ML18058A747
ML18058A747 | |
Person / Time | |
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Site: | University of Missouri-Columbia |
Issue date: | 02/23/2018 |
From: | Meffert B, Sanford M Univ of Missouri - Columbia |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML18058A747 (42) | |
Text
Ii) University of Missouri Research Reactor Center 1513 Research Park Drive Columbia, MO 65211 PHONE 573-882-4211 WEB murr.missouri.edu February 23, 2018 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
REFERENCE:
Docket 50-186 University of Missouri-Columbia Research Reactor Renewed Facility Operating License No. R-103
SUBJECT:
University of Missouri Research Reactor 2017 Reactor Operations Annual Report Enclosed is a copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor (MURR). The reporting period covers January 1, 2017 through December 31, 2017.
This document is submitted to the U.S. Nuclear Regulatory Commission in accordance with the MURR Technical Specification (TS) 6.6.e.
Please note the following three (3) changes in data presentation in this year's report compared to previous years.
- 1. On Page VII-1, the Sanitary Sewer Effluent activities listed in Table 1 are being reported in milliCuries (mCi) this year. In past annual reports, these activities were reported in Curies.
However, these activities are calculated and tracked throughout the year in mCi. So, MURR has changed the annual report activity units to match existing records eliminating the potential for unit conversion errors when transferring data to the annual report. TS 6.6.e(6) requires MURR to summarize radioactive effluents to the environs in the annual report, but the TS does not state the specific radioactivity units to be provided.
- 2. On Page VII-2, the Stack Effluent total release activities listed in Table 2 are being reported in microCuries (µCi) this year. In past annual reports, these activities were reported in Curies.
However, these activities are calculated and tracked throughout the year in µCi. So, MURR has changed the annual report activity units to match existing records eliminating the potential for unit conversion errors when transferring data to the annual report. TS 6.6.e(6) requires MURR to summarize radioactive effluents to the environs in the annual report, but the TS does not state the specific radioactivity units to be provided.
- 3. On Page VIII-5, the Environmental Thermoluminescent Dosimeter (TLD) summary provided in Table 3 has negative values reported for the net millirem (mrem) calculations. Since the net mrem is calculated by taking the gross mrem reading of each individual TLD and subtracting the mrem reading of a control TLD, statistical variations in TLD reading will cause net mrem calculations to be positive, zero, 0r negative. Beginning in 2006, MURR began to report all negative net environmental TLD calculations as zero (0) based on a comnient from an external party. However, reporting zero (0) for every negative number artificially removes data from the annual report.
MURR is now reversing its reporting back to pre-2006 annual report methods by including the actual value of the negative net TLD calculations in an attempt to show all relevant data with its statistical variation.
If you have any questions regarding the contents of this report, please contact Bruce Meffert at MeffertB@missouri.edu or by calling (573) 882-5118.
ENDORSEMENT:
Sincerely, Reviewed and Approved
- £~~ o;Y/~
Bruce A. Meffert , Matthew R. Sanford Reactor Manager Interim Reactor Facility Director BAM/jlm Enclosure xc: Mr. Geoffrey Wertz, U.S. NRC Mr. Johnny Eads, U.S. NRC
UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2017 - December 31, 2017
UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2017 through December 31, 2017 Compiled by the Research Reactor Staff of MURR Submitted by:
Reviewed and approved by:
Matthew R. Sanford Interim Reactor Facility Director
UNNERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2017 through December 31, 2017 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 2017.
Included within this report are changes to MURR operating procedures related to reactor safety; revisions to the Safety Analysis Report (SAR); plant and system modifications; new tests and experiments; special nuclear material and 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 6.6.e.
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 (CFD); 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.
Significant efforts by MURR and NRC staff to complete the process of renewing the Facility Operating License resulted in the NRC issuing MURR's Renewed Facility Operating License No. R-103 on January 4, 2017. This renewed license authorizes MURR to operate until 203 7.
Some of the major facility projects that were supported by Reactor Operations during this past calendar year included (1) installation of two additional charcoal filter banks to the 1-131 processing hot cell ventilation exhaust system, (2)
' of nuclear instrumentation signal processor nos. 1 and 2 fission chambers and cabling, (3) replacement replacement of nuclear instrumentation power range channel no. 6 detector and cabling, (4) replacement of the air actuator latching mechanism for reactor containment building truck entry door 101, (5) replacement of 30 valve diaphragms and 60 flange gaskets in both the primary and pool coolant demineralizer loops, (6) replacement of primary coolant circulation pump 501B casing gasket, and (7) irradiation and processing of multiple natural uranium targets to determine the feasibility of producing molybdenum-99 using a variety of processing technologies.
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 low-enriched uranium (LEU) fuel replacement. Although each one of the five high-performance reactors is responsible for its own feasibility and safety studies, regulatory interactions, and fuel procurement and conversion, there are common interests and activities among all five reactors that will benefit from a coordinated, working-group effort. One PhD student completed their research work in determining the material property changes in the beryllium reflector, and hence its lifetime, as a result of fuel conversion. In August, MURR submitted its LEU Conversion Preliminary SAR to the NRC.
Reactor Operations management also wishes to commend the four individuals who received their Reactor Operator certifications and the two 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.
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TABLE OF CONTENTS I. Reactor Operations Summary ......................................................................................... I-1 through 9 IL MURR Procedures .......................................................................................................... II-1 through 13 A. Changes to Reactor Operations Procedures B. Changes to Emergency Plan Implementing Procedures C. Changes to Radiological Control, Byproduct Material Shipping, and Preparation of Byproduct Material for Shipping Procedures III. Revisions to the Safety Analysis Report ......................................................................... III-1 IV. Plant and System Modifications ...................................................................................... IV-1 V. New Tests and Experiments ............................................................................................ V-1 VI. Special Nuclear Material and Reactor Physics Activities ............................................... VI-1 VIL Radioactive Effluent ........................................................................................................ VII-1 through 2 Table 1 - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII. Environmental Monitoring and Health Physics Surveys ................................................. VIII-1 through 6 Table 1 - Summary of Environmental Set 91 - Spring 2017 Table 2 - Summary of Environmental Set 92 - Fall 2017 Table 3 - Environmental TLD Summary Table 4- Number of Facility Radiation and Contamination Surveys IX. Summary of Radiation Exposure to Facility Staff, Experimenters, ............................... IX-1 and Visitors lll
SECTION I REACTOR OPERATIONS
SUMMARY
January 1, 2017 through December 31, 2017 The following table and discussion summarizes reactor operations during the period from January 1, 2017 through December 31, 2017.
Full Power % of Total Full Power % of Month Full Power Hours Megawatt Days
," Time Scheduled*
January 640.88 267.15 86.1 96.4 February 601.64 250.77 89.5 100.3 March 673.75 280.78 90.6 101.4 April 632.57 263.65 87.9 98.5 May 658.40 274.45 88.5 99.l June 634.62 264.62 88.1 98.9 July 623.47 260.00 83.8 93.8 August 678.06 282.65 91.l 102.0 September 645.20 268.93 89.6 100.5 October 656.66 273.76 88.3 98.8 November 615.37 259.37 85.5 95.9 December 668.87 278.84 89.9 100.7 Total for 7,729.49 3,224.97 88.24 98.86 tine Year
- 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.
JANUARY 2017 The reactor operated continuously in January with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for operator licensing examinations, and three unscheduled/unplanned power reductions. A U.S. Nuclear Regulatory Commission (NRC) license examiner administered reactor operator licensing examinations. On January 4, the NRC issued Renewed Facility Operating License No. R-103.
On January 8, with the reactor operating at 10 MW in the automatic control mode, the reactor automatically scrammed due to a momentary loss of normal electrical power. All immediate and subsequent actions of reactor emergency procedure REP-11, "Momentary Loss ofNormal Electrical Power," were completed. The momentary electrical power loss was confirmed by contacting the University of Missouri power plant. The power plant explained that a high voltage switch failed, knocking out power to half of the plant and causing several voltage spikes throughout the campus 1-1
electrical supply system. The reactor was returned to 10 MW operation after the scheduled maintenance day was completed.
On January 9, while conducting pre-startup checks on the regulating blade with the reactor operating, but all four shim control blades fully inserted at a shutdown power level, the expected 'Reg Rod Bottomed Rod Run-In' annunciation was not received when the regulating blade drive mechanism was inserted to the bottom end of its travel. The duty operator secured the reactor by placing Master Control Switch lSl to the 'OFF' position, thus minimizing the time that MURR deviated from Technical Specification (TS) 3.2.£8. Investigation revealed that the fault was intermittent.
However, the exact faulty component was not found. A suspect relay coil 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." Permission to restart the reactor was obtained from the Reactor Facility Director, and the reactor was subsequently returned to 10 MW operation.
Failure of the regulating blade rod bottomed rod run-in during reactor operation is a deviation from TS 3.2.f.8.
Licensee Event Report No. 17-01 was submitted to the NRC on January 23, 2017,.
On January 10, the reactor was shut down to re-investigate the issue with the regulating blade drive mechanism that may not have been resolved on January 9. After reactor shutdown, the applicable portions ofCP-14 were completed satisfactorily, and an investigation of the lower 'Reg Blade Bottomed' limit switch was performed. The lower limit switch was confirmed to have an intermittent fault and was replaced. After the switch was replaced, electronic maintenance procedure EMP-12B, "Regulating Blade Drive," was performed on the regulating blade drive mechanism, and the applicable portions ofCP-14 were completed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.
On January 17, with the reactor operating at 10 MW in the automatic control mode, a 'Channel 4, 5, or 6 Downscale' alarm was received. Upon discovery that the regulating blade drive mechanism was not operating, the duty operator initiated a manual reactor scram. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed. The output shaft of the gearbox for the drive had sheared. Inspection revealed some misalignment between the gearbox output shaft and the adapter. The cause of the misalignment was angular displacement between the inner and outer race of the thrust bearing which allowed the adapter to misalign. A new bearing with tighter tolerances was installed, and the output shaft was replaced. Operability checks were performed satisfactorily, including the applicable sections of CP-14. Permission to restart the reactor was obtained from the Reactor Facility Director, and the reactor was subsequently returned to 10 MW operation.
Failure of the regulating blade and the regulating blade :Sl 0% rod run-in during reactor operation resulted in deviations from TSs 3.2.a and 3.2.f.8. Licensee Event Report No. 17-02 was submitted to the NRC on January 26, 2017.
Major maintenance items for the month included: replacing the regulating blade drive mechanism lower limit switch; replacing the regulating blade drive mechanism output shaft and thrust bearing; and replacing the anti-siphon system level controller's (LC 965) stainless steel cable that connects the displacer (float) to the controller switch.
FEBRUARY 2017 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements, and one unscheduled/unplanned power I-2
reduction. An NRC inspector conducted a routine scheduled inspection of Security and Material Control and Accountability.
On February 3, the duty operator observed a count rate rise on the iodine channel of the control room off-gas stack radiation monitor strip-chart recorder that corresponded to approximately 87% of the TS effluent release limit.
Throughout the day, actions were taken to manage the release including swapping charcoal filter bank trains, decreasing exhaust ventilation flow rates, attempting to identify and encapsulate potential sources within the 1-131 processing hot cells, and finally completely isolating the 1-131 processing hot cells' exhaust flow. By calendar day February 4, 2017, releases returned to values below the TS limit.
On February 3, it was determined that exhaust ventilation stack effluents had exceeded the maximum controlled instantaneous release concentration limit; therefore, it was a deviation from TS 3.7.b. Licensee Event Report No. 17-03 was submitted to the NRC on February 17, 2017.
On February 7, with the reactor operating at 10 MW in the automatic control mode, the duty operator initiated a manual reactor scram after receiving an 'OPEN' indication on automatic pressurizer water drain valve 527 A without the expected corresponding decrease in pressurizer liquid level. All immediate and subsequent actions of reactor emergency procedure REP-19, "Pressurizer Valves Fail To Operate," were completed. Investigation revealed that pressurizer drain to drain collection system manual throttle valve 515AA immediately downstream of automatic water drain valve 527A was closed, thus preventing the draining of the pressurizer. Manual throttle valve 515AA was repositioned, and the pressurizer drain function was restored and retested. Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.
Major maintenance items for the month included: performing two reactivity worth measurements in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-l 7(B);" loading new de-ionizing bed 'B' and placing it on pool coolant system service; completing Modification Record 16-04, "Upgrade Secondary Coolant System Temperature Transmitters;" and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth of a Shim Control Blade, RTP-1 l(D)."
MARCH2017 The reactor operated continuously in March 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: replacing the air actuator for decay heat removal system isolation valve 546B and completing Modification Record 04-03, Addendum 3, "Removal of Liquid Radioactive Retention System."
APRIL 2017
- The reactor operated continuously in April with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one unscheduled/unplanned power reduction. An NRC inspector conducted a routine scheduled inspection of the Radiation Protection and Shipping Programs.
