ML15061A293
| ML15061A293 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 02/26/2014 |
| From: | Rhonda Butler, Fruits J Univ of Missouri - Columbia |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML15061A293 (45) | |
Text
UNIVERSITY of MISSOURI RESEARCH REACTOR CENTER February 26, 2014 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
REFERENCE:
Docket 50-186 University of Missouri-Columbia Research Reactor Amended Facility License R-103
SUBJECT:
University of Missouri Research Reactor 2014 Reactor Operations Annual Report Enclosed is a copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2014 through December 31, 2014.
This document is submitted to the U.S. Nuclear Regulatory Commission in accordance with the University of Missouri Research Reactor Technical Specification 6. l.h(4).
If you have any questions regarding the contents of this report, please contact John Fruits at FruitsJ@(missouri.edu or by calling (573) 882-5319.
ENDORSEMENT:
Sincerely, Reviewed and Approved John L. Fruits Ralph A. Butler, P.E.
Reactor Manager Director JLF/jlb Enclosure xc: Mr. Alexander Adams, U.S. NRC Mr. Johnny Eads, U.S. NRC 1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: www.murr.missouri.edu Fighting Cancer with Tomorrows Technology
UNIVERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2014 - December 31, 2014
UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2014 through December 31, 2014 Compiled by the Research Reactor Staff of MURR Submitted by:
Join L. Fruits Reactor Manager Reviewed and approved by:
Ralph A. Butler, PE Director
UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2014 through December 31, 2014 INTRODUCTION The University of Missouri Research Reactor (MURR) is a multi-disciplinary research and education facility providing a broad range of analytical, materials science and irradiation services to the research community and the commercial sector. Scientific programs include research in archaeometry, epidemiology, health physics, human and animal nutrition, nuclear medicine, radiation effects, radioisotope studies, radiotherapy, boron neutron capture therapy and nuclear engineering; and research techniques including neutron activation analysis, neutron and gamma-ray scattering and neutron interferometry. The heart of this facility is a pressurized, reflected, open pool-type, light water moderated and cooled, heterogeneous reactor designed for operation at a maximum steady-state power level of 10 Megawatts thermal - the highest powered university-operated research reactor in the United States.
The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2014. Included within this report are changes to MURR reactor operations and health physics procedures, revisions to the Hazards Summary Report, facility modifications, new tests and experiments, reactor physics activities and environmental and health physics data.
This report is being submitted to the U.S. Nuclear Regulatory Commission (NRC) to meet the administrative requirements of MURR Technical Specification 6. l.h (4).
ACKNOWLEDGMENTS The success of MURR and these scientific programs is due to the dedication and hard work of many individuals and organizations. Included within this group are: the University administration; the governing officials of the State of Missouri; the Missouri State Highway Patrol; the City of Columbia Police Department; the Missouri University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our regulators; those who have provided funding including the Department of Energy (DOE) and the National Nuclear Security Administration (NNSA); Argonne National Laboratory (ANL); Idaho National Laboratory (INL); Sandia National Laboratories (SNL); the researchers; the students; the Columbia Fire Department; the Campus Facilities organization; members of the National Organization of Test, Research and Training Reactors (TRTR); and many others who have made, and will continue to make, key contributions to our overall success. To these individuals and organizations, the staff of MURR wishes to extend its fondest appreciation.
Some of the major facility projects that were supported by Reactor Operations during this past calendar year included (1) replacement of the beryllium reflector that surrounds the reactor core, (2) refurbishment of the Regulating Blade Drive Mechanism, (3) irradiating and processing multiple natural and low-enriched uranium (LEU) targets to determine the feasibility of producing molybdenum-99 using a variety of processing technologies, and (4) construction of an eastward expansion to the MURR Industrial Building (MIB), which provides additional laboratory space at MURR - 1,440 ft2 and 1,432 ft2 of net usable space i
on the grade and below grade levels, respectively. Beryllium reflector replacement is a planned evolution that is performed approximately every eight years and takes about seven to nine days to complete, including low power physics testing. During this time the necessary piping and equipment are disassembled, the old beryllium reflector is removed and the new one is inserted, nondestructive testing is performed on the primary coolant pressure vessel spool piece, and then all piping and equipment that was disassembled is once again reassembled. Additionally, in August 2006, MURR submitted a request to the NRC to renew Amended Facility License No. R-103. Significant efforts have already been placed in responding to the Requests for Additional Information and these efforts continued in this past year.
The facility continues to actively collaborate with the Reduced Enrichment for Research and Test Reactors (RERTR) Program and four other U.S. high-performance research and test reactor facilities that use highly-enriched uranium (HEU) fuel to find a suitable LEU fuel replacement. Although each one of the five high-performance reactors is responsible for its own feasibility and safety studies, regulatory interactions, fuel procurement and conversion, there are common interests and activities among all five reactors that will benefit from a coordinated, working-group effort. This past year, resources were focused on completing Phase 2 of the accident analyses for the proposed LEU conversion core. This included finalizing the Maximum Hypothetical, Loss of Coolant, Loss of Flow and Reactivity Insertion Accidents. Additionally, three MU students - two graduate and one PhD - assisted in the fuel conversion work this year. The two graduate students helped perform calculations for the Maximum Hypothetical and Fuel Handling Accidents; whereas, the PhD student assisted in determining the material property changes in the beryllium reflector as a result of a fuel conversion. One of the graduate students received a Master of Nuclear Engineering as a result of his work.
Reactor Operations Management also wishes to commend the three individuals who received their Reactor Operator certifications and the three individuals who received their Senior Reactor Operator certifications from the NRC. These individuals participated in a rigorous training program of classroom seminars, self-study and on-the-job training. The results of this training are confident, well-versed, decisive individuals capable of performing the duties of a licensed operator during normal and abnormal situations.
ii
TABLE OF CONTENTS Section Title PaEnes I. Reactor Operations Summary ............................................................... I-I through 9
- 11. M URR Procedures ................................................................................ H -1 through 7 A. Changes to Reactor Operations Procedures B. Changes to the MURR Site Emergency Procedures and Facility Emergency Procedures C. Changes to Health Physics Procedures, Byproduct Material Shipping Procedures, and Preparation of Byproduct Material for Shipping Procedures III. Revisions to the Hazards Summary Report .......................................... III-I through 4 IV. Plant and System M odifications ........................................................... IV-I through 4 V. New Tests and Experiments ................................................................. V-I through 2 VT. Special Nuclear Material and Reactor Physics Activities ................ VI-i VII. Radioactive Effluent ............................................................................. VII- 1 through 2 Table I - Sanitary Sewer Effluent Table 2 - Stack Effluent VIIl. Environmental Monitoring and Health Physics Surveys ...................... VII-1 through 6 Table I - Summary of Environmental Set 85 Table 2 - Summary of Environmental Set 86 Table 3 - Environmental TLD Summary Table 4 - Number of Facility Radiation and Contamination Surveys IX. Summary of Radiation Exposures to Facility Staff, Experimenters and Visitors ..................................................................................... IX -1
SECTION I REACTOR OPERATIONS
SUMMARY
January 1, 2014 through December 31, 2014 The following table and discussion summarizes reactor operations during the period from January 1, 2014 through December 31, 2014.
Month Full Power Hours Megawatt Days Full Power % of Total Full Power % of Time Scheduled')
January 678.53 282.95 91.2 102.1 February 604.78 252.19 90.0 100.8 March 497.15 207.57 66.8 96.6(2)
April 627.15 261.70 87.1 97.7 May 676.96 282.26 91.0 101.9 June 636.02 265.23 88.3 99.1 July 661.89 276.05 89.0 99.6 August 656.44 273.76 88.2 98.8 September 615.21 256.75 85.4 95.8 October 661.93 276.04 89.0 99.6 November 653.11 272.34 90.7 101.7 December 634.77 265.07 85.3 95.5 Total for 7603.94 3171.91 86.84 % 99.10 %
the Year Note 1: MURR is scheduled to average at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> of full power operation per week. Total time is the number of hours in the month listed or the year.
Note 2: The reactor was shut down for nine days in March for the scheduled replacement of the beryllium reflector.
This time is not included in the "Full Power % of Scheduled" operating time.
January 2014 The reactor operated continuously in January with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and one shutdown for operator training. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: flooding Beamport 'C' for maintenance on beamline instrumentation; replacing the Flux-trap Irradiation Reactivity Safety Trip device sensor switches and cabling; and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of Shim Blade, RTP-1 I(D)."
1-1
February 2014 The reactor operated continuously in February with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and three shutdowns for physics measurements. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: completing Modification Records 03-03, Addendum 1, "Fire Protection in North Office Addition," and 03-03, Addendum 4, "Fire Protection System in the Shipping and Receiving Building;" draining Beamport 'C' and backfilling with helium; flooding Beamport 'D' for maintenance on the facility Deionized Water System; and performing reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP- 17(B)," as part of pre-beryllium replacement reference core determination.
March 2014 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and one unscheduled/unplanned power reduction. An NRC inspector arrived at the facility for a routine inspection of the Radiation Protection Program and Shipping.
On March 2, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction. After a brief investigation, the cause of the rod run-in was determined to be a blown Trip Actuator Amplifier (TAA) power supply fuse and the reactor was shut down.
Subsequent investigation revealed a failure of the R-14 resistor in the rod run-in system TAA. The rod run-in system TAA and Non-Coincidence Logic Unit (NCLU) were replaced. Operability checks of the rod run-in system were performed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
Major maintenance items for the month included: draining Beamport 'D' and backfilling with helium; replacing the air actuator for Anti-Siphon Isolation Valve V543A; and performing a zero, span and calibration of Reactor Core Outlet pressure transmitter PT-944B.
In addition to the items listed above, the reactor was shut down for approximately nine days to replace the beryllium reflector that surrounds the reactor core. During this planned extended shutdown, which is performed approximately every eight years, the following additional tasks were performed: rebuilding Anti-Siphon Isolation Valves V543A and V543B; rebuilding In-Pool Heat Exchanger Isolation Valves V546A and V546B; replacing primary coolant system water addition check valves V550C and V550D; performing nondestructive testing on the primary coolant pressure vessel spool piece; performing a reactivity worth measurement to characterize the new beryllium reflector; and performing a reactivity measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-1 I(D)," in order to determine the new worth values of all four shim control blades and the regulating blade.
1-2
April 2014 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and two unscheduled/unplanned power reductions. Three additional reactor startups and shutdowns were performed in support of NRC operator license examinations.
