual Report: July 1, 2009 - June 30, 2010 for the Maryland University Training Reactor, Docket No. 50-166, License No. R-70 (TAC NO. ME 1592), University of Maryland Enclosed please find the University of Maryland's Annual Report for the period beginning July 1, 2009 and ending June 30, 2010 for the Maryland University Training Reactor, Docket No. 50-166, License No. R-70.
If there are questions about the information submitted, please write to me at:
Department of Materials Science and Engineering, University of Maryland, College Park, MD 20742-2115 or email me at mohamad@umd.edu. I would appreciate it if you would copy Prof. Robert Briber on any such correspondence: Department of Materials Science and Engineering, University of Maryland, College Park, MD 20742-2115; rbriber@umd.edu.
I declare under penalty of perjury that the foregoing response is true and correct.
Sincerely, Mohamad AI-Sheikhly Professor and Director Maryland University Training Reactor Enclosure cc: Robert Briber IVo~D
ANNUAL REPORT: July 1, 2009 - June 30, 2010 FOR THE MARYLAND UNIVERSITY TRAINING REACTOR License No. R-70 Docket No. 50-166 Department of Materials and Nuclear Engineering A. James Clark School of Engineering University of Maryland, College Park College Park, MD 20742-2115
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT TABLE OF CONTENTS TA B LE O F C O N TEN TS ..................................................................................................... 1 I. INTRODUCTION ................................................. 2 II. R EA C TOR U SA GE ........................................................................................................ 3 III. SURVEILLANCE TESTS AND INSPECTIONS ........................................................ 4 IV. CHANGES TO THE FACILITY ................................................................................... 5 V. ENVIRONMENTAL SURVEYS OF SURROUNDING AREAS ................ 6 VI. RADIOACTIVE RELEASE AND DISCHARGE TO THE ENVIRONMENT ............ 7 VII. ALARA REVIEW FOR FACLITY PERSONNEL AND VISITOR EXPOSURE ..... 8 VIII. UNSCHEDULED REACTOR SHUTDOWN/REPORTABLE OCCURENCES ...... 9 IX . SPECIA L EX PERIM EN TS ........................................................................................... 10
- x. CHANGES IN FACLITY STAFF ...................................................... 11......
I A. APPENDIX A: EPA COMPLIANCE .......................................................................... 12 B. APPENDIX B: CONTAMINATION EVENT EXECUTIVE
SUMMARY
................ 16 1
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT I. INTRODUCTION The University of Maryland Training Reactor (MUTR) is an open-pool type, TRIGA fueled reactor licensed for operation at 250 kW thermal power. The core is cooled by natural convection of the pool water with auxiliary cooling provided for protection of the filters and ion exchange equipment associated with reactor support piping.
The MUTR is used for academic instructions and operator training, performance of neutron and gamma irradiations, neutron activation analysis experiments, and tours and demonstrations for groups internal and external to the campus as well as for visiting nuclear power plant trainees.
2
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT II. REACTOR USEAGE During the past year the MUTR operated for a total of 66 runs (Run Numbers 3989 - 4054),
which are categorized below:
Operator Training/Requalification* 25 runs Tours, Labs & Demonstrations** 13 runs Calibration, Maintenance, and Surveillance 14 runs Irradiations and Activations 21 runs
- Note: Some runs involved training and surveillance and may be counted in both categories.
- Note: Some of the runs in the Tours, Labs & Demonstrations category consisted of operator training. They are not included in the training category.
To perform these runs the core produced 25.164 MWh (kWh meter change from 259881 kWh to 285045 kWh), with a corresponding burnup of 1.43 Grams of U-235.
3
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT III. SURVEILLANCE TESTS AND INSPECTIONS All required surveillance tests and inspections were performed at the specified intervals. The required surveillance items for this reporting period include:
Water sample tests Air sample tests Radiation surveys Control rod drop test RAM calibration SNM inventories ALARA review In addition to the above surveillance items, the following maintenance operations were performed on the indicated dates:
9/8/09 Dri-rite baked (Run 4001) 12/6/09 Replaced primary resin 12/15/09 Dri-rite replaced (Run 4014) 3/23/10 Dri-rite baked (Run 4032) 4/20/10 Replaced make-up system resin 6.28/10 Dri-rite replaced (Run 4054)
Additional minor maintenance, such as light bulb replacement and fine tuning of equipment, was performed as necessary.
4
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT IV. CHANGES TO FACILITY There were no significant changes to the Facility during this reporting period.
5
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT V. ENVIRONMENTAL SURVEYS OF SURROUNDING AREAS All continuous monitoring for this year was accomplished using fixed-mounted film badges throughout the interior of the reactor building itself. These badges recorded the following exposures:
Monitor Location Dose (mrem) 1 Control Room 104 2 Pool Surface 1188 3 Hot Room 524 4 Prep Room 236 5 S. Wall Upper 64 6 S. Wall Lower 95 7 E. Wall Lower 176 8 Pump Room 295 9 N. Wall Lower 1563 10 W. Wall Lower 458 6
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT VI. RADIOACTIVE RELEASE AND DISCHARGE TO THE ENVIRONMENT The Reactor Storage Sump was not discharged during this reporting period.
