ML20052D011

Submittal of Annual Operating Report for the University. of Missouri-Columbia Research Reactor as Required by MURR Technical Specification 6.6.e

ML20052D011
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/19/2020
From:	Meffert B, Robertson J Univ of Missouri
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML20052D011 (40)

Text

EiJ University of Missouri Research Reactor Center 1513 Research Park Drive Columbia, MO 65211 PHONE 573-882-4211 WEB murr.missouri.edu February 19, 2020 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

REFERENCE:

Docket 50-186 University of Missouri-Columbia Research Reactor Rep.ewed Facility Operating License No. R-103

SUBJECT:

Submittal of annual operating report for the University. of Missouri-Columbia Research Reactor as required by MURR Technical Specification 6.6.e Enclosed is a copy of the 2019 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 orby calling (573) 882-5118.

ENDORSEMENT:

Sincerely, Reviewed and Approved,

~.:::r- ~~

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

UNIVERSITY OF MISSOURI-COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2019 through December 31, 2019

UNIVE RSITY OF MISSO URI-CO LUMBI A RESEA RCH REACT OR REACT OR OPERA TIONS ANNUAL REPOR T January 1, 2019 through Decemb er 31, 2019 Compiled by the Staff of MURR Submitted by:

Reactor Reviewed and approved by:

Reactor Facility Director

UNIVERSITY OF MISSOURI-COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2019 through December 31, 2019 INTRODUCTION The University of Missouri Research Reactor (MURR) is a multi-disciplinary research and education facility providing a broad range of analytical, materials science, and irradiation services to the research community and the commercial sector. Scientific programs include research in archaeometry, epidemiology, materials science, plant science, nuclear medicine, radiation effects, radioisotope studies, targeted radiotherapy, and nuclear engineering; as well as research techniques including neutron activation analysis, neutron scattering, and gamma-ray imaging. 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 2019.

Included within this report are changes to MURR Reactor Operations and Reactor 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 administration; the governing officials of the State of Missouri; the Missouri State Highway Patrol; the City of Columbia Police Department; the Missouri University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our regulators; those who have provided funding, including the Department ofEnergy (DOE), the National Nuclear Security Administration (NNSA),

the National Science Foundation (NSF), and the NRC; Argonne National Laboratory (ANL); Idaho National Laboratory (INL); Sandia National Laboratories (SNL); the researchers; the students; the Columbia Fire Department (CFD); the Campus Facilities organization; members of the National Organization of Test, Research and Training Reactors (TRTR); and many others who have made, and will continue to make, key contributions to our overall success. To these individuals and organizations, the staff of MURR wishes to extend its fondest appreciation.

Some of the major facility projects that were supported by Reactor Operations during this past calendar year included:

(1) replacement of the pneumatic actuator for anti-siphon system isolation valve V543A; (2) replacement of the pneumatic actuator for in-pool heat exchanger isolation valve V546A; (3) replacement of the drive gear assemblies for personnel airlock doors 277 and 276; (4) implementation of small flux trap sample holder enhancements; (5) replacement of the cabling and switches on the Flux-trap Irradiations Reactivity Safety Trip (FIRST) device; (6) replacement of the demineralizer tanks for the primary and pool coolant systems; (7) replacement of the diaphragms for primary coolant system heat exchangers outlet valves V540A and V540B; (8) installation of an improved control rod operate switch 1S4; (9) replacement of the drain collection system pump; (10) replacement of 2PS1 and 2PS2

power supplies; (11) refurbishment of the main air system with new compressors and dryers; (12) replacement of DPS-930 transmitter and indication; (13) replacement of 1E-901D temperature channel transmitter; and (14) replacement of the servomotor for the regulating blade drive mechanism.

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, the compatibility of LEU fuel stored in HEU fuel locations - both in- and ex-pool, and the effects of the proposed LEU core on the lifetime of the beryllium reflector.

Reactor Operations management also wishes to commend the four individuals who received their Reactor Operator certifications and one individual who received his Senior Reactor Operator certification 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 licensed staff during normal and abnormal situations.

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TABLE OF CONTENTS I. Reactor Operations Summary ............................................................................................... 1-1 through 7 II. MURR Procedures ............................................................................................................... 11-1 through 9 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 Safety Analysis Report ............................................................................ III-1 through 2 IV. Plant and System Modifications ......................................................................................... IV-1 through 4 V. New Tests and Experiments ................................................................................................ V-1 through 2 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- I through 6 Table 1- Summary of Environmental Set 95 - Spring 2019 Table 2- Summary of Environmental Set 96 - Fall 2019 Table 3 - Environmental 1LD Summary Table 4 - Number of Facility Radiation and Contamination Surveys IX. Summary of Radiation Exposure to Facility Staff, Experimenters, and Visitors ............................... IX-1 iii

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I SECTION I REACTOR OPERATIONS

SUMMARY

January 1, 2019 through December 31, 2019 The following table and discussion summarizes reactor operations during calendar year 2019.

January 665.20 277.25 89.4 100.1 February 610.09 254.27 90.8 101.7 March 680.35 283.53 9 102.4 April 629.45 262.38 87. 98.0 May 660.89 275.49 88.8 99.5 June 649.95 270.91 90.3 101.2 July 656.18 273.52 98.7 August 684.25 285.20 103.0 September 649.18 270.59 101.1 October 657.76 274.16 99.0 November 654.27 272.69 90.9 101.9 December 648.18 270.21 87.1 97.5 I

Total for the Year 7,845.75 3,270.20 I 89.57 100.35

• 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 foll power operation per week. Total time is the number of hours in the month or year listed.

JANUARY 2019 The reactor operated continuously in January with the following exceptions: three shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurement, and one unscheduled/unplanned power reduction.

On January 21, with all four shim control rods fully inserted into the reactor core, a deviation from MURR Technical Specification (TS) 3.3.a(l) occurred during performance of a reactor pre-startup checklist due to test jumpers being installed while electrical power was available to all four shim control rod drive mechanism (CRDM) electromagnets.

For approximately 10 seconds, the anti-siphon system was considered inoperable while the reactor was, by definition, operating even though all four shim control rods were fully inserted and a reactor startup had not commenced.

lnoperability of the anti-siphon system during reactor operation resulted in a deviation from TS 3.3.a(l), and Licensee Event Report No. 19-01 was submitted to the U.S. Nuclear Regulatory Commission (NRC) on January 31, 2019.

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On January 27, with the reactor operating at 10 MW in the automatic control mode, the Lead Senior Reactor Operator (LSRO) observed no inward movement of control blade 'A' while completing a routine shimming evolution. A manual reactor scram was immediately initiated by the LSRO due to the inability to manually operate the shim control blades. The LSRO completed all immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," and verified all control blades were fully inserted. Subsequent investigation 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 Reactor Facility Director, in accordance with TS 6.6.c, and the reactor was subsequently returned to 10 MW operation. Inoperability of the control blades during reactor operation resulted in a deviation from TS 3.2.a, and Licensee Event Report No. 19-02 was submitted to the NRC on February 1, 2019.

Major maintenance items for the month included: replacing the pneumatic actuator for anti-siphon system isolation valve V543A; replacing the pneumatic actuator for in-pool heat exchanger isolation valve V546A; replacing control rod operate switch 1S4; loading new de-ionizing bed 'O' and placing it on pool coolant system service; 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-R0-202, "Measurement of Reactivity Worth of Movable Samples, RTP-6."

FEBRUARY 2019 The reactor operated continuously in February 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 pool coolant demineralizer system inlet filters; refurbishing the rod run-in monitoring system; completing Modification Record 18-04, "Reactor Pressure Vessel Cover Gasket;" replacing the drive gear assembly on personnel airlock door 277; replacing the air isolation valves to the sealing gaskets on personnel airlock doors 277/276 and motorized ventilation isolation doors 504/505; 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 ). "

MARCH2019 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurement. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: replacing the pool coolant demineralizer system inlet filters; replacing the thermal column door limit switch; replacing the drive gear assembly on personnel airlock door 276; performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth ofa Shim Control Blade, RTP-ll(D);" 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-R0-202, "Measurement of Reactivity Worth of Movable Samples, RTP-6."

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APRIL2019 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and one unscheduled/unplanned power reduction.

• On April 28, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated upon discovery that shim control blade 'D' would not move in the inward direction while conducting the control blade operability TS 4.2.a surveillance. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed. Troubleshooting revealed a broken wire on the control rod 'D' drive mechanism inward relay. The wire was replaced and control rod 'D' drive mechanism was retested satisfactorily. Permission to restart the reactor was obtained from the Reactor Facility Director, in accordance with TS 6.6.c, and the reactor was subsequently returned to 10 MW operation. Inoperability of control blade 'D' during reactor operation resulted in a deviation from TS 3.2.a, and Licensee Event Report No. 19-03 was submitted to the NRC on May 10, 2019.

Major maintenance items for the month included: replacing the pool coolant demineralizer system inlet filters; loading new de-ionizing bed 'V' and placing it on pool coolant system service; replacing the reactor mechanical equipment room (Room 114) exhaust ventilation charcoal filters; replacing the 3-position control switch for cooling tower fan number 2; completing the biennial change-out of control blade 'A' offset mechanism; completing Modification Record 99-02, Addendum 1, "Small Flux Trap Sample Holder Enhancement;" and 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)."