On April 7, with the reactor shutdown for regularly scheduled maintenance activities, the facility exhaust ventilation system low flow alarm was being tested as part of the pre-startup checks prior to conducting a normal reactor startup.
During this time, Master Control Switch 1S1 was in the 'Test' position in order to complete preventive maintenance on Pool Coolant Circulation Pump P-508A. With Switch IS1 in the 'Test' position, the reactor was not in the secured condition, as defined by Technical Specification 1.20. When the exhaust ventilation fans were secured, this created a situation where one of the six conditions for reactor containment integrity to exist was not satisfied.
Technical Specification 3.5.a requires that reactor containment integrity shall be maintained at all times except when (1) the reactor is secured and (2) irradiated fuel with a decay time of less than sixty days in not being handled.
Immediately upon receipt of the low flow alarm, the exhaust ventilation fan was restarted and reactor containment integrity reestablished. For approximately five seconds, the reactor was not secured while containment integrity did not exist.
Failure of the reactor to be in a secured condition during a period when containment integrity did not exist is a deviation from Technical Specification 3.5.a. Licensee Event Report No. 14-01 was submitted to the U.S. Nuclear Regulatory Commission on May 2, 2014.
On April 8, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was manually initiated when the duty operator noted control blade 'B' would not move in the outward direction. The immediate actions of reactor emergency procedure REP-8, "Control Rod Drive Mechanism Failure or Stuck Rod," were performed. Subsequent investigation determined that control rod drive mechanism 'Out' relay K2 had failed. The relay was replaced and operability checks were performed satisfactorily, including completing compliance procedure CP-10, "Rod Drop Time." The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
On April 23, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was manually initiated when the duty operator noted control blade 'B' was not operable in the inward direction. The immediate actions of reactor emergency procedure REP-8, "Control Rod Drive Mechanism Failure or Stuck Rod," were performed. Subsequent investigation determined that control rod drive mechanism "In" relay KI had failed. The relay was replaced and operability checks were performed satisfactorily, including completing compliance procedure CP-10 "Rod Drop Time." The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
Failure of the control rod drive mechanism to move control blade 'B' in the inward direction resulted in a deviation from Technical Specification 3.2.a. Licensee Event Report No. 14-02 was submitted to the U.S. Nuclear Regulatory Commission on May 16, 2014.
Major maintenance items for the month included: loading new de-ionization bed 'Y' and placing it on pool coolant system service; replacing Control Rod Operate Switch 1S4; and completing Modification Record 86-01, Addendum 4, "Replacement of Graphite Reflector Element '51' - Reflector Tank Position 5A/Irradiation Position L6."
1-3
May 2014 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: performing the biennial change-out of Control Blade 'B' Offset Mechanism and associated retesting; completing compliance procedure CP-26, "Containment Building Compliance Test;" and replacing the backup door air solenoid control valves A-62 and A-63.
June 2014 The reactor operated continuously in June with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: refurbishing and replacing Primary Coolant Circulation Pump P-501A; relocation of the Valve Operating Air Compressor and receiver tank; replacing the Fuel Element Failure Monitoring System anion and cation resins and filter; and replacing the Bridge ALARA area radiation monitoring system detector and associated assembly.
July 2014 The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions.
On July 7, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was automatically initiated when an interruption in electrical supply power from the University Power Plant to the facility occurred. All immediate and subsequent actions of reactor emergency procedure REP-10, "Sustained Loss of Normal Electrical Power," were performed. After the cause of the interruption in electrical power was corrected by the power plant, the reactor was refueled and subsequently restarted to 10 MW operation.
On July 8, with the reactor operating at 10 MW in the automatic control mode, a "Reflector Hi-Lo Differential Pressure" scram was automatically initiated. All other pool coolant flow indications remained normal. Subsequent investigation determined that the incandescent bulb used to actuate the photo-sensor trip unit had dimmed sufficiently to allow the trip unit contacts to open. Differential Pressure Across the Reactor Pool Reflector pressure transmitter PT-917 meter relay unit bulb was replaced and compliance procedure CP-5, "PT-917 - 10MW," was performed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-1 (D);" replacing the fan shaft bearings on Laboratory Exhaust Fan EF-13; and conducting the annual emergency preparedness drill.
1-4
August 2014 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions.
On August 14, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5 or 6 Downscale" annunciation was received. This alarm is initiated when any one of the three Nuclear Instrumentation Power Range Monitor (PRM) channels decrease below a power level set point of 95%. The duty operator observed the regulating blade at a height of 7.85 inches and moving in the inward direction at a rapid rate. All PRM channels indicated a decreasing reactor power level. When the regulating blade reached a height of 5.20 inches (20% withdrawn), the "Regulating Rod 20% Withdrawn" annunciation was received. As the regulating blade continued in the inward direction to a height of 2.6 inches (10% withdrawn), the "Regulating Rod < 10% Withdrawn" annunciation and associated rod run-in occurred. The regulating blade continued moving in the inward direction until it reached the fully inserted position at which time a second rod run-in signal was initiated and the "Regulating Rod Bottomed" annunciation was received. Continued motion of the regulating blade after the initial rod run-in indicated that some type of equipment malfunction had occurred and the reactor was shut down.
After the reactor was secured, the Regulating Blade Drive Mechanism was removed for inspection. Inspection revealed that the regulating blade drive mechanism reduction gearbox output shaft had sheared which prevented movement of the servomotor from being transferred to the lead screw assembly, thus preventing the regulating blade from being able to drive in the outward and inward directions. The regulating blade drive mechanism reduction gearbox was replaced. Operability checks were performed satisfactorily, including the applicable sections of compliance procedure CP-14, "Regulating Rod 10% and Rod Bottomed RRI, Rod Not in contact with Magnet RRI."
The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
Failure of the regulating blade to be operable resulted in a deviation from Technical Specification 3.2.a. Licensee Event Report No. 14-03 was submitted to the U.S. Nuclear Regulatory Commission on August 29, 2014.
On August 31, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was automatically initiated when an interruption in electrical supply power from the University Power Plant to the laboratory and containment buildings occurred. All immediate and subsequent actions of reactor emergency procedure REP-10, "Sustained Loss of Normal Electrical Power," were performed. Investigation determined the cause of the interruption to be a failure of the single phase trip relay unit within the 1600A main supply breaker to Substation 'B.' Electrical phasing and loading were verified correct and electrical power was restored to the laboratory and containment buildings. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.
The reactor was subsequently restarted to 10 MW operation.
Major maintenance items for the month included: performing a chemical cleaning of the secondary coolant side of pool coolant heat exchanger HX-521; transferring de-ionization bed 'W' from primary coolant to pool coolant service; loading new de-ionization bed 'K' and placing it on primary coolant system service; and refurbishing the Regulating Blade Drive Mechanism.
1-5
September 2014 The reactor operated continuously in September with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and four unscheduled/unplanned power reductions.
On September 4, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5, or 6 Downscale" annunciation was received. This alarm is initiated when any one of the three Nuclear Instrumentation Power Range Monitoring (PRM) channels decrease below a power level set point of 95%. All PRM channels indicated a decreasing reactor power level. All primary and pool coolant system pressure, temperature and flow indications were normal. No additional annunciations were received and no rod motion was in progress. The Lead Senior Reactor Operator directed a second operator to the reactor bridge to monitor conditions near the control and regulating blade drive mechanisms. It was determined that the regulating blade drive mechanism would not operate.
A manual reactor scram was initiated and all actions of reactor emergency procedure REP-2, "Reactor Scram," were completed, and the reactor was placed in the secured condition.
After the reactor was secured, the Regulating Blade Drive Mechanism was removed for inspection. Inspection revealed that the regulating blade drive mechanism reduction gearbox output shaft had sheared which prevented movement of the servomotor from being transferred to the lead screw assembly, thus preventing the regulating blade from being able to drive in the outward and inward directions. The regulating blade drive mechanism reduction gearbox and the brass adapter which connects the output shaft of the gearbox to the lead screw assembly were replaced. Operability checks were performed satisfactorily, including the applicable sections of compliance procedure CP-14, "Regulating Rod 10% and Rod Bottomed RRI, Rod Not in contact with Magnet RRI." The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
Failure of the regulating blade to be operable resulted in a deviation from Technical Specification 3.2.a.
Additionally, with the regulating blade in an inoperable state and unable to drive in either the outward or inward directions, a deviation from Technical Specification 3.4.c also occurred. Licensee Event Report No. 14-04 was submitted to the U.S. Nuclear Regulatory Commission on October 1, 2014.
On September 22, with the reactor operating at 10 MW in the automatic control mode, an automatic scram was initiated with no associated annunciation. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Investigation determined the cause of the scram to be a failure of Power Level Interlock relay 1K26. The relay was replaced and operability checks were performed satisfactorily.
Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
On September 26, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact with Magnet" rod run-in was automatically initiated when control blade 'D' anvil separated from its electro-magnet while relocating sample handling equipment in the reactor pool. A sample handling rod inadvertently came in contact with control blade 'D' offset mechanism causing the electro-magnet to separate from the anvil. A visual verification of the pull rod to housing alignment and visual inspection of the offset mechanism were completed. The reactor was refueled and subsequently restarted to 10 MW operation.
On September 28, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact with Magnet" rod run-in was automatically initiated when control blade 'D' anvil separated from its electro-magnet during 1-6
a sample handling evolution. A visual verification of the pull rod to housing alignment and visual inspection of the offset mechanism were performed satisfactorily. The reactor was refueled and subsequently restarted to 10 MW operation.
Major maintenance items for the month included: replacing the pump/motor coupling of Primary Coolant Circulation Pump P-501B; and performing a sample reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP- 17(B)."
October 2014 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and two unplanned/unscheduled power reductions.
On October 19, with the reactor operating at 10 MW in the automatic control mode, a "Bldg Air Plenum and Bridge Hi Activity" reactor scram and containment building isolation were automatically initiated when radiation levels at the reactor pool surface increased above the alarm set point. Immediate actions of emergency procedure EP-RO-012, "Reactor Isolation," were performed. As required by experimental procedure EX-RO-105, "Reactor Irradiation Experiments," the bridge Area Radiation Monitoring System (ARMS) is placed in the 'Upscale' position prior to handling samples in the pool. This increases the reactor isolation set point to prevent an inadvertent isolation during a controlled sample handling evolution [Note: This action is permitted by Technical Specification 3.4.a(2)]. It was determined that the bridge ARMS was not placed in the 'Upscale' position prior to the sample handling evolution.
