ML19057A361

Univ of Missouri - Columbia - Submittal of 2018 Reactor Operations Annual Report

ML19057A361
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/21/2019
From:	Meffert B, Robertson J Univ of Missouri - Columbia
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML19057A361 (43)

Text

EiJ University of Missouri Research Reactor Center 1513 Research* Park Drive Columbia, MO 65211 PHONE 573-882-4211 WEB murr.missouri.edu February 21, 2019 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-Columbia Research Reactor 2018 Reactor Operations Annual Report Enclosed is a copy of the 2018 Reactor Operations Annual Report for the University of Missouri-Columbia Research Reactor (MURR). This document is being submitted to the U.S. Nuclear Regulatory Commission in accordance with the MURR Technical Specification 6.6.e.

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, ci~-----

~David Robertson Reactor Manager Reactor Facility Director BAM/jlm Enclosure xc: Mr. Geoffrey Wertz, U.S. NRC Mr. William Schuster, U.S. NRC

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• UNIVERSITY OF MISSOURI-COLUMBIA RESEARCH REACTOR

• REACTOR OPERATIONS ANNUAL REPORT January 1, 2018 through December 31, 2018-ii -.* -, -~ .,-'-. < .:\ ...:_rJ._r~ -,,~,-.,*~~<*-::- p*-,-, .

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• UNIVERSITY OF MISSOURI-COLUMBIA

• RESEARCH REACTOR I

REACTOR OPERATIONS I

ANNUAL REPORT I

I I January 1, 2018 through December 31, 2018 I

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Compiled by the Staff of MURR I

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• • Submitted by: ,

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Reacto~:::

Bruce A. M ert I Reviewed and approved by:

J. David Robertson

• Reactor Facility Director I

UNNERSITY OF MISSOURI- COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2018 through December 31, 2018 INTRODUCTION The University of Miss01,rri 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, and nuclear engineering; and research techniqu~s 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 2018.

Included within this report are changes to MURR reactor operations and health physics procedures, revisions to the Safety Analysis Report (SAR), facility modifications, new tests and experiments, reactor physics activities, and environmental and health physics data.

This report is being *submitted to the U.S. Nuclear Regulatory Commission (NRC) to meet the administrative requirements of MURR Technical Specification 6.6.e.

ACKNOWLEDGMENTS The success of MURR and its scientific programs is due to the dedication and hard. work of many individuals and organizations. Included within this group are: the University of Missouri admjnistration; 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~rganizations, the staff of MURR wishes to extend its fondest appreciation.

Some of the major facility projects that were supported by Reactor Operations during this past calendar year included (1) replacement of the primary coolant heat exchanger HX503A plates; (2) chemical cleaning of primary coolant heat exchanger HX503B and pool coolant heat exchanger HX521 plates; (3) replacement of 12 paper and pen chart recorders with paperless chart recorders on all process instrumentation, nuclear instrumentation, and stack monitor channels; (4) replacement of the secondary coolant chemical control system; (5) replacement of the personnel entry (airlock) inner and outer door sealing gaskets; (6) replacement of the rod position indication system; (7) installation of a new control rod drive mechanism; (8) refurbishment of anti-siphon system isolation valves V543A and V543B; (9) replacement of the reactor pressure vessel cover backrings; (10) installation of a reactor containment building

differential pressure transmitter, remote indication, and alarm; and (11) implementation of facility security enhancements focusing on the requirements of 10 CFR 37.

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, fuel procurement and conversion, there are common interests and activities among all five reactors that will benefit from a coordinated, working-group effort. This past year, work focused on HEU-to-LEU transition core planning and the effects of fissile targets on the proposed LEU core for the purpose of producing molybedum-99.

Reactor Operations management also wishes to commend the three individuals who received their 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 7 II. MURR Procedures .........................*.................................................................................... II-1 through 11 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 Shipping Procedures III. Revisions to the S~fety Analysis Report.: .......................................................................... III-1 through 5 IV. Plant and SystemModifications ......................................................................................... IV-1 through 3 V. New Tests and Experiments ................................................................................................................. V-1 VI. Special Nuclear Material and Reactor Physics Activities*********:******************************************************** VI-1 VII. 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 ofEnvironmental Set 93 - Spring 2018 Table 2- Summary ofEnvironmental Set 94 - Fall 2018 Table 3 - Environmental TLD Summary Table 4 - Number of Facility Radiation and Contamination Surveys IX. Summary of Radiation Exposure to Facility Staff, Experimenters, and Visitors ............................... IX-1 iii

SECTION I REACTOR OPERATIONS

SUMMARY

January 1, 2018 through December 31, 2018 Tue following table and discussion summarizes reactor operations during the period from January 1, 2018, through December 31, 2018.

• January 650.42 271.11 87.4 97.9 February 609.73 254.37 90.7 101.6 March 673.15 280.57 90.5 101.3 April 616.23 256.82 85.6 96.0 May 609.29 254.20 81.9 91.7

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t June 661.12 275.53 91.8 103.0 July 660.49 275.28 88.8 99.4 August 652.94 272.11 87.8 98.3 September 627.25 261.45 87.1 97.7 October 644.45 268.66 86.6 97.0 November 616.96 257.16 85.7 96.1 December 665.92 277.55 89.5 100.2 Total for the Year 7,687.95 3,204.81 87.78 98.34

• 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.

I I JANUARY 2018 I Tue reactor operated continuously in January with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, and one unscheduled/unplanned power I reduction.

I On January 5, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated as part of an unplanned power reduction to perform compliance procedure CP-17, "Emergency Power Generator Load I Test," after a review of the December 2017 Compliance Procedure Status Report revealed that the 7.5-month "due no later than date" for performance of CP-17 was January 5, 2018. All immediate and subsequent actions of reactor I emergency procedure REP-2, "Reactor Scram," were completed. CP-17 was then completed satisfactorily.

I Permission to restart the reactor was obtained from the Lead Senior Reactor Operator, and the reactor was subsequently returned to 10 MW operation.

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Major maintenance items for the month included: replacing the reactor pool upper bridge radiation monitor upscale switch; replacing the pedestrian entry (airlock) inner door 277 drive sprocket; replacing the regulating blade drive mechanism cable; replacing the pool coolant demineralizer system inlet and outlet filters; loading new de-ionizing bed 'K' and placing it on pool coolant system service; 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)."

FEBRUARY 2018 The reactor operated continuously in February 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 a relay in the drain collection tank control circuit; replacing primary coolant heat exchanger HX503A plates; and replacing the reactor containment building differential pressure gauge.

MARCH2018 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions.

On March 1, 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 monitor nuclear instrumentation (NI) channel no. 6 (PRM-6).

There was no indication of an elevated power level on any NI channel, including PRM-6. PRM-6 rod run-in (RRI) trip unit was replaced, and the drawer operations were tested satisfactorily with completion of compliance procedure CP-34, "Nuclear Instrumentation Power Range Monitor - Channel 6," and the applicable portions of compliance procedure CP-9, "Nuclear Instrumentation Scram and Rod Run-In." Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.

On March 4, with the reactor operating at 10 MW in the automatic control mode, a Reactor Operator Trainee, while conducting a routine facility patrol, inadvertently switched the emergency power generator (EPG) out of automatic control for approximately 10 to 15 seconds before returning the EPG back to automatic control. The reactor was not shut down. Permission to continue operating the reactor was obtained from the Interim Reactor Facility Director.

Inoperability of the emergency electrical power system during reactor operation resulted in a deviation from Technical Specification (TS) 3.6.a, and Licensee Event Report No. 18-01 was submitted to the NRC on March 15, 2018.

On March 19, during a normal reactor startup with the reactor subcritical and shim control blade height at 10 inches, a manual reactor scram was initiated when a control room operator observed anti-siphon system pressure decreasing approximately 2-3 psig every five minutes. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed. Attempts were made to manually seat anti-siphon system isolation valves V543A and V543B in the closed position but were unsuccessful. The primary coolant system was shut down and restarted, and control room operators observed anti-siphon'system pressure for 10 minutes to verify the pressure was holding. Permission to perform a normal reactor startup was obtained from the Lead Senior Reactor Operator, and the reactor was subsequently returned to 10 MW operation.

Major maintenance items for the month included: replacing the wide range monitor NI drawer cable; performing a zero and span on the wide range monitor NI channel; completing Modification Record 13-02, Addendum 1, 1-2 I

"Secondary Coolant System Chemistry Control;" and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-202, "Measurement of Reactivity Worth of Movable Samples, RTP-6."

• APRIL2018 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling. An NRC inspector conducted a routine scheduled inspection of the Radiation Protection and Shipping Programs.

There were no unscheduled/unplanned power reductions this month. However, an unplanned extended maintenance period occurred from April 30 to May 2, 2018. The plates on primary coolant heat exchanger HX503B were replaced on April 30. Later on April 30, it was discovered that one or more replacement plates had leaked. The decision was made to coarsely clean the original plates and put them back into the heat exchanger. The reactor was returned to 10 MW operation on May 2, 2018.

Major maintenance items for the month "included: replacing the pedestrian entry (airlock) outer door 276 sealing gasket; replacing primary coolant circulation pump P50 lA; repairing a leak in pool coolant hold-up tank T504; loading new de~ionizing bed 'L' and placing it on pool coolant system service; and mechanically cleaning the plates in primary coolant heat exchanger HX503B.

MAY2018 The reactor opemted continuously in May with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and 10 unscheduled/unplanned power reductions.

From May 21 through May 27, six different RRis were automatically initiated with the reactor operating at 10 MW in the automatic control mode. For the first five RRI occurrences, no RRI annunciation accompanied the RRI, and no plant condition occurred that would have caused a RRI. On the sixth occurrence, a 'Channel 4, 5 or 6 HI Power Rod Run-In' annunciation was automatically initiated from PRM-6. There was no indication of an elevated power level on any other NI channel. On May 27, investigation concluded that all of the RRis probably occurred due to increased noise from the PRM-6 detector and/or detector cable. The PRM-6 detector and associated cabling were replaced.

Permission to restart the reactor was obtained from the Acting Reactor Manager, and the reactor was subsequently returned to 10 MW operation.

On May 25, with the reactor operating at 10 MW in the automatic control mode, an automatic reactor scram was initiated due to a momentary loss of normal electrical power. All immediate and subsequent actions of reactor emergency procedure REP-11, "Momentary Loss of Normal Electrical Power," were completed. The momentary electrical power loss was confirmed by calling the University of Missouri power plant and the issue was verified to be a fault at the power plant. Permission to restart the reactor was obtained from the Acting Reactor Manager, and the reactor was subsequently returned to 10 MW operation.

On May 27, with the reactor operating at 5 MW in the manual control mode during a normal reactor startup, an automatic reactor scram was initiated while paused to physically adjust the PRM-6 detector drywell. The scram was accompanied by a 'Channel 4, 5 & 6 Hi Power Scram' annunciation. All immediate and subsequent actions ofreactor emergency procedure REP-2, "Reactor Scram," were completed. The power transient was verified on the PRM-6 chart recorder and with no spike noted on PRM-4 or -5. Further investigation revealed that the bolt that holds down the U-clamp bracket on the PRM-6 drywell was loose, which allowed the drywell to move more than intended. The 1-3

bracket was tightened, and the drywell was successfully adjusted during the following startup. Permission to restart the reactor was obtained from the Acting Reactor Manager, and the reactor was subsequently returned to 10 MW operation.

On May 29, with the reactor operating at 10 MW in the automatic control mode, an automatic RRI was initiated due to control rod 'D' disconnecting from its drive mechanism electromagnet. The RRI was accompanied by a 'Rod Not In Contact With Magnet Rod Run-In' annunciation. While loading a silicon sample back into graphite reflector Y6 irradiation position, the sample holder wire caught the north sample rotator causing the holder to swing into control blade 'D' offset mechanism. This caused the control rod to disconnect from the control rod drive mechanism electromagnet. Permission to restart the reactor was obtained from the Lead Senior Reactor Operator, and the reactor was subsequently returned to 10 MW operation.

On May 30, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated due to inoperability of control blades 'A,' 'B,' and 'C.' All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed. Immediately prior, while conducting the control blade operability TS 4.2.a surveillance, it was discovered that shim control blades 'A,' 'B,' and 'C' would not shim in the inward direction (outward direction was operable) when control rod operate switch 1S4 was manipulated.

Troubleshooting determined a failure of control rod operate switch 1S4, and this component was replaced and retested satisfactorily. Permission to restart the reactor was obtained from the Interim Reactor Facility Director, and the reactor was subsequently returned to 10 MW operation. lnoperability of the control blades during reactor operation resulted in a deviation from TS 3.2.a, and Licensee Event Report No. 18-02 was submitted to the NRC on June 11, 2018.