MAY2019 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one unscheduled/unplanned power reduction. NRC inspectors conducted a routine scheduled inspection of the Radiation Protection and Shipping Programs, a non-routine security inspection, and an inspection of activities under the MURR Type B Shipping Casks Quality Assurance Program.

On May 29, while attempting to load a movable experiment into the six-tube center test hole canister with the reactor operating at 10 MW in the automatic control mode, the experiment came into contact with the Flux-trap Irradiations Reactivity Safety Trip (FIRST) device and automatically initiated a FIRST reactor scram. Investigation revealed the FIRST device limit switches were set overly responsive. The switches were adjusted and retested satisfactorily using compliance procedure CP-36, "FIRST Scrams." Permission to restart the reactor was obtained from the LSRO, and the reactor was subsequently returned.to 10 MW operation.

Major maintenance items for the month included: replacing the pool coolant demineralizer system inlet filters; loading new de-ionizing bed 'L' and placing it on primary coolant system service; loading new de-ionizing bed 'W' and placing it on pool coolant system service; completing Modification Record 08-04, Addendum 1, "Modify DI Supply to the Beamport Fill Lines;" replacing the cabling and switches on the Flux-trap Irradiations Reactivity Safety Trip (FIRST) device; and completing compliance procedure CP-26, "Containment Building Compliance Test."

JUNE2019 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance arid/or refueling and two unscheduled/unplanned power reductions.

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On June 2, with the reactor operating at 10 MW in the automatic control mode, an automatic high power reactor scram was initiated and accompanied by a 'Channel 4, 5 & 6 Hi Power Scram' annunciation. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed. The nuclear instrument power range monitor channel 6 (PRM-6) chart recorder was off scale high with no spike noted on PRM-4 or PRM-5. Further investigation revealed that the AR15 DC amplifier in the PRM-6 processing drawer was faulty. The amplifier was replaced and retested satisfactorily using compliance procedure CP-34, "Nuclear Instrumentation Power Range -

Channel 6," and nuclear instrumentation front panel trip and response checks. Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.

On June 24, with the reactor operating at 10 kW in the manual control mode, shim control blade 'B' dropped off its electromagnet during a shimming evolution. The reactor was subsequently shut down by manual scram. All immediate and subsequent actions ofreactor emergency procedure REP-2, "Reactor Scram," were completed. Control rod drive mechanism (CRDM) 744 was replaced with CRDM 317. CRDM 317 was tested satisfactorily using compliance procedure CP-10, "Rod Drop Times," and pre-startup shim blade movement checks. Permission to restart the reactor was obtained from the Reactor Manager, and the reactor subsequently attained 10 MW operation.

Major maintenance items for the month included: replacing AR15 DC amplifier in the nuclear instrument PRM-6 processing drawer; completing Modification Record 19-01, "Replacement of Primary and Pool Coolant System Demineralizer Tanks;" and completing the annual facility emergency preparedness drill.

JULY2019 The reactor operated continuously in July with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions.

On July 1, with the reactor shutdown for scheduled, routine maintenance, a deviation from TS 3.4.b occurred during performance of scheduled maintenance on two shim CRDMs and unscheduled electrical preventative maintenance on two breakers. For approximately 10 minutes, the reactor containment building ventilation system's automatically-closing doors were inoperable due to the doors' breakers being open while maintenance was being performed on the CRDMs, causing the condition of the reactor to be shutdown per TS 1.27 but not secured per TS 1.26. Inoperability of the automatically-closing doors while the reactor was not secured resulted in a deviation from TS 3.4.b, and Licensee Event Report No. 19-04 was submitted to the NRC on July 12, 2019.

On July 29, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated upon discovery that the regulating blade drive mechanism was not operating. All immediate and subsequent actions of reactor emergency procedures REP-2, "Reactor Scram," and REP-7, "Rod Position Indication System Failure,"

were completed. The drive chain for the rod position indication encoder on the regulating blade drive mechanism had disengaged from a sprocket and became bound in another sprocket. The drive chain was replaced, and its sprockets re-aligned. The "Regulating Blade Operation And Rod Run-In Function Test" portion of form FM-57, "Long Form Startup Checksheet," was completed satisfactorily as a pre-startup final test of proper operation of the regulating blade drive mechanism and its rotary limit switch assembly. Permission to restart the reactor was obtained from the Reactor Facility Director, in accordance with TS 6.6.c, and the reactor was subsequently returned to 10 MW operation. Failure of the regulating blade and the regulating blade ::S 10% withdrawn rod run-in function during reactor operation resulted in deviations from TSs 3.2.a and 3.2.f.8, and Licensee Event Report No. 19-05 was submitted to the NRC on August 7, 2019.

On July 31, with the reactor operating at.10 MW in the automatic control mode, a low primary coolant pressure reactor scram was automatically initiated. Upon investigation of the reactor mechanical equipment room (Room 114), which 1-4

contains a large portion of the cooling equipment for the reactor, primary coolant was found leaking from primary coolant system heat exchanger HX-503A outlet valve V540A. Valve V540A was isolated, and the affected section of the primary coolant system was drained to allow for removal and inspection of the bonnet, which revealed that the valve diaphragm had ruptured. The diaphragm was replaced, and the system was refilled and leak tested satisfactorily.

Permission to restart the reactor was obtained from the LSRO, and the reactor was subsequently returned to 10 MW operation following a reactor refuel.

Major maintenance items for the month included: replacing primary coolant system heat exchanger HX-503A outlet valve V540A diaphragm; replacing the pool coolant demineralizer system inlet filters; completing Modification Record 19-02, "Modification of the Laboratory Building Configuration;" replacing control rod operate switch 1S4; and 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)."

AUGUST2019 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: loading new de-ionizing bed 'S' and placing it on pool coolant system service; 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);" 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);" replacing the drain collection system pump; and completing Modification Record 19-03, "Replacement of2PS1 and 2PS2 Power Supplies."

SEPTEMBER 2019 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurement, and two scheduled shutdowns for NRC reactor operator license examinations. There were no unscheduled/unplanned power reductions this month~ An NRC license examiner administered three reactor operator licensing examinations.

Major maintenance items for the month included: replacing primary coolant system heat exchanger HX-503B outlet valve V540B diaphragm; flooding beamport 'D' with super demineralized water; filling beamport 'D' with helium; 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 completing Modification Record 19-04, "Main Air System."

OCTOBER 2019 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one unscheduled/unplanned power reduction.

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On October 15, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated to investigate abnormal temperature indications in the primary and pool coolant systems. Compliance procedures CP-8A, "Primary Coolant System RTDs 901A/B," and CP-8C, "Pool Coolant System RTDs 901C/D,"

were performed satisfactorily to recalibrate three temperature channels. Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.

Major maintenance items for the month included: completing the biennial change-out of control blade 'C' 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-1 l(D);" and completing Modification Record 19-05, "Replacement ofDPS-930 Transmitter and Indication."

NOVEMBER 2019 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one unscheduled/unplanned power reduction. An NRC inspector conducted a routine scheduled inspection of Reactor Operations and Emergency Preparedness.

On November 18, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated to investigate an abnormal pool coolant system temperature indication. The transmitter for temperature element 1E-901D channel was replaced, and compliance procedure CP-8C, "Pool Coolant System RTDs 901C/D,"

was performed satisfactorily as post-maintenance testing. Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.

Major maintenance items for the month included: replacing the transmitter for temperature element TE-90 lD channel.

DECEMBER 2019 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and three unscheduled/unplanned power reductions.

On December 10, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated upon discovery that the regulating blade drive mechanism was not operating. All immediate and subsequent actions of reactor emergency procedures REP-2, "Reactor Scram," and REP-7, "Rod Position Indication System Failure," were completed. The drive chain for the rod position indication encoder on the regulating blade drive mechanism had disengaged from a sprocket and became bound in another sprocket. The drive chain was replaced, and its sprockets re-aligned. The "Regulating Blade Operation And Rod Run-In Function Test" portion of form FM-57, "Long Form Startup Checksp.eet," was completed satisfactorily as a pre-startup final test of proper operation of the regulating blade drive mechanism and its rotary limit switch assembly. Permission to restart the reactor was obtained from the Acting Reactor Facility Director, in accordance with TS 6.6.c, and the reactor was subsequently returned to 10 MW operation. Failure of the regulating blade and the regulating blade :S 10% withdrawn rod run-in function during reactor operation resulted in deviations from TSs 3.2.a and 3.2.f.8, and Licensee Event Report No.

19-06 was submitted to the NRC on December 17, 2019.

On December 12, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated upon discovery that the regulating blade drive mechanism chain was rubbing on the drive housing. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were completed.

Material was removed from the housing to allow increased clearance for the chain, and the entire drive assembly was I-6

l rotated several degrees. Permission to restart the reactor was obtained from the LSRO, and the reactor was subsequently returned to 10 MW operation following a reactor refuel.