1-3
On April 20, with the reactor operating at 10 MW in the automatic control mode, a 'Channel 4, 5, or 6 Downscale' alarm was received. Upon discovery that the regulating blade drive mechanism was not operating, the duty operator initiated a manual reactor scram. All immediate and subsequent actions of reactor emergency procedures REP-2, "Reactor Scram," and REP-7, "Rod Position Indication System Failure," were completed. The drive chain for the rod position indication encoder on the regulating blade drive mechanism had disengaged from a sprocket and became bound in another sprocket. The drive chain was replaced, and its sprockets re-aligned. 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." *Permission to restart the reactor was obtained from the Reactor Facility Director, and the reactor was subsequently returned to 10 MW operation.
Failure of the regulating blade and the regulating blade :S 10% withdrawn rod run-in function during reactor operation resulted in deviations from TSs 3.2.a and 3.2.f.8. Licensee Event Report No. 17-04 was submitted to the NRC on May 3, 2017.
Major maintenance items for the month included: performing a back flush of the secondary coolant system side of pool coolant system heat exchanger 521; performing a back flush of the secondary coolant system side of primary coolant heat exchangers 503A and 503B; and replacing the primary coolant demineralizer system outlet filters.
MAY 2017
/
The reactor operated continuously in May with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and two shutdowns for physics measurements. There were no unscheduled/unplanned power reductions this month. Supplemental Information to Licensee Event Report No. 17-03 was submitted to the NRC on May 16, 2017.
Major maintenance items for the month included: performing two reactivity worth measurements in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" loading new de-ionizing bed 'O' and placing it on pool coolant system service; loading new de-ionizing bed 'S' and placing it on primary coolant system service; completing compliance procedure CP-26, "Containment Building Compliance Test;" replacing 18 valve diaphragms and 36 flange gaskets in both the primary and pool coolant demineralizer loops; and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth of a Shim Control Blade, RTP-1 l(D)."
JUNE 2017 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, and two unscheduled/unplanned power reductions. An NRC license examiner administered senior reactor operator licensing examinations.
On June 18, with the reactor operating at 10 MW in the automatic control mode, a Containment Actuation (Reactor Isolation) was automatically initiated by Air Plenum 1 Area Radiation Monitor (ARM). All immediate and subsequent actions of emergency procedure EP-R0-012, "Reactor Isolation," were completed. Radiation levels were determined to be normal. Based on the duty operator's observation of an elevated reading on the Air Plenum 1 ARM during the event, it is suspected the detector provided an intermittent false high signal that caused the trip. The detector circuit was replaced with a calibrated spare. Operability checks were performed satisfactorily, including the applicable 1-4
sections of compliance procedure CP-30, "ARMS *and 16-inch Valve Cabinet and Associated Homs and Lights."
Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.
On June 26, with the reactor operating at 9 MW in the manual control mode, the reactor automatically scrammed while attempting to adjust the potentiometer to lower Power Range Nuclear Instrumentation (NI) Channel 5 (PRM-5) level indication. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram,"
were completed. The potentiometer was adjusted in the correct downward direction, but an electrical spike caused a
'Channel 4, 5, 6 HI Power Scram.' All NI channels operated properly when checked in accordance with NI procedures. The decision was made to change the amplifier for Signal Processor Drawer No. 2 (SP-2) from its current configuration and place the standby amplifier on-service as a means of troubleshooting. Operability checks were performed satisfactorily, including compliance procedure CP-35B, "Nuclear Instrumentation Signal Processor No. 2,"
and the applicable steps of compliance procedure CP-9, "Nuclear Instrumentation Scram and Rod Run-in," for SP-2.
Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation. During the next maintenance shutdown, further investigation revealed the potentiometer had a position that caused erratic resistance. The potentiometer on the PRM-5 portion of the circuit was replaced, and ~P-35B was again completed satisfactorily.
Major maintenance items for the month included: completing Modification Record 88-07, Addendum 4, "Addition of Charcoal Filters and Dehumidifier to HC-11 Exhaust;" completing the biennial change out of control blade 'A' offset mechanism; replacing the alarm/trip unit on the reactor core differential pressure instrumentation channel (DPS-929);
replacing nuclear instrumentation signal processor drawers no. 1 and no. 2; performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth ofa Shim Control Blade, RTP-1 l(D)."
JULY 2017 The reactor operated continuously in July with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, and three unscheduled/unplanned power reductions.
On July 4, a manual scram was initiated during a normal reactor startup with the reactor subcritical and all shim control blades at a height of 5.00 inches withdrawn due to erratic indication on Source Range Nuclear Instrument Channel 1 meter and chart. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram,"
were completed. The positive and negative power supplies in Signal Processor Drawer No. 1 (SP-1) were replaced.
Operability checks of SP-1 were performed satisfactorily, including compliance procedure CP-35B, "Nuclear Instrumentation Signal Processor No. 1," and the applicable steps of compliance procedure CP-9, "Nuclear Instrumentation Scram and Rod Run-in," for SP-1. Permission to restart the reactor was obtained from the Reactor Facility Director, and the reactor was subsequently returned to 10 MW operation.
Failure of the source range nuclear instrument channel during reactor startup is a deviation from TS 3.5.a.3. Licensee Event Report No. 17-05 was submitted to the NRC on July 17, 2017.
On July 11, with the reactor operating at 7.5 MW in the manual control mode, a reactor scram was automatically initiated due to a Power Range Nuclear Instrumentation Channel 6 (PRM-6) Anomaly. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed. The PRM-6 Drawer Inoperative 1-5
light was illuminated and was the suspected cause of the scram. After several hours of troubleshooting, no cause for the anomaly was found. Permission to restart the reactor was obtained from the Associate Director - Reactor &
Facilities Operations, and the reactor was subsequently re~ed to 10 MW operation.
On July 24, with the reactor operating at 10 MW in the automatic control mode, a 'Power Level Interlock' reactor scram was automatically initiated by relay lK.26 contact loss of conductivity. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed. Investigation revealed contacts 3 and 4 on relay lK.26 could be opened with minimal physical agitation. The contacts 3 and 4 were replaced with spare contacts. Operability checks included a successful simulated Power Level Interlock scram initiated by contacts 3 and 4 on relay lK.26. Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.
Major maintenance items for the month included: replacing nuclear instrumentation Signal Processor No. 2 fission chamber and cabling; replacing the pool coolant demineralizer system inlet filters; replacing a primary coolant system temperature recorder; replacing the emergency power generator batteries; replacing nuclear instrumentation Signal Processor No. 1 fission chamber and cabling; and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-l 7(B)."
AUGUST2017 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, and one unscheduled/unplanned power reduction.
On August 28, with the reactor operating at 10 MW in the automatic control mode, the reactor was shut down by.
manual scram to investigate an abnormally rapid decrease in pressurizer liquid level indication. The pressure vessel head packing and flange gasket were checked, the flange gasket replaced, and the head was reinstalled. The reactor was subsequently returned to 10 MW operation.
Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-l 7(B);" performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth ofa Shim Control Blade, RTP-ll(D);" and replacing the air actuator latching mechanism for reactor containment building truck entry door (Door 101 ).
SEPTEMBER 2017 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one unscheduled/unplanned power reduction.
On September 24, with the reactor operating at 10 MW in the automatic control mode, a 'Reactor Loop Lo Press Scram' was automatically initiated by Pressure Transmitter 943 (PT-943) channel. All immediate and subsequent actions of reactor emergency procedure REP-3, "Primary Coolant System Low Pressure or Flow Scram," were completed. Investigation showed no mechanical reason for a low pressure condition in the system. Calibration and I-6
scram set points of low pressure scram channels PT-943, PT-944A, and PT-944B were checked by performing compliance procedure CP-22, "Pressure Transmitters PT 944A/B and 943." No safety issues were found. However, the set points of PT-943 and PT-944 scrams were higher than the normal pressure band (more conservative than normal). Since this shutdown occurred on a Sunday, the Reactor Manager made the decision not to lower the pressure set points (the non-conservative direction) without more checks and more personnel analyzing the situation.
Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently restarted to 10 MW .operation. The reactor was shut down the next day for scheduled maintenance and refueling, and more checks and testing were conducted on the PT-943 and PT-944 channels, which resulted in lowering the PT-943 and PT-944A scram set points.
Major maintenance items for the month included: replacing the cooling tower cell 1 float valve and inspecting the reactor pressure vessel head seating surface.
OCTOBER 2017 The reactor operated continuously in October with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, and two unscheduled/unplanned power reductions. An NRC inspector conducted a routine inspection of Reactor Operations and Emergency Preparedness.
On October 2, with the reactor operating at 10 MW in the automatic control mode, a 'Channel 4, 5, or 6 HI Power Rod Run-In' was automatically initiated due to excessive movement of the shim control blades while performing the
'Within a Shift' operability checks (TS 4.2.a) of the shim control blades and regulating blade. Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.
On October 10, with the reactor operating at 10 MW in the automatic control mode, the reactor was shut down by manual scram to investigate an abnormally rapid decrease in pressurizer liquid level indication. The pressure vessel head packing and flange gasket were checked, the flange gasket replaced, and the head was reinstalled. The reactor was subsequently returned to 10 MW operation.
Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" loading new de-ionizing bed 'W' and placing it on pool coolant system service; replacing 12 valve diaphragms and 24 flange gaskets in both the primary and pool coolant demineralizer loops; and replacing the pool coolant demineralizer system inlet filters.
NOVEMBER 2017 .
The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and eight unscheduled/unplanned power reductions.
On November 1, with the reactor operating at 10 MW in the automatic control mode, a manual scram was initiated by the duty operator in response to a 'Channel 4, 5, or 6 Downscale' alarm and outward motion on the regulating blade.
All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed.
The power decrease was caused by at-power attempts to manually seat leaking anti-siphon isolation valves 543A and 1-7
543B. After the reactor shutdown, the anti-siphon isolation valves were seated satisfactorily. The reactor was subsequently returned to 10 MW operation.
On November 9, with the reactor operating at 10 MW in the automatic control mode, the reactor was shut down by manual scram to investigate a small leak originating from the pump casing of primary coolant circulation pump 501B.
The pump casing gasket was replaced, and no leakage was observed during the subsequent primary coolant system operation. The reactor was subsequently returned to 10 MW operation.
On November 11 through November 12, six 'Channel 4, 5 or 6 HI Power Rod Run-Ins' were automatically initiated from Power Range Nuclear Instrumentation (NI) Channel 6 (PRM-6). For each of the rod run-ins, there was no indication of elevated power on any NI channel including PRM-6. Each time, the duty operator was able to reset the PRM-6 drawer, reset the rod run-in circuit, and commence power recovery. On November 13, investigation concluded that the rod run-ins probably occurred due to increased noise from the PRM-6 detector and/or detector cable. The PRM-6 detector and associated cabling were replaced.
Major maintenance items for the month included: replacing primary coolant circulation pump 501B casing gasket; completing the biennial change out of control blade 'C' offset mechanism; replacing power range nuclear instrumentation channel 6 uncompensated ion chamber detector and cabling; replacing anti-siphon isolation valve 543B actuator; replacing the north main air compressor; replacing control blade 'C' rod drop timer module; and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth ofa Shim Control Blade, RTP-1 l(D)."
DECEMBER 2017 The reactor operated continuously in December with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and three unscheduled/unplanned power reductions. An NRC license examiner administered a reactor operator licensing examination.
On December 6, with the reactor operating at 10 MW in the automatic control mode, a firemain low pressure alarm was received due to a leak in the campus firemain system. Immediate actions of reactor emergency procedure REP-13, "Firemain Low Pressure," were initiated. The duty operator and reactor management concluded that firemain pressure would not be restored to above the alarm set point in a timely fashion. Therefore, the duty operator initiated a manual scram. Firemain pressure remained high enough during the event to ensure the emergency pool fill system was operable satisfying TS 3.9.b at all times. The firemain leak was eventually isolated, and the reactor was subsequently restored to 10 MW operation.
On December 26, with the reactor operating at 10 MW in the automatic control mode, a 'Channel 4, 5 or 6 HI Power Rod Run-In' was automatically initiated from Power Range Nuclear Instrumentation (NI) Channel 6 (PRM-6). There was no indication of elevated power on any NI channel including PRM-6. The duty operator was able to reset the PRM-6 drawer and the rod run-in circuit. Permission was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.
On December 30, with the reactor operating at 10 MW in the automatic control mode, an operator on routine patrol discovered that the differential pressure gauge in the reactor ,containment building was indicating zero (0) inches of water vacuum as compared to the laboratory building pressure. Initial investigation revealed the backup door in the reactor containment building exhaust air plenum had closed, causing a pressure increase in the reactor containment 1-8
building. The console operator subsequently manually scrammed and secured the reactor by placing Master Control Switch 1Sl to the 'OFF' position, thus ending the time that MURR deviated from TSs 3.4.b and 3.4.a. Further investigation revealed that ice had formed in the ~ompressed air piping that supplied air to hold up the backup door.
The ice in the piping was removed. Operability checks were performed satisfactorily, including compliance procedure CP-20, "Backup Doors." Permission to restart the reactor was obtained from the Interim Reactor Facility Director, and the reactor was subsequently returned to 10 MW operation.