The only release from the MUTR consists of Ar-4 1. From Section 11 of the SER for the MUTR, a 30.0 MWh operation year would result in the generation of 100 mCi of Ar-41 for the entire year from the reactor pool tank. For this operational year, a combined 83.9 mCi of Ar-41 was released to the reactor building. This value was used in the EPA program COMPLY. The MUTR meets the EPA level 2 compliance for airborne release of radioactive materials. A copy of the output for the EPA computer program "COMPLY" is appended with this report. The MUTR was operated for a total of 8.2 MWh with the transport hose of the pneumatic transfer system removed. Measurements conducted by the Radiation Safety Office with the hose both connected and disconnected demonstrated that the removal of the hose contributed no measurable levels above those that exist with the system intact.
7
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT VII. ALARA REVIEW FOR FACILITY PERSONNEL AND VISTOR EXPOSURE A review of exposure records and all facility operations were performed by facility management as part of the annual ALARA audit. For this reporting period, all badged personnel and students received doses less than five per-cent of their annual dose limit.
The Pocket Dosimeters recorded minimal exposure for all guests and service personnel.
Calibrations of these self-reading dosimeters were performed on an annual basis by the University of Maryland's Radiation Safety Office.
On June 3, 2019, an experimental failure resulted in a minor contamination situation on the reactor bridge. The reactor was shut down and secure at the time of the incident. Theexecutive summary describing the event and subsequent actions and decontaminations is attached to this document as Appendix B.
8
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT VIII. UNSCHEDULED SHUTDOWNS/REPORATBLE OCCURRENCES There were two unscheduled shutdowns during this period. During operation numbers 4027 and 4028 conducted on February 19th and 2 2 nd, 2010 intermittent noise spikes resulted in two period scrams.
There were no reportable occurrences during this reporting period.
9
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT IX. SPECIAL EXPERIMENTS There were no special experiments performed during this reporting'period.
10
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT X. CHANGES IN FACILITY STAFF There were significant changes to staffing during this reporting period. The Radiation Safety Officer was replaced in January 2010. One SRO and one RO relinquished their licenses bringing the total to two Senior Operators and two Operators.
I1
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT APPENDIX A: EPA COMPLIANCE Below is the output from the EPA program COMPLY for the Ar-41 release from the MUTR:
COMPLY: Vl.5d. 9/28/10 3:02 40 CFR Part 61 National Emission Standards for Hazardous Air Pollutants REPORT ON COMPLIANCE WITH THE CLEAN AIR ACT LIMITS FOR RADIONUCLIDE EMISSIONS FROM THE COMPLY CODE, VERSION 1.5d Prepared by:
University of Maryland, College Park Maryland University Training Reactor Building 090, Stadium Drive Mohamad Al-Sheikhly mohamad@umd.edu (301) 405-5214 Prepared for:
U.S. Environmental Protection Agency Office of Radiation Programs Washington, D.C. 20460 12
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT COMPLY: Vl.5d. 9/28/10 3:02 FY 2010 Argon Calculations SCREENING LEVEL 1 DATA ENTERED:
Effluent concentration limits used.
DATA ENTERED FOR STACK 1:
CONCENTRATION Nuclide (curies/cu m)
AR-41 1.55E-05 DATA ENTERED FOR STACK 2:
CONCENTRATION Nuclide (curies/cu m)
AR-41 1.55E-05 NOTES:
Input parameters outside the "normal" range:
None.
RESULTS:
You are emitting 4560.0 times the allowable amount given in the concentration table.
- Failed at level 1.
13
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT COMPLY: Vl.5d. 9/28/10 3:02 FY 2010 Argon Calculations SCREENING LEVEL 2 DATA ENTERED:
I RELEASE RATES FOR STACK 1.
Release Rate Nuclide (curies/YEAR)
AR-41 1.550E-05 RELEASE RATES FOR STACK 2.
Release Rate Nuclide (curies/YEAR)
AR-41 1.550E-05 SITE DATA FOR STACK 1.
Release height 10 meters.
Building height 10 meters.
The source and receptor are on the same building.
Stack diameter 1.00 meters.
Distance from the source to the receptor is 1 mieters.
Building width 15 meters.
Default volumetric flow rate from the stack used (0.3 cu m/sec).
SITE DATA FOR STACK 2.
Release height 10 meters.
Building height 10 meters.
The source and receptor are on the same building.
Stack diameter 1.00 meters.
Distance from the source to the receptor is 1 Pneters.
Building width 15 meters.
14
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT COMPLY: Vl.5d. 9/28/10 3:02 Default volumetric flow rate from the stack used (0.3 cu m/sec)
Default mean wind speed used (2.0 m/sec).
NOTES:
Input parameters outside the "normal" range:
Receptor is unusually CLOSE.
RESULTS:
Effective dose equivalent: 2.0E-02 mrem/yr.
Comply at level 2.
This facility is in COMPLIANCE.
It may or may not be EXEMPT from reporting to the EPA.