Major maintenance items for the month included: replacing the pool coolant demineralizer system irilet filters; completing the biennial change-out of control blade 'B' offset mechanism; performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth of a Shim Control Blade, RTP-ll(D);" replacing the RR.I system non-coincidence logic unit and trip actuator amplifier; replacing control rod selector switch 1S3; replacing control rod operate switch 1S4; replacing PRM-6 RR.I dual trip unit; and completing compliance procedure CP-26, "Containment Building Compliance Test.

I JUNE 2018 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements, and two shutdowns for license examinations. There were no unscheduled/unplanned power reductions this month. An NRC license examiner administered a reactor operator licensing examination. Dr. J. David Robertson was appointed the Reactor Facility Director on June 15.

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);" and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth ofa Shim Control Blade, RTP-ll(D)."

JULY2018 The reactor operated continuously in July 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.

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Major maintenance items for the month included: replacing the pool coolant demineralizer system inlet filters; replacing the primary and pool coolant demineralizer flow recorder; conducting chemical cleanings of primary coolant heat exchanger HX503B and pool coolant heat exchanger HX521; loading new de-ionizing bed 'G' and placing it on pool coolant system service; replacing truck entry door 101 clutch pins; installing .a desiccant air dryer in the reactor containment building supply and exhaust plenum backup doors compressed air supply line; replacing the pedestrian entry (airlock) outer door 276 seal air supply regulator and pressure relief valve; performing a reactivity worth measurement in accordance with reactor procedure RP-R0-202, "Measurement of Reactivity Worth of Movable Samples, RTP-6;" and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loadings ~r Individual Samples, RTP-17(B)."

AUGUST2018 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and two shutdowns for physics measurements. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: replacing the pedestrian entry (airlock) inner door 277 sealing gasket; replacing the pressure vessel cover east backring; replacing the primary coolant reactor inlet and outlet temperature recorder; replacing the pool coolant demineralizer system inlet filters; completing Modification Record 96-02, Addendum 2, "Installation of Power Motion Inc. Rod Position Indication System;" performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth of a Shim Control Blade, RTP-ll(D);" 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-17(B)."

SEPTEMBER 2018 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements, and two unscheduled/unplanned power reductions.

On September 5, with the reactor operating at 10 MW in the automatic control mode, an automatic containment isolation was initiated, which automatically shut down the reactor. All immediate and subsequent actions of emergency procedure EP-R0-12, "Reactor Isolation," were completed. Troubleshooting revealed that the radiation signal from containment building exhaust plenum no. 1 area radiation monitor decreased to a level that caused the electronic circuit to sense a failure on low level. The installed sources in both exhaust plenums nos. 1 and 2 had decayed significantly over several years. Replacement sources were installed. Permission to restart the reactor was obtained from* the Lead Senior Reactor Operator, and the reactor was subsequently returned to 10 MW operation.

On September 14, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated when the console operator discovered that the backup doors to the containment building ventilation supply and exhaust duct doors 504 and 505 closed. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram/' were completed. Further investigation revealed that the compressed air supply line to the backup door air cylinders was damaged when an operator became entangled in an electrical extension cord that was attached to the air line. The air line was repaired, and operation of the backup doors was verified satisfactory by performing compliance procedure CP-20, "Backup Doors." Permission to restart the reactor was obtained from the Lead Senior Reactor Operator, and the reactor was subsequently returned to 10 MW operation.

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Major maintenance items for the month included: replacing the primary coolant system flow 'A' recorder; replacing the water pump on the diesel engine of the EPG; and 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)."

OCTOBER 2018 The reactor operated continuously in October with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurement, and one unscheduled/unplanned power reduction. An NRC inspector conducted a routine scheduled inspection of Reactor Operations and Emergency Preparedness.

On October 13, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated as part of an unplanned shutdown with Reactor Manager concurrence. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed. Anti-siphon system isolation valves V543A and V543B were leaking causing air to collect within the reactor loop vent system tank. Solenoid-operated vent valve V552A would periodically open to vent the air out of the tank, which released small amounts of activated air to the facility ventilation exhaust stack. After the reactor and primary coolant system were shut down, the primary coolant system was restarted and secured several times until anti-siphon system isolation valves V543A and V543B were seated with minimal leakage noted. Permission to restart the reactor was obtained from the Lead Senior Reactor Operator, and the reactor was subsequently returned to 10 MW operation.

Major maintenance items for the month included: completing Modification Record 18-02, "Fabrication of a New Control Rod Drive Mechanism;" replacing control rod 'B' drive mechanism; replacing the pool coolant heat exchanger inlet and outlet temperature recorder; replacing the pool coolant demineralizer system inlet filters; loading new de-ionizing bed 'K' and placing it on pool coolant system service; completing the biennial change-out of control blade

'D' offset mechanism; performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth of a Shim Control Blade, RTP-11(0);" 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-17(B)."

NOVEMBER 2018 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions. *1 On November 9, with the reactor operating at 10 MW in the automatic control mode, an automatic reactor scram was initiated due to a loss of normal electrical power to the reactor containment and laboratory buildings. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed. Investigation revealed the supply breaker on a substation 'B' was tripped. The cause of the breaker trip was a malfunction inside a breaker located in motor control center no. 3. The failed breaker was disconnected, and power to the reactor I containment and laboratory buildings was restored. Permission to restart the reactor was obtained from the Lead Senior Reactor Operator, and the reactor was subsequently returned to 10 MW operation.

On November 20, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was I

initiated as part of an unplanned power reduction due to abnormal noise coming from primary coolant circulation I pump P501A breaker located in motor control center no. 5. All immediate and subsequent actions of reactor I

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emergency procedure REP-2, "Reactor Scram," were completed. When the primary coolant circulation pump was started, the breaker contact block most likely did not seat properly when the coil activated, which caused a significant buzzing noise. After the reactor was shut down, the primary coolant system was restarted allowing the primary coolant circulation pump P501A breaker contact block to seat properly. Permission to restart the reactor was obtained from the Lead Senior Reactor Operator, and the reactor was subsequently returned to 10 MW operation.

Major maintenance items for the month included: completing Modification Record 18-01, "Installation of Containment Differential Pressure Transmitter, Remote Indication, and Alarm;" transferring de-ionizing bed 'K' from primary coolant system service to pool coolant system service; loading new de-ionizing bed 'Y' and placing it on primary coolant system service; replacing the intermediate range monitor level recorder; replacing the secondary coolant system recorder; replacing the source range monitor level recorder; replacing the wide range level monitor recorder; replacing the reactor pressure vessel cover backrings; refurbishing anti-siphon system isolation valves V543A and V543B; replacing the primary coolant system flow 'B' recorder; and replacing the pool coolant demineralizer system inlet filters.

DECEMBER 2018 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenap.ce and/or_refueling and one shutdown for physics measurement. There were no unscheduled/unplanned power reductions this month. An NRC license examiner administered a reactor operator and a senior reactor operator licensing examinations.

Major maintenance items for the month included: replacing the pool coolant system flow recorder; replacing both off-gas stack monitor recorders; refurbishing both primary coolant circulation pump bypass valves V538A and V538B; replacing the power range monitor level recorder; replacing the pool coolant demineralizer system inlet filters; completing Modification Record 99-01, Addendum 1, "Replace Process Instrumentation Recorders - 2018;"

completing Modification Record 99-05, Addendum 2, "Replace Eberline Stack Monitor Recorder - 2018;"

completing Modification Record 95-01, Addendum 2, "Replace Nuclear Instrumentation Recorders - 2018;"

completing Modification Record 09-03, Addendum 2, "Replace Lab Impex Stack Monitor Recorder - 2018;"

performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth of a Shim Control Blade, RTP-ll(D);" 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-17(B)."

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SECTION II MURR PROCEDURES January 1, 2018 through December 31, 2018 As required by administrative MURR Technical Specification (TS) 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 TS 6.2.a(2).

A. CHANGES TO REACTOR OPERATIONS PROCEDURES As required by the MURR TS, 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 64 revisions issued to the Reactor Operations procedures, forms, policies, and charters. One new charter and one new procedure were issued, while one form and one procedure were obsoleted. The majority of these r(?visions 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, policies, and charters:

AP-R0-105 MURR Operator Requalification Process O 12/18/18 New Procedure I-------!----------~~-------------- - ------- -----------

AP-R0-110 ConductofOperations 25 07/12/18 MinorEditorial AP-R0-110 Conduct of Operations 26 12/18/18 Minor Editorial AP-R0-130 Crane Operation - - - - - - - - - - - - - + - - - - - - Minor Editorial 9 10/03/18 AP-RR-003 10 CFR 50.59 Evaluations 12 12/12/18 Minor Editorial AP-RR-014 On-Site Fingerprinting Program 1 10/02/18 Minor Editorial Access Authorization Program for Irradiated AP-RR-033 2 10/02/18 Minor Editorial Reactor Fuel in Transit EX-R0-110 I Pneumatic Tube System 1 12/10/18 Minor Editorial Type B Shipment of Spent Fuel Using the BEA FB-SH-110 I1 Research Reactor Package 5 01/04/18 Minor Editorial FB-SH-llO I Type B Shipment of Spent Fuel Using the BEA I Research Reactor Pack~e 6 03/16/18 Minor Editorial

.- - - - - - - - - - ~ ~ - - - - - - - - - - - - 1 FB-SH-llO I TypeB ShipmentcifSpentFuelUsingtheBEA 7 05110118 MinorEditorial

____________ jResearch Reactor Packag!) __ __ -----------1----** --*-**-- . ---***-**-*---**-***--***-****--*

FM-15 10 CFR 50.59 Qualified Reviewers List 23 07/12/18 Minor Editorial

_F__M_-1_6_ _ ___,_P_rnn_*ary - Pool Coolant Water Analysis _ ___ _________!_~-- __ g_!!04/_!_8 _Q~S._()_le_t~d___ _ ____

FM-18 Deviation From Procedure Report 11 12/10/18 Minor Editorial FM-19 Unscheduled/Unplanned Power Reduction Report 7 12/18/18 , Minor Editorial FM-21 ARMS Trip Setpoints 12 07/12/18 Cover Page 1-------~----"--"----------*-------i---t-----+----~

FM-21 ARMS Trip Setpoints 13 10/03/18 Minor Editorial FM-43 Nuclear and Process Data Sheet 26 05/10/18. Minor Editorial FM-43 Nuclear and Process Data Sheet 27 12/10/18 Minor Editorial II-1

.* N)iw~ft' .  :>,:Jt. :,'.Nam¢::,:;:~t/ ']n/\1< . . ,/J:Xif:':: :. );;Tf~t::*. *. ; s:t\l~y.:J *R¢y]!ate' :1 *:~tit~~,***.\-.l:f'J})t..

FM-56 Reactor Routine Patrol 23 05/10/18 Minor Editorial FM-56 -~j.leactor Routine Patrol -~4 _ 10/03/18 _ ~}'Editorial __

FM-57 I Long Form Startup Checksheet 27 01/24/18 I Minor Editorial FM-57 I Long Form Startup Checksheet 28 05/10/18 Minor Editorial

_JM-57 Long Form Startup Ch_ecksheet -------*- 29 10/03/18 I Minor Editorial FM-57 Long Form Startup Checksheet 30 12/10/18 Minor Editorial FM-58 Short Form Startup Checksheet 14 04/23/18 Minor Editorial

....-*-----*-***-***--*-*-*****-** l - - - - - - - - - - - - - - - - - - - - - - * * * - - - - - - - * - - - - * - ***-*-- **-***--**

FM-58 l Short Form Startup Checksheet 15 12/10/18 Minor Editorial FM-90 - --Tp~;~onal Hist~cyQuestiooo~ire (PHQ) and Self--;---;---- ***~*;/07~;-- *-~:r ~~~rial--

I Disclosure Personal History Questionnaire (PHQ) and Self-FM-90 I1 Disclosure 10 1

12/12/18 Minor Editorial FM-143 FM-152 --1 I 1/M Graph Fuel Ele~~~t Inspection _________________ - 4 3

10/03/18 Minor Editorial

--121i-wi8-- Minor Editorial FM-200 I Authorization to Conduct Background 2 08/07/18 Minor Editorial l Investigation for Unescorted Access to MURR i LCC-001 Reactor Advisory Committee Charter 1 10/02/18 Cover Page

-****-------- .~---*

LCC-002 Reactor Safety Subcommittee Charter 1 05/09/18 Cover Page

. LCC-003_ -----~ Isotope Use Subcommittee Charter----**-*--**-***----* 1 __.2?!~~!!~ .. Cover Page***---

LCC-004  ! Reactor Safety Procedure Review Subcommittee 1 03115118 Cover Page 1 Charter

• I Isotope Use Procedure Review Subcommittee --- LCC-005 , Charter 1 01/25/18 I Minor Editorial LCC-006 Reactor Action Subcommittee 0 10/02/18 New Charter OP-R0-210 Reactor Startup - Normal 20 04/23/18 I Minor Editorial