Loss of reactor containment building negative pressure with respect to surrounding areas while the reactor is not secured is a deviation from TSs 3.4.b and 3.4.a. Licensee Event Report No. 17-06 was submitted to the NRC on January 12, 2018.
Major maintenance items for the month included: replacing the primary coolant demineralizer system outlet conductivity probe; replacing the primary coolant demineralizer loop outlet isolation valve 527F air actuator and bonnet; and replacing flange gaskets-on primary coolant demineralizer loop piping.
I-9
SECTION II MURR PROCEDURES January 1, 2017 through December 31, 2017 As required by administrative MURR Technical Specification 6.6.e(5), this section of the Reactor Operations 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 Safety Procedure Review Subcommittee and/or the Isotope Use Procedure Review Subcommittee of the Reactor Advisory Committee to meet the requirements of MURR Technical Specification 6.2.a(2).
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 120 revisions issued to the Reactor Operations procedures, forms, operator aids, and policies. Two new procedures, one new form, one ne"" operator aid, and five new charters were issued. The majority of these 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, operator aids, policies, and charters:
I.Number Name Rev* Rev::nate N9tes
~:~g:ii~ .* * * * * * \ ~~~~~~~~~gp:~:~!~~:***** * * * * * * * * * * * * * * * * * ;! !~~~;;~i ~ * * \ . . . ~.~~~ ~~!~~~!:~
1 AP-R0-115 ___J fy!c:i_~ifl.~~tJon R~~CJ_!:~~------ , 11 i 02/13/17 I Full Review AP-R0-115 1 12 '"Tifo3;1 i**1-*M~~~-Editori~i---
AP~RO-=T:fo o
, c~~~~ ~iation 8 06iish7 ! Minor Editorial
,.. :!... 12/12/17
_AP-R0-135 ___) Reactor Utilization Requests---**** ... - - -
AP-RR-003 AP-RR-014 I 10 CFR 50.59 Evaluations
! On-Site Fing~rinting Program O r M~()r Edi!g_rjii_l J 11 'i.***** 03/08/17. Minor Editorial 04/28/17 , New Procedure AP-RR-0 33 1:<:?(::g,Q::.!Q?
i Access Authorization Program for Irradiated I Reactor Fuel in Transit
_I . Reactor*I~adiatio~~~periment~*- * - - * *==*-=j=-:~4 ;
1
- -~~~=~- 17 12/22/1. 7 i
J_Mi~~=~itori_~~--
j Minor Editorial EX-R0-110 \ Pneumatic Tube S stem O l 12/22/17 ! New Procedure
~~:~g:i;~-*-=+::::~-0~:~:g~:::~~-- --- . -**-----*-*--* ,_.1~ I o~~i~~i; !. ~:~~ ~~!~~;!:~
EX-R0-122 I Beam ort 'C' 0 eration 8/18/17 : Minor Editorial EX-R0-123 .- .J Beamport 'D' OpEation_____ /17 i Minor Editorial E?(::g,Q:!~~- . . . . . . . . iBeamport 'E' Operation l 16 08/18/17 ' 1.'1.i,i:l<?t~cl_itorial EX-R0-125 [ Beam ort 'F' 0 eration 1 17 08/18/17 Minor Editorial
,!<M:9_~ : Fuel Movement Sheet _ . _ ___ . I 9 I 11/03/17 ! Min.:c:>_! Eel_~!.<?!!!!!
FM-15 ' )OCFR 50.59Qualified Reviewers List i 22 ..
'*, 0412 8! 17. . . . j' Minor Editorial FM-16 : Primar - Pool Coolant Water Anal sis 11 0211311 7 Full Review EM:!.§.__ i Primary - Pool Coolant Water Analysis ******--*- 1 12 ' 03/28/17 , .¥J!:i:.2.r. Ecl_itoti_iiL.
FM-16 )Primary-Pool.Coolant. WaterAnalysis . )3 ' 07/25/17 ! Minor Editorial FM-18
- Deviation From Procedure Re ort ! 9 i 05/02/17 Minor Editorial FM-18___ :Deviation From_Procedure Rep~rt . -*-*---** J }O ..L.J.!!.Ql~.!.7 ! Mirl,CJ!_:§_ditorJiiL ....
' 11-1
. Numbei:. * ",Name , ,,g, ;::,,_ E.ev Rev Date ,; Notes.,:,
~~~;~ ---- ! ::res~: ~::~!:t~eport i -~ ~ i 6~~;;~~ ~ j M~~:e~~i~~al
_Y_M::...4~---- _____ i__~1:1,c;l~~!~11-~-~-<?c;_~ss D_~a She~--- 2. , ~.Jt .<:8/17 l Minor E~ito!~ .
FM-43 l Nuclear and Process Data Sheet J 25 L 06/09/171 MiP.:()E~4i!orial FM-47 I Deviation From Procedure Report l 7 1 12/11/17 1 Minor Editorial FM-5 5 --*-----*-- I Startug Nuclear Data Sheet __________________ L . 8 __ I__ 05/02/17 __ I__M.~2!.E.dit.9r~l __ _
FM-56 Reactor Routine Patrol
- 21 J Q?D}D? : Full Review FM-56 J Reactor Routine Patrol 22 i 06/09/17 Minor Editorial
_!"M-57 _____ !_Long Form Startup_Checksheet ____________________ i _)5_).06/09/17 ____ _E~!-~ey!~~- __
FM-57 JLongFormStartupChecksheet 26 i 11/03/17 JY!iP.:C>~~4it()ria.:L FM-58 ' Short Form Startup Checksheet 13 I 01/27/17 J Minor Editorial
--~~=~l~--
_i_._
i
~~ _ :e:~:
Filter Status Log
~;keupLog **------*---- ....... . . ----1 182 __
8 I 12/12/17
+~~~~~~~~-~:+=:*~-2~~:~- ~:;:-~:
- Cover Page Customer Sample Pre-Encapsulation Evaluation 1, - -
FM-66 9 05/15/17 Minor Editorial
* .}Y_C>~~l?:~~!...... --------------*-**- . - -*-**-------* **' ________ I _ _ 06/097i_7_i--*-c P .......... .
FM-71 JPneumaticTubeUser_Approval 4 _ _ _ _ _ _ _ _ _ over age Personal History Questionnaire (PHQ) and Self- Full Review 1
FM-90 8 04128117 j
. Disclosure 1
. . ****--* J_ PostMaintenanceValve_Line-upShecksheet ....... : 7 ! _Q.?!?Q!l.? . I Cover Page FM- 127 I MURR Irradiations Encapsulation Evaluation 4 1 06105117 f- M:~~-~~~torial
______________ ' ~~~-~~~et----*-*---------*** ____________ ----; ----:---**--*- --*----------**-*--*-*- ---------------------*-----*
- ~~~~ ****-***********--***--***-****-**---;~~~~~;
- ~t~:~-It~s~:c~~::t--Ba~kw~~~d ~ *****----1.--- ~:;~:;: ~ l ---*--------------~::r~:::*----*
i Investigation for Unescorted Access to MURR 1-------~-~ 1 1
-:::::":5J~~:,;:~;n':=:~=i~~ I~~~?i;;:;-f FM-200 Autho~iza!ion to Conduct Background , 1 03127117 Minor Editorial
~:=~g:: ;;
LCC-001 Reactor Advisory Committee Charter I O 02/14/17 M~:~~~da1 i *-.....,.---,------,---------------*----*--*-----------
New Charter
t22=66l-** ---------*-*----*-* * * * *i-~~i~~0~\~:r~~~!~~~tt.~hf~:r~~-- -* *- * *--** *-l---------i---------- i;;ttt-~--------i-*- ~:: 2~:::~
Lcc 004
_ i Reactor Safety Procedure Review Subcommittee i
' Charter O 02114117 I New Charter
- --***-*----*-**-**********-*-..- *******--***-***- .-***-**--*-*----*--*-*****-**---*-----*---*****--*--******---********-*******----***--********- ***************--. --**-----1*--------*--***1* ****************-**--*--****-***--*------*-*
Lcc _005 I Isotope Use Procedure Review Subcommittee Charter O I 02/14/17 \
' 1 New Charter OA-4 I Valve Operation Air Compressor 10 I 02/13/17 ! Full Review
_QA-~?................ ______J_Regulating Blade Drive Tower..... _ 0 . 10/09/17 i New Operator Aid __
OP-R0-101 _ -* i I11~!~1!1~ll!~i.r..~x~!~ll:1. - ' 13 : 03/28/17 I CoverPage OP-R0-210 Reactor Startup-Normal 17 I 06/09/17 i Minor Editorial OP-R0-210 ____ i Reactor Startup-Normal ______ *---.. *--*-*-----***---- _18 _L__ 10/03/17_}__ Minor Editorial . . . .
OP-R0-210 JReactor Startup-Normal 19 I 12/12/17 1 Minor Editorial OP-R0-211 i Reactor Startup - Hot 15 I 10/03/17 I Minor Editorial OP-R0-212 i Reactor Startup - Recovery from Temporary 15 I 12/22/17 I Minor Editorial
' Power Reduction , ,
- ,5p~o=220 ~~R~acto~-sh~tdo~~110-:;~~--R~d~ction*- . -- . . . . . ' 11 - : .. 01125111 '(-*Mhior Editorial ---
OP-R0-230 I Changing Reactor Power Level *
- L 10 07/25/17 i Minor Editorial OP-R0-250 ! In-PoolFuel Handling _______________i_ __ 18_ . . . . . 03/281}? i ___M!ll()E~~itorial OP-R0-250 - : In-Pool Fuel Handling I 19 : 06/09/17 Minor Editorial OP-R0-250 I In-Pool Fuel Handling i 20 i 08/18/17 j Minor Editorial Q~~RQ-3 lQ_ .........i Nuclear Instrumentation~SignalProcessor # 1_ L
__I _1_? . . . . Q<5(02(17 I .. JY!i.I1C>f_ ~4i.!_C>r_il!L OP-R0-310 JNuclearinstrumentation -SiSllalProcessor#l ' 13 10/03/17 1 Minor Editorial OP-R0-311 i Nuclear Instrumentation - Signal Processor #2 i 13 06/09/17 I Minor Editorial 11-2
- Number ":Notes*
OP-R0-311 [Nuclearinstrumentation-SignalProcessor#2 j 14 J)2/22/17 1i Minor Editorial OP-R0-312
! Nuclear Instrumentation Power Range Monitor -
15 06109 17 Minor Editorial I Channel 6
_9_!1:g,Q:~3 0---~- Nuclear Instrumentation - . Wide Range Monitor _ ..._l~ J Q~(Q?!!Z._'. ___ Minor Editorial_
OP-R0-340 J Nuclear Instrumentation Adjustment ! 12 I 06/09/!] L Minor Editorial i Reactor Power Calculator Flow Potentiometer 1 1
OP-R0-350 I Adjustment 10 1 07/25/17 J Minor Editorial 1
OP-R0-410 i Primary Coolant System 14 ! 05/02/17 I Minor Editorial g::~g::;~ ! :~!::g::;~:~1S<<r!~:~~ly~is . ~~~~~~i ~ . ; ~:~~ ~:!!~~!:i 1
OP-R0-461 __J_Pool Coolant System- One Pump_ Ogeration _!.L.' .. !9/03/1_?.__l__fy!.i:r:ior Ec_ii~<::>rial _
g;:~g::~~ * * * * * * * \:~~i* ~:~:i* *~~~!~~~**:* ~~~7~~:i~~:t~~te~ *******t*! i******~*~;~~;H********;*************~~~~ ~~H~~t:~*
OP-R0-480 1
"' .. ,.,~'.:. r,~ ::!ant System _____ ---------*-**- 21 ! 01/03/17 I Minor Editorial g::~g:;i~ l ~~er~~~~: ~y~te~
OP RO 516 i 1
Valve Operation Air System
. . 113 ! ~;~~~~g lI ~:~~ ~:!!~~!:i
! 12 ! 07/25/17 Cover Page
.. - - .......----..!--- * * --***-***-------*- ....................-.............. 15 I 06/20/17 ! Minor EditOrial g;:~g:;~~ +~::~::~~~ ;~::~ g:~:~:!~~ . i6 : io)o3/i7 i Minor Editorial 2-R0-525 ____ ! Chill Water System **-******--* _ ...............L ...... 9 . 05/02/17 i _¥.!!1.<::>!_~c_litg!!~.L-g::~g:;~~ ************i~r~:~~r:~~e:~:~:~~~;~%t~~ntem .. + t! . ~~~~~~i~ I ~:~~ ~~~!~~!:~
OP-R0-532 I .Drain Collection System I 11 ; 07 /25/17 I Cover Page 0P=Ro~"533- . . . . . . . . . Skimmer . System...................................
1.... .*. . . . . . . . 1 l. .
- 10. . . . . 12/12/17 : . . . . . . . . . cover . Page . ..