On December 19, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated upon discovery that the regulating blade drive mechanism was not operating. All immediate and subsequent actions of reactor emergency procedures REP-2, "Reactor Scram," and REP-7, Rod Position Indication System Failure," were completed. Troubleshooting revealed the regulating blade drive mechanism servomotor had seized. A new servomotor was installed, and the regulating blade drive mechanism was bench tested satisfactorily. The

Regulating Blade Operation And Rod Run-In Function Test" portion of form FM-57, "Long Form Startup Checksheet," was completed satisfactorily as a pre-startup final test of proper operation of the regulating blade drive mechanism and its .rotary limit switch assembly. Permission to restart the reactor was obtained from the Reactor Facility Director, in accordance with TS 6.6.c, and the reactor was subsequently returned to 10 MW operation. Failure of the regulating blade and the regulating blade :S 10% withdrawn rod run-in function during reactor operation resulted mdeviations from TSs 3.2.a and 3.2.f.8, and Licensee Event Report No. 19-07 was submitted to the NRC on December 23, 2019.

Major maintenance items for the month included: replacing the regulating blade drive mechanism servomotor; 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)."

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SECTION IT MURR PROCEDURES January 1, 2019 through December 31, 2019 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 73 revisions issued to the Reactor Operations procedures, forms, operator aids, policies, and charters. One new operator aid and one new procedure were issued. The majority of these revisions were strictly format or editorial in nature, such as cover page changes. The following is a list of the new and revised procedures, forms, operator aids, policies, and charters:

AP-R0-115 I ModificationRecords 13 05/02/19 MinorEditorial AP-RR-001 I Corrective Action Program 14 08/15/19 Minor Editorial AP=RR-003-****--1-*1ocFR**so:59E~;i~;ti~;:;*-* ***-* --*13 05/30/19 Minor Editorial AP-RR-005 \ Security of"For Official Use Only" Information 13 10/17/19 Minor Editorial I Fingerprint-Based Criminal History Records AP-RR-008 j Checks Program for Granting Unescorted Access 4 11/12/19 Minor Editorial Ai>=ii=oii--**--+;:~i~~c:~~t:s:~~~::ds Information -- _ ... _r-2r******************************-***************+************

10/04/19 Minor Editorial AP-RR- Access Authorization Program for Irradiated .

033 3 10/28/19 Minor Editorial 1*

Reactor Fuel in Transit EX-R0-105 I Reactor Irradiation Experiments 25 10/17/19 Minor Editorial EX-R0-110*1 Pneumatic T~b~-sy;t;~----*-----*****-----*******-* -

2 06/26/19 Minor Editorial EX-R0-120 I Beamport 'A' Operation 16 10/22/19 Minor Editorial 10/22/19 Minor Editorial 10/22/19 Minor Editorial EX-R0-123 I Beamport 'D' Op~ration 16 10/22/19 Minor Editorial EX-R0-124 jBeamport'E'Operation_______________________ 17 10/22/19 Minor Editorial EX-R0-125 I Beamport 'F' Operation 18 10/22/19 Minor Editorial FB-SH-110

! Type B Shipment of Spent Fuel Using the BEA 8 02/11/19 Minor Editorial

\ Research Reactor Packag_e_ _ _ _ _ _ _ _-+----+------+---

FM-02 1 MURRAccessRequestForm 28 10/17/19 , Minor Editorial II-1

Num~er .?:' . ! ~aID.e\~  ? j ****** \  ;. ' '}: *:'<,:, ;,> fRe~T'! Rev Date .:Notes :;: C' \

FM-03 i Sponsor List 29 05/01/19 Minor Editorial FM-03 J Sponsor List 30 07/24/19 Minor Editorial FM~04- -- -******--1-vi~it~;/Aft~;=ii~~~.A~~~~~R;q~~;tF~~--,--- ---- 17 - 05/01/19 Minor Editorial FM-11 Reactor Shutdown Checksheet 8 02/05/19 Minor Editorial FM-15 I 10 CFR 50.59 Qualified Reviewers List 24 0 6 / 2 ~ o r Editorial FM~i9 - I Unscheduled/Unplanned Power Reduction Report 8 --- 05/02/19--r:Mhlor Editorial -

FM-43 Nuclear and Process Data Sheet 02/05/19 Minor Editorial FM-56 Reactor Routine Patrol 03/08/19 Minor Editorial FM-56 Reactor Routine Patrol 10/22/19 Minor Editorial FM-57 Long Form Startup Checksheet 31 02/05/19 Minor Editorial FM-57

_........ .. I Long Form Startup Checksheet

. . . . . . .,,. *-*!--,*-***. ***----*-..,----***-,. . . . . . . ._. . . . . _. ___. . .___. . .__. . .. 32 10/22/19 Minor Editorial FM-58 j Short Form Startup Checksheet 16 10/22/19 Minor Editorial FM- j MURR Irradiations Encapsulation Evaluation 127 5 09/11/19 Minor Editorial 1 Worksheet FM-136 J MURR Aluminum Sample Welding Qualification I 1 01/09/19 Cover Page

-- I Record

- -

• 1 MURRAluminmn Sample Welding Qualification ,. . . . . . . . . . . . . . . ,. . . . . .. . .. . . . . . . . * -***. .. . . . . . ,. . . Min .. . .d.. . ....t. .o. . .n. * .* a-.l*. . . . . . . . ._.,

. . . . . . . . . .o.....r. . .E FM- l3 6  ! Record 2 0 7 1 2 4 1 1 9 1 FM-140 \ MURR Access Inactivation Form 6 02/11/19 Minor Editorial i--F-M--1-4-3-.. . .-.. . .-.. . .-.. . .-.. . . **1 ......1/M. Graph _ .... .......... . . . . . . . . . _ __ . . . . . . . . . . . . . . . . . . __ ~ 10/04/19 Minor Editorial FM-152 l Fuel Ele111ent Inspection __ 5 11/12/19 ~Ptlitnri<>l FM-200 I Authorization to Conduct Background 3 02/28/19 i Minor Editorial I Investigation for Unescorted Access to MURR FM- 200 Authorization to Conduct Background 4 11* 0- 1*0- 41..JL~-, ! I'\/l'm* .. or Editorial

..... __ ......................... Investigation forUnescorted Accessto MURR ___J ____ ***-- ~~, ___~___/. *-*-"*--*--**. .*. ---**-------..*---*

IRR-PS0-100 Scheduling Flux Trap Tubes 10 /19 Minor Editorial IRR-PS0-110 Target Encapsulation /0 al LCC-001 Reactor Advisory Committee Charter 19 1 Minor Editorial LCC-002 RP.llr.tor Safety Subcommittee Charter 02/28/19 Minor Editorial LCC-003 Isotope Use Subcommittee Charter . 2 03/22/19 Minor Editorial Reactor Safety Procedure Review Subcommittee LCC-004 2 02/28/19 Minor Editorial

• • ---...................................... ................-*-****..,.....Charter ,. ,. , ,

LCC-00 Isotope Use Procedure Review Subcommittee 2 02/28/19 Minor Editorial 5

Charter LCC-006 Reactor Action Subcommittee Charter 1 02/28/19 Minor Editorial 61:is :e:'::'v~~~vc::::::.;: Seals * - -- ~ ~ : : :;1~~:o, Aid

~;:;~~********-***I OP-R0-212

~;i~!:-i;~ ~-** * --- *

\ Reactor Startup - Recovery from Temporary

• • r-~--~!;~:~:::::--

16 01/09/19 I Minor Editorial Power Reduction OP-R0-220 Reactor Shutdown or Power Reduction 12 01/09/19 Minor Editorial OP-R0-220 Reactor Shutdown or Power Reduction n - ~~, ~/

Minor Editorial OP-R0-250 I In-Pool Fuel Handling 21 fl.r /"IC./1 0 Minor Editorial OP-R0-250 In-Pool Fuel Handling 22 10/17/19 i Minor Editorial OP-R0-310 Nuclear Instrumentation - Signal Processor# 1 14 01/09/19 Minor Editorial OP-R0-311 Nuclear Instrumentation - Signal Processor #2 15 01/09/19 Minor Editorial OP-R0-330 Nuclear Instrumentation - Wide Range Monitor 13 08/08/19 Minor Editorial II-2

OP-R0-340 I Nuclear Instrumentation Adjustment 13 01/09/19 Minor Editorial OP-R0-410 __ ~ Primary Coolant System ________ _ _ _17 10/04/19 Minor Editorial OP-R0-480 Secondary Coolant System 24 05/02/19 Minor Editorial OP-R0-530 j Demineralized Water Supply System 20 08/08/19 OP-R0-741 I Waste Tank System Operation

• • • • • • • • • • • • • • • • • • • --*-*****-****-**r*-*************-**-*--**-*-*****-*******--*************-*******-***--******-*-************************** * * * * - - - -

• 25 POL-20 l Special Nuclear Materials Manual 5

• or Editorial RM-R0-400 Waste Tank System Filter Replacement RP-R0-100 Fuel Movement Measurement of Differential Worth of a S RP-R0-200