---

~-------------+---+----+--------- -

OP-R0-210 I Reactor Startup - Normal 21 12/10/18 Minor Editorial OP-R0-211 I Reactor Startup - Hot 16 04/23/18 Minor Editorial OP-R0-230 i Changing Reactor Power Level 11 Minor Editorial 12/18/18 **--****--***-***-*---------

' Nuclear Instrumentation Power Range Monitor -

OP-R0-312  !, Channel 6 16 12/18/18 Minor Editorial OP-R0-410 Primary Coolant System 16 05/10/18 Minor Editorial OP-R0-420 I PrimaiyandPool Water Analysis __________________l_O_i----*- 01/04/18 Minor Editorial OP-R0-480 Secondary Coolant System 22 01/12/18 Minor Editorial

__9R:~Q:.~~~******* _ J- Secondary Coolant System . __ ---*-****--- ----* *--- 23 07/12/18 Minor Editorial OP-R0-516 _ 1Valve Operation Air System 08/09/18 Minor Editorial

---+--1_3_+-------+-*****

OP-R0-520 I Emergency Power Generator 17 12/10/18 Minor Editorial OP-R0-525 *-~- Chill Water System ________***--**--------**---- *******- .__ !.2. _. __ 12/10/18 Minor Editorial OP-R0-531 i Primary and Pool Sample Station 15 07/12/18 Minor Editorial OP-R0-555 I Fire Protection System 16 04/23/18 Minor Editorial OP-R0-555 Fire Protection System 17 12/18/18 , Minor Editorial

---

+-----~------------1---+-----

OP-R0-730 F acility Exhaust System 18 05/10/18 Minor Editorial OP-R0-741 Waste Tank System Operation 23 05/31/18 Minor Editorial OP-R0-741 Waste Tank System Operation 24 12/18/18 Minor Editorial 1---------!--------"----"-----------+---+--

POL-20  ! Special Nuclear Materials Manual 4. 01/04/18 Minor Editorial RM-R0-405 i Reactor Demineralizer System *-------****--*- *****-*--**-*** 16 01/24/18 Minor Editorial RM-R0-405 I Reactor Demineralizer System 17 05/10/18 Minor Editorial

-e-------+---------

-RM-*-_-R:_0___4__ 05---+j-R_e_a-ct-o--r-D-emineralizer System -*--- 18 08/09/18 Minor Editorial RM-R0-405 Reactor Demineralizer System 19 12/10/18 Minor Editorial II-2 I

Measurement of Differential Worth of a Shim RP-R0-200 8 12/10/18 Minor Editorial Blade, RTP-11 Receipt, Inspection and Accounting of RP-R0-300 6 07/12/18 Minor Editorial Unirradiated Fuel

---*-**-****-------------------+------------------ --------- ------+----------------+---------------------------------*

i Removal, Transfer or Installation of an Offset SM-R0-025 3 10/01/18 Minor Editorial j Mechanism ----------------1---+-------'!--

SM-RO-l 00 Draining and Filling the Primary Coolant Side of 4 10/01/18 Minor Editorial Prima Coolant S stem Heat Exchan ers SM-R0-200 1 Manual Operation of Airlock Doors 276 and 277 5 01/31/18 Minor Editorial 1-SM_-_R_0__-2_0_0_ _-+j_M_an_u_a__l _O~p_era_fi~J?-~f Airlock Doors 276 and 277 6 12/11/18 Minor Editorial SM-R0-300 1* Control Console And Instrument Panel-Securing 13 06/28/18 Obsoleted

, Power B. CHANGES TO EMERGENCY PLAN IMPLEMENTING PROCEDURES As required by the MURR TS, 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 21 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:

!!:Jiiinb~

EP-R0-001 Definitions 5 04/25/18 I Minor Editorial EP-R0-006 Radiological Emergency 9 - 04/25/18 I CoverPage Emergency Planning Zone and Site Area EP-R0-0.14 10 04/25/18 Minor Editorial Evacuations EP-R0-015 Emergency Notifications 17 04/25/18 Minor Editorial EP-R0-015 Emergency Notifications 18 Minor Editorial EP-R0-017 Emergency Air Sampling ____________,____ 8 Cover Page o------***------

EP-R0-017 Emergency Air Sampling 9 Minor Editorial EP-R0-018 Emergency Radiation Exposure 8 5/18 i CoverPage EP-R0-019 Emergency Dosimeters 4 04/25/18 I Cover Page

~1---~~-----------------------------------1------;-

EP-R0-020 Emergency Equipment Maintenance 7 04/25/18 \ Minor Editorial FM-104 Emergency _Call List _______ ____ _ --------+---,-----------------------;------- 34 01/02/18 Minor Editorial FM-104 Emergency Call List 35 04/25/18 Minor Editorial

- - - - - - - - - - - ~ ~ - - - - - - - - - - - - - - - - - - - - - - - ! - - - - - + - - - -- - --*-***-

FM-104 Emergency Call List 36 10/01/18 Minor Editorial FM-104 Emergency Call List 37 12/17/1 'al

---

----------------------------!-------I-OA-10 Fire Extinguisher Locations and Types 15 12/17/18 Minor Editoriai OA-20 Emergency Equipment 23 01/02/18 Minor Editorial OA-20 Emergency Equipment 24 04/25/18 Minor Editorial OA-20 Emergency Equipment 25 12/17/18 Minor Editorial REP-R0-100 Reactor Emergency Procedures 22 03/15/18 Minor Editorial REP-R0-100 Reactor Emergency Procedures 23 06/14/18 Minor Editorial

---

+-

REP-R0-100 Reactor Emergency Procedures 24 12/31/18 Minor Editorial II-3

C. CHANGES TO RADIOLOGICAL CONTROL, BYPRODUCT MATERIAL SHIPPING, AND PREPARATION OF BYPRODUCT MATERIAL FOR SHIPPING PROCEDURES As required by the ~ TS, 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 234 revisions issued to the radiological control, byproduct materials shipping, and preparation for shipping byproduct material procedures, forms, operator aids, and plans. One new operator aid and four new procedures 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, and plans:

9 j 05/09/18 Cover Page ACG-NAA-218 I Cleaning Options for High Purity Materials , 8 j 02/02/18 Cover Page ACG-NAA-221 I ~;~e;:~Mat~riiisAnalysisFiuxMonitor i 10 I 02/02/18 .Co~~~-;;~-------

~~~~~~-;2;-1-~::::~;::~ and. Disposalo~Waste Acids From -1 ; I ~;;~~118 . Cover;:~-;--*

i Hi Pun Matenals Processm '

AP-HP-105 I Radiation Work Pennit I 16 I 10/19/18 Minor

-**--l*-------------*-*-------------. ---------------***---------------------. ---------------------------*-*------*--*-t--------------+------*---,. ,..............,_..

Editorial

~~!!!1..~1.Q?_ +Health Physics Emergency Eqmpment Checks ___ ' 1 !- 02/19/18***. _Mi:1..1~~E~!?rial AP-HP-115  ! Iodine 131 Bioassay 4 i 01/24/18 Cover Page AP-HP-117 J MURRinitialRadiationWorkerTrainingProgram

---

*-------------------------------t--*-----;---

15 I 12/12/18 MinorEditorial AP-HP-119 I HighRadiationAreaAccess I 10 i 02/19/18 CoverPage AP-HP-123 I Visitor Dosimetry- Reception Desk 13 02/19/18 Minor Editorial AP-HP-125 I Review of Unplanned Radiation Exposure 7 02/02/18 Cover Page **--

AP-HP-129 Hot Cell HC-01 Control 16 05/25/18 Minor Editorial AP-HP-129 Hot Cell HC-01 Control 17 06/21/ l AP-HP-135 ______! Project Authorization Requests -------------L 1 _j_ 04/05/18 __

AP-HP-150 J Source Calibration ' 7 \ 04/05/18 1

Access Authorization Program for Category 1 AP-RR-013 and/or Category 2 Quantities of Radioactive 2 10/03/18 Minor Editorial Material I Access Authorization Program for Category 1 AP-RR-013 I and/or Category 2 Quantities of Radioactive 3 , 12/13/18 Minor Editorial

. i Material i

---

*------,,,. . .--*--------+--*-----. . . . ----- .------------*-------*-----------.------ . _____________,,....... ------------*i---------***------'--. i .,,............................... -------*-------*---------------------*-*--------*

AP-SH-OOl I:~strat1ve Procedure - Rad10achve Matenal l 12 \ 12110118 Cover Page

_ _ _ _ _ _ _ _ _ _ _ 1___ ~pmg ___________*-----------------*------1'---*--------* ----------------------

BP-SH-005 Packaging of Type A Radioactive Material Using 2 ' 051241181 Covtir P age SAFKEG-LS and SAFKEG-HS Packaging Radioactive Material for a Limited BP-SH-010 9 10/19/1

• or Editorial Quanti Shi ment Packaging of Type A Radioactive Material Using BP-SH-011 USA DOT 7A 55-Gallon ---*-*-------*-*-----L_.

I 10 10/03/18 Minor Editorial BP-SH-012 DOT-7A Package Certification 8 03/16/18 Cover Page Packaging of Type A Radioactive Material Using BP-SH-013 10 Cover Page USA DOT 7A 5- to 30-Gallon Reusable Drmn Packaging of Type A Radioactive Material Using BP-SH-013 11 10/03/18 Minor Editorial USA DOT 7A 5- to 30-Gallon Reusable Drum ************"**********-*-*-***-----

Packaging Type A Radioactive Material in an BP-SH-014 8 03/16/18 Cover Page Ove ack 11-4

.*Numil~f~i~~f/1,. \* 1::&aµie;i1~;\Jt:. '. i'.'f$t'i;'J1 ~1f{i::i; *.. CJ ,, *,,z1p*~+, *

• 1

,I{~v;t!;}ll"'v '.Date::l'.Ni,i~s/ ;, 5 ::*i~tt Packaging of Reusable Type A Radioactive BP-SH-017 6 10/03/18 Mnior Editorial Material Using Tracerco LS-6 Packaging of Type A Radioactive Material Using BP-SH-018 USA DOT 7A NorthStar Medical Radioisotopes 6 04/23/18 Minor Editorial Package Packaging of Type A Radioactive Material Using BP-SH-018 USA DOT 7A Northstar Medical Radioisotopes 7 07/19/18 Minor Editorial Package Packaging of Type A Radioactive Material Using BP-SH-031 5 05/24/18 Cover Page DOT7A20WC-1 Radioactive Material Shipment Package BP-SH-052 18 I 06/21/18 Minor Editorial Documentation and Labeling Spectratek Services Reusable Packaging of Type BP-SH-059 8 10/03/18 Minor Editorial A Radioactive Material ***---*-******--*-***--*-****-

Packaging of Type A Radioactive Material Using BP-SH-099 8 12/10/18 Cover Page USADOT7AMURRModel 1500 Packaging of Type A Radioactive Material Using BP-SH-145 3 06/21/18 Minor Editorial USA DOT 7A F-458 Packaging of Radioactive Material Using USA BP-SH-192 2 II 04/05/18 Minor Editorial DOT 7A Model MURR MAX I BP-SH-192 Packaging of Radioactive Material Using USA 3  ! 05/24/18 Cover Page

--..DOT 7A Model MURR***-*-**

- ..-*--*****--** MAX I -*- *-----------**-**

BP-SH-192 Packaging of Radioactive Material Using USA 4

I 10/03/18 Minor Editorial DOT 7A Model MURR MAX - - - - * - *-*-*--*-***-****-*-****--*****- ----------------*****-*-

Packaging of Type A Radioactive Material Using BP-SH-302 11 10/03/18 Minor Editorial USA DOT 7A MURR Model 6 or 12 BPB-SH-020 Receipt Inspection _Of Type B Shipping Package 8_J__Q_~/o5/18 Cover Page --------

BPB-SH-023 Type B Eq11..i.e:111ent Calibration 7 I 05/10/18 Cover Page * - - -

Type B USA/0697/B(U)-96 (F-458 Series)

BPB-SH-024 9 10/19/18 Minor Editorial Packaging of Type B Radioactive Material Packaging of Type B Radioactive Material Using BPB-SH-025 6 10/19/18 Cover Page USA/0562/B(U)-96 (BEATRICE)

I Survey and Decontamination of Returned BPB-SH-027 9 I 12/10/18 Minor Editorial Shinning Containers I Packaging of Type B Radioactive Material Using BPB-SH-028 USA/9337/B(U)-96 (SAFKEG-LS) and 7 12/20/18 Cover Page USA/9338/B(U)-96 (SAFKEG-HS)_ _ _ _**- _ II *****-*****-*****--**----

Type B Shipment of Spent Fuel Using the BEA I FB-SH-110 Research Reactor Package 5

I 01/04/18 Minor Editorial Type B Shipment of Spent Fuel Using the BEA FB-SH-110 6 03/16/18 Minor Editorial Research Reactor Package Type B Shipment of Spent Fuel Using the BEA FB-SH-110 7 05/10/18 Minor Editorial Research Reactor Package FM-13 Receipt of Radioactive Material 9 I 01/24/18 Cover Page FM-17 Radiation Work Permit 15 I 02/02/18 Cover Page FM-27 In-House Radioactive Shipping Request Form 18 03/16/18 Minor Editorial

-*FM-27 In-House Radioactive Shipping Request Form 19 07/19/18 Minor Editorial Control Checksheet for Packaging of Radioactive FM-39 17 10/03/18 Minor Editorial Material for a Limited Quantity Shipment I Control Checksheet for Documentation and FM-52 21 06/21/18 Cover Page Labeling of Radioactive Material Shipment FM-54 Report of Personnel Contamination 10 03/15/18 Cover Page II-5

! Control Checksheet for Spectratek Services I FM-59 J Reusable Packaging of Type A Radioactive *1. 11 10/03/18 Minor Editorial

' Material Control Check Sheet for Packaging of Type A FM-60 Radioactive Material Using USA DOT 7A Model 8 07/19/18 Cover Page E-Box 030-181 FM-62 Radiation Instrument Certificate of Calibration

---

+-------------------------------------- -----+-----------------1--------------------1 9 05/10/18 Minor Editorial eceipt of Radioactive Gemstone Shipping FM-67 10 01/24/18 Cover Page ontainers Control Checksheet for Packaging of Type A FM-69 Radioactive Material Using USA DOT 7A 5- to 14 03/16/18 Cover Page 30-Gallon Reusable Drum Control Checksheet for Packaging of Type A FM-70 Radioactive Material Using Tracerco LS-6 6 10/03/18 Minor Editorial Reusable FM-76 Personnel Contamination 6 05/25/18 Cover Page Lutetium. Chloride Radiation Protection Data FM-79 SheetB FM-80 , Material License Project Review Report I orial FM-91 l Declaration of Pregnancy

---

1-------------------------------------------------------------------------------------- -----------------------,

I FM-94 Exclusive Use Shipment Controls i FM-96 Dysprosium. Dissolution Data Sheet , 4 - - - - - - - - - - - - - - - - - - - - - - - _ _ Cover_ Page _ __________

-- ---- -- I Control Checksheet for Packaging of Type A i FM-98 I Radioactive Material Using USA DOT 7A MURR i 13 10/03/18 Minor Editorial

---

1-------- I Model 6 or 12 Control Checksheet for Packaging of Type A I FM-99  ! Radioactive Material Using USA DOT 7A MURR 12 I 12/10/18 Cover Page I Model 1500  !

FM-107 ---T-Rcodn~ol <?hecMakshe~tlf~r-Pacok~higTk-yp~x-----

1 a 10act1ve tena m an ve ac

~~--1 I

03/1  ;;~-;-*--rl-~:~:;*-;:;~----------

FM-109 I Dy/Ho-166 Separation Data Sheet 1 3-----__JI___________

---

-------------------------------------------------------------------------------------------------------------------------------------------------------------.1------------ 10/01/18 -----------------------------------------------

Cover Page FM-120 1 Individual Type B QA Training Certification I 8 J 12/10/18 Cover Page FM-126 j Do.cum.entationofComplianceforDOT-7A I Shi m Packa e

' I 6 I 03116 18 Cover Page

~

{ll----=--- 1