Remote monitoring of all containment ARMS indicated no elevated levels, and the containment building was reentered. The reactor was refueled and subsequently restarted to 10 MW operation.
On October 20, during a reactor startup with the reactor power approaching 2.5 kW, a "Rod Not in Contact with Magnet" rod run-in was automatically initiated when control blade 'D' anvil separated from its electro-magnet during a shimming evolution. The reactor was shut down. An inspection of the offset mechanism pull rod and housing revealed a slight misalignment. The offset housing was realigned, and the control rod was satisfactorily withdrawn to the full our position as part of the retest by performing compliance procedure CP-10, "Rod Drop Times." Permission to restart the reactor was obtained from the Reactor Manager. The reactor was restarted to 10 MW operation.
Major maintenance items for the month included: performing the biennial change-out of Control Blade 'D' Offset Mechanism and associated retesting; performing a zero, span and calibration of Reactor Core Outlet pressure transmitters PT-944A and PT-944B; performing a zero, span and calibration of Primary Coolant Heat Exchanger Outlet pressure transmitter PT-943; and conducting a facility-wide evacuation exercise for training.
November 2014 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and one unscheduled/unplanned power reduction. NRC inspectors arrived at the facility for a routine inspection of Reactor Operations and Emergency Preparedness.
On November 18, with the reactor operating at 10 MW in the automatic control mode, the duty operator noted that Control Rod Operate Switch 1S4 would not fully return to its central, neutral position following a routine shimming 1-7
evolution. Switch 1S4 is a 3-position (In-Normal-Out), spring return to neutral position switch that is used to withdraw or insert the shim control blades manually. Although failure of the switch to fully return to the neutral position did not prevent the shim control blades from operating in both directions either manually or automatically, the duty operator felt operating the remainder of the week in this condition was unacceptable and shut down the reactor. Switch 1 4 was replaced and operability checks were performed satisfactorily. The reactor was refueled and was subsequently restarted to 10 MW operation.
Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" loading new de-ionization bed 'V' and placing it on pool coolant system service; replacing Reactor Core Outlet Alarm Meter Unit 944A; and replacing Control Rod Operate Switch 1S4.
December 2014 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and four unscheduled/unplanned power reductions.
On December 15, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was initiated. The control room operator immediately noted all four shim control blades moving in the inward direction and reactor power decreasing. After the reactor was shut down, troubleshooting of all relays, switches and wiring associated with the rod run-in system did not identify a failed component; however, the most likely cause was a momentary failure of either the rod run-in system Non-Coincidence Logic Unit (NCLU) or the Trip Actuator Amplifier (TAA). The rod run-in system TAA and NCLU were replaced.
Operability checks of the rod run-in system were performed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
On December 17, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5 & 6 High Power" rod run-in and a reactor scram were automatically initiated. The duty operator noted that the reactor power
"< 115%" alarm light on the front panel of Nuclear Instrumentation Power Range Monitor (PRM) Channel No. 6 was illuminated. A review of all PRM charts did not indicate a high power condition. All immediate and subsequent actions of reactor emergency procedure REP-5, "Nuclear Instrument Failure," were performed. Troubleshooting revealed a breakdown of the insulation of the detector cabling or connections on the uncompensated ion chamber.
The detector and associated cabling were replaced and instrument channel calibration and pre-operational checks were performed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
On December 25, with the reactor operating at 10 MW in the automatic control mode, the duty operator noted that control blade 'A' would not move in the outward direction. After verifying the ability to insert the control rod the duty operator initiated a manual reactor scram and the immediate actions of reactor emergency procedure REP-8, "Control Rod Drive Mechanism Failure or Stuck Rod," were performed. Subsequent investigation determined a wire connection to the control rod drive mechanism "Out" relay K2 had broken. The connection was repaired and operability checks were performed satisfactorily, including completing compliance procedure CP-10, "Rod Drop Time." Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled subsequently restarted to 10 MW operation.
1-8
On December 31, with the reactor operating at 10 MW in the automatic control mode, the duty operator noted a fault code on the Rod Positon Indication (RPI) central control chassis and observed a change in regulating blade position indication with no associated regulating blade movement. The Lead Senior Reactor Operator initiated a manual reactor shutdown to further investigate the RPI anomaly. Additional troubleshooting did not reveal a failed component; however, the RPI fault code indicated the problem was most likely generated from either the regulating blade encoder/resolver or the associated encoder/resolver circuit board. The encoder for the regulating blade RPI was replaced and the encoder/resolver circuit board tested satisfactorily. Operability checks including applicable sections of compliance procedure CP-14, "Regulating Rod 10% and Rod Bottom Rod Run-In, Rod Not in Contact with Magnet Rod Run-In," were completed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
Major maintenance items for the month included: completing Modification Records 14-01, "Interfacing MURR Systems with the MIB Eastward Expansion;" 90-01, Addendum 3, "Evacuation System Changes in Support of the MURR Industrial Building Eastward Expansion;" 03-03, Addendum 5, "Fire Protection System Changes in Support of the MURR Industrial Building Eastward Expansion;" 14-02, "Normal Electrical Distribution in MIB Eastward Expansion;" 14-01, Addendum 1, "Construction of Usable Laboratory Spaces Within the Expanded MURR Industrial Building;" 03-03, Addendum 6, "Fire Protection System Changes in Support of the MIB Eastward Expansion Fit-out;" 04-03, Addendum 2, "Liquid Radioactive Waste in MIB Eastward Expansion;" 01-09, Addendum 5, "Emergency Electrical in MIB Eastward Expansion;" 88-07, Addendum 3, "Exhaust Ventilation in MIB Eastward Expansion;" and 01-02, Addendum 11, "Intercom and Paging System Changes in Support of the MURR Industrial Building Eastward Expansion;" replacing the rod run-in system Non-Coincidence Logic Unit and Trip Actuator Amplifier; and replacing the uncompensated ion chamber detector and detector cabling for Nuclear Instrument Power Range Monitor Channel No. 6.
1-9
SECTION II MURR PROCEDURES January 1, 2014 through December 31, 2014 As required by administrative Technical Specification 6.1.h(4), this section of the Annual Report includes a summary of procedure changes. These procedure changes were reviewed by the Reactor Manager or Reactor Health Physics Manager, as applicable, and others to assure compliance with the requirements of 10 CFR 50.59. These procedure changes were also reviewed by the Reactor Procedure Review Subcommittee of the Reactor Advisory Committee to meet the requirements of Technical Specification 6.1 .c(1).
A. CHANGES TO REACTOR OPERATIONS PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Reactor Operations Procedures and found them to be adequate for the safe and reliable operation of the facility.
There were sixty-five (65) revisions issued to the reactor operations procedures, forms and operator aids.
Additionally, one (1) new procedure was issued and two (2) operator aids were obsoleted. The majority of the revisions were strictly format or editorial in nature, such as cover page changes. The following is a list of the new and revised procedures, forms and operator aids:
AP-RO-1 10 Conduct of Operations 19 1/22/2014 Minor Editorial AP-RR- 115 Modification Records 8 1/22/2014 Minor Editorial AP-RR- 115 Modification Records 9 11/24/2014 Cover Page AP-RR-003 10 CFR 50.59 Evaluations 9 7/8/2014 Minor Editorial EX-RO-105 Reactor Irradiation Experiments 20 9/22/2014 Cover Page EX-RO-120 Beamport "A" Operation 11 6/5/2014 Minor Editorial EX-RO-120 Beamport "A" Operation 12 9/4/2014 Minor Editorial EX-RO- 121 Beamport "B" Operation 11 6/5/2014 Minor Editorial EX-RO-121 Beamport "B" Operation 12 9/4/2014 Minor Editorial EX-RO- 122 Beamport "C" Operation 11 6/5/2014 Minor Editorial EX-RO- 122 Beamport "C" Operation 12 9/4/2014 Minor Editorial EX-RO-123 Beamport "D" Operation 11 6/5/2014 Minor Editorial EX-RO- 123 Beamport "D" Operation 12 9/4/2014 Minor Editorial EX-RO-124 Beamport "E" Operation 12 6/5/2014 Minor Editorial EX-RO-1 24 Beamport "E" Operation 13 9/4/2014 Minor Editorial EX-RO-125 Beamport "F" Operation 13 6/5/20*14 Minor Editorial EX-RO-125 Beamport "F" Operation 14 9/4/2014 Minor Editorial EX-RO-126 Thermal Column Door 9 9/22/2014 Cover Page FB-SH-110 Type B Shipment of Spent Fuel Using the BEA 4 7/25/2014 Minor Editorial Research Reactor Package FM-I5 10 CFR 50.59 Qualified Reviewers List 17 1/9/2014 Minor Editorial FM-15 10 CFR 50.59 Qualified Reviewers List 18 4/29/20 14 Minor Editorial i FM-16 Primary-Pool Coolant Water Analysis 7 6/15/2014 Minor Editorial FM-16 Primary-Pool Coolant Water Analysis 8 9/22/2014 MiorEditorial I1-1
FM- 18 I Nmbe Deviation Nae From Procedure Report e.C Revisionl Dat 7 11/24/2014
~ Cover Notes~
Page FM-43 Nuclear and Process Data 19 10/20/2014 Minor Editorial FM-S6 Reactor Routine Patrol 17 11/24/2014 Minor Editorial FM-S7 Long Form Startup Checksheet 22 7/21/2014 Minor Editorial FM-57 Long Form Startup Checksheet 23 9/22/2014 Minor Editorial FM-58 Short Form Startup Checksheet 12 12/2/2014 Cover Page FM-64 DI Resin Log 6 10/8/2014 Minor Editorial FM-65 Filter Status Log 6 10/8/2014 Minor Editorial FM-68 Target Material Control Checksheet 13 7/21/2014 Minor Editorial FM-93 Post Maintenance Valve Line-up Checksheet 6 11/24/2014 Cover Page OA-1~ Facility Exhaust Fans EF- 13 and EF-14, EF- 13 Obsoleted Running Facility Exhaust Fans EF- 13 and EF-14, EF- 14 OA-2 Running Obsoleted OA-3 Beamport and Pool Overflow Loop Seals 8 1/22/2014 Cover Page OA-3 Beamport and Pool Overflow Loop Seals 9 6/25/2014 Minor Editorial OA-4 Valve Operation Air Compressor 7 11/24/2014 Cover Page OA-5 Emergency Air Compressor 7 11/24/2014 Cover Page OP-RO-250 In-Pool Fuel Handling 16 9/22/2014 Cover Page OP-RO-350 Reactor Power Calculator Flow Potentiometer idutet8 5/6/2014 Cover Page Adjustment_______________
OP-RO-460 Pool Coolant System - Two Pump Operation 15 5/6/2014 Minor Editorial OP-RO-461 Pool Coolant System - One Pump Operation 15 5/6/2014 Cover Page OP-RO-465 Pool Level Control - Skimmer System 9 6/25/2014 Cover Page OP-RO-466 Pool Level Control - Pool Coolant System 11 6/3/2014 Minor Editorial OP-RO-466 Pool Level Control - Pool Coolant System 12 7/21/2014 Minor Editorial OP-RO-480 Secondary Coolant System 19 5/6/2014 Minor Editorial OP-RO-515 Emergency Air System 10 10/8/2014 Minor Editorial OP-RO-516 Valve Operation Air System 10 7/21/2014 Cover Page OP-RO-520 Emergency Diesel Generator 11 10/8/2014 Minor Editorial OP-RO-530 Demineralized Water Supply System 14 6/12/2014 Cover Page OP-RO-531 Primary and Pool Sample Station 12 .6/12/2014 Cover Page OP-RO-532 Drain Collection System 9 6/25/2014 Cover Page OP-RO-533 Skimmer System 7 6/25/2014 Cover Page OP-RO-555 Fire Protection System 12 10/08/2014 Minor Editorial OP-RO-730 Facility Exhaust System 15 7/21/2014 Minor Editorial OP-RO-741 Waste Tank System Operation 15 2/19/2014 Minor Editorial POL-20 Special Nuclear Materials Manual 2 1/22/2014 Minor Editorial RM-RO-405 Reactor Demineralizer System 13 10/8/2014 Minor Editorial SM-RO-0 11 Beryllium Reflector Replacement 3 2/24/2014 Updated Procedure SM-RO-200 Manual Operation of Airlock doors 276 and 277 3 6/26/2014 Cover Page SM-RO-4 10 Partially Draining the Pool Hold-Up Tank (T504) 1 6/26/2014 Cover Page Replacement of Flux Trap Irradiations Reactivity 11/6/2014 Cover Page SM-RO-500_ Safety Trip Support Rig SM-RO-620 Control Blade Leak Test 5 1/23/2014 Minor Editorial 11-2
[Number Name >K~~ Rev. Reision Imp Ntes.