• or Editorial Blade, RTP-11 D Receipt, Inspection and Accounting of RP-R0-300 7 06/17/19 Minor Editorial Unirradiated Fuel SM-R0-011 I BerylliumReflector_Replacement_____ _ _ _ 7-+-***----+*-- 09/10/19 Minor Editorial SM-RO-llO l Venting Primary, Pool, and Secondary Coolant 0 10/31/19 New Procedure I S stem Transmitters SM-R0-200 Manual Operation of Airlock Doors 276 and 277 7 06/20/19 Minor Editorial SM-R0- Replacement of Flux Trap Irradiations Reactivity 500 3 10/28/19 Minor Editorial

• • • • • • • • -**********---****-*********-**---*!-s. __afi_._e_ty_., TripSupportRig ____ *............ ... ... ......... --****************+************************************-****--**-+*******

SM-R0-660 Replacement of Inner and Outer Pressure Vessels 7 01/28/19 Minor Editorial 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 15 revisions issued to the Emergency Plan implementing procedures, forms, and operator aids. All 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:

EP-R0-002 I Emergency Responsibilities 7  ! 07/12/19 j Minor Editorial EP-R0-004 i Fire 8 I 07/12/1 Minor Editorial EP-R0-008 I Threat To Security , 5 I 10/02/19 I Minor Editorial EP-R0-013 I Facility Evacuation I 11 ! 07/12/19 I Minor Editorial 1---*-*****************-**---***-

EP-R0-015  ! Emergency Notifications i 19 I 07/12/19 J Minor Editorial EP-R0-017 I Emergency Air Sampling 10 I 07/12/19 Cover Page FM-104 I Emergency Call List 38 I 07/12/19 Minor Editorial OA-20 1 Emergency Equipment REP-R0-100 I Reactor Emergency Procedures Il-3

C. CHANGES TO RADIOLOGICAL CONTROL, BYPRODUCT MATERIAL SHIPPING, AND PREPARATION OF BYPRODUCT MATERIAL FOR SHIPPING PROCEDURES As required by the MURR 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 161 revisions issued to the radiological control, byproduct materials shipping, and preparation for shipping byproduct material procedures, forms, operator aids, policies, and plans. Two new forms and five new procedures were issued, while one form was obsoleted. The majority of these revisions were strictly format or editorial in nature, such as cover page changes. The following is a list of the new, revised, and obsoleted procedures, forms, operator aids, policies, and plans:

ACG-NAA- 218 i Cleaning Options for High Purity Materials 9 I

05/01/19 I Cover Page i Processin I

-NAA- I High Purity Materials Analysis Flux Monitor ACG 221 j Measurement 11 05/01/19 I Cover Page ACG-NAA- 222 ! Neutralization and Disposal of Waste Acids From ' 5 05129119 1. Cover Page

,__ _ _ _ _ ___,_i_Hi_"gh Puri!).:: Materials Processing_______-+------cc-------------* 1 AP-HP-115 I Iodine 131 Bioassay I 5 ! 08/15/19 I Minor Editorial AP~HP:117  ! MURR Initial Radiation worker Training Program ! i6 < -*io/04/19 Minor Editorial i 1

-~:~~_!_!_~--- _ ' High Radiation Area Access_____

• al AP-HP-122 i Material License Pro* ects Quarterly Review AP-HP-123 l Visitor Dosimetry - Reception Desk AP-HP-123 ' Visitor Dosimetry - Reception_.D . . .-e. __s. k*--*-*******-*****-**-*****-**********-*******-******-*-****

AP-HP-124 Ordering and Assigning Dosimetry AP-HP-129 Hot Cell HC-01 Control AP-HP-135  ! Project Authorization Requests I CoverPage j Access Authorization Program for Category 1 i AP-RR-013 I and/or Category 2 Quantities of Radioactive 02/11/19 i Minor Editorial

! Material AP-SH-004 j Notification for Category 2 Material per Export I License PXB143.0l 2 05/29/19 I Minor Editorial

-~!1~:§_!!:2.~Q __ )Receiptinspection Of Type B Shipping Package 2. 1 _9?!~2!!2_ J MiE?.~-~_<!~!.?.!i~L ___

BPB-SH-023 I Type B Equipment Calibration 8 05/29/19 \ Cover Page 02 4

! Type B USA/0697/B(U)-96 (F-458 Series) 10 05/10/19  ! Minor Editorial 1-B_P_B_-s_H_-__ _ __-,-i_P_ac_k_aging of Type B Radioactive Material I Packaging of Type B Radioactive Material Using '

BPB-SH-028 l USA/9337/B(U)-96 (SAFKEG-LS) and 8 05/01/19 I Minor Editorial j USA/9338/B(U)-96 (SAFKEG-HS)

I Packaging of Type B Radioactive Material Using BPB-SH-028 I USA/9337/B(U)-96 (SAFKEG-LS) and 9 05/07/19 I Minor Editorial

-****-*--***-**********--** I USA/9338/B(U)-96 (_SAFKEG-HS) . -*---! --l- -*-----

Receipt Inspection of New SAFKEG LS/HS Type BPB-SH-030 i B B roduct Material Shi in Packa es 4 05/01/19 i Minor Editorial j Bubble Testing Acceptance for Croft SAFKEG-BPB-SH-031 0 06/07/19 New Procedure 1 HS Insert Model No. 3987

Packaging of Type A Radioactive Material Using BP-SH-005 3 07/24/19 Cover Page I SAFKEG-LS and SAFKEG-HS BP-SH-012 I DOT-7A Package Certification 9 05/29/19 Cover Page 11-4

Number BP-SH~Ol3 I Packaging of Type A Radioactive Material Using 12 05/01/19 I Cover Page

! USA DOT 7A 5- to 30-Gallon Resuable Drum BP-SH~014 I Packaging Type A Radioactive Material in an 9 05/01/19 Minor Editorial 1-------+

!_9ve ack i I Packaging of Type A Radioactive Material Using BP-SH-018 I USA DOT 7A NorthStar Medical Radioisotopes 8 05/29/19 J Cover Page

______ _ _ _____ \_Package . _ --*------*------*-*-*--*****- , ************---****-: *-------**-**-!-*-****--***--****--***-**-*******-*****-***-*---

! Packaging of Type A Radioactive Material Using  !

BP-SH-018 i USA DOT 7A NorthStar Medical Radioisotopes 1

9 i Minor Editorial

______ !. . Package_*---*---*--*--**-*---* *- +----

BP-SH-052 j Radioactive Material Shipment Package 1 19 I Documentation and Labeling 1 1

FM-26 / MURR Radiation Worker Training Quiz 16 e FM-27 \ In-House Radioactive Shipping Request Form 1 CoverPage FM-29 i Dosimetry Request Packet I CoverPage FM-54 / Report of Personnel Contamination i 11 .___!~C_over Page ___ _

1 Control Checksheet for Packaging of Type A FM-69 I Radioactive Material Using USA DOT 7A 5- to 15 05/01/19 I Cover Page

. . . . . . . . . . . . . . I 30-Gallon Res!:1~~1.~_:Q~_ ___ --*--*-* i FM-91 i Declaration of Pregnancy - - - - - 9~* 03/01/i9**-J*****c~~~~-P~g~-

FM-94  : Exclusive Use Shipment Controls 11 0510 v19 : Cove(Page ___

____ _ _ ____,_I_C_o_n_tr_o_lC-he_c_k-sh_e_e,_t_fo_r_P_a-ck_a_g_in_g_T_yp_e_A___ 1 __ _

i-FM j-05/01/19 ! Cover Page 107 J Radioactive. Material.in an Overpack _

12 FM-109 I Dy/Ho-166 Separation Data Sheet 1 - - - - - - - t - ~ - - - - . o _ _ . - - - - - - - - - - - * - - - - * : - - *4- - - - 05/01/19 : Cover Page

-;-----;----~---I FM-119 I Health & Safety Standing Order Form i 3 05/31/19 i Cover Page FM-125 I Lutetium Chloride Process Notification

• • • • • • • • • • • • • • • • • • • • frio~~~iiiaiioii0Tcompli~~~io;rior:1A - ---**--,-- --

I 6 05/Q?!~? JCover Page FM-126  ! Shipping Package 7 03/22/19 I Cover Page FM-137 i Type B Qualified Shipper List 26 i 03/07/19 I Minor Editorial __

FM-13 7 __ L!:)'JJe._!3..9~~!i~e.~§_~J?J~.e.£_J.::~!___ ---*' __?.}_ 9?!!_Q(!~.--!* Minor.Editorial **--*****-

FM-137 j Type B Qualified Shipper List I 28 *1 06/20/19 i Minor Editorial FM-137 I Type B Qualified Shipper List I 29 I 12/06/19 Minor Editorial

-F~~~;;-------rL{itcti~~Chlorid~ R~Kiiation_P_r_o_te-cti-oii-Data-  :

8

i 05/02/19 Minor Editorial

. . . . . L. .~1.:1:(;l(;lt. g___ -****--- --- -- . . . . -***** . _. . . . . . . . . . ,. . . . . . . . . . . . . . ..