~~~:;;~;:t:~~:;~;;~atashee!===~--~1-_---_--_--_-_-_--_-!-----__-__ _ _ _ 1________ _ _ _~-----(---~------~----/-J-----~--------_-_-_-_+___----~------~--'.:---;---~------;------;--'"i-;___n_ _ _ _a_________________1 9 0 1 Control Checksheet for Packaging of Type B FM-135 Radioactive Material Using USA/0562/B(U)-96 7 10/19/18 Cover Page (BEATRICE) 01/04/18 Minor Editorial 02/19/18 Minor Editorial 03/29/18 Minor Editorial FM-137 I Type B Qualified Shipper List 24 06/29/18 Minor Editorial FM-137 l Type B Qualified Shipper List ----- ----- --- 25 07/19/18 MinorEditorial 1 Control Checksheet for Leak Testing the FM-138 I SAFKEG-LS or SAFKEG-HS Shipping Package 8 12/20/18 Cover Page

' Usin the CALT Leaka e Testin Device

' Lutetium. Chloride Radiation Protection Data FM-139 6 04/05/18 Cover Page Sheet C Lutetium. Chloride Radiation Protection Data FM-139 7 12/10/18 Minor Editorial Sheet C II-6

• ,:~4ev)liii'!e~PiiteJ N4tes i

• Y'.CY*X,", ?

FM-141 Control Checksheet for Packaging of Type A Radioactive Material Using SAFKEG-LS and I 5 I 05/24/18 Cover Page SAFKEG-HS I I FM-144 Control Checksheet for Packaging of Type A I 3 I 10/03/18 Minor Editorial Radioactive Material Using Tracerco LS-1  !

Control Checksheet for Packaging of Type A FM-145 3 i 06/21/18 Cover Page Radioactive Material Using USA DOT 7A F-458 Control Checksheet for Packaging of Type A FM-147 4 08/07/18 Cover Page Radioactive Materiai'Using Tracerco LS-15 i Control Checksheet for Packaging of Type A '

FM-147 Radioactive Material Using Tracerco LS-15 5

I 10/03/18 Minor Editorial FM-149 Personnel Radiation Dose Estimate 02/19/18 2 ___ .._......................................... _,,-

Cover Page Control Checksheet for Packaging of Type A FM-151 , ~~::ctive-~~erialUsingUSADOT7A55- j 14 10/03/18 Min~r_E_di_*t_o_n_*al _ _,

FM-157 ' Control Checksheet for Type B USA/0697/B(U)- I 11 10119118 Minor Editorial 96 (F-458 Series) Radioactive Material Package I I Control Checksheet for Health Physics Review of 10 1 04105118 . Minor Editorial FM-159 Radioactive Material Shipment Documentation 11 Control Checksheet for Type B Radioactive I

~~:-~~~----;s~:~1g~~~~=::rs~~~~~~---,--..-~~-1. I Control Checksheet for Type B Radioactive  !. l

~2/02~~---~:~.~~~~orial__ _

FM-163 I Material Using USA/9337/B(U)-96 (SAFKEG- i 11 j 12/20/18 Minor Editorial

___________ '_ LS} and USA/9338/B(U)-96 (.§_AFKEG-l!fil_______J.___t_________ . . . . . _______________.

FM- 164 Authorization For Use of North Office Addition 5 I 04105118 Cover Page West Passageway (C2001) I Control Checksheet for Packaging of Type A i FM-169 Radioactive Material Using USA DOT 7A 20WC- 5 05/24/18 Cover Page 1

Control Checksheet for Packaging of Type A FM-170 Radioactive Material Using USA DOT 7A 5 , 04/05/18 Minor Editorial

___________ Northstar Medical Radioisoto~s Packag~ ----------"-----__! _____. ____ . . _. ___________,

Control Checksheet for Health Physics Review of I* I FM-173 Excepted (Limited) Quantity Radioactive Material / 2 j 03/15/18 Cover Page Shipment . _ I____- { - - - - + - - - - - - - - ,

FM-174 Instrument Pre-Start-Up Check Sheet  ! 1 j 05/25/18 Cover Page FM-175 i Control Checksheet for Receipt Inspection of I' 3 j 10119118 Cover Page

, Customer Owned Type B Shipping Package I

[ Control Checksheet for Packaging of Type A I I Cover Page Radioactive Material Using USA DOT 7A 3 j 12120118 FM-176 Northstar Medical Radioisotopes Package with 7.5 'I _J Ci ofMo~99* - * - - - - - - - - - - - - - , - - - - -----+-----------

Control Checksheet for Receipt Inspection of FM-177 3 10/19/18 Cover Page SAFKEG LS and HS Type B Shipping_]>ackag_~----+--------+------

FM-178 Control Checksheet for Hot Cell HC-01 Access 4 01/04/18 Cover Page FM-178 Control Checksheet for Hot

......-----********---*-**--****** --**------------........................____________________________________________.._________...,...- ....--.. Cell HC-01 Access 5 06/21/18 Minor Editorial Control Checksheet for Documentation and FM-179 Labeling of Excepted (Limited) Quantity 2 03/16/18 Cover Page Radioactive Material Shipment Control Checksheet for Packaging of Type A I FM-192 Radioactive Material Using USA DOT 7A Model 1 1 05/24/18 Cover Page MURRMAX 1 II-7

.Noirtb,¢r}. 2'\,i.(: ~""'.'iil'.~}tzr,ii;)l\ <; *\>\.  : I' / :{}tf)5,/:}i{~Jil('lley*Uiti~<l:Notes*' '.}/. /~'.*:

Control Checksheet for Packaging of Type A j FM-192 Radioactive Material Using USA DOT 7A Model

• 2 110/03/18 Minor Editorial MURRMAX I i Control Checksheet for Documentation and 1 ,

FM-194 II Labeling of Radioactive Material Shipment 1 10/19/18 Cover Page Packaged in an Overpack 1 1

-~LP-MCE-002 I Installation of Gamma Spectroscopy Detector 2 I 06/20/18 Minor Editorial GLP-MCE-00 3 ' Performance Checks of the High Purity j 5 1*

09127118 Minor Editorial Germanium Detectors . 1 I-G_MP_-_B_R_-_40_4_--t-_M_o_-_99_P_ro_c_es_s_C_l_ea_mn_*_,g""-an_d_L_in_e_C_le_ar_an_c_e_ _+i_6__ 08_/_2:2/_1_8-+_Min_._or_E_di_to_r_ia_l_ _. J

_G~_::!l..!:{.-404 ....... Mo-99 Process Cleaning an_d_L_in_e_C_le_ar_an_c_e___,1_7_-_110!2 __/_2_3_/1_8-+_Min_'_o_r_E_di_'t__or_ia_l_******-

GMP-BR-502 SodiUI)llodideI-131 SolutionBatchRecord l 4 ! 04/10/18 Minor Editorial GMP-BR-502 1 Sodium Iodide I-131 1----**----............................._______........--r---*-*----------*****-***-**--.

Solution Batch Record

.--....................................................................... ,_,_____,...............--.. I'.**-*******-******-

5 Ji,-*-**-** 06/11/18

. --..--............................Minor

,_____.........Editorial GMP-MCE- 122 ! Establis~g Calib~atio~ Factors !or Calicheck j 3 / 09127118 Minor Editorial I Dose Calibrator Lmearity Test Kit I i

-~~-~C~-124 ~aning, Maintenance and Operation ofHC-08 I ~--1-0--1/-2--3-/_1__8-+-Min-.-o-rE-d1-'to_n_'a_l__

GMP-MCE-124 ,

I Cleaning, Maintenance and Operation ofHC-08 9 06/08/18 Minor Editorial I A1B GMP-MCE- 129 j OperationandMaintenanceforaTuttnauer3870 I 5 1.

09127118 MinorEditorial

. EA-BIL Electronic Tabletop Autoclave _J 1 ..... ,---****---*****---

GMP-PRC-201 I ~~ans:rofcGMPLu-177 ChlorideProductto I 11 I 03/22/18 Minor Editorial

-* ~ g . *****-**-*****-**-*****-*-**-*-*-**--**--*--*- --***---***{--*****--- -------***---*

GMP-PRC- 400 I Transfer ?f cGMP _Potassium Molybdate Final 2 I 08121118 Minor Editorial

! Intermediate Solution to Customer I GMP-QC- 021  ! p~ Dete~ati?n of Lu-177 Chloride Solution by 5 1 01112118 Minor Editorial I Microcombmatlon pH Probe 1

-~~-RA-~~:______ I ~~dc~:::~~-~~~e--~~131 Productio~Facility I ~-~1251~~CoverP.age I

GXP-EPRT-067 and Performance Qualification for a Capintec New and/or Retrospective Installation, Operation, )

'. 0 06/13/18 New Procedure CRC-77tHR Dose Calibrator

-*-------*--!-------------------.. --------- -,-- *-* .. ---- --- .............. -*--**-*****----*********-******-*******--*****--*-* l GXP

-MCE-123 Cleaning, Maintenance and Operation of Hot Cell i HC-04

• i 3 II 02120118 Minor Editorial GXP-MCE- 123 I ~~~~!ng, Maintenance and Operation of Hot Cell I 4 I 05116118 Cover Page HC-PS0-00 2 I Hot Cell Preparation of Radioactive Material for I

,__ _ _ _ __,_S_hi~ip~m_e_n_t_ _ _ _ _ _ _ _ _ _ _ _ __, __1_9_ I 10/03/18 Minor Editorial IC-HP-300 Calibration - Radiation Survey Instruments  ! 9 l 06/07/18 Minor Editorial Calibration - Eberline PCM-1 Contamination IC-HP-313 1 02/19/18 Minor Editorial Monitor IC-HP-340 Calibration - Bladewerx Saber BPM Air Monitor