SM-RO-630 Removing and Reinstalling Reflector elements in the 0 4/1/2014 New Procedure GH and No. 9 Positions SM-RO-630 Removing and Reinstalling Reflector elements in the 1 7/5/2014 Minor Editorial GH and No. 9 Positions SM-RO-640 Retracting and Reinserting Beamport 'F' Liner 6 12/2/2014 Cover Page SM-RO-660 Replacement of the Inner and Outer Pressure Vessels 4 4/9/2014 Minor Editorial B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Emergency Plan Implementing Procedures and found them to be adequate for the safe and reliable operation of the facility.
There were eight (8) revisions issued to the emergency procedures, forms and operator aids. The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures, forms and operator aids:
Number Name. R ev. Revisio Date Notes EP-RO-006 Radiological Emergency 6 7/14/14 Minor Editorial EP-RO-013 Facility Evacuation 6 7/14/14 Minor Editorial EP-RO-015 Emergency Notifications 12 10/31/14 Minor Editorial FM-104 Emergency Call List 23 5/23/14 Minor Editorial FM-104 Emergency Call List 24 10/31/14 Minor Editorial OA-10 Fire Extinguisher Locations and Types 10 7/14/14 Minor Editorial OA-20 Emergency Equipment 17 7/14/14 Minor Editorial OA-20 Emergency Equipment 18 10/31/14 Minor Editorial C. CHANGES TO HEALTH PHYSICS PROCEDURES, BYPRODUCT MATERIAL SHIPPING PROCEDURES, AND PREPARATION OF BYPRODUCT MATERIAL FOR SHIPPING PROCEDURES As required by the MURR Technical Specifications, the Reactor Health Physics Manager reviewed the procedures for radioactive materials handling, shipping, and preparation for shipping of byproduct materials.
There were eighty-two (82) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. Additionally, four (4) new procedures were issued, and three (3) procedures and two (2) forms were obsoleted. The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures and forms:
AP-HP- 105 Radiation Work Permit 11 4/7/2014 Minor Editorial AP-HP- 119 High Radiation Area Access 6 2/27/2014 Minor Editorial AP-HP-125 Review of Unplanned Radiation Exposure 5 2/11/2014 Cover Page AP-HP-129 Hot Cell, HC-0 1 Control 10 4/7/2014 Minor Editorial 1Bagging and Labeling of Non-Waste Radioactive 0 8/4/2014 New Procedure AP-HP-140 NeMaterial Procedure........
11-3
Number_______ lName~ Re.Rv~oj aeNO AP-HP-150 Source Calibration 5 5/12/2014 Cover Page 20WC- 1 Packaging and Shipment of Type B Non-BPB-SH-002 12 7/9/2014 Minor Editorial iBPB-SH-002 20WC- 1 Packaging and Shipment of Type B Non- 12 10/8/2014 Obsoleted Waste Radioactive Material BPB-SH-005 DOT 6M Packaging of Type B Radioactive 11 11/19/2014 Obsoleted Material BPB-SH-021 20WC-1 All-Thread Rod Replacement 3 5/5/2014 Minor Editorial BPB-SH-022 Painting USA DOT 20WC- I Overpack 3 5/27/2014 Minor Editorial BPB-SH-023 Type B Equipment Calibration 3 4/22/2014 Minor Editorial BPB-SH-023 Type B Equipment Calibration 4 7/9/2014 Cover Page BPB-SH-024 Type B(U) F-458 Series Packaging of Type B Radioactive Material 3 8/29/2014 Minor Editorial Type B(U) USA/9337/B(U)-96 (LS) Packaging of BPB-SH--028 1 4/1/2014 Minor Editorial Radioactive material Type B(U) USA/9337/B(U)-96 (SAFKEG-LS)
BPB-SH-028 and USA/9338/B(U)-96 (SAFKEG-HS) 2 8/29/2014 Minor Editorial Packaging of Radioactive material BPB-SH-030 Receipt Inspection of New Type B Byproduct 0 7/8/2014 New Procedure Material Shipping Packages Packaging and Shipment of Radioactive Materials BP-SH-013 Using Reusable Type A Package (5 to 30-Gallon 6 1/3/2014 Minor Editorial Drum)
BP-SH-014 Packaging and Shipment of Radioactive Material 5 7/9/2014 Minor Editorial Using an Overpack Packaging and Shipment of Radioactive Material BP-SH-015 Using USA DOT 7A Model E-Box 030-181 4 7/9/2014 Minor Editorial Package BP-SH-0 17 Packaging and Shipment of Radioactive Material 1 8/12/2014 Minor Editorial Using Tracerco LS-6 Reusable Type A Package BP-SH-052 Radioactive Material Shipment Package 12 4/22/2014 Minor Editorial Documentation and Labeling BP-SH-099 Packaging of Radioactive Material Using MURR 4 4/22/2014 Minor Editorial Model 1500 FB-SH- 110 Type B Shipment of Spent Fuel Using the BEA 7/25/2014 Minor Editorial Research Reactor Package FM-13 Receipt of Radioactive Material 7 1/3/2014 Cover Page FM-17 Radiation Work Permit 12 4/7/2014 Minor Editorial FM-27 In-House Radioactive Shipping Request Form 13 2/11/2014 Cover Page FM-35 Control Checksheet for NeoRx Type B USA DOT 16 1/3/2014 Minor Editorial 20WC- 1Radioactive Materials Shipment FM-35 Control Checksheet for NeoRx Type B USA DOT 17 8/29/2014 Minor Editorial 20WC-1 Radioactive Materials Shipment Control Checksheet for NeoRx Type B USA DOT 20WC-I Radioactive Materials Shipment FM-52 Control Checksheet for Documentation and 13 4/22/2014 Minor Editorial
............. Labeling of Radioactive Material Shipment Control Checksheet for Documentation and FM-52 Labeling of Radioactive Material Shipment 14 _7/9/2014 CoverPage 11-4
FM-62 Radiation Instrument Certificate of Calibration 7 7/11/2013 Cover Page Control Checksheet for Spectratek Services FM-59 Reusable Type A Package Radioactive Materials 7 5/5/2014 Minor Editorial Shipment tFM-60 Control Check Sheet for MURR Shipment Using USA DOT 7A Model E-Box 030-181 Package Mio
___55204 _Eiora FM-67 Receipt of Radioactive Gemstone Shipping 7 1/3/2014 Cover Page Containers Control Checksheet for Reusable Type A FM-69 Radioactive Materials Shipment (5-to 30-Gallon 9 5/5/2014 Minor Editorial Drums)
FM-70 Control Checksheet for Tracerco LS-6 Reusable 1 4/55/2014 Minor Editorial
__ __ Type A Package Radioactive Materials Shipment FM-74 Control Checksheet for Type B USA DOT 6M 15 1/9/2014 Minor Editorial Radioactive Materials Shipment FM-74 Control Checksheet for Type B USA DOT 6M 15 11/19/2014 Obsoleted Radioactive Materials Shipment FM-94 Exclusive Use Shipment Controls 7 5/27/2014 Cover Page FM-98 Control Check Sheet for MURR Shipment Using 5/5/2014 Minor Editorial USA DOT 7A MURR Model 6 or 12 FM-99 Control Checksheet for USA DOT 7A MURR 8 5/5/2014 Minor Editorial Model 1500 Series FM- 126 Documentation of Compliance for DOT-7A 3 5/5/2014 Cover Page Shipping Container ...........
'"FM-128 Control Check Sheet for MURR Shipment Using 3 5/5/2014 Minor Editorial USA DOT 7A MURR Model H or I FM-129 Control Checksheet for Receipt and Inspection of Type B Byproduct Material Shipping Containers 4 __/04_vrPg FM-135 Control Checksheet for Type B(U) ZA/NNR 1005 3 1/9/2014 Minor Editorial (Beatrice) Radioactive Materials Shipment FM-137 Type B Qualified Shipper List 2 1/9/2014 Minor Editorial FM-137 Type B Qualified Shipper List 3 4/4/2014 Minor Editorial FM-137 Type B Qualified Shipper List 4 10/10/2014 Minor Editorial Control Checksheet for Leak Testing of the LS FM-138 Shipping Container Using the CALT 9 Leakage 1 1/3/2014 Minor Editorial
_Testing Device Control Checksheet for Leak Testing of the LS or FM-138 HS Shipping Container Using the CALT 9 2 8/12/2014 Minor Editorial Leakage Testing Device Control Checksheet for Leak Testing of the FM-138 SAFKEG-LS or SAFKEG-HS Shipping Container 3 8/29/2014 Minor Editorial Using the CALT Leakage Testing Device Control Checksheet for USA DOT 20WC- 1 FM-_154 Overpack Rod Replacement 4 5/27/2014 Cover Page FM- 155 Quality Assurance Control Checksheet Exterior Painting of USA DOT WC-1, Type B Overpack FM- 157 Control Checksheet for Type B(U) F-458 Series 3 1/9/2014 Minor Editorial Radioactive Materials Shipment Control Checksheet for Type B(U) F-458 Series 4 7/9/2014 Minor Editorial FM-.... .7 Radioactive Materials Shipment ...... ... ..... ............ . .