/ Control Checksheet for Packaging of Type A i FM-141 l Radioactive Material Using SAFKEG-LS and 6 07/24/19 I Cover Page I SAFKEG-HS FM-150 I Statement of Training and Experience 7 01/09/19 I Cover Page FM-150 ...............~.... statement of Training and Experience_. __ .____ j 8 05/3Q(!~ /Cover Page 1 Required Documentation for Non-MURR Owned Ii FM- 156 7 08/13/19 Cover Page i-------+' I ~TYI?e B Shipping Packag~e_s_ _ _ _ _ _ _ _-+-----1-----+' -------*

FM-159 i* Control Checksheet for Health Physics Review of I 03/07/19 , MinorEditorial i Radioactive Material Shipment Documentation - + -11 - + - - - - - 1 ~_ _ _ _ _ _ _ 1 I Control Checksheet for Health Physics Review of I* 12 10117119 i Minor Editorial

-1*-~~~:;~~~:~:~:~:i~~/;:~

I I,'.

I FM-159

~~:~~~:ion****-***** ****i ...... --+-------*--1--**-***--*-

FM-163 1 Material Using USA/9337/B(U)~96 (SAFKEG- 12 . 05/01/19 Minor Editorial i

_JLS)and.USA/9338/B(U)-96{SAFKEG-HS)_

j Authorization for Use of North Office Addition

... J-*-----!i -----*----*-'

! 1/

. Minor Editorial 1

FM-164 6 1 0510 19 I WestPassa ewa (C2001) 1 1 Il-5

Nuij;lbei. ::{,.*f.)f~jime i: , .;;; *;]ii;\ *::* *. ~:i, . .* ' . -'f f ********.* r*iR~vN . Rey:Oate,\cN9tes .*.* . }*<

• 1

~\

. Authorization for Use of North Office Addition I FM-164 I West Passageway (C2001) 6 12/09/19 Obsoleted FM-165 I Mo-99 Radiation Protection Data Sheet A 4 08/15/19 I Minor Editorial l Control Checksheet for Packaging of Type A i FM-170 J~~~==~!1::t;~~~~~:~ ~a~J~~- J - ~~~~:.~-~-J 1 Control Checksheet for Health Physics Review of

_ _ 6 1 1

Cover P:~-~----*-

FM-173 I Excepted (Limited) Quantity Radioactive Material 3 05/01/19 I Cover Page i Shipinent i Control Checksheet for Docum.entation and J I FM-179 I Labeling of Excepted (Limited) Quantity I,. 3 05/29/19 I Cover Page i Radioactive Material Shipinent i Control Checksheet for Docum.entation and FM-201 I Labeling ofNorthStar Radioactive Material 0 07/24/19 I New Form i Shipinent i Control Checksheet for Docuinentation and FM-201 Labeling ofNorthStar Radioactive Material 1 1 10/03/19 I Minor Editorial

.. __ _Ship;nent ___ __ _ _ _ _ _ __ _ __ .... i ********-******-

FM-202 Control Checksheet for Receipt Inspection of  ! 0 I 08113119 New Form

. . . . _SAFKEG_HSModelNo.3987 . TypeBinserts_ , ____ ; --*****-

GMP-BR-216 Lu-177 Chloride Process Rework 3 10/02/19 Minor Editorial i Lutetium. Chloride Batch Record for Variable GMP-BR-217 11 05/21/19 , Minor Editorial i Concentration i Lutetium. Chloride Batch Record for Variable GMP-BR-217  ! Concentration 12 10/02/19 Minor Editorial GMP-BR-218 j Teflllinal Sterilization ofLutetiUin Chloride

--*-------+---+------+-----=-----

8 i 03/27/19 Cover Page GMP-BR-218 _[ Teflllinal St~rili~ation ofLutetiUin Chlon_*d_e___~j-+-_9_1-+-l_0_/0_2_/1_9_1 Minor Editorial GMP-BR-405 ) Mo-99ProductionApparatus Asseinbly _ I . . ?.. ! 01/11/19 j Minor Editorial

, Telluriuin Dioxide Target Preparation Batch J  ! .

GMP-BR-501 , Record 6 01128119 I Minor Editorial GMP-BR-502 i Sodium. Iodide I-131 Solution Batch Record 6 04/15/19 I Minor Editorial i i GMP-MCE- 124 J ~aning, Maintenance and Operation ofHC-08 10 12/20/19 I Minor Editorial

.. - - --- **********roperation and MaintenanceforaTu~auer3870 GMP-MCE- 129 I EA-BIL Electronic Tabletop Autoclave , 6 j 01/02/19 j Minor Editorial GMP-MCE- 129 i Operation and Maintenance for a Tuttnauer 3870 7 I I 05/22/19 j Minor Editorial i EA-BIL Elec~onic Tabletop Autoclave GMP-PRC-501 , I-131 Pre- and Post-Process Checks 6 !I 10/02/19 il ~ r Edit~rial__ _

• • • • • • • • • • • • • • • • • • • • • • • • • • '<m****-****m***-****mwm.***~

06/21/19 I Minor Editorial GMP-PRC-508  ! I-131Pre-ProcessSysteinDry0ut 04/15/19 I NewProcedure GMP -QC-254 j Activity Concentration Verification ofLu-177 i Chl .d S 1 ti

3 01109119 I, Minor Ed"t 1 ona1

--********-*****-* _ ***--*****!* *- _on . .e o u . . on ___***-*--***-****-***********************-*************-************-****-'*****************-: ---*-*-************-r-**----------****

GMP-QU-011 I Dose Calibrator Linearity Check - Decay Method 8 j 10/17/19 I Minor Editorial GS-RA-Ol 4 j uL.sftine.andCOperation of the I-131 Production Facility 1 _1~g rane  :

3 ' 05101119 Cover Page I1 1

GXP-APRT-20 8 i Stability Study for llllpleinentation of 8 Ci IN 4.0 I 06/11/19 , New Procedure 0

J IllL Orders for Lu-177 I

, New and/or Retrospective Installation, Operation, j GXP-EPRT-051 I and Performance Qualification or Requalification i 5 . 11/07/19 I Minor Editorial

• • • • • • • • • • • • • • • • • • • • • • • • • • • ---**----! of the ALM0-1 Activity Meter .. _ _____ ___ I______L ______ I_**--******************-*************-*****

GXP-MCE-050 ! Operation ofl-131 Can Opener ' 4 ! 09/24/19 I Minor Editorial II-6

GXP-MCE-l3 4 ' ~~aning, Maintenance and Operation ofHC-02 5 11119119 Minor Editorial Hot Cell Preparation of Radioactive Material for HC-PS0-002 20 \ 09/20/19 Minor Editorial Shipment HC-PS0-00 3 l ~~~v~:n~x Preparation of Radioactive Material for 13 I 09120119 Minor Editorial

- - - - - - - -- -- ~ - - --------------------------------------------------------------------------------- ____J______________________________________ -----------

IC-HP-343 1 Calibration - Sodium Iodide Detector 7 I 03/07/19 Minor Editorial IC-HP-346 Calibration - Lab lmpex Smart MCA Continuous 6 I 05131119 Minor Editorial Air Monitor Calibration - Lab Impex Smart MCA Continuous IC-HP-346 7 11/12/19 Minor Editorial Air Monitor

---

r-----------------------------------------------------------------------------------------------------f-----------t------------------------;----------------------------------------1 IC-HP-349 I Cali?ration - Lab Impex Stack Monitor - 10 05102119 Cover Page

_________________ -----------------! ____ Particulate Channel __ ___________ ___ ___ ___ -------------------------*-------------------------------,---------------------------+---------------------------------------------------------------*

IC-HP-350 I Calibration - Lab Impex Stack Monitor - Iodine 7 05102119 I 1 Channel ------'------i------!--c_o_ve_r_P_a_g_e _ _ _1 1

I Calibration - Lab Impex Stack Monitor - Flow 1 1

IC-HP-352 I Calibration i 8 07115119 I Minor Editorial

~:::::: I~~h~:: : : ~A~x=~:."c~~:~, --:~ 1 Flow Calibration  ; 4

_O~IOJ!l9 10/17/19 fMJn-"'~to!!aJ.. -

I Minor Editorial IC-HP-357  ! Calibration - NOA Lab Impex Monitor - DP2001 / 3 05/02/19 I Cover Page IC-HP-367 i Calibration - I-131 Bioassay Detection System r-caiibratio~-~-ALM0--6 Radiation Monito~g

+ 4 I 25-(_2.~!~~ -! ~?Y."'.~-1.:1~"'.