• • -----------------1---+---*-*-*

1 I 04/05/18 Cover Pag. - e ---,

--~~:~~-34_1____ -~~i~;~~;~~t~~:°.~:~~::.~:::_ _ _ _ --+J---~---!!-;_0_5_11_0_11__8____c_o_v~=-~~:____

IC-HP-343 Calibration - Sodium Iodide Detector I 6 I 03/15/18 Minor Editorial IC-HP- 346 j C~librati?n - Lab Impex Smart MCA Continuous I 4 03130118 Minor Editorial

__ .* _____________1_ Arr Momtor_ _ _ _ __ __ ___ __ ___ .. __ _________ -***-*'******-*-*-* ........................... ******-*- **************---*********-**-****** **********-*--*******

IC-HP- 346 I C~librati?n - Lab Impex Smart MCA Continuous I 5 07/19/18 Minor Editorial t Arr Momtor  !

f-IC-HP-348 j Calibration - Canberra S5XLB-G-----* [ 8 05/25/18 Minor Editorial IC-HP- 349 I Calibration - Lab Impex Stack Monitor - I Particulate Channel I 9 01/04/18 Minor Editorial II-8

I '.Numli~r~1l~i<,-,;, Nadi~:~$lt/i:C, ~:

IC-HP-350

'i;; ':t~:ri!fi,:<' ', ,-;,,;,g*;:~?;,;i:

Calibration - Lab Impex Stack Monitor Iodine Channel

, JR,iv/1l1i,1t~vDat,l <<;~lites\

6 01/04/18 Minor Editorial

' tDt~

• IC-HP-351 ~:~:fon - Lab Impex Stack Monitor - Gas IC-HP-352 a raon CCalli~bbratiti_on - Lab Impex Stack Momtor - Flow 6

---

*-*-- --1-<<<<<<<<< -*<<<<<<

7 j 01/04/18 Minor Editorial 01104118 Minor Editorial

• IC-HP-353 * - Calibration - Lab Impex Monitor - DP2001 IC-HP-359

---

f---**

IC-HP-361 IC-l,!P-363 Calibration - Ludlum Model 177 Frisker Calibration - Canberra GEM V Portal Eberline BC-4 Beta Swipe Counter - Calibration Monitor 3---+-i-0-2-/1_9_/_18- ~~ Page 3 02/02/18 Minor Editorial

- - - - - - ! - - , - -.. ------ii--*--~------***------******

2 05/25/18

- - - - - f - - -..- - + - - - - - f - - - ~ -...- -

2 Cover Page 02/02/18 Cover Page

J .!~-~

:~.?_+/- ----- .Calibration -.Ludlum Model 3030.Swipe IC-HP~365 Calibration - Thermo PM-12 Portal Monitor Counter ...... 2 2

02/02/18 02/19/18

<<<<<<<<------+-*--*<<<<--+<<<<<<<<<<<<-

J IC-HP-366 Eberline Model PM-7 Portal Monitor Calibration 1 02/02/18 Cover Page IC-HP-367 Calibration - I-131 Bioassay Detection System 3 05/25/18 Minor Editorial

J IC-HP-368 Calibration - ALM0-6 Radiation Monitoring 1 02/02/18 Cover Page Instrument *-**------

J ----****

IRR~PS0-112 Preparing Shipping Paperwork 10 , 07/20/18 Minor Editorial J -~~~~---********** :r:::tsuthor~:~o~cation for the ___ 1. L 10103118 --e-~or_~-~~~~~--

J -OA-26------=~~~:a~:~:i~cens~ ~~rificationReportfor 1 I. 12113118 _cover~~~=-----

_60 Packaging of Type A Radioactive Material Using f c p

J OA USA DOT 7A ModelE-Box 030-181 2 I 07119118 i

I over age Packaging of Type A Radioactive Material Using

~ OA-99 USADOT7AMURRModel 1500 2 J 08/07/18 Cover Page I

~

OA-128 OA-192 Packaging of Type A Radioactive Material Using USA DOT 7A MURR Model H or I

- ... - - - - - - + - - - - - - - - - - - ' - - - - - - - - - - - - - - - - - > - - - - - - - - -

Packaging of Type A Radioactive Material Using USA DOT A Model MURR MAX 7*----*

2 , 05/24/18 Cover Page O

II 06/08/18 New Operator Aid

• OP-HP-200 Air Sampling - Containment Building Tritium 8 02/02/18 Cover Page OP-HP-221 Environmental Sample - Analysis 8 I 05/10/18 i

OP-HP-222 Air Sampling - Containment Building Ar-41 9 I 02/19/18 OP-HP-224 Spent Fuel Shipping Cask Air Sample Analysis 6 Ii 05/25/18

• OP-HP-228 OP-HP-236 Performing Iodine 131 Bioassay Measurements ---,----f-------1-Min_*

Respirator Selection, Issuance, and Wearing 6

2 I 11 I 02/02/18 12/11/18 _o_r__E_d_it_or_i_al__ 1 04/23/18 Cover Page OP-HP-300 Receipt of Radioactive Material OP-HP-306 ____ H_ea__l\h Physics D~~1.Y F~~ility Checks 9 ____ J._ _ 02/19/18

J OP-HP-306 Health Physics Daily Facility Checks 10 10/19/18 Minor Editorial

_9_!-~~g_ ______ Particulate andfodine Filter - Analysis,___ ,____ <<<<<< ,_ ____?_ ___ 2.?}-2?~~ << _C_<l_~! p~~~--<<<< ---

J _9P-HP-353 __ Waste Tank Sample - Analysis 9 05/10/18 Cover Page North Office Addition Waste Tank System Filter 10/03/18 Minor Editorial OP-HP-354 3 Replacement North Office Addition Waste T~ System 5 10/03/18 Minor Editorial OP-HP-355 Operation

• OP-HP-356 OP-HP-356 Operation - Lab Impex Stack Monitor: Filter

,_________C_h_an_~~d Source Checks Operation - Lab Impex Stack Monitor: Filter Change and Source Checks Operation - Lab Impex Smart MCA Continuous 8

9 01/04/18 03/22/18 Minor Editorial Minor Editorial

] OP-HP-358 1 02/02/18 Cover Page

, Air Monitor Filter Change and Source Check I II-9

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Operation - Lab Impex Smart MCA Continuous OP-HP-358 \I 2 05/10/18 Minor Editorial Air Monitor Filter Change and Source Check OP-HP-359 I  !~f;! Bag-Out for Changing Bank Exhaust j: 0 03/22/18 New Procedure op-HP-365 Iodine 131 Processing Hot Cells Radiation Monitor (ALM0-6) 2 12111118 C p over age OP=HP-420 - De~~ationofE~~~~~-;-~-u~~* --1 6 I 02/19/18 MinorEdit~;i~l--

_9-_~~.!!!1.::.:1'20 ____ ,__ Decon~amination of Enclosed Processin~ Units **r* 7_j 12/20/18 Minor Edi!?!!~

OP-HP- 500 O_peration of the Hot Cell (HC-09) Intenm Storage 2 02119118 Cover Page Silo ---+----~~----*----

Operation of the Hot Cell (HC-09) Interim Storage I OP-HP-500 Silo 3 07/19/18 Cover Page PLAN-130 10 CFR 37 Security Plan for the University of I 1 04/23/18 Minor Editorial Missouri Research Reactor I PRC-RRD-OOl Preparing ~d Submitting a Radioactive Sample I 6 02126118 Cover Page

---

*--*---* ___ forPaclrngmg_ _ -----.------- .. *-* -***--*-*-*-! ******--** __ **----- -----..*--*----*----..

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PRC-RRD-106 I Separation of Dy/Ho 166  ! 3 10/01/18 Cover Page PRC-RRD-217 I Dissolving Lu-177 I 3 05/11/18 Minor Editorial PRC-RRD-2181 Lu-177 Distribution - - j 9 02/26/18 Minor Editorial PRC-RRD-219 ! Lu-177m Processing 4 12/20/18 I Minor Editorial

_RR_C~~.::1_13_ _A_u__D_is_s_ol_u_ti_on ___*---*---*-**--*-*--**-*----- _6 __ ~10/01/18 _ Minor Editon_*a_l__, L PRC-RRD-314 Neodymium Dissolution 7 12/11/18 I MinorEditorial

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~-~-~-iii---~~!J~~~i1:~:f£!!i2___-----*-----**-- * -** * * * * * *- ~

PRC-RRD-317 Ce-Oxide Dissolution 3

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12/11/18 Cover Page

!'-~g.::-~~-~-!..~---. Dissolution of Copper Nitrate _ -*******----..*--*------------**--..*--*-***--L.. 2:2i~~!~- . ~?.!E~~!.?.~ll_!_.___

_XRC-.RRD-'!:9? _ . . Dissolving Sm-153 ------------*--------*-----*****---*****-*-*-****------*,-*__'! __ _91~__ 111_8_ ~.?.~_E.E._i!.?.!1_* al_****-******

PRC-RRD-414 Dissolution of Gadolinium Nitrate 7 02/26/18 Cover Page

...R~C-~-420 I Rh-105 Processing --*-*-----=-8--1-1-0-/1_8_/_18---+-F-u_ll_R_e_v_,,ie"--w---1 PRC-RRD-421 Dissolving Re-186 7 12/20/18 Minor Editorial PRC-RRD-424 Dissolving Platinum Powder I 3 05/11/18 Minor Editorial Sodium Iodide Spectral Qualitative Analysis for J

,__Q._A_-_s.-H. _-0_0_2_*-*---************+-*:-*-~-c-~~1~~~~~;.~M:~!~:ii~=;~!~~-A, ~~~~~: _j~9----+---0-4._/_o._5_/_1_8-+-Min_* ___o_r_ ~-d-ito_n_*a_l__ _

Sodium Iodide Spectral Qualitative Analysis for I QA-SH-002 Excepted, Type A, and Type B Radioactive 1* 10 . 12/10/18 Minor Editorial f----..-**--*---

Material Shipments ___ _ _ _1 ___

QA-SH-003 Release ofNorthStar Mo-99 Product Vessels O 12/13/18 New Procedure

-QAB-SH-005 **-- Type B QA Personnel Training*---------*****************---*-- .. __?. ___ -*-~?.!!9-(_!_!__ __ fyfin.?.! Edit~~-1_

Leak Testing the SAFKEG-HS or SAFKEG-LS QAB-SH-007 Shipping Package Using the CALT Leakage I 7 12/20/18 Cover Page

--- ___ Testin~ice___ --- -r-- -~-**-**-*****----+----------,

QAB-SH-008  !:~:e;~r Type B Shipment Leak Test \ 3 1011911~ I Cover Page RCP-PS0-002 P-33 Glove Box Can Opening I 9 12/10/18 Minor Editorial RCP-PS0-003 P-33 Purification Set-Up I 12 J 12/21/18 Minor Editorial II-10

1:1~'11'.JJ,iti~i,;';~l", *1{ .I :NaJ¥"e}~c * *:{(:~~:,, ;~: _!::*, ){' :)t: '*ilf J;;f;\J .~ 1-!~v: :l&R,~y,D@Je ,J'.Ni{t~s:iit* ,~t *'&:: 't RCP-PS0-020 .Selenium-75 Process 3 12/10/18 Minor Editorial RCP-PS0-400 Operation and Cleaning of Shielded Mo-99 0 10118118 New Procedure

. . ----*--.. -- . . . . . . . . . . .  !!~8-f.~!~(?~--*--*- ---*-------*--- *************-****!*-**-* ...... - - * - ---*---****----..*-*-*-....--*-

RM-~~~02  :;~xMonitor Preventative Maintenance - ~~~ ' 3 I 02102118 Cover Page RM-HP- 102 Stack Monitor Preventative Maintenance - Lab I --t 4 \ 12/11/18 Minor Editorial Impex RP~HP-100 Contamination Monitoring - Performing a Swipe I 8 02/02/18 Cover Page

---

**---***----- -------**-*******-**** *-***-******--******-***-----+-----**-****----*** -* --*--**--*--------

RP-HP-105 Tra1:1~fer of Radioactive Material Within the  ! 13 12111118 Cover Page

- - - - - * ! -Fa~th!>-'. - --*--*---

RP-HP-115 Returning Lead Pigs to Service 7 05/10/18 Cover Page RP-HP-120 Personnel Radioactive Contamination 13 03/15/18 Minor Editorial

.. _ _ _ .. _ ...... t--.... - - - - * - -..----*--*--..---..* - - - - - * - - - - - - - - - -......._.. _ ..........._._....... - ..-i,-..*---..-*!-*-..* - - - - - -....-+ .... --..* - - - - - -....... _

RP-HP-120 Personnel Radioactive Contamination 14 06/21/18 Minor Editorial

+-----+---*--..-..- ~ 1 - - - -

Radiation Monitoring - Performing and 02/19/18 Cover Page RP-HP-125 5 Documenting a Survey Radiation Monitoring - Performing and 10/03/18 Minor Editorial RP-HP-125 6 1

Documenting a Survey RP-HP-130 Rec_eipt ofUnirradiated Fuel 9 I 04/23/18 Cover Page RP-HP-135 Room 114 Entry- Self Monitored 8 i 04/05/18 Cover Page

_RP-HP-13 7 _____ Handling Radioactive Material in the Reactor Poo!_ _ 16_.J_02/02/18 _ . . Cover Page-*-.. --. __

-:~~~~~ 0 ___. _ 1:::g~~t~S;::erial int~-~-~~~E!~~~()!_i-*-{--\-- i~~i~~~: ~~~:ri3!