OP-R0-555 I Fire Protection System
- 15 03/28/17 i Minor Editorial OP-RO-710 I Area- Radiation Monitoring System 5/17 1 Minor Editorial OP-RO- 720 I Radiation Monitoring - Stack Monitor Operational i 15 03128117 I Minor Editorial I Check , ; 1
-;*;:; _;;~
0
1 1
Off-Gis.(St~ck) Radiatf~i=;-M~~itor.Operati~~~T---j Checks I
-~~*1**-; 7;;-T 8125
~:~~-~~;;~;i~l----
OP=Ro:7jo I Facility Exhaust System * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * . I 17 05/02/i?*j* 1 Minor Editorial
_OP-R0-741__ I WasteTankyy~mOperation___ ---*-******-- _ 22 ~ 05/02/17 I MinorEditorial POL-20 JSpecialNuclear MaterialsManual . . . . . 13 ; 01/27/17 ! Minor Editorial RM-R0-400 I Waste Tank System Filter Replacement 9 03/28/17 l Cover Page RM-R0-405 : Reactor Demineralizer System , 15 I 06/09/17 i Minor Editorial Ri>=ili5~Toci ___ I Fuel Movement ---*--:-13*r 08/25/17J Minor Editorial RP-R0- 200 i Measurement of Differential Worth ofa Shim 7 I 08118117 Minor Editorial I Blade, RTP-11 (D)
RP-R0- 201 I Meas_urement o~~eactivity Worth of Flux Trap 5 08118117 Cover Page
__________ , _Loadmg~ or Ind1v1dual Samp)es, RTP-17(B) ____ , _______ , __________ ,__________________
- Measurement of Reactivity Worth ofMovable ' ;
RP-R0-202 4 06109 17 Minor Editorial
! Samples,RTP-6_ ................................... .... _ L .:
RP-R0-203 I Measurement of Primary Coolant/Moderator 1 , 10103117 , Minor Editorial
+-i_T_e_mperature Coefficient of Reactivity, RTP-19 i SM-R0-025 I Removal, Transfer or Installation of an Offset 2 07/10/17 ' Minor Editorial J Mechanism SM-RO-lOO j D~aining and Filling the Primary Coolant Side of 2 01127117 ! Minor Editorial
- -****-*************-*****------L Pnmary Coolant_System Heat Exchangers ---*-* ------------- , _______
SM-RO-lOO
- I Draining and Filling the Primary Coolant Side of 3 -- ,--~~~~-~~itorial SM-R0-300 ~ : ~~!~rg::,1:i:!~:7.:';!:~~~~1:.:;;f';:~~;;~g +;3__ i. :~:; i- Minm Editorial SM-R0-420 ____J Pressurizer 012,eration - Maintenance &Test J _]___ ,__08/18/17 J Minor.~c_lit<::>!!ll_L __
11-3
Numb~r Name Rev Rev Date-* 1Notes SM-R0-6.~Q j g()nt.E()l~~~~t::~t::~tTi::~t . .. . . :. . . 7 L 01/Q}/ L Minor Editorial i Measuring Control Blade Pull Weight and Blade ' ' I SM-R0-625 I Drop Time with the Test Magnet Assembly, RTP- 5 03/31/17 Minor Editorial
\ 21 SM-R0-635 _____ J_Retractingyrui Reinserting Bearpp5>1t'A'Liner .. ___6 01/27/17 --* Mino.!_~~i!()E~~-l.-
SM-R0-636.......... JRetractingandReinsertingBeamport'B'Liner , 6 . . . . . . . . . .9.1127/17 i Minor Editorial SM-R0-637 I Retracting and Reinserting~ort 'C' Liner I 6 I 01/27/17 i Minor Editorial SM-R0-638 _J_Retractingynd Reinserting Beamp5>rt 'D' Liner ____ I 7 .i.. 01/27 /17 l ~in()r Edit()Ei~!
~~:~g:~!~*************************l*****~::;:~:!::***::~**~:!:::~!:;~~~~. :;:. t:~:;*******. **********!****** ~ **********)******** ~ ~~~;~~ ;********]***** ~:~; ~~!:~;!:~ §.JY.!::~0-66Q. _ J_ Replacement of Inner and Outer Pressure Vessels _J 6 . I 03/31/17 J *- Cover Pag~_
SM-R0-661 I !Poot! Ct~olant Hold-Up Tank Welding Repair 4 . 09/26/17 Minor Editorial
, ns rue ions B. CHANGES TO EMERGENCY PLAN IMPLEMENTING 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 42 revisions issued to the Emergency Plan implementing procedures, forms, and operator aids. The majority of these revisions were strictly format or editorial in nature, such as cover page changes. The following is a list of the revised procedures, forms, and operator aids: !{Number J; Nanie. .:ti, i ,ti * . '.\.:t. ** :S.~v ,Rev Date ,,Notes i. _EP-R0-001 _____ i.P_t::finitio~---**------**-------*-**-**----- i 4 I 09/01/17j MinorEditorial EP-R0-002 ; EmergencyResponsibilities i 6 ; 09/01/17 I Minor Editorial EP-R0-003 \ Emergenc~aredness Training I 5 i 09/01/17 \ Cover Pag_e__ -~~-R0-0..Q.'.! .J. Fire *-*-*********-**-*---*--------***-***** I 7 i 09/01/17 I Minor Editorial
. g:?.:13::Q::QQ5 JMedica!Emergency*************************** --*-----.........*....... 3_ j 09/0U17_J -*-co~er-*P-~g;**-*
EP-R0-006 I Radiological Emergency i 8 I 09/01/17 i Minor Editorial ~~~13:Q~_QO? ________Severe_Natural Phenomenon ***********---- I 7 i 09/01/17 i Cover Page EP-R0-008 \Threat To Security ! 3 . 09/01/17 ' * ** or Editorial EP-R0-009 i Notification of Unusual Event 1 3 I 09/01/17 I Cover Page EP-R0-010 I Alert i 3 I 09/01/17 ! Cover Pag_e__
*****-****-**--*****--*-****-----*---****- ***************-********-**-****-*****----*-**-*-***-****-****- ****-**- ' ****-*******-**-*1 * - - - * - - - - , * - * * * - - - - - - - - - - - * * * - - * * -..- - ~~:~g:~ ~; [~~:~~:~~!~~o~ency I ! . ~~~~~~~; i ~~::; ~:;:
_E.!1.:.~.9..:Q.l} ______JFacilityEvacuation -**--***-**-**** ************- -*** 10 09/01/17 i Minor Editorial EP-RO-Ol 4 I ::::;~i~tanning Zone and~~~~ Ar-~:*--*-**-** :.. 9-_ J_~~~~-~.~:.t~0~ii~~t~-~~~~
~~:~g:~ ~ ~ +~::;~: ~;~~:!~~::t~: * *
- _§:?.:.g..Q..::.Ql.§______ : Public Information *-*-----*** ____ J i t~ T g~76i~~; . . i. ~!:~; :~!:~;!:~
3 [ 09/01/ 17 : Minor Editorial EP-R0-017 ___ JEmergencyAirSampling 7 I 09/0.1./17f JY.!ino~..e..~itorial EP-R0-018
- Emergency Radiation Exposure . 7 i 09/01/17 ; Minor Editorial EP-R0-020_______LEmergency%quipment Maintenance _ , 6 ! 09/01/17 : ******- Cover Page-*-*-
~~:~~~ . i ;;~r~:~~g~~~:;ation *-----**- / ~ i ~~~~~~~; * ~~::~~:~: ...
FM-102 I EmergencyEventLog 3 ! 09/01/17 __ CoverPage _____ -FM=io3*i . . Facility _Status.................................. -**-----****** : . . . . .3 . )09/0.1/17: . . . . . . . . . cover . Page . . . . . f.1.\'!.:}04 __ . JEmergencyCaUList *-*** --***********-******** *****-*-** J 3 l_J_03/29/l 7 J Minor§.~.i.!.Qrial . . .. II-4
'Number ,~:. Na'me ,:, ~r '
- R~v Rev Date ;;,!Notes N'
;~:~~: ' ' ' ' ' ' ' ' 'j' ' ~: ~: ~~;* ~:~~. ~~:~ *************************************************i******H I ~6J~~;H1** * * * * ~:~~ ~~~i~~}:l*
- J.
FM-105 _____ .. Initial/Follow-Up Emergency Message ___________ [___ 3__J 09/01/17 !***- Minor Editorial
. . FM-106 ____i .... Logo(Personnel.ReleasedFromSite - - !. . . . . . 3 ) . . . . 09/01/17 ... ,cover . J?~ge _
FM-110 i Fire Flowchart l 5 , 09/01/17 I CoverPag~
;~: ~;
FM-113
~ *-=*t~a~~l~~y~~~;!:1chart l Severe Natural Phenomenon Flowchart ***====~* -~===*=-*=I ~=~=J-.-~~~~~~~ ~. . ~==~~~:~. ~:~e*:*-- 3 i 09/01/17 Cover Pag~
FM-114 I SecurityFlowchart . 3 I 09/01/17 t CoverPage FM-115 J Plant Conditions Flowchart ! } I Q~!Q}/Er gc:,y~~)?~g~ FM-116 ! ClassificationFlowchart i 3 I 09/01/17 ! CoverPage C. CHANGES TO RADIOLOGICAL CONTROL, BYPRODUCT MATERIAL SHIPPING, AND PREPARATION OF BYPRODUCT MATERIAL FOR SHIPPING PROCEDURES As required by the MURR Technical Specifications, the Reactor Health Physics Manager reviewed the radiological control procedures and the procedures for the preparation for shipping and shipping of byproduct materials. There were 258 revisions issued to the radiological control, byproduct materials shipping, and preparation for shipping byproduct material procedures, forms, operator aids, and plans. Six new procedures, four new forms, two new operator aids, and one new plan were issued. Three procedures and two forms were obsoleted. The majority of these revisions were strictly format or editorial in nature, such as cover page changes. The following is a list of the new, revised, and obsoleted procedures, forms, operator aids, and plans:
"Number Name Rev Rev Date
- 1' Cleaning Lab Ware for High Purity Materials ,
ACG-NAA-200 7 07/24/17 j Cover Page JAnalysis. ""' . + : + ACG-NAA- 201 I Preparation and Measurement of Standard 7 1 09129117 II Minor Editorial 1 Geometries for High,__P_u_r_ity"--M_a_t_er_i_al_s_ _ _ _ _. . , _ _ _ _ - - + - - - - - + - - - - - - - - i 1 ACG-NAA- I Scheduling and Sample Preparation of High Purity 9 07124117 Minor Editorial 210 I Materials
~~~~::~~~~ *--1 *~l:R!~;i~Yf~::~::~i~:~~~;~:t:;~;~e~e~t-of* ******************************************. _ ........!..... High.Purity.Materials___ ____ . **** : i-~~;;~~;- ********************* 1 *********************-******
1
**---~:::: :::~----
ACG-NAA-1725 I Anal zing Platinum in Silicone 7 I 07 /24/17 Cover Pag_e_ AP-HP-105 ! Radiation Work Permit 15 12/22/17.. '.-- _Cover Page AP-HP-110 . :controlledSpecialExposures .. _?_\ 10/25/17 J . . . . . . . . . coverPage AP-HP-117 MURR Initial Radiation Worker Training Pro~a 13 I 02/14/17 Minor Editorial
-~~-!:l.!':L!? Initial Radiation Worker Training Progra_ _14 _J_ 12122117 . __!\1i1!9L~~it_c:,~i.1!L
- AP-HP-119 Radiation Area Access 9 04/26/1 Minor Editorial AP-HP-122 I Material License Projects Quarterly Review 11 i 07 /10/17 i Cover Pag_e__
~.:!:l_l?.:!}3- _ . . . . . . 1.Yisitor. Dosim~ry_-Reception Desk __ _ - -..-1-2-* 1_ 04126111_! .M~9~__g_4~tsiti.1!L AP-HP-124 I Ordering and Assigning Dosimetry ' 1 12/22/17 1 Cover Page 11-5
.Number . Name .. : ~::J Rev Rey Date .. ;.Notes. 1**
AP-HP- 127 ! Radioactive Material Licensing and Project 5 j 02113117 Obsoleted AP-HP-129 j~~~i&irt~6~~ac~~!:ruest .. ---*- j i4-j04/26/17 Mi~~~Editorial
-~~HP-l~_ _ JHotCellHC-OlControl______ : 15 I 06/09/17
- MinorEditorial
~~~~~i~~ --!~:~~~r;~~~~;i~:~~~~~~alReview _, __ ~ j ~~~~~~i; ~=~!~i~d~:l AP-HP- 140 [ !:~:!~:i and Labeling ofNon-Waste Radioactive ' 3 I 07124117 1
Cover Page i Access Authorization Program for Category 1 l I ' AP-RR-013 I and/or Category 2 Quantities of Radioactive I O ; 02/03/17
- New Procedure i Material
- 1
! Access Authorization Program for Category 1 I AP-RR-013 Minor Editorial I ~!;~~ateg::~~~::1.~1.~:::~~:~i::~t~:: __ J 1 l 06/16/17 AP-SH-001 1 Administrative Procedure - Radioactive Material 10 i 05101117 M. Ed'
- 1 i Ship~g~----------------t---+------;---m_o_r 1 __1t_o_n_a_ 1 AP-SH-OOl i Administrative Procedure - Radioactive Material 11 I 11116117 Cover Page
________________ ;_Ship2._ing__ _ _________ ________ j BPB-SH-023 [Type B_Equipment . Ca1ibration . . ............... I, 6 , 06/02/17 J Cover Page BPB-SH- 024 I Type B USA/0697/B(U)-96 (F-458 Series)
. . . . . . . . . i. . Packagingof.Type . B . RadioactiveMaterial..............................