IC-HP-368 2 11/12/19 I Minor Editorial

\ Instrument Calibration - ALM0-6 Radiation Monitoring 12/06/19 I Minor Editorial II IC-HP-368 3

, Instrument IC-HP-371 I Calibration - Protean ASC-950 Swipe Counter 0 I 07/15/19 I1------****-***-**-----*-****---******-

, ---------------***r**-----------*-------- NewProcedure I Importing Authority Notification for the I I 2 :, 05/01/19 II Minor Editorial OA-8 I Netherlands OA-26 I NRC 749 Manual License Verification Report for 2 07/24/19 j Minor Editorial j Catego!)'. 2 Materials I

• -O-P--HP---2--2-1--+-\-E-n~vironmental Sample -Analysis \_ 9 I 03/07/19 j Minor Editorial

--oii=-HP-222 1

' !- '"' piing - Containment Building Ar-41 10 J 05/02/19 / Cover Page -

OP-HP-222 l Air Sampling - Containment Building Ar-41 11 j 12/06/19 Cover Page OP-HP-228 ( Performing Iodine 131 Bioassay Measurements J I 7__ 08/15/19 Minor Editorial -J OP-HP-231 OP-HP-232 I Respirator Cleaning and Care 2 j. 05/02/19 Minor Editorial I Respirator Storage, Maintenan--ce_an_d_In-sp._e_c-ti-on---+---2-+!_0_7_/-24_/_1_9---+---Min-.-or_E_d_i-to_n_*a-l-----1 I

OP-HP-233 I Respirator Fit Test 2 u,, u/19 Minor Editorial OP-HP-233 / Respirator Fit Test i 3 11/12/19 Minor Editorial OP-HP-234 I Physical Exam for Respirator Program 2 05/02/19 I Minor Editorial OP-HP-234 I Physical Exam for Respirator Program 3 I 07/24/19 Minor Editorial OP:HP=235____ Annual Respirator Training *-r-- 2 /--05)02/19 i Minor Editorial

~~=~¥o------ -i~~f~!~-i:~i~;~~!:~~~~~~~~-

OP-HP-305 1

dering or Transfer of Radioactive Materials

---

+-1 2-'-6~~~~~

j 3

8 07/26/19 . Cover Page

--l~~; : !~~::~ - -

6~=~]i----

OP-HP-353 E:!!!!:~:1~:;;:il:iil~!e~~ange Waste Tank Sample -Analysis

---

 !---~1 I 10

-H~~~;~~:-r~:;

03/07/19 I Minor Editorial

!:orial -

OP-HP-355 North ?ffice Addition Waste Tank System 6 03122119 I Minor Editorial Operation II-7

Nii01bet *. :;: ,Na01e *. *. '::.*'. . .* * * ***, *:' \ *(..'ii F:Rev*l .RevDai;: I*N,Otes ,***::r .**)',**\~**

OP-HP-358 Operation - Lab Impex Smart MCA Continuous J I [ Minor Editorial I 3 , 08115119 I J

1 Air Monitor Filter Change and Source Check OP-HP-359 Bag-In Bag-Out for Changing Bank Exhaust 1 07; 2 6/19 '1 Filters Minor Editorial OP-HP-365 I Iodine 131 Processing Hot Cells Radiation \ 3 J 08115119 Minor Editorial

---**-**-***********- *i**** Monitor_(ALM0-6)_ ...................................................... ----************* _ L_........ --*****--*-**--* ,---***-*******-******-*****

OP-HP-400 1 Gemstone Shipping Barrel Analysis 1 12 1 05/01/19 ' Cover Page I 10 CFR 37 Security Plan for the University of I '

• -*r PLAN-130 2 I Ol/l 7119 Minor Editorial i Missouri Research Reactor

,l~- --Ji---o-J POL-03 ~ Radiation Protection Pr~gr-am-,-F-eb*-ru-ary_ _ 1-8 5-/0-l-/l-9-.--+ .. -~~--~~-~-:-.~-i~-~n-.~.~- . ~.--.---

. PO-L- - I MURR Radiation Protection Program, June 2019 j 19 I 10/16/19 Minor Editorial I MURR Type B Shipping QA Program, University I POL-14 l of Missouri-Columbia Research Reactor Facility, 7 07124119 ! CoverPage I

j Shipping Quality Assurance Program for Type B 1 1 - - - - - - - i - !~S=hi:.cm.i.:.rnm=*g Casks I I POL-24 I Iodine Bioassay Program 2 I 02/28/19 I Cover Page POL-25  ! MURR Respiratory Protection Program 1 4 I 06/20/19 I Minor Editorial

..........................._..............................,.*-***-***-*--*********-*****-***********************--*--**--*******--*****-*-****-******************r*****-*********,-*-***-********-*******r-*******-***********************-**********

~~~:-001. I :~e;:~~~~::c:;:!:o:: Sample--t.-  :- : :::::::: r. :::::i~orial **-

,_______!__ fo_r_P_a_ck_afil!!g .  !  ! I g PRC-RRD-W3 .. LRemote Quartz VialWashing _ 1 6 L 02/28/19JCover Page PRC-RRD-104 I Miscellaneous Radiopharmaceutical Isotopes j 6 I 05/01/19 ! Minor Editorial PRC-RRD-108 I DissolvingHo-166Nitrate

-PRC-RRD-~211*************1 Di;;~i~;gL~~7--------*----- -

4 4

t osioiii9-1 c~~~;P;g~

• • • • • • • • 1

• 11/12/19 I MinorEditorial PRC-RRD-218 J Lu-177 Distribution 1 10 10/01/19 I Cover Page

~i~=~ij i-~:::~~;i::rmationof Au.Nanoparticles .L *****~ * * *1- ~~~~~~i~ I ~~~~~ii~~~i PRC-RRD-319 j Cd-115/In-115mProcessing 2 I 07/24/19 CoverPage

• ~i~~=1i~

PRC-RRD-424 ~~gPlatinum Powder I :~:~~!~o;;::::rnPowder ----*-**--*-*****

--+

!* : *******)

5 i

~: ~ i~~i~

12/06/19 / Minor Editorial J=: ~  :~  ! ~  :  :~

QAB-SH-002 j Procurement of Type B Packages J__ 7 ___1, 03/07/19 / Cover Page QAB-SH-003 I Material Control for Type B Shipping Program 9 I 05~0 1 1

Cover / 1P9e

• QAB-SH-004 Type B Program Vendor Qualification  ! 9 I 03 e QAB-SH-005 J Type B QA Personnel Training I 6 I 08/13/19 Cover Page QAB-SH-00 8 I Training for Type B Shipment Leak Test I 4 05101119 ,I Cover Page l Performers I i Material and Document Control Program for I RCP-PS0-035 Carbon Adsorbers Used in Association with 2 09/20/19 J Minor Editorial Radioiodine (I-131) Production I RCP-PS0-040 I Preparation ofI-131 Liquid Spill Kits O . 07/24/19 . . .1.. New. Procedure RM-HP-101 J Stack Monitor Preventive Maintenance - Eberline i 7

• • • • • • • • • 1-07124119 Minor Editorial IPinglA '

RM-HP-102 I Stack Monitor Preventative Maintenance - Lab I 5  ! 07/24/19 Minor Editorial Impex

~I Transfer of Radioactive Material Within the RP-HP-105 14 12/09/19 j Minor Editorial Facility_______ .. ................ -*-******-****- _____ . . . . -****** *-******-1* ******--*..********* ..*........................... ~---*-*****-*-**-*---*-*----

I RP-HP-120 , Personnel Radioactive Contamination I 15 07/26/19 I Minor Editorial RP-HP-130 I Receipt ofUnirradiated Fuel 10 05/01/19 Cover Page II-8

2N*u*.*m*be**r***.;,. ..,.'.,:.>**'*11*i.:N*.*.**a*

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Rey ** ****** .

• Rev:Dafe\f,NoteS:.')b'. ., ,

RP-HP-135 Room 114 Entry- Self Monitored 9 I 10/17/19 Minor Editorial RP-HP-135 i Room 114 Entry- Self Monitored *****--****---*****------'.*-*-****-*-i-- 10 12/09/19 Minor Editorial

-*-**""""*l*---*-""""">>-----*

SI-PS0-009 I Operation of the Can Press 5 05/02/19 Minor Editorial SV-HP- lOO I Reactor Chemistry Isotope Counter Trending and I 10 03122119 I Minor Editorial

,____ _ _ _ __,,_I_In_v_e_st~igative Level Determination 1 SV-HP-110 I Environmental Sampling

"""'""'"""'"'""-""""'-'('""" * ' .......,,,_,,,__ _,,,.,,,,,,,,,,,,,,,,,__,,_, _ _ ,____,,,,,,,,,,,, ** -----"""""" - I i -- -

10 05/02/19 - ,,,,_,,, Cover ' Page _____ ,,, -- '" ""

Sv -HP-l l 5  ! Bmldmg Exhaust Stack Effluent - Tntium I 8 1 03101119 C p i Monitorin . ' I , over age

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SV-HP-117 I Secondary Coolant and Sump Water Analysis i 8 J 05/02/19 I Cover Page SV-HP-119 __JProperty Release - - * - - _ ,,,,,,,_____ _ ___ 13 _j_05/01/19 Jcover Page --- L

-~V-~-1=~-******* _!..

TPZ-PS0-001

~~~~~~~~~~~~~:~~~~:~~-~~~-~-**------1 I Receiving Gemstone Irradiation Shipping Drums

• 9 1 05/02/19 1 Cover Page

.. 9. . . . . 1. . ~~~02~.~ .... J_:_~~~~-=~ge TPZ-PS0-002 Irradiation of Gemstone Irradiation Containers 10 05/02/19 Minor Editorial TPZ-PS0-003 Loading Gemstone Shipping Drums 8 05/02/19 Cover Page TSP-02 Transportation Security Plan 10 02/28/19 Cover Page

-~-SH-lQQ__ I Radioactive Waste - Preparation and Storage --;--1~_1 05/01/19 ! Minor Editorial

__-_S_H_-1_1_5_--+-I_Io_d_in_e_I_-1_3_l_W_a_s_te_H_an_dl_in_,,g'-----------cL <l ' 05/01/19 I Minor Editorial 1-WM WM-SH-115 I Iodine I-131 Waste Handling I Exclusive Use Shipment ofLSA or SCO r-s I

11/12/19 I Minor Editorial I

WM-SH-300 i Radioactive Waste 18 05/01/19 CoverPage I II-9

l SECTION ill REVISIONS TO THE SAFETY ANALYSIS REPORT January 1, 2019 through December 31, 2019 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.