11-5
Nube Name______ Rev._____________________
RevisionDate Notes i FM-M16 160 Control Checksheet Raiatv Type B(U) F-327 Series aeilfor hpet2 1/9/2014 Minor Editorial
____________Radioactive Materials Shipment FM-FM- 160 160 Control Checksheet for Type B(U)
RdoctvMaeilShp nt3 F-327 Series 7/9/2014 Minor Editorial Radioactive Materials Shipment_________
Control Checksheet for Type B(U)
FM-163 USA/9337/B(U)-96 (LS) Packaging of 2 1/3/2014 Minor Editorial
____________Radioactive Material ....... .
Control Checksheet for Type B(U)
F-6 USA/9337/B(U)-96 (LS) and B(U)
USA/9338/B(U)-96 (HS) Packaging of 3 8/12/2014 Minor Editorial Radioactive Material Control Checksheet for Type B USA/9337/B(U)-
F1 163 S FM- 96 (SAFKEG-LS) and USA/9338/B(U)-96 3 8/29/2014 Minor Editorial (SAFKEG-HS) Packaging of Radioactive Material Shipment FM-164 Authorization For Use of North Office Addition 1 2/11/2014 Minor Editorial West Passageway (C2001)
HC-PSO-005 Hot Cell Loading of Host Cans 12 3/24/2014 Minor Editorial IC-HP-341 Calibration - High Resolution Gamma 6 2/11/2014 Minor Editorial
_ _ _ Spectroscopy Systems IC-HP-357 Calibration - Ludlum Model 177 Frisker 0 9/23/2014 New Procedure OP-HP-224 Spent Fuel Shipping Cask Air Sample Analysis 4 8/12/2014 Minor Editorial OP-HP-300 Receipt of Radioactive Material 8 1/3/2014 Cover Page OP-HP-306 Health Physics Daily Facility Checks 4 1/22/2014 Minor Editorial OP-HP-306 Health Physics Daily Facility Checks 5 10/24/2014 Minor Editorial OP-HP-350 Eberline Model Ping lA - Filter Change 5 7/4/2014 Cover Page OP-HP-352 Particulate and Iodine Filter - Analysis 4 5/12/2014 Minor Editorial OP-HP-420 Decontamination of Enclosed Processing Units 4 1/3/2014 Cover Page OP-HP-505 Emergency Stack Monitor Filter Analysis 5 8/12/2014 Minor Editorial QAB-SH-002 Procurement of Type B Packages 3 5/27/14 Cover Page QAB-SH-003 Material Control for Type B Shipping Program 4 8/29/2014 Minor Editorial QAB-SH-004 Type B Program Vendor Qualification 4 7/9/2014 Cover Page Leak Testing of the LS Shipping Container Using 1 5/27/2014 Minor Editorial QAB-SH-007_ the CALT 9 Leakage Testing Device Leak Testing of the SAFKEG-LS or SAFKEG-HS QAB-SH-007 Shipping Package Using the CALT Leakage 2 8/29/2014 Minor Editorial Testing Device RM-HP- 101 Stack Monitor Preventative Maintenance - 4 12/2/2014 Minor Editorial Eberline Ping lA RP-HP- 105 Transfer of Radioactive Material - In Facility 8 2/11/2014 Minor Editorial RP-HP-137 Handling Radioactive Material in the Reactor Pool 12 2/11/2014 Minor Editorial SI-PSO-008 Post-Irradiation Processing: Exported Flooded 7 7/21/2014 Minor Editorial Silicon Cans SI-PSO-009 Operation of the Denison Can Press 0 10/20/2014 New Procedure j SP-SH-002 NeoRx 20WC- 1 Packaging and Shipment of Type 2 10/8/2014 Obsoleted B Non-Waste Radioactive Material SV-HP-. 100 Reactor Chemistry Isotope Counter Trending and 6 1/22/2014 Minor Editorial Investigative Level Determination ..........
SV-HP-110 Environmental Sampling 6 5/12/2014 Minor Editorial 11-6
SV-HP-119 Property Release 6 1/3/20'14 Cover Page SV-HP- 131 Emergency Analysis of Environmental Samples 3 10/20/2014 Minor Editorial TPZ-PSO-002 Irradiation of Gemstone Irradiation Containers 7 2/21/2014 Minor Editorial WM-SH-105 IRadioactive Waste Processing 9/23/2014 Cover!r Page .
11-7
SECTION III REVISIONS TO THE HAZARDS
SUMMARY
REPORT January 1, 2014 through December 31, 2014 These changes were approved by the Reactor Manager and reviewed by licensed staff and members of the Reactor Safety Subcommittee and have been determined not to involve a change to the Technical Specifications. These changes have all been reviewed in accordance with 10 CFR 50.59.
HAZARDS
SUMMARY
REPORT (ORIGINAL JULY 1, 1965)
Original HSR, page 2-4, Figure 2.3, Site Plan (as revised by the 2012 Reactor Operations Annual Report):
Replace with: Updated Figure 2.3, Site Plan Original HSR, page 3-11, Figure 3.1, Beam Hole Level Plan (as revised by the 1972-1973, 1990-1991, 1995, 1996 and 2012 Reactor Operations Annual Reports):
Replace with: Updated Figure 3.1, Basement Level Plan (MURR Dwg. No. 1145 Sheet 1 of 5, dated 10/07/14)
Original HSR, page 3-12, Figure 3.2, Grade Level Plan (as revised by the 1972-1973, 1979-1980, 1990-1991, 1995, 1996, 2012 and 2013 Reactor Operations Annual Reports):
Replace with: Updated Figure 3.2, Grade Level Plan (MURR Dwg. No. 1145 Sheet 2 of 5, dated 10/06/14)
Original HSR, page 3-16, Figure 3.4, North and East Elevation (as revised by the 1995 Reactor Operations Annual Report):
Replace with: Updated Figure 3.4, North and East Elevation Original HSR, pages 7-21, Section 7.2.9, Table 7.2 (as revised by the 1995, 2001, 2007, 2009, 2011, 2012 and 2013 Reactor Operations Annual Reports):
Delete: Entire Table 7.2, which states:
TABLE 7.2 PAGING SYSTEM SPEAKER LOCATIONS Containment Building North Office Addition Room 101 (3) Corridor C2000 Room 2009A Containment Building Third Level Corridor C2002 (2) Room 2011 Containment Building Grade Level (2) Room 2005 Room 2015 (17)
Containment Building Fourth Level Room 2006 Room 2041 Room 2007 Room 2045A' Room 2008 Room 2045B Shinning and Receiving Building Room 2008A Room 2046 Room 2008C Room 2047A Room 101 (2) Room 2009 Room 2048 IHI-1
Reactor Laboratory Building Cooling Tower Grade Level Room 210, Lobby Room 244 Room 278 (2)
Outside Room 114 Room 212 Room 245 Room 280 Outside Room 214A Room 215A Room 247 Room 281 Outside Room 224 Room 216 Room 251 Room 288 Outside Room 228 Room 218 Room 255 Room 299 Outside Room 241 Room 224 Room 257 Corridor C299D Outside Room 244 Room 227 Room 258 Room 299N Outside Room 258 Room 231 Room 259 Room 299P Outside Room 264 Room 231A Room 260 Room 299Q Outside Room 288 Room 23 IC Room 262 TOB-1 Outside Room 293 Room 232B Room 267A TOB-2 Room 103 Room 238 Room 269 TOB-3 Room 110 Room 241 Room 271 TOB-4 Room I Il Room 242 Room 273 TOB-5 Room 202 Replace with:
TABLE 7.2 PAGING SYSTEM SPEAKER LOCATIONS Containment Building North Office Addition Room 101 (3) Corridor C2000 Room 2009A Containment Building Third Level Corridor C2002 (2) Room 2011 Containment Building Grade Level (2) Room 2005 Room 2015 (17)
Containment Building Fourth Level Room 2006 Room 2041 Room 2007 Room 2045A Room 2008 Room 2045B Shipping and Receiving Building Room 2008A Room 2046 Room 2008C Room 2047A Room 101 (2) Room 2009 Room 2048 Reactor Laboratory Building Cooling Tower Grade Level Room 212 Room 246 Room 299D Outside Room 114 Room 213 Room 247 Room C299D Room 199 (2) Room 215A Room 251 Room 299F Outside Room 214A Room 216 Room 255 Room 299N Outside Room 224 Room 218 Room 257 Room 2990 Outside Room 228 Room 224 Room 258 Room 299P Outside Room 241 Room 225 Room 259 Room 299Q Outside Room 244 Room 227 Room 260 Room 299U Outside Room 258 Room 231 Room 269 Room C299U Outside Room 264 Room 231 A Room 271 Room 299T Outside Room 288 Room 231C Room 273 Room 299V Outside Room 293 Room 232B Room 278 (2) TOB-I Room 103 Room 238 Room 280 TOB-2 Room 110 Room 241 Room 281 TOB-3 Room 111 Room 242 Room 288 TOB-4 Room 202 Room 244 Room C299A TOB-5 Room 210, Lobby Room 245 UI-2
ADDENDUM 1 - HAZARDS
SUMMARY
REPORT (FEBRUARY 1966)
HSR, Addendum 1, Section 3.8, paragraph 4, page 24, (as revised by the 1989-90, 2002, 2004 and 2010 Reactor Operations Annual Reports):
Delete: "3) Diesel Room Distribution Panel which provides control power for the EG room ventilation system."
Replace with: "3) Diesel Room Distribution Panel which provides power for the EG controls, emergency lighting, and selected receptacles."