--~!=~~_2-~_2.Q_~----*- _Operation of the Can Press -----------*-*****------* 4 06/21/18 Minor Editorial SV-HP-lOO React~r C~emistry Isotope ~01.~ter Trending and 9 02102118 Cover Page

_______._____ )nvestl~hve Level Deternnnation --*----*-- _______. _

SV-HP-105 Sealed Calibration Source - Leak Check 10 04/23/18 Cover Page J

_SV-HP-llO______ Environmental Sampling --.. -*---*--*----.. ------ __ 9__ 05/10/18 Cover Page ___ _

SV-HP-l1 5 J Buil~in~ Exhaust Stack Effluent-Tritium 6 02119118 Cover Page

-*------*------ .. ~ M~m~onng -------------*---.................................... ............ _. __ . __ . _._. 1.......... ._ _ ...

SV-HP-l1 5 1 Buil~m~ Exhaust Stack Effluent- Tntmm 7 1 08107118 Minor Editorial I Momtonng

. SV:~:!!Z____*-..*-- __Secondary Coolant and Sump Water Analysis _ . _.Z_*-*- ___Q?.{!2(! 8_ Cover. Page

_S"':_~~~-!_19 __ _ Property Release _______ .__________ _ _____ _i!__ __Q_'!{Q5/18 Minor E~_*t_otjal __ _

SV-HP-119 Property Release 12 12/11/18 Minor Editorial

, Building Exhaust Stack Effluent - Ar-41 05/10/18 Cover Page SV-HP-121 8 I Monitoring

. . .SV-HP-135

--..*-------*--*-........*-*1---.

TPZ-PS0-002 i Containment . .--..*--

.-.. . -.. . . . . .Air - - - *Remote Emergency I Irradiation of Gemstone Irradiation Containers Sampling 9

r---..

. ___.___. ._. . .6. . . . . . . I 12/11/18 Cover Page 03/15/18 Minor Editorial TPZ-PS0-003 j Load~~ Gemstone Shipping Drull?:_5- -*- . __ ?J__Q}/15/1!_ . . ~or Editor.ial__ _

TSP-02 Transportation Security Plan --------*** _ 9 I 12/11/1 ~- . Minor Editorial -

• WM-SH-100 Radioactive Waste - Preparation and Storage 11 03/16/18 Cover Page WM-SH-105 ' Radioactive Waste Processing 14 07/19/18 _Cover Page

-~_;;~llO -Radio~ctive Waste - Barrel Analysis for Shipment 4 12110118 Cover Page

____. ____ ---~* D1s~sal ____._________. . ____. _____. ._ . *-*---*--~ **-..--..*-- ......_. ___. . _. __.-.. .- * - - -..-

WM-SH-115 Iodinel-131 Waste Handling 3 02/02/18 Cover Page II-11

SECTION ID REVISIONS TO THE SAFETY ANALYSIS REPORT January 1, 2018 through December 31, 2018 On August 31, 2006, MURR submitted a request to the U.S. Nuclear Regulatory Commission (NRC) to renew Amended Facility Operating License No. R-103 for another twenty years of operation, at which time MURR also provided its proposed Safety Analysis Report (SAR). On January 4, 2017, the NRC issued Renewed Facility Operating License No. R-103.

During 2017 and 2018, thousands of person-hours were spent by MURR staff to update the August 31, 2006, SAR with all of the facility changes and modifications that had 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 the first half of 2019.

During calendar year 2018, modifications or changes to the facility occurred that required the following revisions to the ~AR, as submitted to the NRC in 2006 for relicensing. The following changes have been reviewed, in accordance with 10 CFR 50.59, by licensed staff and members of the Reactor Safety Subcommittee; determined not to involve a change to the MURR Technical Specifications; and approved by the Reactor Manager.

CHAPTER 3 - DESIGN OF STRUCTURES, SYSTEMS, AND COMPONENTS Section 3.5.2, first paragraph, fourth sentence (page 3-30)

Revise to read: "Each drive mechanism consists of a single-phase motor connected to a lead screw assembly through a reduction gear box and adapter."

CHAPTER 4 - REACTOR DESIGN Section 4.2.2.l, fourth paragraph, second sentence (page 4-15)

Revise to read: "Each control blade drive mechanism consists ofa 0.02-HP, 115-volt, one-amp, single-phase, 60-cycle motor connected to a lead screw assembly through a reduction gear box and adapter."

Section 4.2.2.l, fourth paragraph, fourth sentence (page 4-15)

Delete Section 4.2.2.1, last paragraph, second sentence (page 4-17)

Revise to read: "Signals from the shaft encoder are converted into actual rod position by the Rod Position Indication (RPI) chassis mounted into the control room instrument panel."

ill-1

CHAPTER 6- ENGINEERED SAFETY FEATURES Section 6.2.3, second paragraph (page 6-5)

Insert new sentence at end of paragraph to read: "One line used for containment DP instrumentation exits the containment structure through one of the penetration plates."

Section 6.2.3.1, Table 6-1 (page 6-6)

Insert new row to read: \ Containment DP Instrumentation \ Manual Valve 1 Section 6.2.4, second paragraph, third sentence (page 6-13)

Revise to read: "Air is supplied to the pneumatic cylinders from the facility main air compressors and the emergency air compressor via a point-of-use air dryer to prevent moisture accumulation."

CHAPTER 7 - INSTRUMENTATION AND CONTROL Section 7.3.1, Table 7-3 (pages 7-12 to 7-15)

Delete "2 Source Range Monitor Level Recorder" Revise No. 3 to read: "Intermediate Range Monitor Level Recorder" Revise No. 4 to read: "Source and Wide Range Monitors Level Recorder" Revise No. 5 to read: "Power Range Monitor Level Recorder" Revise No. 85 to read: "Primary Coolant Th - Tc Recorder" Revise No. 87 to read: "Pool Coolant Th - Tc Recorder" Revise No. 89 to read: "Primary Coolant System Flow Recorder" Revise No. 90 to read: "Pool Coolant System Flow Recorder" Revise No. 91 to read: "Primary & Pool Coolant Demineralizer Flow Recorder" Revise No.* 108 to read: "Secondary Coolant System Recorder" Revise No. 128 to read: "Off-Gas Radiation Monitor Recorder" Revise No. 130 to read: "Off-Gas Radiation Monitor Recorder" Insert "135 Containment Differential Pressure Indication/Alarm" Section 7.4.2.1, first paragraph, last sentence (page 7-22)

Revise to read: "A paperless recorder mounted on the instrument panel records Channel 1 source range level and transfers the data to a server for archiving."

Section 7.4.2.2, first paragraph. last sentence (page 7-22)

Revise to read: "A paperless recorder mounted*on the instrument panel records Channel 2 and 3 intermediate range levels and transfers the data to a server for archiving."

ill-2

Section 7.4.2.3, first paragraph, last sentence (page 7-23)

Revise to read: "A paperless recorder mounted on the instrument panel records Channel 4, 5, and 6 power range levels and transfers the data to a server for archiving."

Section 7.5.2, second paragraph, third sentence (pages 7-25 to 7-26)

Revise to read: "Each control rod drive mechanism consists of a 0.02-HP, 115-volt, one-amp, single-phase, 60-cycle motor connected to a ball-bearing lead screw assembly through a reduction gear box and adapter."

Section 7.5.2, second paragraph, sixth sentence (page 7-26)

Delete Section 7.5.6 (pages 7-35 to 7-36)

Revise, in its entirety, to read:

"Control rod position indication is provided by a system of microcomputer controlled instruments located in the reactor control room. The Rod Position Indication (RPI) system is designed to provide the following:

• Continuous precision rod position indication; and

• Security against tampering or inadvertent alteration by use of tiered password control.

The RPI system consists of the following major components: five encoder transducers, one mounted on each control rod drive mechanism; a chassis with installed hardware; and a remote Operator Display Assembly (ODA).

Signals from the encoders are converted to relative control rod positions by the Programmable Logic Controller (PLC) in the RPI chassis. The chassis, mounted in the instrument panel, contains an AC to DC power supply, circuit breaker, a network switch for module communication, a Human Machine Interface (HMI), and a PLC consisting of the following components: a fieldbus logic controller, five Synchronous Serial Interface (SSI) encoder input modules, one digital input module, one digital output module, and an end module. All inputs for the system are through either the HMI on the front panel of the chassis, or the HMI serving as the ODA.

The ODA is a second HMI identical in every way to the front panel of the chassis. The ODA is connected to the chassis through a communication cable and a power cable. The power for the ODA is from the power supply in the main rack mounted chassis.

The RPI system consists of three main screens. Along the bottom of each screen are three menu navigation buttons, and they are as follows:

1. Alarms: The alarms screen shows a log of all faults and alarm situations. This log requires a user password to clear the alarm log.

2. Auto Run: The default screen is the "AUTO RUN" screen which displays the .five control rod positions. It will also display calculated control rod travel speed when enabled.

3. Setup: The setup. screen requires a user login to access. A User login will allow the zero position of the control rods to be set. The remainder of the settings require an Admin login.

The system defaults to the "Auto Run" screen after a timeout of five minutes in the setup menu."

III-3

Section 7.6.2.1, second paragraph, first sentence (page 7-37)

Revise to read: "Reactor inlet and outlet temperatures are recorded with a paperless recorder mounted on the instrument panel which transfers the data to a server for archiving."

Section 7.6.2.1, second paragraph, third sentence (page 7-37)

Revise to read: "The output signal from the RID Transmitter for TE 901A is directed to an Adder-Subtractor Module (ASM) and the recorder."

Section 7 .6.2.2, second paragraph, first sentence (page 7-38)

Revise to read: "Pool coolant heat exchanger inlet and outlet temperatures are recorded with a paperless recorder mounted on the instrument panel which transfers the data to a server for archiving."

Section 7.6.2.2, second paragraph, third sentence (page 7-38)

Revise to read: "The output signals from the RTD Transmitters for 1E 901D and 1E 901C are then directed to an Adder-Subtractor Module (ASM) and the recorder."

Figure 7.7 (pages 7-39/40)

Update with Print No. 41, Sheet 2 of 4, "lOMW Process Instrumentation Control & Interlock (Temperature Inst.),"

Rev. 28 dated 01/10/19 Figure 7.8 (pages 7-41/42)

Update with Print No. 41, Sheet 3 of 4, "Process Instrumentation Control & Interlock," Rev. 37 dated 01/10/19 Figure 7.9 (pages 7-43/44)

Update with Print No. 41, Sheet 4 of 4, "lOMW Process Instrumentation Control & Interlock," Rev. 5 dated 01/10/19 Section 7.6.4.1, second paragraph, first sentence (page 7-46)

Revise to read: "Primary coolant system flow is recorded with a paperless recorder mounted on the instrument panel which transfers the data to a server for archiving."

Section 7.6.4.1, second paragraph, third sentence (page 7-46)

Revise to read: "The output signal (10 to 50 mA) generated by each flow transmitter is directed to a Square Root Converter which provides a linear output signal for the recorder and a Dual Alarm Unit."

Section 7.6.4.1, last paragraph, first sentence (page 7-48)

Revise to read: "Primary coolant demineralizer flow is recorded with a paperless recorder mounted on the instrument panel which transfers the data to a server for archiving."

Section 7.6.4.1, last paragraph, third sentence (page 7-48)

Revise to read: "The output signal generated by the flow transmitter is directed to a Square Root Converter which provides a linear output signal for the recorder."

ill-4

Section 7.6.4.2, second paragraph, first sentence (page 7-48)

Revise to read: "Pool coolant system flow is recorded with a paperless recorder mounted on the instrument panel which transfers the data to a server for archiving."

Section 7.6.4.2, second paragraph, third sentence (page 7-48)

Revise to read: "The output signal generated by the flow transmitter is directed to a Square Root Converter which provides a linear output signal for the recorder."

Section 7.6.4.2, last paragraph, first sentence (page 7-49)

Revise to read: "Pool coolant demineralizer flow is recorded with a paperless recorder mounted on the instrument panel which transfers the data to a server for archiving."

Section 7.9.5. l, last paragraph, fourth sentence (page 7-67)

Revise to read: "The output from each radiation detector is displayed on a local meter in counts per minute (cpm) and on a paperless recorder mounted on the instrument panel in the reactor control room which transfers the data to a server for archiving."