From 2017 through 2019, a significant amount of effort was 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.

During calendar year 2019, modifications or changes to the facility occurred that required the following revisions to the SAR, 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 1-THE FACILITY Section 1.2.2, Figure 1.2 (page 1-6)

Update with Print No. 1145, Sheet 2 of 5, "Placement of Emergency Equipment - Grade Level," Rev. 39 dated 12/17/19 CHAPTER5-REACTORCOOLANTSYSTEMS Section 5.5.2, first paragraph, first sentence (page 5-10)

Revise to read: "The water purification system consists of three stainless steel demineralizer tanks sized to hold up to 25.6 cubic feet (0.72 m3) of mixed bed resin."

CHAPTER 6 - ENGINEERED SAFETY FEATURES Section 6.2.3.1, last paragraph (page 6-7)

Delete "k. 3/8-inch cooling water discharge line (from the experimental facilities);" and re-alphabetize the remainder of the list of services and lines through the seal trench Section 6.2.3.3, Figure 6.2 (page 6-8)

Update with Print No. 1145, Sheet 2 of 5, "Placement of Emergency Equipment - Grade Level," Rev. 39 dated 12/17/19 III-1

CHAPTER 7 - INSTRUMENTATION AND CONTROL Section 7.3.1, Table 7-3 (pages 7-12 to 7-14),

Revise No. 20 to read: "+24 Vdc Regulated Power Supply Drawer (2PS1)"

Revise No. 21 to read: "-24 Vdc Regulated Power Supply Drawer (2PS2)"

Delete "95 Pressurizer Water Level Indication Meter" Section 7.6.5, seventh paragraph, first sentence (page 7-51)

Delete Section 7.6.5, seventh paragraph, third sentence (page 7-51)

Revise to read: "This signal is sent to a paperless chart recorder on the instrument panel which provides the reactor operator with a continuous indication of pressurizer liquid level."

CHAPTER 9- AUXILIARY SYSTEMS Section 9.4, Table 9-1 (page 9-11)

Add a line to read: "Room 299T HC-11" Section 9.14.2 (page 9-23)

Revise, in its entirety, to read: "The main air system utilizes two compressors, designated the North and South Main Air Compressors, which supply the majority of the compressed air needs of the reactor facility. Both compressors have a discharge capacity of around 100 c:fm. The two compressors automatically alternate roles between lead and lag unit each time the lead compressor cycles in order to equalize wear. When in the lead role, the compressor will automatically start when main air pressure reduces to a pre-established low setpoint and secure when main air pressure reaches a pre-established upper setpoint. If main air system pressure cannot be kept within this band and continues to lower, the lag compressor will start at a pre-established lower setpoint to aid the lead compressor. This condition also initiates the lag alarm circuit, which generates a local alarm and illuminates a local warning lamp. The lag compressor will receive a signal to stop at a lower setpoint than the lead as pressure rises. The control system also allows for a manual mode of control for either compressor. When in manual control, the selected compressor will cycle within a pre-established pressure band."

CHAPTER 11- RADIATION PROTECTION PROGRAM AND WASTE MANAGEMENT Section 11.1.1.3, Table 11-9, last row, fourth column (page 11-11)

Revise to read: "18-25 ft3 of mixed bed resin stored in 4 steel tanks Typically:

In Primary Service (1);

In Pool Service (1);

Depleted (2);"

ill-2

SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2019 through December 31, 2019 For each facility modification described below, MURR has on file the safety screen or evaluation, as well as the documentation ofreview, performed pursuant to 10 CFR 50.59.

MODIFICATION RECORD 18-04 Reactor Pressure Vessel Cover Gasket This modification record documents replacement of the reactor pressure vessel cover gasket with a different material.

The previous gasket material contained asbestos with a stainless steel ring surrounding it. Tue gasket material was utilized at MURR in this application for many years. However, due to significant issues related to the adverse health risks associated with asbestos, the material had become challenging to procure. Tue replacement gasket material is made of Ethylene Propylene Diene Monomer (EPDM). It has very good flexibility, superior resistance to water and steam, excellent resistance to heat, is inexpensive, and is readily available. This material was tested over a period of several weeks prior to being placed in service. Tue new material has performed as well or better than the previous asbestos material.

MODIFICATION RECORD 19-01 Replacement of Primary and Pool Coolant System Demineralizer Tanks This modification record documents changes to the primary and pool coolant demineralizer (DI) system. The scope of this work included full replacement of the DI tanks (DI-200, DI-201, and DI-202), the resin storage tank, and necessary piping to connect the new tanks to the existing system. Tue original resin tanks were carbon steel, cylindrical tanks that had an internal rubber lining for corrosion resistance. Tuey were sized to hold 12 cubic feet of mixed bed resin with each bed capable ofremoving 1,500 grains of hardness per day from water at a design flow rate of 50 gpm and a temperature not to exceed 140°F. Tue primary motive for implementing this modification was significant degradation of the existing resin tank rubber liners. Initial indications of this degradation were increased fouling of the primary and pool coolant inlet filters with abnormally dark residue and a reduction in DI system flow rate. Tank inspections confirmed that the inner rubber liner within the tanks was degraded and being introduced into the system. The tanks were replaced with a stainless steel design that do not require a liner. Tue new tanks are stainless steel pressure vessels with a design pressure of 100 psig and a nominal flow rate of 50 gpm. These tanks were designed to utilize the same or similar type of mixed bed resin that was previously.in use at MURR. However, the new tanks are a larger diameter and therefore require a larger volume of resin to maintain the same depth and ion exchange capability. Although this resulted in a larger volume ofresin, it should also result in a greater length of time between resin bed replacements. This should keep the volume of radioactive waste from the spent resin relatively constant over time. All tank internals are constructed of stainless steel with the exception of the gasket material. The piping that connects the tanks to the primary and pool coolant DI systems are constructed of aluminum or stainless steel.

IV-1

MODIFICATION RECORD 19-03 Replacement of2PS1 and 2PS2 Power Supplies This modification record documents the replacement of low voltage power supplies 2PS 1 and 2PS2. 2PS 1 supplies

+24-volt direct current (DC) power to both process instrumentation reactor safety system strings (green and yellow legs), the process instrumentation rod rod-in string (blue leg), both non-coincidence logic units (NCLUs) for the reactor safety system, both NCLUs for the rod run-in system, the wide range monitor nuclear instrument drawer, and the power range monitor channel 6 nuclear instrument drawer. 2PS2 provides volt power to the wide range monitor nuclear instrument drawer and the power range monitor channel 6 nuclear instrument drawer. Failure of either the 2PS 1 or the 2PS2 power supply will cause a reactor scram. In addition, both the 2PS 1 and 2PS2 racks house a potentiometer and ammeter for adjusting shim control blade electromagnet current. However, 2PS1 and 2PS2 do not provide power to the electromagnets. Electromagnet power is provided by separate power supplies inside the associated reactor safety system trip actuator amplifiers. 2PS 1 and 2PS2 are identical power supplies, and the analog power supply used was the General Electric Model 104B2731, which was capable of supplying up to 10 DC amperes in a range of 10-35 volts. The polarity of voltage is determined by the connection to the power supply output. MURR replaced the original power supplies due to obsolescence and potential equipment degradation. The replacement analog power supplies are the Acopian Model 24PT10 which are capable of supplying up to 10 DC amperes at 24+/-

0.5 volts. Again, MURR has designed both the new power supply racks to house a potentiometer and ammeter for adjusting shim control blade electromagnet current. No new failure modes are associated with the replacement Acopian Model 24PT10. One new improvement to the new racks is a protective shroud around the power supply input AC toggle switch which will reduce the potential for inadvertent actuation of the toggle switch that would cause a reactor scram.

MODIFICATION RECORD 19-04 Main Air System This modification record documents significant enhancements to the main air system, which includes a change to the air compressor control system; as well as removal of the current air dryer, cyclone separator, Deltech filters, and associated piping and valves. These changes were made in order to increase the reliability and flexibility of the system.