ADDENDUM 3 - HAZARDS
SUMMARY
REPORT (AUGUST 1972)
HSR, Addendum 3, page vi, List of Figures:
Delete: "2.3a Electrical Distribution .......................................... 18 2.3b Electrical Distribution ............................................. 19" Replace with: "2.3 Electrical Distribution ............................................... 18" HSR, Addendum 3, page 15, Figure 2.2.a, Secondary Cooling System (as revised by the 1990, 1991, 1994, 1995, 2001, 2002, 2003, 2004, 2005, 2006 and 2012 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.2.a, Secondary Cooling (MURR Dwg. No. 502 Sheet I of 3, dated 04/16/14)
HSR, Addendum 3, page 15A, Figure 2.2.b, Secondary Cooling System (as revised by the 2012 and 2013 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.2.a, Secondary Cooling System (MURR Dwg. No. 502 Sheet 2 of 3, dated 08/08/14)
HSR, Addendum 3, page 18, Figure 2.3.a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011, 2012 and 2013 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg.
No. 522, Sheet 1 of 5, dated 10/07/14)
HSR, Addendum 3, page 19A, Figure 2.3.c, Electrical Distribution (as added by the 2004 and revised by the 2005, 2007, 2009, 2010, 2011, 2012 and 2013 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.3.c, Electrical Distribution Reactor/Laboratory Panels (MURR Dwg. No. 522, Sheet 3 of 5, dated 05/15/14)
HSR, Addendum 3, page 19B, Figure 2.3.d, Electrical Distribution (as added by the 2007 and revised by the 2008, 2009, 2010, 2011, 2012 and 2013 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.3.d, Electrical Distribution Reactor/Laboratory Panels-2 (MURR Dwg. No. 522, Sheet 4 of 5, dated 02/20/14) 111-3
ADDENDUM 4 - HAZARDS
SUMMARY
REPORT (OCTOBER 1973)
HSR, Addendum 4, page A-21, Figure A.3, 10 MW Process Instrumentation Control & Interlock - 3 of 3 (as revised by the 1995, 1998, 2001, 2005, 2006, 2007 and 2008 Reactor Operations Annual Reports):
Replace with: Updated Figure A.3, Process Instrumentation Control & Interlock (MURR Dwg.
No. 41 Sheet 3 of 4, dated 11/17/14)
HSR, Addendum 4, page A-22, Figure A.4.a, Reactor Control System - 10 MW, Sheet 1 of 2 (as revised by the 2001, 2004, 2006, 2007 and 2013 Reactor Operations Annual Reports):
Replace with: Updated Figure A.4.a, Reactor Control System (MURR Dwg. No. 42 Sheet 1 of 2, dated 07/01/14)
HSR, Addendum 4, page A-24, Figure A.5, Process Instrumentation Control & Interlock - 1 of 3 (as revised by the 1995, 2001, 2005, 2006, 2008 and 2009 Reactor Operations Annual Reports):
Replace with: Updated Figure A.5, Process Instrumentation Control & Interlock (MURR Dwg.
No. 41 Sheet 1 of 4, dated 11/17/14)
HSR, Addendum 4, page A-29, Figure A.11, Schematic Diagram of Laboratory and Containment Buildings Ventilation System (as revised by the 1995, 2002, 2005, 2009, 2010, 2011, 2012 and 2013 Reactor Operations Annual Reports):
Replace with: Updated Figure A.5, Schematic Diagram of Laboratory and Containment Buildings Ventilation System (MURR Dwg. No. 1125 Sheet I of 4, dated 05/22/14)
ADDENDUM 5 - HAZARDS
SUMMARY
REPORT (JANUARY 1974)
HSR, Addendum 5, page 4, Figure 2.1, Electrical Distribution (as revised by the 1989-90, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011, 2012 and 2013 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg.
No. 522, Sheet 1 of 5, dated 10/07/14) 111-4
SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2014 through December 31, 2014 For each facility modification described below, MURR has on file the safety screen or evaluation, as well as the documentation of review, performed in accordance with 10 CFR 50.59.
Modification 86-01, Addendum 4:
Replacement of Graphite Reflector Element '5F' - Reflector Tank Position 5A/Irradiation Position L6 This addendum to Modification Record 86-01, "Reflector Element 5A and 5B Replacement," documents the replacement of graphite reflector element 5I; the reflector element that accommodates irradiation position L6.
Addenda 1 and 3 documented the replacement of the same element, which occurred in March 2000 and March 2006, respectively. This graphite reflector element was replaced with an element of similar design and this Modification Record was used as documentation for the replacement time, sequence, and pre- and post-maintenance tests. Replacement was due to demonstrated signs of binding between the irradiation sample holder and irradiation position inner wall.
Modification 88-07, Addendum 3:
Exhaust Ventilation in MIB Eastward Expansion This addendum to Modification Record 88-07, "Exhaust Ventilation Upgrade," documents the installation of radioactive exhaust ventilation in the newly expanded MURR Industrial Building (MIB). The system consists of charcoal and high efficiency particulate air (HEPA) filter banks, constant volume control valves (CVCVs),
hot cell ventilation exhaust fans, flow and pressure measurement devices, and associated ducting and dampers.
The modification to the exhaust ventilation system in the MIB Eastward Expansion is designed to maintain Rooms 299T, 299U and 299V at a slight negative pressure with respect to the surrounding areas; maintain hot cells HC- 11 A, HC- 11 B and HC- 11 C at a negative pressure; provide the necessary charcoal and HEPA filtration to ensure radioactive airborne being released to the environment are kept at minimum concentrations; and provide continuous monitoring of all radioactive airborne releases discharged through the MIB Eastward Expansion exhaust ventilation system.
Modification 90-01, Addendum 3:
Evacuation System Changes in Support of the MURR Industrial Building Eastward Expansion This addendum to Modification Record 90-01, "Evacuation Horns," documents changes to the facility Evacuation System that are necessary in order to safely occupy the MURR Industrial Building (MIB) Eastward Expansion. This modification adds three evacuations horns to areas in the MIB Eastward Expansion.
Modification 01-02, Addendum 11:
Intercom and Paging System Changes in Support of the MURR Industrial Building Eastward Expansion This addendum to Modification Record 01-02, "Installation of a New Reactor Facility Intercommunication and Paging System," documents changes to the MURR Intercommunication and Paging System that enhances communications in the MURR Industrial Building (MIB) Eastward Expansion through the addition of six paging speakers. The installation of an additional amplifier reduces loading on existing paging speaker amplifiers throughout the facility and provides capacity for future system growth facility-wide. It also documents the addition of a speaker in the Laboratory Building, as well as correcting minor discrepancies found during a speaker location audit.
IV-I
Modification 01-09, Addendum 5:
Emergency Electrical in MIB Eastward Expansion This addendum to Modification Record 01-09, "Installation of Emergency Lighting Panel No. 1," documents the addition of loads to the Emergency Electrical Power System in the MURR Industrial Building (MIB)
Eastward Expansion. The addition provides a single 120V circuit, supplied by the Diesel Room Distribution Panel, to the MIlB Eastward Expansion for supplying emergency lighting.
Modification 03-03, Addendum 1:
Fire Protection in North Office Addition This addendum to Modification Record 03-03, "Installation of a Facility Fire Detection/Suppression System,"
documents the installation of an additional Fire Protection System in the North Office Addition (NOA) to the existing MURR Fire Detection/Suppression System. The new NOA system provides two functions: a detection system compromised of heat, smoke and remote manual devices, and a suppression system that incorporates a traditional sprinkler system with a pre-action system used in areas with sensitive electrical equipment. These systems are integrated with the remainder of the MURR Fire Detection/Suppression System at the central control panel located in the Main Lobby. The control station continuously monitors each system component and will annunciate if any component is not in its normal condition. The sprinkler system is supplied by the MURR Fire Main Loop.
Modification 03-03, Addendum 4:
Fire Protection System in the Shipping and Receiving Building This addendum to Modification Record 03-03, "Installation of a Facility Fire Detection/Suppression System,"
documents the installation of an additional Fire Protection System in the Shipping and Receiving Building (SaRB) to the existing MURR Fire Detection/Suppression System. The SaRB system provides two functions: a detection system compromised of heat, smoke and remote manual devices, and a suppression system that incorporates a traditional sprinkler system. The sprinkler system is supplied directly from the University water distribution system and is separate from the MURR Fire Main Loop. The detection system is connected to the facility control station in the Main Lobby and will also annunciate if any component is not in its normal condition.
Modification 03-03, Addendum 5:
Fire Protection System Changes in Support of the MURR Industrial Building Eastward Expansion This addendum to Modification Record 03-03, "Installation of a Facility Fire Detection/Suppression System,"
documents the installation of a Fire Protection System in the new MURR Industrial Building (MIB) Eastward Expansion. This phase of the modification only provides the addition of a traditional sprinkler system for the MIB Eastward Expansion stairwell and mezzanine areas. The sprinkler system is connected to the existing MIB sprinkler header.
Modification 03-03, Addendum 6:
Fire Protection System Changes in Support of the MIB Eastward Expansion Fit-out This addendum to Modification Record 03-03, "Installation of a Facility Fire Detection/Suppression System,"
documents the installation of additional Fire Protection System equipment in the newly constructed MURR Industrial Building (MIB) Eastward Expansion. The MIB Eastward Expansion system provides two functions:
a detection system compromised of heat, smoke and remote manual devices, and a suppression system that incorporates a traditional sprinkler system. The sprinkler system is supplied from the MURR Fire Main Loop via the MIB sprinkler header. All of these systems and devices combine to form a complete Fire IV-2
Detection/Suppression System and are integrated with the remainder of the MURR Fire Detection/Suppression System at the central control panel in the Main Lobby.
Modification 04-03, Addendum 2:
Liquid Radioactive Waste in MIB Eastward Expansion This addendum to Modification Record 04-03, "Liquid Radioactive Waste Modification," documents the changes required to extend the facility Liquid Radioactive Waste (LRW) System to the eastward expansion of the MURR Industrial Building (MIB). This modification documents the installation of two lift stations and an elevator sump with associated connections to the existing MIB LRW header. Drainage from a small sink and eyewash station on the grade level is connected to a small lift station which in turn discharges to a larger duplex lift station located in the NIB Eastward Expansion basement. The basement lift station also receives condensate from the air handling units, cooling coils of the air conditioning system and a sink in the grade level laboratory (Room 299V). The elevator sump discharges directly to the MIB LRW header.