III-5

.- SECTIONN PLANT AND SYSTEM MODIFICATIONS

• January 1, 2018-through December 31, 2018 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.

J MODIFICATION RECORD 13-02, ADDENDUM 1 J Secondary Coolant System Chemistry Control This Modification Record documents changes to the secondary coolant system chemistry control program. MURR made the decision to switch to a different chemical. vendor (Nalco) and adopted their chemical control, storage, and delivery systems. This included modifications to the chemical injection locations within the secondary coolant system.

The transition to Nalco included the adoption of 3D TRASAR technology. This included the replacement of two Honeywell controllers with a 3D TRASAR controller, as well as the Nalco series of chemicals and chemical delivery components. The 3D TRASAR controller monitors the water parameters and Nalco chemical product concentrations in a sample stream of the secondary c~)Olant. The controller determines the level of scaling, microbiology, and corrosion stress conditions of the secondary coolant system. It also provides control signals for chemical dosing pumps and the blow down valve, in order to maintain optimal chemistry conditions. Finally, the controller is capable of sending monitored data to the Nalco server for trending and Nalco support.

MODIFICATION RECORD 96-02, ADDENDUM 2 Installation of Power Motion Inc. Rod Position Indication System ii This addendum to Modification Record 96-02, "Rod Position Indication Change from Veeder-Root to Encoder Type,"

~'J documents the change from the General Electric rod position indication system to.a component-based system. The new system, which was collaboratively desigm;d by Power Motion Inc. and MURR, is a collection of discrete components that can be replaced or upgraded individually rather than a complete system made of largely proprietary

• components. The main drawer has a touch screen.interface on the front panel to serve as the primary display. An identical remote display is mounted in the reactor control console and has both power and signal wires provided from the main drawer. The touch screen operator terminals allow either screen (primary or remote) to operate the programmable logic controller functions and access to the setup menus.

_]

MODIFICATION RECORD 18-02

J Fabrication of a New Control Rod Drive Mechanism

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This Modification Record documents the fabrication of a new control rod drive mechanism ( CRDM). The previously installed CRDMs have been in operation for nearly 52 years with minimal preventive maintenance performed on them

J over that time period. Although they were fairly reliable, the objective of fabricating a new CRDM is to systematically remove from service each installed CRDM with the intent to completely refurbish_ them and return them back to

~] service. This also creates a readily available spare CRDM should one fail.

_:]

• N-1

MODIFICATION RECORD 18-01 Installation of Containment Differential Pressure Transmitter, Remote Indication, and Alarm This Modification Record documents the addition of a remote indication of reactor containment building differential pressure (DP) and a low level alarm inside the control room, which enhances the ability of the operators to determine II containment integrity status at all times. This facilitates a quicker re~ponse to any degradation of containment DP, up to and including shutting down the reactor if containment integrity is lost. *Two DP indicating transmitters are mounted in parallel, inside the reactor containment building to allow for isolation during calibration and testing. These are located on.the beamport floor, near the utility entry seal trench. The low pressure side of the transmitters are open to containment atmosphere. The high pressure side of the transmitters are routed to a common containment wall penetration. This penetration passes through the east wall of the containment structure into the laboratory building basement, near the utility entry seal trench. One of the transmitters provides a local indication of containment DP in the reactor containment building basement, and transmits a 4 to 20 mA signal to a remote process controUer mounted on the control room instrument panel. -The second-transmitter also provides a local indication and can be rotated into II the primary role. This provides operational flexibility should one of the transmitters fail, and to facilitate removing them from service for calibration. The process controller has its own direct current power supply from lighting panel LP-21 and provides an alarm on the auxiliary annunciator when DP conditions reach a low level condition.

MODIFICATION RECORD 99-01, ADDENDUM 1 (

Replace Process Instrumentation Recorders - 2018 This addendum to Modification Record 99-01, "Replace Process Instrumentation Recorders," documents the replacement of the primary coolant reactor inlet and outlet temperature; pool coolant heat exchanger inlet and outlet C,_

temperature; primary coolant flow through heat exchanger HX503A; pi;imary coolant flow through heat exchanger [

HX503B; pool coolant flow; primary coolant and pool coolant demineralizer flow; and secondary coolant flow, inlet temperature, and outlet temperature strip-chart, pen recorders with new paperless recorders. With the exception of the secondary coolant flow, inlet temperature, and outlet temperature recorder, all the recorders were Honeywell DPR II lOOC chart recorders. The secondary coolant flow, inlet and outlet temperature recorder was a Yokogawa model C

µRl 000 recorder. The process instrumentation recorders were in need of replacement due to their age, unavailability of spare parts, and the expense of purchasing pens and paper for the .charts. The replacement recorders are Yokogawa model DX1006N paperless recorders and are equivalent or superior in performance to the previous recorders. The new recorders display parameter indication locally, provide relay outputs *for alarms, are capable of mathematical calculations with the parameter data, and are connected to a network computer system which archives the data and allows for trending, reformatting, and analysis of the data at any time after data collection. Overall, the replacement C paperless recorders should be more reliable than the previous recorders as indicated by other research reactor facilities that have already converted to paperless recorders.

MODIFICATION RECORD 99-05, ADDENDUM 2

[~

"L CJ Replace Eberline Stack Monitor Recorder - 2018 C-._

This addendum to Modification Record 99-05, "Installation of Eberline Model PING-IA Stack Monitor," documents replacement of the strip-chart, three-pen recorder for the Eberline stack monitor. The previously installed M-TEK 2803 three-pen chart recorder was replaced by a Yokogawa paperless recorder. The previous stack monitor recorder was in need of replacement due to obsolescence, unavailability of spare parts, and the expense of purchasing pens and paper for the recorder. The replacement Yokogawa model DX2008 paperless recorder is superior in performance. It N-2

• displays parameter indications in the control room, provides additional high activity alarms to assist ~perators in determining the extent of a release, and is connected to an air-gap network computer system, which archives the data and allows for trending, reformatting, and analysis of the data at any time after data collection.

MODIFICATION RECORD 95-01, ADDENDUM 2 Replace Nuclear Instrumentation Recorders - 2018 This addendum to Modification Record 95-01, "Replacement of Nuclear Instruments," documents the removal of the strip-chart; pen recorders for the source range nuclear instrumentation (NI) channel no. 1 (SRM-1), wide range N1 channel (WRM), intermediate range N1 channel nos. 2 and 3 (IRM-2 and IRM-3), and power range N1 channel nos.

4, 5, and 6 (PRM-4, PRM-5, and PRM-6). The Yokogawa strip-chart, pen recorders used for recording the WRM;

] IRM-2, -3; and PRM-4, -5, -6 signals were replaced, by Yokogawa paperless recorders. The current Speedomax H

• J one-pen chart recorder for SRM-i was removed and that space in the instrumentation cabinet was blanked off. The SRM-1 and WRM signals are now displayed on a single Yokogawa paperless recorder. The N1 recorders were in need of replacement due to their age, unavailability of spare parts, and the expense of purchasing pens and paper for the charts. The replacement recorders are Yokogawa model DX2008 paperless recorders and are equivalent or superior in performance to the previous recorders. The new recorders display parameter indication locally, provide relay outputs for interlocks, and are connected to a network computer system which archives the data and allows for trending, reformatting, and analysis of the data at any time after data collection.

• MODIFICATION RECORD 09-03, ADDENDUM 2 Replace Lab Impex Stack Monitor Recorder - 2018 j

This addendum to Modification Record 09-03, "Lab Impex Stack Monitoring System," documents the replacement of

~ the M-TEK 2803 three-pen chart recorder for the Yokogawa paperless recorder. The previous stack monitor recorder was in need of replacement due to obsolescence, unavailability of spare parts, and the expense of purchasing pens and

=1 paper for the recorder. The replacement Yokogawa model DX2008 paperless recorder is superior in performance to the previous recorder. The new recorder displays parameter indication in the control room, provides additional high

~ activity alarms to assist operators in determining the extent of a release, and is connected to an air-gap network computer system, which archives the data and allows for trending, reformatting, and analysis of the data at any time

~ after data collection.

J J

J

'-::J

~

-=:J

• ':J J

~

• IV-3

• SECTIONV

• NEW TESTS AND EXPERIMENTS

• January 1, 2018 through December 31, 2018

"] No new tests or experiments were initiated or approved during this period under a Reactor Utilization Request (RUR);

however, the following amendments were made to existing RURs in order to either improve the production of the

• 1 desired isotopes or to improve the efficiency of the processes:

J

] RUR 282, AS AMENDED

• ]

Osmium Irradiation This RUR amendment authorizes the irradiation ofup to 75.0 mg of enriched osmium ( enriched in Os-189) in the flux trap region of the reactor for research and development activities.

]

_] RUR 435, AS AMENDED J Molybdenum Oxide Irradiation This RUR amendment authorizes the use of quartz as secondary encapsulation for irradiating natural molybdenum II oxide in the graphite reflector region of the reactor in support of product development activities.

RUR 440, AS AMENDED Irradiation of Tellurium Oxide This RUR amendment authorizes the use of single aluminum encapsulation for the irradiation of tellurium dioxide in the graphite reflector region of the reactor in support of product development activities.

In addition, MURR continued to participate in molybdenum-99 research and development, and production activities by performing test and production 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 I

I SECTION VI I SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES I January 1, 2018 through December 31, 2018 I

I INSPECTIONS I The U.S. Nuclear Regulatory Commission (NRC) conducted one routine inspection reviewing Special Nuclear Material (SNM) activities. All records and activities were found to be in compliance with NRC mies and regulations.

I No violations were noted.

I I MISCELLANEOUS SNM SHIPMENTS I Four unirradiated low-enriched uranium (LEU) targets were shipped to the MARIA Reactor in Poland on behalf of Northwest Medical Isotopes, LLC, for molybdenum-99 research.

I I REACTOR CHARACTERISTICS MEASUREMENTS I Sixty-three refueling evolutions were completed in 2018_. Reactor core excess reactivity verifications were performed for each refueling. The largest measured excess reactivity was 3.88%. MURR Technical Specification (TS) 3.1.a I requires reactor core excess reactivity above reference core condition to be less than 9.8%.

I I REACTIVITY MEASUREMENTS I Differential blade-worth measurements of seven shim control blades were performed following either a planned replacement of a control blade or characterization of the burn-in effect of a new control blade.

I Six reactivity measurements were performed to determine the reactivity worth of all samples, including the sample I holder, loaded in the flux trap region.

One reactivity measurement was performed to determine the reactivity worth of a newly fabricated flux trap region sample holder.

.,I Three reactivity measurements were performed to determine the reactivity worth of the small flux trap tube sample holder loaded with the maximum number of samples in order to confirm that their reactivity worth is less than the TS I movable experiment limit.

• Two reactivity measurements were performed to investigate the reactivity worth impact of a target can design change as well as target mass changes of iridium samples irradiated in the flux trap region.

l VI-1

SECTION VII RADIOACTIVE EFFLUENT

)

January 1, 2018 through December 31, 2018 J TABLE 1 SANITARY SEWER EFFLUENT Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci I  ;;~i1!{1H::~licXfcl~."-:f.ft J; *17:}*(JIY~ifi{lty'.(fu:q~)f~[tf:J; H-3 j 2.52E+02 J S-35

---

*-----J----*--------

l.33E+Ol Co-60 9.46E+OO Zn-65 4.56E+OO Cr-51 2.59E+OO Ca-45 1.60E+OO P-32 1.54E+OO Tc-99m 7.25E-01

---

1-------------------------

Fe-59 6.78E-01 Sb-124 5.57E-01 1---------------+-------------

Mo-99 4.37E-01 Cd-109 2.17E-01 Sc-46 2.14E-01 Mn-54 2.lOE-01 J ..........-...........Na-24 1.07E-01 _

-, I Pd-109 1.02E-01

__J Co-58 4.12E-02 1-124 3.64E-02 Lu-177 2.99E-02 Sb-122 l.60E-02 1-131 l.15E-02 TotalH-3 2.52E+02 Total Other 3.64E+Ol I

Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal by Release into Sanitary Sewerage."

VII-1

I I

TABLE2 I STACK EFFLUENT I

Ordered by% Technical Specification Limit I

I Ar-4!:___ fl-___2_.2_8E_-_06________!:_:~~0_9_ _ _ _ _ _ _3_50____ _ 65.1667 I I-131 l.93E-12 9.00E+02 1 0.9628 I

H-3 l.34E-08 6.29E+06 350 0.0384 Xe-13lm 7.67E-08

-**--****-****--**----+---------------

3.58E+07 350 0.0110 I

Co-60 8.26E-16 3.86E-01 1 0.0017 t***********************-*****-*******************-**I****-*************-**********--**********--*****--**--***---**-**----*****-*****-***-------*----<------*-**-**--***-****--**-*-**--***---**** **********-***--****-*********---**-*-**********-*-*-**-****-********--

I Os-191 , l.29E-14 6.0lE+OO 1 0.0006

-- . -*-+---*-**------*----+-----*--*--*--- **---**-*----*-----*- ****--*-*- -*-----**---**-****--**--***-** I C-14* I 2.06E-11 9.36E+03 1 0.0001 I-133 2.20E-13 l.03E+02 350 0.0001 I

I I

I I

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I I

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I I

• C-14 activity is calculated based on the ratio of argon to nitrogen in the air and the (n, p) reaction cross sections for I the activation ofN-14 to C-14.