I 8 J 12/27/17 Cover Page I Packaging of Type B Radioactive Material Using BPB-SH-025 5 09/28/17 Cover Page i USA/0562/B(U)-96 (BEATRICE) BPB-SH- 027 I S~e~ and Dec_ontamination of Returned 8 08104117 Minor Editorial
***-*--*--*-***--, Sh1pp}tlg~amers__ ----*-****************-**-****-*-*---**-**-.***--***--****--,--*****-*--*--*--**--*-****--** ******************-----*-***
i Packaging of Type B Radioactive Material Using i ! I BPB-SH-028 : USA/9337 /B(U)-96 (SAFKEG:-LS) and 6 1 12/27/17 Minor Editorial I l ______ .................................... 1.... USA/9338/B(U)-96 . (SAFKEG-HS)___ , 1 ____ __ BPB-SH-030 I ~~~::o~~~te~::r~:1~~;::?ac~a~~~~ ~~e 3 08/04/17 Cover Page i Packaging Radioactive Material for a Limited BP-SH-010 8 09/28/17 Minor Editorial i Quantity Shipment I 01127117 1--------;--c~~
! Packaging of Type A Radioactive Material Using Minor Editorial BP-SH-011 8 ! USA DOT 7A 55-Gallon , ,
I: Packaging of Type A Radioactive Material Using : I BP-SH-011 I USA DOT 7A 55-Gallon 9 J 1 09128117 Cover Page I Packaging of Type A Radioa~tive Material Using BP-SH-015 6 Minor Editorial i USA DOT 7A Model E-Box 030-181 0 3/08/17 I Packaging of Type A Radioactive Material Using BP-SH-015 7 12/27/17 Cover Page i USA DOT 7A Model E-Box 030-181 BP-SH-Ol 6 i PackagingofRadioactiveMaterial Using USA , 8 : 08117117 Cover Page ______ __________ J DOT.7A.Model_HorIPackag~------ ______ J _____ . . ., _______ --'-- _________________ _
.BP-SH-017 I Packaging of Reusable Type A Radioactive I 5 f 09128117 Minor Editorial Material Using Tracerco LS-6 . . I ! ! Packaging of Type A Radioactive Material Using 1 1
BP-SH-018 f USA DOT 7A NorthStar Medical Radioisotopes 4 07/24/17 Minor Editorial i---------,-i_P_ac_k~a~-----------,--------;----;-------;--------i I Packaging of Type A Radioactive Material Using BP-SH-018 i USA DOT 7A NorthStar Medical Radioisotopes 5 10/11/17 Minor Editorial i Package "---------------*------+-----+----*-------1 BP-SH-031 I Packaging of Type A Radioactive Material Using 4 06102117 Minor Editorial i DOT 7A 20WC-l *
- -********-*--*-----*-******---***-**-- ****-**--*--------- ***************-***---*-********-----*---*-*-*-****-*-*****- .***********-****---******--***--**-****--**** *****--**--*-****** I **************-*****-******-*---*--**-*-*-***- ***********-*-*******--*-****---**-*******--*-
BP-SH- ! Radioactive Material Shipment Package 052 i 17 ! 07 /24/17 Minor Editorial
!Documentation and Labeling . . .
11-6
BP-SH-059 1
- i.;~r.~:~!f ;~;t~!;table Packagin~. .:.~.~*~*~: . 1......
Spectratek Services Reusable Packaging of Type 6 i I' 01/27/17 I Minor Editorial BP-SH-059
, A Radioactive Material 1 I 11116111 I Cover Page 1
Packaging of Type A Radioactive Material Using BP-SH-099 7 10/24/17 Cover Page
- USA DOT 7AMURRModel 1500
' Packaging of Type A Radioactive Material Using BP-SH-145 2 08/17/17 I Cover Page USA DOT 7A F-458 i:--*-----****-*-*----****---*----*----*----****-*-----.. ---*-*-*****-**'--*----- :-----*--; *---**--**********--****+-**-*-*-******-----
BP-SH-192 Packaging of Radioactive Material Using USA O 1 06102117 1. New Procedure DOT 7A Model MURR MAX 1 1 11 BP-SH-192 I ~~~at:~:d~;~~~~erial UsingUSA I *1** ! -~~~~~; 17 Minor Editorial BP-SH-302 l PackagingofTypeARadioactiveMaterial Using 1 Cover Page 10 1 08117117
\ USADOT7AMURRModel6or12 .
J:lM~Qr:===-=~--i. . :~===~~~-**:* *
- 1 Gem~hl~el~adiation. .sieet ----** 7 .... L-1-.. ~-(--Q7_!_1_?_. .-.,+L--.. _M_m_'-o-r *-E.-ditorial FM-12 i Gemstone Loading Sheet 7 ! 12/07/17 I Minor Editorial J
J'M.:28 ________ Controlled Sp=! Exp-OSure Authorization _________6. i 10/11/17 I CoverPytg~ _ FM-29 JDosimetry RequestPacket ! 9 I 01/27/17 I Minor Editorial FM-29 i Dosimetry Request Packet i 10 f 10/11/17 ! Minor Editorial FM-39 ! Contr~l Checks~e~t for Pack~ging ?fRadioactive i 15 05101117 I Minor Editorial -~M-;----- ---r ~:~;;~~l~~::k:;:~:~~r~::~~z;:opfr;a~ioactive 1---l 6 1* 08/17 /17 : -
- Cover Pa e --
FM-51, - -=L ~i~::~:~:;r:a~~::~:d~t::~i~ns~~a~~!et C *:::J=:4 l 07 /07 /17 + Obsolete: FM-52 ' Control Checksheet for Documentation and 19
- 02110117 I Minor Editorial 1 - - - - - - - - , . *_L_a_b_el_in~g of Radioactive Material Shipment I FM-52 Control Checksheet for Documentation and L b I' fR d' . M . I Sh' 20 I 09/28/17 I Minor Editorial 1--------- , a e mg o a 10act1ve atena 1pment __ _ -*-----*----* *-----i
~:~~;~~~!~:~~=~: ;~~~~:t~:~~~~:j.~-~~ . . . . . . . . . \
1 FM-53
. . . . . . . . . i. . ;--\ 02/13/17 I Obs~leted
- ,. Control Checksheet for Spectratek Services 1 II T FM-59 i Reusable Packaging of Type A Radioactive 10 I
1 11/16/17 1., Cover Page
' Material i Control Check Sheet for Packaging of Type A I I
FM-60 Radioactive Material Using USA DOT 7A Model 7 i 7/24/17 i Cover Page
, E-Box 030-181 I I I Control Checksheet for Packaging of Type A I FM-70 Radioactive Material Using Tracerco LS-6 I 5 9/28/17 iI Minor Editorial Reusable i !
FM-76 :::- .. ,~1 Contamination Log 5 6/19/17 Minor Editorial Lutetium Chloride Radiation Protection Data FM-79 11 9/19/17 Cover Page Sheet B FM-81 Yb/Lu-177 Sc;:;~.auuu D~ n 5 12/20/17 Cover Page FM-82 Concentration of Lu. 177 Datasheet 6 12/20/17 Cover Page FM-83 Concentration of PM-149 Data Sheet 6 12/20/17 Minor Editorial FM-84 Dissolution of Lutetium Datasheet 6 12/20/17 Cover Page Control Checksheet for Packaging of Type A FM-98 Radioactive Material Using USA DOT 7A MURR 12 8/17/17 Cover Page
, Model 6 or 12 ! ' Control rhP,.;i,-.,i.oot for Packaging of Type A FM-99 Radioactive Material Using USA DOT 7A MURR 11 10/24/17 Cover Page ! Model 1500 i II-7
FM-107 I Control Checksheet for Packaging Type A I 10 I 06102117
- Minor Editorial
... . . . . . . .l...~a4i<>.a.c:!~Y~. .M.11.!~.r.ial.ii:1:ai:1: . 9Y~1Pac:J<:. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . . . ]. * * * * * *-* * * * * * * --***** .
,_F_M_-_1_20_ _ _ _ _ln_d_i_v1_*d_u_a_lT_ype B QA Training Certification
+-i . 6 I 05/01/17 Minor Editorial
_F_l\l.:!?:Q_ _ _ _J Individual Typ~B QA Trainmg Certification ______J 7 _j . . 11/16/17 f- ____ Cover Pagy; - *
. . Y.M~.!.?:t.. .. . . . . . J !:-1:1!~ti1:1~ Gh:l<>.Et<:ii;: .I>.r.<>.c:~s.s._~<>.!t!}c:a!i<>.i:1:_ L__4 I 03129111 . . . . ggyt::!_I>ag~
FM-125 I Lutetium Chloride Process Notification 5 I 09/19/17 Minor Editorial I Control Checksheet For Packaging of Type A FM-128 i Radioactive Material Using USA DOT 7A MURR 7 08/17/17 Cover Page I Model H or I , __FM-l~Q______ J Ho-166 Nitrate Data Sheet _ -----------------,--1_4***--*i---1_2. ._/2__0_/_1_7_,--._C_overPage _ I Control Checksheet for Packaging of Type B I FM-135 I Radioactive Material Using USA/0562/B(U)-96 ' 6 12/27 /17 Cover Page
......................................!..... (BEATRICE)...... ............................... ,............................... _
FM-137 ! Type B Qualified Shipper List 16 02/10/17 Minor Editorial _FM-137 _________ i_TypeB Qualified Shlpper List 17 __ Q.?_{Q_l/_1_7___Ming.r.~4i!<>._rial__ FM-137......... jTypeBQualifiedShipperList ---- __ 18 ( 07/18/17 M~()E~<:li!<>.!ial FM-137 I Type B Qualified Shipper List i 19 08/04/17 Minor Editorial _:f_l\::!:!_n __ _ ____ I Ty~ Qualified Shipp_erList _ _ I 20 11/08/17 Minor Editorial i Control Checksheet for Leak Testing the FM-138 j SAFKEG-LS or SAFKEG-HS Shipping Package 6 01/27/17 Minor Editorial
... .......... JU sing.the CALTLeakage TestingDevice . ..
j Control Checksheet for Leak Testing.the . FM-138 ! SAFKEG-LS or SAFKEG-HS Shipping Package 7 12/27/17 Minor Editorial
. j Using .the CALTLeakageTesting Device ....................
FM-139
' Lutetium Chloride Radiation Protection Data Sheet C 5 i 03/29/17 Minor Editorial I Control Checksheet for Packaging of Type A FM-141 I Radioactive Material Using SAFKEG-LS and 4 , 06/12/17 Minor Editorial *********-******--***-**------*' SAFKEG-HS -----*--**--**-*-**-*--***-*****-----**--*-****- : I *******-**-***********-*****---****--- ~~:Hi ***************************************I*****~~~-~}*~:~~:~:~~~~**~}~~::~:~; * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 1
***** ~ /. ~~~~~~~; ! ~~~:~**~:::
- 1 FM- 144 I Con!rol~heckshe~tfor~ackagingofTypeA 2 08117117 CoverPage I Rad10actlve Material Usmg Tracerco LS-1 . . _ __J _____ ****--*---*-*--*****-**-*****-
FM-145 I Con!rol ~heckshe~t for ~ackaging of Type A -* __ !_;_j . . 08117117 I Cover Page _______ -**--1 Rad10actlve_Matenal UsmgUSADOT)A.F-458_+----- ***!*-*---***** _____ , ________ --*---- FM-l47 ..............J.I... Radioactive Control Checksheet
. Materialfor Packaging of Type A ................. :............2.................. 06102117 UsingTracercoLS-15. 1.' ...... Minor Editorial FM-147 ! Control Checksheet for Packaging of Type A 3 08/17/17 Cover Page i Radioactive Material Using"Tracerco LS-15 -----------"---+------'---------1 I Control Checksheet for Packaging of Type A I FM-151 I RadioactiveMaterialUsingUSADOT7A55- i 13 / 09/28/17 I MinorEditorial
_______ ,, -*-----** 1 Gallon -* ---****-------*-****-**-******--*********-----**-******-**-***-*******-********- *****'--**********--*-_.]**-**-****-**-*--*--**-*******-**- 1***-***-*-*-**-**---**********-*******-***-*-***-* FM-lS I Required Documentation for Non-MURR Owned 6 6 1 08/04/17 Cover Page
- -**********---- ........................................ i_.Typ_e B . .Shipping.Packages.................................. _.......................................................... 1.............................. 1 FM-lS I Control Checksheet for Type B USA/0697/B(U)-
7 9 06/02/17 Minor Editorial 5 FM-157 ****************************************! ~~~~~~ ~ 11~ ~~;~~:ia:o~o;~~:e13M ;~~~6 ~;~(~j= * * * * * '- 10 1 09/28/17 Minor Editorial I 96 (F-458 Series) Radioactive Material Package "---..-- 1- - + - - - - - - - - - - - - - ! FM-158 . I NOA Waste Tank Sample Analysis 5 07/24/17 Cover Page
*----*************-******--*********-***********-******************!**********************-***+**************-****************************-**-**,---*****************-********-*-***-***--*-=**************-****-***!