Modification 14-01:
Interfacing MURR Systems with the MIB Eastward Expansion This Modification Record documents the basic construction of the MURR Industrial Building (MIB) Eastward Expansion as well as the initiating document to ensure that all systems related to emergency response have been identified and modified prior to safely occupying the facilities in the MIB Eastward Expansion. Actual modifications to these systems - facility evacuation, fire protection, intercommunication and paging, and emergency electrical power - were performed under addendums to previously approved Modification Records.
The MIB Eastward Expansion provides approximately 2880 ft2 of usable space to the MURR facility. The building is construction type 1I-B with a grade level floor of poured concrete designed with a heavy load rating.
The basement flooring is also rated for heavy loads. The steel and concrete structure rests on pilings driven to bedrock. The east wall of the building has a masonry shield wall in part of the structure to reduce possible dose to the public. The building is equipped with standard heating, ventilation and air conditioning.
Modificationl4-01, Addendum 1:
Construction of Usable Laboratory Spaces within the Exnanded MURR Industrial Building This addendum to Modification Record 14-01, "Interfacing MURR System Changes in Support of the MURR Industrial Building Eastward Expansion" documents the construction of laboratory spaces within and extension of MURR systems to, the dedicated laboratory facility in the new eastward expansion to the MIURR Industrial Building (MIB). The laboratory contains three adjoined and inter-connected hot cells located on the grade level. Each hot cell is heavily shielded with lead. The area to the rear of the cells, the cask loading area, is where the cell support facilities and equipment are located and where cells inputs and outputs occur. The area in front of the cells, the operator area, is where the cell windows, manipulators, glove boxes and controls are located. There is an additional laboratory on the grade level and a full basement beneath the expansion. The extension of existing systems such as fire protection, liquid radioactive waste, radioactive exhaust ventilation and electrical modifications were covered by addendums to existing Modifications Records.
Modification 14-02:
Normal Electrical Distribution in MIB Eastward Expansion This Modification Record documents the expansion of the Normal Electrical Power System for the eastward expansion to the MURR Industrial Building (MIB). Electrical power is supplied from the facility 2000-kVA transformer through high voltage panel HVP-3 and the 120/208V Distribution Center 1 to a newly installed high voltage panel HVP-3A and two new low voltage panels designated LP-46 and HC- 1I Electrical Power Panel.
IV-3
All electrical components have sufficient capacity to provide the necessary loads and remain below an 80%
overall panel loading.
IV-4
SECTION V NEW TESTS AND EXPERIMENTS January 1, 2014 through December 31, 2014 New tests or experiments approved during this period under a Reactor Utilization Request (RUR) were as follows:
RUR 219, as amended: Enriched Cadmium Oxide - Reflector
Description:
This RUR was amended to increase the authorized mass from 2.0 milligrams to 5.0 milligrams and to increase the enrichment of Cadmium-144 in the cadmium oxide compound from 98% Cd- 114 up to 100% Cd- 114 in support of research and development activities.
RUR 449: Preliminary TeO 2 Target Irradiations
Description:
This RUR authorizes the irradiation of up to 180.0 grams of natural tellurium dioxide in support of research and development activities.
RUR 440: Tellurium Dioxide Irradiation
Description:
This RUR authorizes the irradiation of up to 180.0 grams of tellurium dioxide in support of research and development activities.
RUR 443: Low Enriched Uranium Foil in an Aluminum Foil Recoil Barrier
Description:
This RUR authorizes the irradiation of up to 5.0 grams of low-enriched uranium foil, wrapped in an aluminum recoil barrier, in support of research and development activities.
RUR 444: Irradiation U0 2 (LEU) Powder contained in SiC Target Holder
Description:
This RUR authorizes the irradiation of up to 3.5 grams of low-enriched uranium oxide powder, enclosed in a silicon carbide cylinder encapsulated in titanium, in support of research and development activities.
RUR 445: Uranium Dioxide (Natural U0 2) Microspheres
Description:
This RUR authorizes the irradiation of up to 50.0 grams of natural abundance uranium dioxide microspheres in support of research and development activities.
RUR 450: Enriched U0 2 Microspheres
Description:
This RUR authorizes the irradiation of up to 1.5 grams of low-enriched uranium dioxide microspheres in support of research and development activities.
Each of these tests or experiments has a written safety evaluation on file and a 10 CFR 50.59 Screen, if applicable, to assure that the test or experiment is safe and within the limits of the Technical Specifications.
V-1
The safety evaluations have been reviewed by the Reactor Manager, Reactor Health Physics Manager, Assistant Reactor Manager-Physics, and the Reactor Safety Subcommittee, as applicable.
V-2
SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2014 through December 31, 2014 Inspections:
There was one NRC inspection reviewing Special Nuclear Material (SNM) activities. All records and activities were found to be in compliance with NRC rules and regulations. No violations were noted.
Reactor Characteristic Measurements:
Sixty-nine (69) refueling evolutions were completed in 2014. Excess reactivity verifications were performed for each refueling. The largest measured excess reactivity was 4.06%. MURR Technical Specification 3.1 (f) requires excess reactivity to be less than 9.8%.
Reactivity Measurements:
In March 2014, the beryllium reflector, which surrounds the reactor core, was replaced. As part of this major maintenance activity, the change in reactivity due to the reflector replacement was quantified.
Additionally, the thermal and epithermal neutron flux profiles in the center test hole (flux trap) and graphite reflector region were measured using flux wires after the replacement.
Differential blade-worth measurement of all four (4) shim control blades and the regulating blade were performed following the beryllium reflector replacement. Additionally, differential blade-worth measurements of four (4) shim control blades were performed following either planned maintenance of a control blade or characterization of the bum-in effect of a new control blade.
Four (4) reactivity measurements were performed to determine the reactivity worth of all samples, including the sample holder, loaded in the flux trap region.
Two (2) reactivity measurements were performed to determine the reactivity worth of a fueled experiment conducted in the graphite reflector region.
Two (2) reactivity measurements were performed to determine the reactivity worth of the newly installed graphite reflector element No. 51 (Position 5A) and the sample irradiation position "L-6," associated with the new reflector element.
VI-I
SECTION VII RADIOACTIVE EFFLUENT January 1, 2014 through December 31, 2014 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2014 through December 31, 2014 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide Activity (Ci)
H-3 2.598E-01 S-35 1.227E-02 Co-60 6.416E-03 Zn-65 1.93 1E-03 P-32 1.257E-03 Ca-45 6.246E-04 Tc-99m 3.586E-04 Ag-i 10m 2.894E-04 Cr-51 2.791E-04 Mo-99 2.751E-04 Sc-46 1.439E-04 Sb-124 1.192E-04 Ru-103 7.37 1E-05 Lu-177 7.123E-05 Mn-54 5.676E-05 Fe-59 2.423E-05 W-181 2.189E-05 In-l 5m 2.060E-05 Cs- 134 1.138E-05 Cs-137 1.1lIE-05 Total H-3 2.598E-01 Total Other 2.425E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."
VII-1
TABLE 2 STACK EFFLUENT January 1, 2014 through December 31, 2014 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration Total Release TS Limit Multiplier % TS (jCi/ml) (Ci)
Ar-41 2.59E-06 1.16E+03 350 74.2642 1-131 4.40E-13 1.97E-04 1 0.2201 H-3 1.95E-08 8.72E+00 350 0.0558 C-14 2.35E-11 1.07E-02 1 0.0079 Hg-203 3.3 1E-14 1.48E-05 1 0.0033 1-133 1.05E-1 1 4.69E-03 350 0.0030 Au-196 1.46E-15 6.50E-07 350 0.0004 Os-191 4.17E-15 1.86E-06 1 0.0002 Xe-133 2.98E-10 1.33E-01 350 0.0002 Sn- 113 1.00E-15 4.46E-07 1 0.0001 Ru- 103 7.42E-16 3.31E-07 1 0.0001 Note: C-14 activity is calculated based on the ratio of argon to nitrogen in the air and the (n, p) reaction cross sections for the activation of N-14 to C-14.
Isotopes observed at < 0.0001% Technical Specification limit are not listed.
Stack Flow Rate = -30,000 cfin Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, Amended Facility License No. R-103 Technical Specifications.
VII-2
SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2014 through December 31, 2014 Environmental samples are collected two times per year at eight (8) locations and analyzed for radioactivity. Soil and vegetation samples are also taken at each location. Water samples are taken at three (3) of the eight (8) locations. Subsurface soil samples are taken at six (6) locations each period. Analytical results are shown in Tables 1 and 2.
Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2014. All doses are approximately 29 mR/year or less, except monitor numbers 9 and 15. These monitors are located at or near loading dock areas where packages containing radioactive material are loaded or traverse prior to being placed on transport vehicles. The doses recorded by these monitors are considered to be the result of exposure to packages in transit. The environmental monitoring program confirms that minimal environmental impact exists from the operation of the MURR facility.
The number of radiation and contamination surveys performed each month is provided in Table 4.
TABLE 1
SUMMARY
OF ENVIRONMENTAL SET 85 - Spring 2014 Detection Limits' Matrix Alpha Beta Gamma Tritium Water 1.27 pCi/L 5.14 pCi/L 186.03 pCi/L 5.19 pCi/mL of sample Soil 0.73 pCi/g 3.30 pCi/g 0.58 pCi/g N/A Vegetation 1.44 pCi/g 8.28 pCi/g 1.42 pCi/g 5.07 pCi/mL of distillate Subsurface Soil 1.15 pCi/g 4.38 pCi/g 0.59 pCi/g N/A Activity Levels - Vegetation Alpha Beta Gamma H-3 Samle (pCi/gram) (pCi/gram) (pCi/gram) (<Ci/m.)
1V85 < 1.44 18.91 < 1.42 < 5.07 2V85 < 1.44 21.95 < 1.42 < 5.07 3V85 < 1.44 13.75 < 1.42 < 5.07 4V85 < 1.44 34.52 < 1.42 < 5.07 5V85 < 1.44 23.34 < 1.42 < 5.07 6V85 < 1.44 25.89 1.49 < 5.07 7V85 < 1.44 22.38 < 1.42 < 5.07 10V85 < 1.44 27.81 < 1.42 < 5.07 VIII-1
TABLE 1 (Cont'd)
SUMMARY
OF ENVIRONMENTAL SET 85 - Spring 2014 Activity Levels - Soil Alpha Beta Gamma Sample (pCi/gram) (pCi/gram) (pCi/gram) 1S85 < 0.73 20.75 3.17 2S85 1.72 17.43 3.56 3S85 < 0.73 17.90 2.11 4S85 0.96 18.61 2.38 5S85 0.94 17.43 2.29 6S85 0.95 12.06 2.33 7S85 0.95 14.18 2.20 10S85 < 0.73 19.24 3.39 Activity Levels - Water Alpha Beta Gamma H-3 Sample (pCi/gram) (pCi/gram) (pCi/gram) (<Ci/m9 4W85 < 1.27 <5.14 < 186.03 <5.19 6W85 < 1.27 <5.14 < 186.03 <5.19 10W85 < 1.27 <5.14 < 186.03 < 5.19 Activity Levels - Subsurface Soil Alpha Beta Gamma Sample (pCi/gram) (pCi/gram) (pCi/gram)
SWSS85 < 1.15 20.53 5.17 NESS85 1.54 25.37 4.28 NSS85 < 1.15 19.56 17.45 WSS85 < 1.15 20.72 4.23 ESS85 < 1.15 19.94 15.25 SSS85 1.78 20.72 3.90 Note 1: Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity (MDA).