I Isotopes observed at< 0.0001 % Technical Specification (TS) limit are not listed.

I Stack Flow Rate= -30,000 cfm I Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, Renewed Facility I Operating License No. R-103 TS.

VII-2

• I I

I

~

• SECTION VIII I ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS I January 1, 2018 through December 31, 2018 I

I 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 I samples are taken at six locations each period. Analytical results are shown in Tables 1 and 2.

I Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2018. All doses fluctuate around background except monitor numbers 8, 9, and 45. These monitors are located at or hear loading do.ck I areas where packages containing radioactive material are loaded or traverse prior to being placed on transport vehicles.

I The doses recorded by these monitors are considered to be the result of exposure to packages in transit. The environmental monitoring program confirms that minimal environmental impact exists from the operation of the I MURR facility.

The number of radiation and contamination surveys performed each month is provided in Table 4.

I TABLE 1

SUMMARY

OF ENVIRONMENTAL SET 93 - SPRING 2018 I

Detection Limits*

N I

Vegetation 1.45 pCi/g 8.86 pCi/g 1.65 pCi/g 6.25 pCi/mL N Soil 0.00 pCi/g 4.66 pCi/g 0.66 pCi/g NIA Water 0.62 pCi/L 4.90 pCi/L 190.5 pCi/L 7.98 pCi/mL I Subsurface Soil 0.72 pCi/g 5.53 pCi/g 0.61 pCi/g NIA

~

Activity Levels - Vegetation 1V93 <MDA 33.11 <MDA <MDA

• --**-*-.....................----*---*--+----..- -..- -....--t----------------*-*+*-*--..................----*--*-"""'"' **-----*****-----------

2V93 <MDA 20.52 <MDA <MDA 3V93 <MDA 12.96 <MDA <MDA 4V93 <MDA 30.95 2.19 <MDA 5V93 <MDA 40.67 <MDA <MDA 6V93 <MDA 31.67 <MDA <MDA 7V93 <MDA 29.15 <MDA <MDA 10V93 <MDA .30.95 <MDA <MDA Vill-1

I I

TABLE 1 (Cont'd) I

SUMMARY

OF ENVIRONMENTAL SET 93 - SPRING 2018 I

Activity Levels - Soil I

I 3.36 M 2S93 0.93 16.74 2.60 3S93 1.25 16.56 2.66

• • • • -**--**-******-*---**-*********-*--**---- ****-*****-***-**********--****+-**---****************-***-*****-*--**-**--*********---*-*-**-**--+--*-----

4S93 0.62 11.40 2.43 5S93 0.78 22.50 3.50

---** -***-**----*****--*-*-***********-----*--+-------------4-----

6S93 0.78 7.74 1.79 7S93 1.25 - 19.80 3.44 10S93 1.09 21.96 3.92 I

Activity Levels.- Water 4W93 <MDA <MDA <MDA <MDA 6W93 0.66 <MDA <MDA <MDA 10W93 <MDA 8.86 <MDA <MDA Activity Levels - Subsurface Soil I

S93 <MDA 4.54 SW93 0.93 19.86 4.58 l-----------+-----------1---*--*------l-----------l W93 <MDA 19.86 4.00 N93 NE93 0.77 0.77 18.80 17.20 3.60 4.20 I

I I

• Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights. HPGe spectral I analyses were performed on any sample with a gamma activity greater than minimum detectable activity (MDA).

VIII-2 I I

l I

] TABLE2

SUMMARY

OF ENVIRONMENTAL SET 94 - FALL 2018 Detection Limits*

J Vegetatio~---- _____o_.o~_p_C_il_g*-*- _____ ?.90 y_S:~g_______1_____ !_:_?~_.RS:~L-***-*- --~-~~-1-1-~!!~---

Soil 0.72 pCi/g

---

+-------f-------+-------1 3.55 pCi/g I 0.60 pCi/g NIA Water . 0.62 pCi/L 4.47 pCi/L I 186.0 pCiJ!:,_ 5.64 pCi/ml I Subsurface Soil 0.72 pCi/g 3.95 pCi/g 0.53 pCi/g NIA Activity Levels - Vegetation i

' 1V94 0.31 2V94 0.31 37.79 <MDA <MDA 3V94 <MDA 80.26 <MDA <MDA 4V94 <MDA 27.35 <MDA <MDA 5V94 0.31 62.27 <MDA <MDA I 6V94 <MDA 27.71 <MDA <MDA 7V94 <MDA 44.99 <MDA <MDA J 1 - - - - - - - - - --*---*-***---*-***-****---*--

10V94 0.62 29.51 1----- <MDA <MDA Activity Levels - Soil I

1S94 1.25 19.98 2S94 0.78 19.62 2.95 3S94 <MDA 25.02 2.24 4S94 0.93 21.06 2.06 5S94 0.93 21.06 2.81 I 6S94 0.78 16.74 2.36 7S94 1.09 21.96 2.00 I 10S94 1.25 3.43 I

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I I Vill-3 I

~

I TABLE 2 (Cont'd) I

SUMMARY

OF ENVIRONMENTAL SET 94 - FALL 2018 I

Activity Levels - Water I

I 4W94 0.66 37.26 <MDA <MDA I 6W94 2.00 37.79 <MDA <MDA 10W94 <MDA 21.11 <MDA <MDA I I

Activity Levels - Subsurface Soil

• I I

E94 0.77 17.73 4.11 I S94 1.08 19.33 4.09

• -*-*---------------* - - * - - - - - - - - - l - - - - - - - - - + - - - - - - - - -

SW94 <MDA 21.10 4.52 I

- ------..-----*-**----------**--***--**-*** ***-----**------***---**-----**** *****-***-*- **-****--*-*-**-****-----------1 W94 1.08 19.51 5.11 N94 1.54 23.76 4.57 I

NE94 <MDA 22.88 4.07 I I

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• Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights. HPGe spectral analyses were performed on any sample with a gamma activity greater than MDA.

I VID-4

I I TABLE3 R

ENVIRONMENTAL TLD

SUMMARY

r~:~~~l:f~:i:~~;, f~,t!~~I ;~~e~~~t:~'1! ~:~:~~rJ-:~{;e~!~!t~:i'~~~~~t~; ~{tJZ~!!;~ 2 I o*

1*

Control Schnieders NIA NIA I 34

-2 I 26

-1 23 3

27 2

I 110 2

I- - ----------------------- ------------------------ ---------------1'--------------l---------------- --------------- ------------------- ----------------

I 1 2* Schnieders NIA -2 [ -1 0 2 -1 3 W 34 I -9 j -4 -5 -3 -21

,--:--t----:;---i-- --Ns I = ~-- -~~-- ~~---!-- ~~ I }---~- ~!~

11

_ I -- 6 :1

~-- I I ~! ~- -~ --~------+---J. 6 I 7 I 8 I -SW I 30 I O I 8 I 9 I 16 I 33 9 ssE 24 1 19 1 18 1 11 r n-i 15 I

!~ I ~ f  !:~ i ~~ I ~~ I ~ t ~ I -~ 2 I

I - H--:! SSW s

+-~!~-t-:~+t~~~~-

• t-***-*****--***-*..*--**-*--**-*---

I

---

+-------------

73 13 -4 I

_---t---3

-4

--r-o -r--

I o I

-:-1 -~-

o I

-c----r-----14 -8 16 SE 104 -10 I 17 18 E

NE 299 456

-5

-8 L-~ -4

-2

-2 0

-1

-10

-15 19 NE 674 -13 -8 -8 -7 -36 I 20 NE 895 -6 -7 -7 -6 -26

• ~~--i ss~ --j-- ~~~ -4

-11

-2

-7

-1

-5 1

-4

-6

-27 I 23 I ~: I I NW s:; -~- :~

I 96 -6

~~ t-- ~}--

0 1

-2

-1 I

[____ 2 3 -2

-8

. - - -..--------t--*****-**--*------

I 0 -12 26 I SW I 323  ! -9 I -4 I -1 I -1 I 27 SW 198 , -9 -7 I -3 . -6 28 I WNW I 255 i O I O 2 II 1 I 29 NW 262 1- -6 -4 -3 * -2 I ~--!~ -~- ~--l-----!~:-----1---~; -+- -----~~---------!------ -i- :

---

1-------

-4

-1 E-J*=~; _::~-m =t~-*- _:~=t----::-~- ~--==i 2

I -4

-7 I

I H

37 I s::

NE

--+-I :~! 736 1

i

-- -~

-10

-~

I

-~t----~ --------t----

-8 I +---~-'

9

- , -12

__ __:29 38 WNW 516 I -3 2 1 1 I 1 I  !~ ----1--------~ ------j------- ~~~ ---+-------:o -j- - ~:~ -~ I ~~

F 1

-lO

-22 I 41 NE 158 I -7 -5 -2 -3 I -11 42 43 In Building Spare

~A NIA 1 -5

-4 1

}-- r ~ 1 2 8 r 1 0

I I

~  !

44 SW 100 -5 -10

~

45 SE 1---------------1--

94 I 3 I -: I 19 46 SE 105 I 1 -2 I o I o -1 I

• The control monitors are approximately 50 miles SE of MURR, and gross values are shown.

I VIII-5 I

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TABLE4 I NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS I

I I

January 102 102 64 18 7 February 91 91 58 7 7 I

March 90 90 63 8 5 I April 78 78 58 16 9 I

May 104 104 66 19 12 81 81 62 7 8 I

June~ --- -

July 97 97 65 16 7 I August 96 96 66 14 7 I September 79 79 56 12 7

• • • -*******--*----- ------***--**-*--****---**-*** I October 104 104 69 13 5 November 84 84 57 14 7 I December 80 80 49 11 4 I TOTAL 1,086 1,086 733 155 85 I

• In addition, general building contamination surveys are conducted each normal working day.

I

• • Air samples include stack Ar-41, containment Ar-41, special I-131 monitoring, and hot cell entries.

I I

Miscellaneous Note During calendar year 2018, MURR shipped 180 cubic feet oflow-level radioactive waste containing 12,900 mCi of I activity.

I I

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• I Vill-6

3111111*

- - -- .. al'

- -- L___j l

' ~ LJ LJ :_ .. J SECTION IX

'. _* \_J ,.__ ! l __f \_ __J.

L-3 ' =**===*

SUMMARY

OF RADIATION EXPOSURE TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS January 1, 2018 through December 31, 2018 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 64 0 0 0 237 203 1 13 1 50 1,759 18 47 0 0 89 147 0 29 2,658 February 75 0 0 0 206 170 0 5 0 16 1,685 13 43 0 1 90 154 1 24 2,483 March 53 0 0 2 161 239 8 0 2 33 2,015 23 31 7 27 84 182 14 8 2,889 April 58 0 0 19 160 156 0 3 18 24 2,387 22 66 0 19 107 312 2 168 3,521 May 51 0 0 0 196 185 0 3 28 7 1,861 10 37 0 1 121 242 2 5 2,749 June 46 0 0 8 233 153 0 0 16 80 2,005 9 52 0 3 137 279 10 46 3,077 July 73 7 3 24 178 342 0 5 38 16 2,133 30 60 14 2 143 366 3 15 3,452 August 101 10 2 16 263 263 0 29 32 28 2,098 6 70 7 11 91 254 15 3 3,299 September 127 0 4 8 175 214 0 0 10 99 1,584 23 84 7 9 48 249 8 0 2,649 October 139 0 1 231 195 165 0 1 0 19 1,671 31 74 0 0 81 227 2 0 2,837

>l November 68 0 0 57 194 203 0 1 4 51 3,081 41 80 4 6 86 200 0 0 4,076 I

December 64 0 0 70 206 115 0 I 3 64 1,916 16 70 0 1 55 143 0 3 2,727 Total for Year 919 17 10 435 2,404 2,408 9 61 152 487 24,195 242 714 39 80 1,132 2,755 57 301 36,417 Monthly Average 77 1 1 36 200 201 1 5 13 41 2,016 20 60 3 7 94 230 5 25 3,035 HighestWB 239 7 5 134 973 683 4 12 36 82 1,340 103 158 9 30

• 285 1,564 29 20 (annual)

High Extremity 887 97 NM 622 2,649 1,034 25 747 36 421 2,590 488 1,465 71 714 1,259 2,421 126 25 (annual)

AC/PRD-Analytical Chemistry/Production HP-Health Physics OPS-Operations SH-Shipping BCS-Busmess & 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-HotCell 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.

Dosimetry services are provided by Mirion Technologies (except self reading dosimetry).