FM-159 FM-159
................................... 1....
iI Control Checksheet for Health Physics Review of Radioactive Material . ShipmentDocumentation .............
' Control Checksheet for Health Physics Review of 8
9 06/09/17 12/22/17 J Minor Editorial Minor Editorial
- Radioactive Material Shipment Documentation II-8
I Control Checksheet for Type B Radioactive FM-163 I Material Using USN9337 /B(U)-96 (SAFKEG- 8 08/04/17 Minor Editorial
. . . . . . . . . :. . LS)andUSN9338/B(U)-96(SAFKEG-HS) * * * * * * * * * * * * * * * '* * * . . . . . . . . . j Control Checksheet for Type B Radioactive J 1 FM-163 .... ,~)1.~~~1g~~~~~~9cU~~wi~~~G- .J ~ J. . . 12/27/17****11 Mcm*oovreErdP1"atogre1*a1 FM-165 l Mo-99 Radiation Protection Data Sheet A 2 I 03/29/17
_F_M_-l6J _______:_ j ~~!!iR;i~i~~~;~~:ciizfk;:gs:;i~~e_A___ ----: 3 -*rQ?!Q._7_./1 __7~1__,__C_over_Pag!? _ FM-169 I Radioactive Material Using USA DOT 7A20WC- i 4 1 06/02/17 Minor Editorial
*-*-* I1 . i I Control Checksheet for Packaging of Type A I FM-170 I Radioactive Material Using USA DOT 7A 3 I 06/12/17 Minor Editorial i Northstar Medical Radioisotopes Package ~---~-~------------,
I Control Checksheet for Packaging of Type A FM-170 I Radioactive Material Using USA DOT 7A 4 10/11/17 Minor Editorial I Northstar Medical Radioisotopes Packag'--e----+--~-----1---------1 FM-172 , Lutetium Chloride Radiation Protection Data i Sheet D I 1 / 07121 ; 17 ~ M" Ed"t
- 1
, I mor 1 ona .................---:-***------*--------**-----**--**-**-********--*--*~--'*,""*"'*--****-**--.--*********-*********- ...... _______: **--***--*--*-***--*-----*- *-----**--*********-**-***--*--**-*--****-*
FM-173
....... r.... ~:~~~!~::~~~e:a~~~~~:h ~~r::i~~ . ~~;~:~~********
Control Checksheet for Health Physics Review of
?.......... ?~~?~~.~.?.1: ... ~=~~.~~**********************
FM-173 I Excepted (Limited) Quantity Radioactive Material 1 06/09/17 I Minor Editorial
- ~~~t:~n~hecksheet for Receipt Inspection of [..
FM-175 2 10/24/17 Cover Page Customer Owned Type B Shipping Packag~e----t---------------, Control Checksheet for Packaging of Type A FM-176 FM-176 Radioactive Material Using USA DOT 7A
, Northstar Medical Radioisotopes Package with 7.5 I Ci ofMo-99 ! Control Checksheet for Packaging of Type A ! Radioactive Material Using USA DOT 7A i Northstar Medical Radioisotopes Package with 7.5 \
2 1 1 i i j 05/01/17
, 10/11/17 1
Minor Editorial Minor Editorial 1 I Ci ofMo-99 i , -FM- l 7? i Control Checksheet for Receipt Inspection of i 2 i 10124117 \ C~~*;r-;~~~-- FM-178 i ~:t~~he~k~~~~~~>Jot~~~i~~~{~~~:~s . */ 2 l O1/20/17 j Cover Page FM-178 i Control Checksheet for Hot Cell HC-01 Access I 3 i 02/14/17 Minor Editorial
* ! Control Checksheet for Documentation and
- 1 FM-179 I Labeling of Limited Quantity Radioactive Material O 1 1
03/08/17 New Form FM-179 ~::~1~~~~o~~t:)e~.:~,;"d i ; J- 06/12/17 i Mino,Editorial
********************-~~~~~~~~~:!t::~;~:rhf!a~::;fug of Type A *********************l ****************************** -
FM-192 ~~c~aterial Using USA DOT 7A Model j O 06/02/17 New Form Control Checksheet for Documentation and I FM-194 Labeling of Radioactive Material Shipment , 0 ! 06/23/17 I New Form 1:!::~:;~=~12;;!:riE::;!~~~:~1:;~~~A/B ~=Ft~~;~~:; l-=~-~:-d-Ii~tm-GMP-BR-404 .. J Mo-99 Process Cleaning and Line Clearance . 1
! 5 J 11/14/17 ' Minor Editorial GMP-BR-502 Sodium Iodide 1-131 Solution Batch Record 3 i 09/15/17 j Min~~ Edito~i;i--
11-9
i:\R~v Rev Da:te ** t Notes t~ ** GMP-MCE- 124 : ~aning, Maintenance and Operation ofHC-08 6 01/04/17 Minor Editorial l
**-*************************************************************************************************************************************;******************************l*****************************************-*****;.......................................................****.*......*......................J GMP-MCE-124 I! A/B Cleaning, Maintenance and Operation ofHC-08 i 7 10/02/17 Minor Editorial GMP-MCE-129 i Operation and Maintenance for a Tuttnauer ~870 3 01/19/17 Minor Editorial ! EA-BIL Electronic Tabletop Autoclave ~--------;----z----*-;----------1 GMP-MCE- 129 I Operation and M~intenance for a Tuttnauer 3870 j 4 11107117 I Minor Editorial
____________ :_EA-BIL Electromc Tab~ Autoclave ___________ i __ _ GMP-PRC- 201 I ~;;ns~er of cGMP Lu-177 Chloride Product to
- 03107117 I Minor Editorial *
...........1.................. ppmg GMP-QC-201 i Determination of the Metal Content and Specific 8 05/22/17 Full Review *---+--~
I Activity of Lu-177 Chloride Solution I Determination of the Metal Content and Specific GMP-QC-201 \ Activity of Lu-177 Chloride Solution , 9 , 10/0 2/1 7 , Minor Editorial I Determination of the Metal Content and Specific *
- GMP-QC-201 I Activity of Lu-177 Chloride Solution .......
10
*f 12/01/17 Minor Editorial GMP-QC-252 I Determination of Radiochemical Purity of Lu-177 ! I Minor Editorial i Chloride Solution l4 03/09/17 GMP-QC-252 i Determination of Radiochemical Purity of Lu-177 * *
- l 10/02/17 Minor Editorial f Chloride Solution 15 GMP-QC- 253 i Lu-~ 77 ld~n~ificat~on and Determination of , 20 i 09114117 ! Minor Editorial i Rad10nuchd1c Purity
--*----*-*--------*,-----******------*-----*-***-****************-*****************-******---~.-----***-*****r***-*-*----,.-..- i I i GMP-QC-253 i Lu-~ 77 ld~n~ificat~on and Determination of I 21 10102117 i Minor Editorial I Rad1onuchd1c Punty , I ' i.* Use and Operation of the 1-131 Production Facility l 1 GS-RA-014 l Lifting Crane 1 I 04/28/17 i Minor Editorial GXP-MCE-123 i Cleaning, Maintenance and Operation of Hot Cell 2 1 05118117 Minor Editorial i HC-04 GXP-MCE- 127 I Operation and Maintenance of Optima 2100 DV 8 j 11107117 i Minor Editorial --***-*--*-- * **-* i ~!{~i7: Verification of Potassium Molybdate .. * : ---!-*-**********-*******----*;**-*****---*-*-****** GXP-QC-400
- GXP-QC-400
! :~:i:::::::;::::::~::.,,
(Mo-99) Final Intermediate Radiochemical 4 5 I 03/23/17 12/01/17
*i _ Minm Editorial Cover Page Solution i 1 Radiochemical Purity of Potassium Molybdate !
GXP-QC-402 (Mo-99) Final Intermediate Radiochemical 4 l 02/13/17 Minor Editorial Solution I I Radiochemical Purity of Potassium Molybdate i i GXP-QC-402 , (Mo-99) Final Intermediate Radiochemical 5 12/01/17 Minor Editorial I *
- --***********-**-**-*****!* Solut1on ............... ________*-*************************-****--*-********-*---*-**-**-**- **********---**-**-* ! *--********-*-*-*-****----***-
! Radionuclidic Purity and Identity Confirmation of i GXP-QC-403 I Potassium Molybdate (Mo-99) Final Intermediate j 4 12/01/17 Minor Editorial .................... ______ !.. Radiochemical. Solution ***---*--*- -** ______ : --.--l.........- .........-*--*' *-*-********-***-*-**-*****--*-*****
GXP-QC- : Potassium Molybdate (Mo-99) Final Intermediate 406 4 10/02/17 Cover Page
.. [Peroxide Concentration .Verification .. *****-..-.............. Ti ..... .
I Hot Cell Preparation of Radioactive Material for HC-PS0-002 17 07/07/17 Minor Editorial I Shipment HC-PS0-00 2 I H~t Cell Preparation of Radioactive Material for .
- -*-*-*-********* ........................... i. . .Sh1pment**************-****-********-************--******************------*--*-************* ***, -~~-**
HC-PS0-00 3 I Glove Box Preparation of Radioactive Material for
- 12 I
?.~~-=~~:-~- - .
08117117
~~~-~~-:di~~rial Cover Page ..................J .... Ship~ent...... .. . . . ,............................1......
HC-PS0-005 [ Hot Cell Loading of Host Cans 17 : 10/25/17 Cover Page 11-10
21Number <::'"',,) tc<"<c . "- N ame ~1':~;...
.:,:, .. :\ ..:..: . rf,t{: . I:. , . Rev ... Rev,Date jii:Notes J:
IC-HP-305 Calibration - Electrostatic D " m v Dosim"t"'" 10 I 12/22/17 Obsoleted Calibration - Eberline Model PING IA Stack l IC-HP-310 8 02/22/17 Full Review Monitor - Particulate Channel i Calibration - Eberline Model PING lA Stack IC-HP-310 9 06/09/17 Minor Editorial Monitor - Particulate C,,. m,-,, Calibration - Eberline Model PING IA Stack IC-HP-311 9 02/22/17 Full Review Monitor - Iodine <:himnP.1 [ Calibration - Eberline Model PING IA Stack IC-HP-311 10 06/09/17 Minor Editorial Monitor - Iodine Channel Calibration - Eberline Model PING IA Stack IC-HP-312 8 03/23/17 Minor Editorial Monitor - Gas Channel Calibration - Eberline Model PING lA Stack IC-HP-312 9 06/09/17 Minor Editorial Monitor - Gas Channel
\ Calibration - Lab Impex Smart MCA Continuous IC-HP-346 j
- 3 10/11/17 Minor Editorial nitor libration - Lab Impex Stack Monitor -
IC-HP-349 6 02/22/17 Full Review Particulate Channel Calibration - Lab Impex Stack Monitor - IC-HP-349 7 06/09/17 Minor Editorial Particulate Channel Calibration - Lab Impex Stack Monitor - IC-HP-349 8 11/02/17 Minor Editorial
, Particulate Channel Calibration - Lab lmpex Stack Monitor Iodine IC-HP-350 4 02/22/17 Full Review Channel IC-HP-350 Calibration - Lab Impex Stack Monitor Iodine 5 ! 06/09/17 Minor Editorial ! Channel -HP_ I Calibration - Lab Impex Stack Monitor - Gas 1 Ic 351 I Channel . 4 j 02122117 . Full Review IC-HP-351 . ~~~::~ion - Lab lmpex Stack Monitor - Gas. . I 5 I 06/09/17 I Minor Editorial ~~~~;~;;;**- tZ:.~!~i:tf~: :i-;b*I~p~x st;~k Mmiitor ~~~:: ___ ; 5 J ?=~==~1.7 J-;;:ll Revi~: .
IC-HP-352 , Calibration - Lab Impex Stack Monitor - Flow 6 06109117 Minor Editorial l Calibration j Calibration - NOA Lab Impex Stack Monitor - Gas IC-HP-355 3 07124117 Cover Page I Channel 1 * , IC-HP-356 f ;~:r~~µ;~~~~~~ Lab Impex Stack Monitor - I 3 l.1.?~?:~l? J ~~~~~~~;~~~~~--- IC-HP-357 ! Calibration - NOA Lab lmpex Monitor - DP2001 2 ! 06/23/17 I Minor Editorial IC-HP-359 I Calibration - Ludlum Model 177 Frisker 2 i 06/05/17 Minor Editorial
- Calibration - Eberline/Thermo Model AMS-4 I I IC-HP-362 I Continuous Air Monitor: Radial Or In-Line 3 J 07 /10/17 I Minor Editorial
=1c:HP:367-~=:-~::~~!:~~~1~(Bi0a~~ayDetectio~sy~t~~----- : I.