You may contact your regional EPA office for more information.
- END OF COMPLIANCE REPORT
- 15
MARYLAND UNIVERSITY TRAINING REACTOR 2009-2010 ANNUAL OPERATING REPORT APPENDIX B: CONTAMINATION EVENT EXECUTIVE
SUMMARY
16
APPENDIX B UNIVERSITY OF 3115 Chesapeake Buidinig 338 MARYLAND CoEcgc Park, Maryland 20)742-3 133
.- 4i5,3t)60 TEL 301.114.9294 FAX DEPAR.MENT OF ENVIRONME.NTh/ SAFETY MEMO TO. Dr. Mohamad AI-Sheikhly, Director Radiation Facilities FROM: Mary 3.Dorman, Radiation Safety Officerw DATE: September 28, 2010 RE: Executive Summary - Radioactive Material Spill June 3, 2010 On June 3, 2010 a spill involving a radioactive material occurred on the bridge of the Maryland University Training Reactor (MUTR). At the time of the spill the reactor was off and secure. The Senior Reactor Operator (SRO}, a graduate student and a Health Physicist (HP) from the Radiation Safety Office were present on the bridge at the time of the incident, The spill occurred as graphite samples were being removed from a heater apparatus following irradiation in the MUTR pneumatic transfer system, Prior to removal from the pneumatic transfer system, the samples had sat in the pool for over one week post irradiation to allow the short lived radioactive material to decay and reduce the potential external radiation fields to the SRO performing the operation.
As the heater was being opened to remove the graphite samples, a polyethylene tie holding together wires, tubing and two aluminum "wings' connected to the heater, broke. This caused a small quantity of gray powder to become airborne. Upon investigation, it was concluded that the powder was from a section of PVC tubing attached to the heater apparatus that degraded during the irradiation in the reactor. The potential for degradation and powder was not anticipated by the Individuals involved. Gamma spectroscopy of samples indicated the primary activation product involved in this spill to be Antimony-124. The materials involved were later reassessed for a half-life review; results confirm the 60.2 day half-life of Antimony-.24.
The individuals immediately vacated the facility and incident response actions were initiated. Assessment of personnel exposures was the priority. All personnel exposures resulting from this incident were determined to be below the Nuclear Regulatory Commission (NRC) annual limits for occupational exposure.
initial surveys indicated one individual had skin contamination present on the arm and back of the head.
Decontamination was successful. The shallow dose for this individual was calculated using Varskin Mod 3.
Based upon a conservative estimate of activity, the maximum shallow dose was calculated to be 10 rem. The Radiation Safety Officer is working with the University's dosimetry vendor to ensure this calculated shallow dose is captured in the individual's permanent record. Surveys of the two additional individuals present on the bridge at the time of the spill, showed no personal contamination.
II Page
External dosimetry for the individuals involved was processed. Occupational radiation exposure recorded in the wear period of this incident is as follows:
Individual/Badge Type DDE (mrem) LDE (mrem)- SDE (rorem)
SRO Whole-Body *
- SRO Ring NA NA
- SRO Wrist NA NA
- HP Whole-Body *
- 20 Graduate Student Whole-Body 11 11 11
(*) Less than the minimum reporting limit of 10 mrrem.
Internal doses were assessed. Urine bioassays taken immediately and days after the spill showed no detectable radioactivity above background. To fully assess uptake of radioactive material, the three individuals involved in the incident received a whole-body scan at the Navy Dosimetry Center's In-vivo Counting Facility in Bethesda, Maryland. The report from the Department of the Navy, states "no radioactivity that could be distinguished from that found in nature was detected by the whole-body scan". The RSO consulted with a Certified Health Physicist at Dade Moeller & Associates for consultation and verification of the methodologies used to determine personnel exposures.
Surface contamination was identified in the immediate area of the spill. Low levels of contamination were found in areas where the grey powder had settled. The facility clean-up activities were managed by the Radiation Safety Officer. RSO Inc., with offices in Laurel, Maryland was hired to perform the decontamination.
The bridge and accessible surfaces throughout the facility were decontaminated to meet NRC Regulatory Guide 1.86 limits for release for unrestricted use.
A thorough discussion of the incident was held at a Reactor Safety Committee Meeting. The potential degradation of the PVC tubing was not anticipated by the individuals involved with the retrieval of the graphite samples from the heater apparatus. The Reactor Safety Committee concluded that an integrity analysis is required on the materials involved, if this experiment is to be performed again. Radiation Safety highlighted the need to be aware of, and institute contamination control techniques, whenever the potential for degradation or contamination exists.
In an effort to prevent a similar incident, at the Reactor Safety Committee meeting the RSO requested to re-review all experimental procedures performed at the MUTR. The RSO is working with the Facility Director to develop an outline to accomplish this project. The Reactor Director is also seeking a third-party consultant to review this incident and provide an analysis of the root-cause of this incident.
A full report for this investigation is on file at the University of Maryland's Radiation Safety Office. Question or comments should be directed to Mary J. Dorman, the Radiation Safety Officer at 301-314-8336 or mdormangumd.edu.
21 Page