VIU-2
TABLE 2
SUMMARY
OF ENVIRONMENTAL SET 86 - Fall 2014 Detection LimitsI Matrix Altha Beta Gamma Tritium Water 0.00 pCi/L 3.17 pCi/L 210.94 pCi/L 5.32 pCi/mL of sample Soil 0.71 pCi/g 3.38 pCi/g 0.63 pCi/g N/A Vegetation 0.00 pCi/g 6.52 pCi/g 1.77 pCi/g 5.29 pCi/mL of distillate Subsurface Soil 1.23 pCi/g 3.89 pCi/g 0.68 pCi/g N/A Activity Levels - Vegetation Alpha Beta Gamma H-3 Sample (pCi/gram) (pCi/gram) (pCi/gram) (nci/ml) 1V86 0.63 38.52 < 1.77 < 5.29 2V86 0.61 21.88 < 1.77 < 5.29 3V86 0.60 8.94 < 1.77 < 5.29 4V86 0.60 23.95 < 1.77 < 5.29 5V86 1.20 32.88 < 1.77 < 5.29 6V86 0.60 35.74 < 1.77 < 5.29 7V86 0.63 17.86 < 1.77 < 5.29 10V86 1.20 54.33 < 1.77 < 5.29 Activity Levels - Soil Alpha Beta Gamma Sample (pCi/gram) (pCi/gram) (pCi/gram) 1S86 1.55 22.83 2.67 2S86 <0.71 14.77 1.96 3S86 0.78 19.16 2.60 4S86 1.35 15.01 1.94 5S86 1.21 21.84 3.55 6S86 <0.71 15.51 2.53 7S86 <0.71 15.31 2.80 10S86 1.53 21.88 3.43 VIII-3
TABLE 2 (Cont'd)
SUMMARY
OF ENVIRONMENTAL SET 86 - Fall 2014 Activity Levels - Water Alpha Beta Gamma H-3 Sample (lvCi/g'am) (pCi/gram) (pCi/gram) (<Ci3ml) 4W86 0.92 6.20 < 210.94 < 5.32 6W86 0.31 <3.17 < 210.94 < 5.32 10W86 0.31 7.66 < 210.94 < 5.32 Activity Levels - Subsurface Soil Alpha Beta Gamma Sample (pCi/ram) (pCi/gram) (pCi/gram)
SWSS86 < 1.23 18.97 1.48 NESS86 < 1.23 22.84 1.73 NSS86 1.55 17.68 3.45 WSS86 < 1.23 18.78 3.16 ESS86 < 1.23 24.92 1.65 SSS96 < 1.23 21.15 1.48 Note 1: Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity (MDA).
VIII-4
TABLE 3 ENVIRONMENTAL TLD
SUMMARY
January 1, 2014 through December 31, 2014 Badge Direction Map Distance from 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total Number From MURR MURR Stack 2014 2014 2014 2014 2014 (meters) Net mR Net mR Net mR Net mR Net mR Control 0 N/A 26.0 27.0 27.0 27.0 107.0 1 Control 1 16600 27.0 27.0 27.0 25.0 106.0 2 Control 2 16600 26.0 27.0 22.0 26.0 101.0 3 SSW N/A 0.0 1.0 0.0 0.0 1.0 4 SSW 50 14.0 5.0 5.0 5.0 29.0 5 NE 57 12.0 7.0 5.0 5.0 29.0 6 N 34 2.0 3.0 3.0 2.0 10.0 7 SW 27 4.0 4.0 0.0 0.0 8.0 8 S 27 8.0 3.0 0.0 2.0 13.0 9 NE 149 19.0 20.0 11.0 14.0 64.0 10 NW 149 0.0 0.0 0.0 0.0 0.0 11 ENE 301 2.0 3.0 0.0 0.0 5.0 12 NNE 316 2.0 1.0 0.0 2.0 5.0 13 S 156 0.0 0.0 0.0 0.0 0.0 14 S 65 0.0 1.0 0.0 0.0 1.0 15 SE 107 18.0 13.0 17.0 16.0 64.0 16 E 293 0.0 0.0 0.0 0.0 0.0 17 NE 476 0.0 0.0 0.0 0.0 0.0 18 NNE 606 0.0 0.0 0.0 0.0 0.0 19 NE 907 0.0 0.0 0.0 0.0 0.0 20 SE 236 0.0 0.0 0.0 0.0 0.0 21 ESE 168 2.0 0.0 0.0 0.0 2.0 22 NW 110 0.0 0.0 0.0 0.0 0.0 23 SSW 328 4.0 2.0 1.0 0.0 7.0 24 SSW 480 0.0 0.0 0.0 0.0 0.0 25 SW 301 3.0 0.0 0.0 0.0 3.0 26 WSW 141 0.0 0.0 0.0 0.0 0.0 27 WNW 210 0.0 0.0 0.0 0.0 0.0 28 NW 255 0.0 1.0 0.0 0.0 1.0 29 NNW 328 0.0 0.0 0.0 0.0 0.0 30 NNW 671 0.0 0.0 0.0 0.0 0.0 31 NNW 724 0.0 0.0 0.0 0.0 0.0 32 E 671 0.0 0.0 0.0 0.0 0.0 33 ENE 587 NR 0.0 0.0 0.0 0.0 34 SSE 499 0.0 0.0 0.0 0.0 0.0 35 SE 419 6.0 7.0 3.0 5.0 21.0 36 NE 690 0.0 0.0 0.0 0.0 0.0 37 NW 556 0.0 0.0 0.0 0.0 0.0 38 W 491 1.0 0.0 0.0 0.0 1.0 39 N 541 0.0 0.0 0.0 0.0 0.0 40 NNE 137 0.0 0.0 0.0 0.0 0.0 41*
42*
43 Spare N/A 0.0 1.0 0.0 0.0 1.0 44 S 65 2.0 0.0 0.0 0.0 2.0 45 E 70 7.0 9.0 1.0 6.0 23.0 46 ESE 95 0.0 0.0 0.0 0.0 0.0
- These badge numbers are no longer used.
VII-5
TABLE 4 NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS January 1, 2014 through December 31, 2014 Radiation Surface Contamination* Air Samples** RWPs January 82 82 55 11 February 82 82 27 7 March 87 87 39 9 April 76 76 16 12 May 100 100 9 8 June 93 93 27 21 July 100 100 45 11 August 103 103 49 8 September 105 105 65 5 October 92 92. 68 10 November 82 82 52 9 December 107 107 57 13 TOTALS 1109 1109 509 124
- In addition, general building contamination surveys are conducted each normal work day.
- Air samples include exhaust stack Ar-41, containment building Ar-41, sump entries, and hot cell entries.
Miscellaneous Notes Miles Watson was hired as an Health Physics Technician in July 2014.
Taylor Damyen was hired as an Health Physics Technician in October 2014.
Adam Jandeska was hired as Assistant Reactor Health Physics Manager in August 2014.
During calendar year 2014, MURR shipped 850 cubic feet of low-level radioactive waste containing 508 mCi of activity.
VIII-6
SECTION IX Summary of Radiation Exposure to Facility Staff, Experimenters and Visitors January 1, 2014 through December 31, 2014 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP AC BCS DO FOE HC/SH HP IRR NA NS OPS PRO QA RES RP SIL TEE WC Total January 0 0 0 2 360 95 2 6 59 1585 248 33 2 9 219 0 50 2670 February 0 16 0 3 494 77 8 9 63 1123 177 69 2 31 146 0 21 2239 March 4 31 2 215 510 622 0 2 14 6395 101 137 1 24 107 2 100 8267 April 11 3 0 0 387 105 1 16 37 1950 161 133 4 103 203 0 102 3216 May 0 4 2 0 421 139 2 4 25 1351 178 152 94 18 251 6 41 2688 June 5 17 1 21 663 241 10 13 114 2663 284 256 62 45 365 14 176 4950 July 0 0 0 47 580 178 10 29 1 1978 154 66 0 33 629 4 20 3730 August 0 0 0 0 468 230 0 12 53 2032 191 55 6 19 377 0 14 3457 September 0 0 0 0 632 331 8 24 110 2058 184 51 2 38 412 0 90 3940 October 0 2 0 0 440 248 8 34 36 2204 175 48 1 13 333 0 153 3695 November 3 3 15 4 298 78 0 26 4 1703 167 82 6 7 225 0 69 2690 December 0 3 0 5 305 186 2 8 13 1485 99 77 0 19 301 0 43 2546 Total for Year 23 80 20 297 5558 2530 51 183 529 26527 2119 1159 180 359 3568 26 879 44088 Monthly Avg 2 13 2 25 463 211 4 15 44 2211 353 97 15 30 297 9 147 3674 Highest WB 13 22 3 95 1441 776 48 49 135 1460 383 287 54 60 1340 8 297 (annual)
High EXT 261 93 NM 123 3805 1312 21 2672 698 2223 7612 795 375 1348 3854 382 993 (annual)
AC - Analytical Chemistry BCS - Business & Central Services HP - Health Physics OPS - Operations RP - Radiopharmaceutical DO - Director's Office IRR - Irradiations PRO - Isotope Processing SIL - Silicon FOE - Shops & Support NA - Nuclear Analysis QA - Quality Assurance TEE - Trace Elemental Epidemiology HC/SH - Hot Cell/Shipping NS - Neutron Scattering RES - Research WC - Work Control WB = Whole Body NM = Not Monitored Analysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA.
Radiation workers who are not full time staff members have radiation exposures which are generally lower than full time radiation workers.
NOTES:
Dosimetry services are provided by Mirion Technologies (except self reading dosimetry).
March personnel doses are significantly higher than average due to the removal and installation of the beryllium reflector which occurs approximately every eight years.