2 . . 06/05/17J _cover Pag~~--* IC-HP-369 l Calibration 131 Lab lmpex Monitor - DP2001 0 I 07 /13/17
- New Procedure IC-8._~~~?? *******--- \_~i~~?}i:~~-~i~~-:::~~~-~i:~:m~~:. -.-.-
IRR-PS0-112 ' ; PreparingShippingPaperwork
. . .M . . o** * *d* * *:* * *l*..-.*.*.-. . 0- _
9 o6~?:~2_ - J__07/07/17 i, - - ~~w P~~c~~~- Minor Editorial _ i Importing Authority Notification for the O 08117117 OA 8 1,.
, Netherlands New Operator Aid ~~=-~. _ _ _
1 0 __j_ ;~~:;~1-~~~~kshee~ ~°-~-~~:~ging~~~~~~~-~~~-- ________ _:..__, ~8/:~~~-?- _ **-M_i_no!_~~~~~~~~~*-***** OA-25
- Control Checksheet for Changing P-Tube Pre- I '
Minor Editorial i Filters L. 3 L 10125117.J 11-11
/
Num'.6]}: Name Rev Dat~J!'X"
- Notes I NRC 749 Manual License Verification Report for OA-26 0 10/24/17 New Operator Aid J Category 2 _Materials*-**
i Packaging of Type A Radioactive Material Using OA-60 1 I 06/02/17 Cover Page I USA DOT 7A Model E-Box 030-181
! Packaging of Type A Radioactive Material Using OA-99 1 J 08/17/17 Cover Page I USA DOT 7AMURRModel 1500 I Packaging of Type A Radioactive Material Using j OA-128 1 08117117 Cover Page ! USA DOT 7A MURR Model H or I * * .---****-*-****-*-*-*****---*******--------*---******-*-*---** ;***--**-*T***-*****-**-*********-*--****-**-*-
I l
- OP-HP-220 I Tntmm B10assay , 12 i 06/09/17 ,
OP-HP-221 i Environmental Sample - Anal sis ' 7 ' 03/08/17 OP-HP-222 I Air Sam ling - Containment Buildin Ar-41 8 03/23/17 OP-HP-228. LPerformingiodine)31Bioassay Measurements .................... ~ . . . 10/11/17 OP-HP-231 I Res irator Cleaning and Care 1 1 07 /10/17 OP-HP:J.32 __ ___ I. Respirator StoragA Maintenance and Inspection __ I 1 _ 06/19/17 Minor §~-~!<:>E~a.! . 1
. . . 9R:::!il?_:::~~3 . .L~~~p~r:i!c:>~fi!. Ie~!. ***************************************************- ..........................................................*. J . . . . . . f .....9?!JQ!E_ . . . _Cover_Page . . ..
OP-HP-234 I PhysicalExamforRespiratorPro am 1 I 07/10/17 CoverPa e _Q.11_:::.tl_l?:::~_31_____ LAnnual_RespiratorTraining_ _________ . . . . l __ l: __ 07/10/17 Cover Page OP-HP-300 ! Recei t of Radioactive Material ; 10 I 03/31/1 l Review OP-HP-305 Ordering or Transfer of Radioactive Materials 7 I 08/03/17 Cover Page _QR:::!-.l~_:}50___ JEberline Model PING_ IA -Filter Change _ --- ___ '____ 8 __ _L 06/19/17 _i __ Minor Edito~ OP-HP-354 NOA Waste Tank S stem Filter Re lacement
- 2 I 07 /24/17.........*****---................... Minor Editorial OP-HP-355 ! NOA Waste Tank S stem O eration 4/17 Minor Editorial OP-HP-356 I Operation - Lab Impex Stack Monitor: Filter 6 Minor Editorial
_____ ___ I Change and Source Checks : 1 . ; OP-HP-356 I Operation - Lab Impex Stack Monitor: Filter 1 7 l 10/02/17
- Minor Editorial
!Changeand. SourceChecks OP-HP-357 ! Operation - NOA Lab Impex Stack Monitor - i I Filter Change and Source Checks 5 ! 07/10/17 Minor Editorial
,-------+-------' OP-HP-365 I ~~:;o'.~~t;.';"o~ng Hot Cells Radiatio".__~ i~ ;_~:7/~~:!/~_77_ ---- :::oorr EEdd** *-1~tt-~orr-~1:~al1*-* * --** OP-HP-400. JGemstoneShipping.Barrel . Analysis__ _ J Operation of the Hot Cell (HC-09) Interim Storage OP-HP-500
,,1 . Silo 1 03131117 Minor Editorial .................. **********-*-**-***-**- **********************************- ******************-*- *******************-****-*******--**** ... ********************************************- *-- ****************-**- '-**** . I
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- Cd-115/In-115m Processing 1 : 07/07/17 Cover Pag_e__
PRC-RRD-401 I PreparingSm-153DOTMPfromLyophilizedKits i 2 i 07/07/17 I _CoverPage ____
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PRC-~~4~1 ;J?t~~<:>l:yit1g_~~=1.?.t __ .__ .... --~- _ -:--?. I 03/24/17 ' . . . . M~()t~c:l~!~t:ir:i!_ PRC-RRD-422 ! Prep~g 153Sm EDTMP From Lyophilized Kits 2 07/07/17 CoverPag_e__ QAB~SH-002 . I Procurement of Type B Packages .. . I 5 J 03/08/17_!____ Cover Jag~ __ Q~:::§!-.l~QQ3 JMa.!e~ir:il g()ll!E<:>lf<:>EIYPe 1?.§.hippit1g R~c:igr:r:il!l 7 I 05/01/17 . ;Mill()E~~i!grial QAB-SH-004 I Type B Progi:am Vendor Qualification 7 i 03/08/17 Cover Page II-12
QAB-SH-005 JTypeBQAPersonnelTraining I 4 I 9?/Ql/1.?L Minor Editorial QAB-SH-006 I T pe B Shipping Program Quality Audits 1 3 1 08/17 /17 Minor Editorial I Leak Testing the SAFKEG-HS or SAFKEG-LS I QAB-SH-00~---' i:Z:;J;~;:ge Leak Testing the SAFKEG-HS or SAFKEG-LS Usi~~-~~:~~T Le:~ag~--- ----~ : 01/27/17 J__ 1
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QAB-SH-007 I Shipping Package Using the CALT Leakage 1 6 12/27/17 I Minor Editorial I Testing Device I i
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QA-SH-002 'i Excepted, License-to-License, Type A, and Type 8 11/02/17 I Minor Editorial RCP-Pso=oo 1 j :~~3a~i~~~~a~i:a~e:!~Shipments__ 9 I 10/25/17*1 Cover P~g~ ..... . _RCP-PS0-002 I P-33 Glove Box Can Opy:nillg ___ I 8 1 12/22/17 I Minor Editorial
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- Receiving Gemstone Irradiation Shipping Drums 8 l 07 /21/17 , Cover Pag_e__
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- Solidification of Radioactive Liquid for Shipment I 2 I 05/01/17 I Minor Editorial
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- Exclusive Use Shipment ofLSA or SCO WM-SH-300
' Radioactive Waste 17 i 12/27/17 I Cover Page 11-13
SECTION III REVISIONS TO THE SAFETY ANALYSIS REPORT January 1, 2017 through December 31, 2017 On January 4, 2017, the U.S. Nuclear Regulatory Commission (NRC) issued Renewed Facility Operating License No. R-103. During calendar year 2017, no modifications or changes to the facility occurred that required a revision to the Safety Analysis Report (SAR) as submitted to the NRC in 2006 for relicensing. During, 2017, thousands of person-hours were spent by MURR staff to update the 2006 edition of the SAR with all the modifications that occurred between 2006 and 2017, and with applicable information from the hundreds of MURR responses to NRC Requests for Additional Information during the relicensing process. MURR expects to complete the SAR revisions and updates during 2018. III-1
SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2017 through December 31, 2017 For each facility modification described below, MURR has on file the safety screen or evaluation, as well as the documentation ofreview, performed pursuant to 10 CFR 50.59. MODIFICATION RECORD 16-04 Upgrade Secondary Coolant System Temperature Transmitters This Modification Record documents the replacement of the existing Rosemount Alphaline 442 Platinum Resistance Temperature Detector (RTD) and Transmitter Assemblies with new Rosemount 3144P 3-wire Platinum RTD and Temperature Transmitters in the Secondary Coolant System. Based on comparative specifications, these were determined to be equivalent design replacements of the existing assemblies. MODIFICATION RECORD 04-03, ADDENDUM 3 Removal ofLiguid Radioactive Waste Retention System This addendum to Modification Record 04-03, "Liquid Radioactive Waste Modification," documents the removal of the stand-alone Liquid Radioactive Waste (LRW) Retention Tank System in MURR Industrial Building (MIB) Room 299A from the rest of the Facility LRW Retention Tank System. This included dismantling and removal of Waste Tanks 299-1, 299-2, and 299-3; Waste Pump WP-33; and associated piping and valves. The remaining MIB stand-alone LRW Retention Tank System remains functional and connected to the Facility LRW Retention Tank System. MODIFICATION RECORD 88-07, ADDENDUM 4 Addition of Charcoal Filters and Dehumidifier to HC-11 Exhaust This addendum to Modification Record 88-07, "Exhaust Ventilation Upgrade," documents the addition of two sets of charcoal filters in the Hot Cell 11 (HC-11) exhaust ventilation line, a recirculation line for HC-11 cleanup, and the addition of a dehumidifier loop supporting HC-11. This modification facilitates proper humidity control, which will improve filter performance. Additionally, the two new filter banks and recirculation line will provide greater exhaust treatment and defense-in-depth against challenging Technical Specification exhaust limits, should a radioactive release occur within the hot cells. IV-1
SECTIONV NEW TESTS AND EXPERIMENTS January 1, 2017 through December 31, 2017 New tests or experiments approved during this period under a Reactor Utilization Request (RUR) were as follows: RUR455 Gallium Nitride Irradiation This RUR authorizes the irradiation of up to 77 .0 grams of gallium nitride wafers in the graphite reflector region of the reactor in support of research and development activities. In addition, MURR continued to participate in molybdenum-99 research and development work by performing test irradiations and target processing using various methodologies. 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. 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-1
I SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2017 through December 31, 2017 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-one refueling evolutions were completed in 2017. Reactor core excess reactivity verifications were performed for each refueling. The largest measured excess reactivity was 3.3%. MURR Technical Specification 3.1.a requires
- reactor core excess reactivity above reference core condition to be less than 9.8%.
REACTIVITY MEASUREMENTS Differential blade-worth measurements of five shim control blades were performed following either a planned replacement of a control blade or characterization of the bum-in effect of a new control blade. Two reactivity measurements were performed to determine the reactivity worth of all samples, including the sample holder, loaded in the flux trap region. Five reactivity measurements were performed to determine the impact of TheraSphere target can design and target mass changes for irradiation in the flux trap region. One reactivity measurement was performed to determine the reactivity worth of a target consisting of silicon microspheres in the flux trap region. VI-1
I SECTION VII RADIOACTIVE EFFLUENT January 1, 2017 through December 31, 2017 TABLE 1 SANITARY SEWER EFFLUENT Descending Order of Activity Released for Nuclide Totals > l.OOOE-05 Ci Nuclide Activity (mCi) H-3 l.001E+02 S-35 8.905E+OO Co-60 6.494E+OO Zn-65 2.953E+OO Lu-177 2.lOOE+OO Ca-45 l.268E+OO P-32 l.232E+OO Mo-99 5.721E-01 Sb-124 4.920E-01
- Sc-46 2.234E-01 Fe-59 l.596E-01 Mn-54 1.448E-01 Tc-99m l.288E-01 Cr-51 8.253E-02 1-124 4.646E-02 Cd-109 4.392E-02 Pd-109 3.369E-02 Lu-177m 2.769E-02 W-181 2.738E-02 Ru-105 l.589E-02 Total H-3 1.001E+02 Total Other 2.495E+Ol Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal by Release into Sanitary Sewerage."
VII-1
1 TABLE2 ST ACK EFFLUENT Ordered by% Technical Specification (TS) Limit Average Concentr~tion Total Release Isotope TS Liniit Multiplier %TS (µCi/ml) (µCi) Ar-41 l.99E-06 9.31E+08 350 56.9143 1-131 3.36E-12 l.57E+03 1 1.6785 C-14* l.80E-11 8.19E+03 1 0.6000 H-3 l.17E-08 5.46E+06 350 0.0333 Co-60 l.05E-14 4.89E+OO 1 0.0209 1-125 l.18E-14 5.50E+OO 1. 0.0039 Kr-79 6.93E-10 3.24E+05 350 0.0028 Xe-131m l.68E-08 7.85E+06 350 0.0024 Sc-46 3.21E-15 l.50E+OO 1 0.0011 Os-191 8.16E-15 3.82E+OO 1 0.0004 Ba-140 5.30E-15 2.48E+OO 1 0.0003 Hf-181 1.38E-15 6.43E-01 1 0.0002 Cs-137 4.53E-16 2.12E-01 1 0.0002 Sb-124 l.14E-15 5.32E-01 1 0.0001
- 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 ofN-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, Renewed Facility Operating License No. R-103 Technical Specifications. VII-2
r-----. SECTIONVID ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2017 through December 31, 2017 Environmental samples are collected two times per year at eight locations and analyzed for radioactivity. Soil and vegetation samples are also taken at each location. Water samples are taken at three locations while subsurface soil samples are taken at six 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 2017. All doses are approximately 10 mrem/year or less, except monitor number 9. This monitor is located at or near loading dock areas where packages containing radioactive material are loaded or traverse prior to being placed on transport vehicles. The dose recorded by this monitor is 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 91 - Spring 2017 Detection Limits* Matrix Alpha Beta Gamma Tritium Vegetation 1.43 pCi/g 9.45 pCi/g 1.44 pCi/g 5.02 pCilmL Soil 0.72 pCi/g 4.72 pCilg 0.62 pCi/g NIA Water 1.02 pCi/L 4.95 pCilL 193.38 pCi/L 4.94 pCi/mL Subsurface Soil 1.01 pCilg 5.12 pCilg 0.51 pCilg NIA Activity Levels - Vegetation Alpha Beta Gamma Tritium Sample (pQLgl (pQLgl (pQLgl (pCi/mL) 1V91 <MDA 34.03 <MDA <MDA 2V91 <MDA 21.29 1.45 <MDA 3V91 <MDA 24.70 <MDA <MDA 4V91 <MDA 80.19 <MDA <MDA 5V91 <MDA 45.77 <MDA <MDA 6V91 <MDA 40.45 1.99 <MDA 7V91 <MDA 40.80 1.44 <MDA 10V91 <MDA 32.35 <MDA <MDA VIII-I
I TABLE 1 (Cont'd)
SUMMARY
OF ENVIRONMENTAL SET 91 - Spring 2017 Activity Levels - Soil Alpha Beta Gamma Sample .(pQLg)_ .(pQLg)_ .(pQLg)_ 1S91 <MDA 12.59 3.43 2S91 <MDA <MDA 3.09 3S91 <MDA 21.64 2.58 4S91 1.09 24.96 2.27 5S91 0.93 18.24 3.79 6S91 0.93 16.53 2.64 7S91 <MDA 11.77 2.86 10S91 <MDA 24.13 3.79 Activity Levels - Water Alpha Beta Gamma Tritium Sample {pCi/L) {pCi/L) {pCi/L) {pCi/mL) 4W91 <MDA <MDA <MDA <MDA 6W91 <MDA <MDA <MDA <MDA 10W91 <MDA 11.00 <MDA <MDA Activity Levels - Subsurface Soil Alpha Beta Gamma Sample .(pQLg)_ .(pQLg)_ .(pQLg)_ S91 <MDA 18.61 3.57 SW91 <MDA 31.92 3.59 W91 <MDA 20.02 3.73 N91 <MDA 22.52 4.23 NE91 <MDA 19.67 3.85 E91 <MDA 21.28 3.47
- 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-2
TABLE2
SUMMARY
OF ENVIRONMENTAL SET 92 - Fali 2017 Detection Limits* Matrix Alpha Beta Gamma Tritium Vegetation 2.03 pCi/g 10.98 pCilg 1.83 pCi/g 5.05 pCilmL Soil 0.72 pCilg 4.69 pCilg 0.59 pCi/g NIA Water 0.00 pCi/L 2.99 pCilL 185.55 pCi/L 5.01 pCi/mL Subsurface Soil 1.01 pCilg 4.19 pCi/g 0.66 pCi/g NIA Activity Levels - Vegetation Alpha Beta Gamma Tritium Sample fu.QLg} fu.QLg} fu.QLg} (pCilmL) 1V92 <MDA 27.48 <MDA <MDA 2V92 <MDA <MDA <MDA <MDA 3V92 <MDA <MDA <MDA <MDA 4V92 <MDA 22.49 <MDA <MDA 5V92 <MDA 31.05 <MDA <MDA 6V92 <MDA 13.56 <MDA <MDA 7V92 <MDA 16.42 <MDA <MDA 10V92 <MDA 21.42 <MDA <MDA Activity Levels - Soil Alpha Beta Gamma Sample fu.QLg} fu.QLg} fu.QLg} 1S92 0.93 19.81 3.19 2S92 0.77 10.71 2.82 3S92 1.08 15.71 2.21 4S92 0.94 16.58 3.08 5S92 1.70 36.05 3.75 6S92 0.77 13.43 2.34 7S92 <MDA 13.03 3.16 10S92 0.92 18.73 3.13 VIII-3
TABLE 2 (Cont'd)
SUMMARY
OF ENVIRONMENTAL SET 92 - Fall 2017 Activity Levels - Water Alpha Beta Gamma Tritium Sample mQLg)_ mQLg)_ mQLg)_ (pCi/mL) 4W92 0.15 7.85 <MDA <MDA 6W92 0.31 6.42 <MDA <MDA 10W92 0.15 12.85 <MDA <MDA Activity Levels - Subsurface Soil Alpha Beta Gamma Sample mQLg)_ mQLg)_ .(pQLg)_ E92 1.08 24.12 5.22 S92 <MDA 19.67 4.32 SW92 1.54 22.35 4.53 W92 1.08 21.64 5.08 N92 1.08 23.41 5.05 NE92 <MDA 23.35 4.22
- 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
TABLE3 ENVIRONMENTAL TLD
SUMMARY
' Direction Map,Distance from .* 1st Qtr 2nd Qtr 1 3rd Qtr 4th Qtr I Total Badge : from MURRStack
- 2011 2011 ,I 2011 . 2011 ; 2011 Number: MURR (meters) (net nirem) (net mrem) (net mrem) I (net mrem), (net mrem)
O* Control 72210 23.0 21.0 25.0 33.0 102.0 1* Schnieders 72210 24.0 24.0 26.0 25.0 99.0 2* Schnieders 72210 23.0 21.0 25.0 30.0 99.0 3 w 31 12.0 -8.0 -14.0 -19.0 -29.0 4 SW 49 3.0 -5.0 -16.0 -20.0 -38.0 5 NE 119 6.0 -8.0 -13.0 -15.0 -30.0 6 NNE 87 12.0 -2.0 -7.0 -10.0 -7.0 7 NE 55 9.0 -4.0 -10.0 -17.0 -22.0 8 SW 33 0.0 0.0 0.0 0.0 0.0 9 SE 28 25.0 9.0 0.0 1.0 35.0 10 NE 149 -8.0 -9.0 -11.0 -20.0 -48.0 11 NNW 149 11.0 -5.0 -9.0 -16.0 -19.0 12 NE 284 16.0 -6.0 -8.0 -11.0 -9.0 13 SE 320 -9.0 -9.0 -13.0 -19.0 -50.0 14 SSW 166 8.0 -6.0 -8.0 -15.0 -21.0 15 s 74 7.0 ** ** -16.0 -9.0 16 SE 114 9.0 -7.0 -10.0 -16.0 -24.0 17 E 299 4.0 -10.0 -14.0 -19.0 -39.0 18 NE 454 4.0 -9.0 -11.0 -19.0 -35.0 19 NE 671 3.0 -13.0 -17.0 -22.0 -49.0 20 NE 872 -11.0 -11.0 -16.0 -19.0 -57.0 21 SSW 294 10.0 -7.0 -10.0 -15.0 -22.0 22 SW 174 1.0 -9.0 -16.0 -22.0 -46.0 23 NW 67 10.0 -5.0 -9.0 -16.0 -20.0 24 SSW 499 7.0 -8.0 -8.0 -17.0 -26.0 25 NNE 123 9.0 -8.0 -11.0 -20.0 -30.0 26 SW 318 7.0 -9.0 -11.0 -19.0 -32.0 27 SW 174 3.0 -11.0 -16.0 -22.0 -46.0 28 NE 496 8.0 -6.0 -7.0 -12.0 -17.0 29 NE 498 5.0 -8.0 -10.0 -15.0 -28.0 30 N 340 5.0 -10.0 -13.0 -21.0 -39.0 31 NNE 687 6.0 -7.0 -12.0 -13.0 -26.0 32 NNE 616 9.0 -7.0 -9.0 -17.0 -24.0 33 ESE 572 2.0 -11.0 -16.0 -22.0 -47.0 34 NE 613 2.0 -13.0 -18.0 -23.0 -52.0 35 SSE 473 13.0 -4.0 -6.0 -9.0 -6.0 36 SE 428 8.0 -8.0 -13.0 -18.0 -31.0 37 NE 734 3.0 -10.0 -14.0 -21.0 -42.0 38 NW 517 9.0 -6.0 -8.0 -12.0 -17.0 39 w 535 6.0 -8.0 -11.0 -15.0 -28.0 40 N 470 5.0 -9.0 -14.0 -19.0 -37.0 41 NE 155 7.0 -6.0 -14.0 -21.0 -34.0 42 Spare NIA 10.0 -2.0 ** -17.0 -9.0 43 Spare NIA 11.0 -5.0 -8.0 -16.0 -18.0 44 SW 99 8.0 -5.0 -13.0 -18.0 -10.0 45 SE 98 20.0 0.0 -2.0 -8.0 10.0 46 SE 105 8.0 -7.0 -10.0 -17.0 -26.0 The control monitors are approximately 50 miles SE of MURR, and gross values are shown.
** During collection, three TLDs were reported missing; therefore, data is not available.
VIII-5
TABLE4 NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS Surface Radiation. Contamination* Air Samples** RWPs January 103 103 62 17 February 85 85 59 13 March 88 88 68 18 April 94 94 60 23 May 93 93 67 10 June 100 100 66 24 July 86 86 58 16 August 91 91 67 10 September 100 100 62 8 October 87 87 66 22 November 88 88 59 20 December 94 94 62 11 TOTALS 1,109 1,109 756 192
- 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 Note During calendar year 2017, MURR shipped 1,270.4 cubic feet of low-level radioactive waste containing 23,400 mCi of activity. VIII-6
SECTION IX
SUMMARY
OF RADIATION EXPOSURE TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS January 1, 2017 through December 31, 2017 Total Personnel Dose (mrem) by Dosimetry Group AC/PRD BCS DO FOE HC HP IRR NA NS NSP OPS PRO QA RES RP SH SIL TEE WC Total January 83 0 0 0 233 131 0 7 15 12 1336 6 64 1 1 166 219 6 13 2293 February 63 0 0 0 171 170 0 4 52 4 1336 15 62 11 3 98 191 0 13 2193 March 95 0 0 7 221 183 3 5 49 2 1393 0 93 4 0 94 108 13 25 2295 April 110 8 0 0 261 202 3 13 16 11 1509 11 141 2 21 111 153 0 108 2680 May 61 2 0 0 324 226 5 0 39 18 1707 12
- 113 3 9 112 159 1 28 2819 June 45 0 0 0 267 510 0 6 36 17 1540 0 41 2 6 126 120 0 16 2732 July 96 2 0 0 249 167 0 10 11 22 1886 8 34 2 9 90 127 0 35 2748 August 91 5 0 2 311 187 13 16 53 27 1197 1 46 4 0 114 124 3 14 2208 September 62 0 0 1 262 150 0 5 15 0 1118 0 4 6 3 85 132 3 28 1874 October 128 6 0 0 227 229 8 5 14 23 1347 3 39 0 0 91 116 0 38 2274
...... November 43 0 0 0 193 237 0 2 14 2 1741 0 13 0 0 131 134 0 103 2613 I December 86 0 0 0 262 159 0 1 22 4 1706 11 81 0 3 106 134 0 25 2600 Total for Year 963 23 0 10 2981 2551 32 74 336 142 17816 67 731 35 55 1324 1717 26 446 29329 Monthly Average 80 2 0 1 248 213 3 6 28 12 1485 6 61 3 5 110 143 2 37 2444 HighestWB 231 17 0 3 1130 617 15 35 113 49 1113 28 172 21 23 308 1134 13 98 (annual) High Extremity 4870 26 NM 21 3237 687 433 2073 213 94 1414 59 1118 677 284 902 2219 54 671 (annual) AC/PRO-Analytical Chemistry/Production HP-Health Physics OPS-Operations SH-Shipping BCS-Business & Central Services IRR-Irradiations PRO-Isotope Processing SIL-Silicon DO-Director's Office NA-Nuclear Analysis QA-Quality Assurance TEE-Trace Elemental Epidemiology FOE-Shops & Support NS-Neutron Scattering RES-Research WC-Work Control HC-Hot Cell NSP-NorthStar Partners RP-Radiopharmaceutical 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. No significant personnel exposures occurred during this monitoring year. NOTE: Dosimetry services* are provided by Mirion Technologies (except self reading dosimetry).}}