The air dryer and cyclone separator were replaced with two non-cycling refrigerated compressed air dryers, each with a capacity of 100 cfin. The air dryers are configured in parallel, which provides flexibility for dual operation or isolation of one dryer from the system. This portion of the modification has significance as it directly relates to prevention of recurrence of the condition that resulted in Licensee Event Report (LER) No. 17-06. Excessive moisture in the main air system caused the containment backup door air supply to freeze, allowing the door to close, which then reduced containment differential pressure and resulted in a violation of MURR Technical Specifications 3.4.b and 3.4.a(6). The air dryers are designed to provide reliable, dry air at an ISO 8573.1 quality class 4-5, which is more than suitable for the air systems at MURR. The lines that supply air to the backup door cylinders are exposed to potentially freezing conditions. The new design air dryers provides a higher quality of air providing greater assurance that a freezing condition will not recur in those lines. The existing Deltech filter was replaced by a set of two enhanced filters, designed to remove water, oil, and other particulate from the air. The filters are located immediately upstream and downstream of the air dryers. The first filter is designed to remove bulk particulate, oil, and water from the air prior to entering the dryers. The second filter is designed for coalescing fine water and oil aerosols and removing solid particulate to 0.01 microns. Both filters have a differential pressure gauge for easy identification of optimum filter cartridge replacement. Another significant change to the main air system is the control system of the main air compressors. The compressors will now automatically alternate roles as being the lead and lag unit. Under normal conditions, the compressor in the lead role will start at an established low pressure setpoint and then secure at a higher pre-determined setpoint. The compressor roles will then reverse such that the other compressor is in the lead position.

N-2

I This cycle will repeat as long as the system is in automatic control in order to keep main air system pressure within that established band. A second lower pressure band has been established so that if main air system pressure reduces below a pre-determined low-low setpoint, the lag compressor will start along with the lead compressor. Once pressure reaches a pre-determined setpoint, the lag compressor will stop. When the lag alarm circuit is initiated, a local lag alarm will sound and a local lag lamp will illuminate. The alarm can be silenced with a local push button switch and the entire circuit reset once pressure rises above a pre-determined setpoint. fu addition to these automatic features, the new air compressor control system has provisions to operate either compressor in manual mode without the control panel in service. When in manual mode, whichever compressor is selected will cycle in a pre-determined range of pressures.

MODIFICATION RECORD 19-05 Replacement ofDPS-930 Transmitter and fudication This modification record documents the replacement of the pressurizer level transmitter (DPS-930) and meter due to failing upscale. The transmitter is mounted next to the pressurizer and produces a DC milliampere signal proportional to the differential pressure created by a dry reference leg and a wet variable leg. .The output signal is directed to a pressurizer liquid level indication in the instrument cabinet of the control room. The original equipment, a 0-60" H20 GE transmitter (SN BK04500l-001), sent a signal to a +20" to -30" analog meter and was replaced with a 0-150" H 20 Rosemount 1151DP differential pressure transmitter. Additionally, the pressurizer liquid level indication was transferred from the analog level meter in the instrument cabinet to the demineralizer flow paperless recorder as a third input and display to that recorder. This indication is normally buffered to provide a single digit inch liquid level indication but can be unbuffered when desired to provide an indication of one tenth of an inch. fu order to facilitate this change, minor transmitter piping and mounting modifications were implemented but did not affect transmitter functionality. The former pressurizer liquid level indication meter has been temporarily covered pending future instrument cabinet modifications.

MODIFICATION RECORD 99-02, ADDENDUM 1 Small Flux Trap Sample Holder Enhancement This addendum to Modification Record 99-02, "Six Barrel Flux Trap," documents enhancements to the small flux trap sample holder and sample canister. The previous configuration required extensive underwater manipulation to remove the sample canister from the aluminum rod and to remove the aluminum rod from the upper stamless steel section of the holder. This was a cumbersome process that resulted in additional time and dose to Reactor Operations and Reactor Health Physics (HP) personnel. Additionally, the aluminum rods were removed each week, which generated a substantial volume of radioactive waste and also consumed storage space within the reactor pool. The new design of the small flux trap sample holder consists of a single assembly, which is attached to the sample canister via a spring-loaded dovetail connection. A mating dovetail connection on the sample canister provides a secure attachment to the holder. The top end of the sample holder is spring-loaded to the inner connecting rod such that when the top is forced down against the spring, the dovetail end of the rod is exposed to mate with the canister connection.

When the top is released, the force of the spring pushes the inner rod upward and retracts the dovetail connection into the outer tube.

• The top is then pinned in place, which prevents inadvertent actuation of the holder with the sample canister attached. A rope or wire is connected to the top of each holder and extends to the pool surface. This enhanced design provides the following key benefits: (1) it will significantly reduce the amount ofradioactive waste generated from the weekly replacements of the aluminum connecting rods; (2) it will reduce the amount of temporary storage in the reactor pool; (3) it will reduce the disposal costs; and (4) it will reduce operator and HP dose since sample canister replacements will generally be performed under water.

IV-3

I MODIFICATION RECORD 08-04, ADDENDUM 1 Modify DI Supply to the Beamport Fill Lines This modification record documents the reconfiguration of demineralized (DI) water piping in Room 101 (beamport floor) to supply DI water to both the beamport manifolds from existing DI supply lines coming through the utility entry water seal (seal trench). This modification also disconnected, capped, and abandoned the DI supply piping from the Room 114 pipe tunnel to Room 101 which had deteriorated and was leaking water into Room 101 when pressurized.

N-4

SECTIONV NEW TESTS AND EXPERIMENTS January 1, 2019 through December 31, 2019 The following new and amended tests or experiments were approved during this period under a Reactor Utilization Request (RUR):

RUR456 Holmium Complexed PLA Microspheres This RUR authorizes the irradiation ofup to 2.0 g of holmium-doped, synthetic polymer microspheres in the bulk pool region of the reactor for use in therapeutic applications.

RUR 456, AS AMENDED Holmium Complexed PLA Microspheres This RUR amendment authorizes the use of sealed aluminum as the primary outer encapsulation for this therapeutic application irradiation in either the bulk pool or graphite reflector regions of the reactor.

RUR 456, AS AMENDED Holmium Complexed PLA Microspheres This RUR amendment authorizes the use of high density polyethylene as the primary outer encapsulation for this therapeutic application irradiation in either the bulk pool or graphite reflector regions of the reactor.

RUR 219/234, AS AMENDED Irradiation of Tellurium Metal This RUR amendment authorizes an increase in the target mass of tellurium-122 (metal) from 20 mg to 30 mg for irradiation in the center test hole region of the reactor in support of product development activities.

RUR 209/219, AS AMENDED Irradiation of Holmium Oxide This RUR amendment authorizes an increase in the mass of holmium oxide from 200 mg to 1.0 g for irradiation in the center test hole region of the reactor in support of product development activities.

V-1

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 MURR 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-2

SECTIONVI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2019 through December 31, 2019 INSPECTIONS 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 rules and regulations.

No violations were noted.

MISCELLANEOUS SNM SHIPMENTS One shipment containing 16.4 grams of low-enriched uranium (LEU) U02 was sent to Oregon State University on behalf of Northwest Medical Isotopes, LLC, for molybdenum-99 research.

REACTOR CHARACTERISTICS MEASUREMENTS Fifty-eight refueling evolutions were completed in 2019. Reactor core excess reactivity verifications were performed for each refueling. The largest measured excess reactivity was 4.16%. MURR Technical Specification (TS) 3.1.a requires reactor core excess reactivity above reference core condition to be less than 9.8%.

REACTIVITY MEASUREMENTS Differential blade-worth measurements of six shim control blades were performed either following a planned replacement of a control blade or to ensure compliance with TS 4.2.g.

One reactivity measurement was performed to determine the reactivity worth of a newly fabricated center test hole removable experiment sample canister.

Two reactivity measurements were performed to determine the reactivity worth of the small flux trap tubes of the center test hole removable experiment sample canister loaded with the maximum number of samples in order to confirm that their reactivity worth is less than the movable experiment limit of TS 3.8.c.

Five reactivity measurements were performed to estimate the total reactivity worth of the center test hole removable experiment sample canister, in addition to all samples loaded in the center test hole region of the reactor.

Two reactivity measurements were performed to investigate the reactivity worth of irradiation cans containing enriched molybdenum targets irradiated in the center test hole region of the reactor.

VI-1

SECTIONVIl RADIOACTIVE EFFLUENT January 1, 2019 through December 31, 2019 TABLE 1 SANITARY SEWER EFFLUENT Descending Order of Activity Released for Nuclide Totals > l.OOOE-05 Ci l;~t;. .\Nttiuile ~g;;Jtf *I J " Acti"jtyJ(niP) *; r!

H-3 I 1.18E+02 Co-60 1.16E+Ol S-35 1.14E+Ol ............- ....... ............................

Zn-65 4.07E+OO Cd-109 2.72E+OO P-32 l.24E+OO Ca-45 l.22E+OO Fe-59 4.52E-01 Pd-109 4.0lE-01 Sb-124 3.84E-01 Mn-54 3.48E-01 Cr-51 3.27E-Ol Lu-177 2.04E-01 Sc-46 l.92E-01 A04hl=l-0 Tc-99m 1.12E-01 Mo-99 I 2.97E-02 Co-58 2.34E-02 Rh-105 l.31E-02 Total H-3 1.18E+02 Total Other  ! 3.49E+01 l

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

VII-1

TABLE2 STACK EFFLUENT Ordered by % Technical Specification Limit Ar-41 1.17E+09 350 74.2682 1-131 3.27E-12 l.47E+03 1 1.6329 C-14* 2.34E-11 l.06E+04 1 0.7800 H-3 2.02E-08 9.10E+06 350 0.0577 Xe-131m 2.39E-07 l.08E+08 350 0.0341 Co-60 2.12E-15 9.55E-01 1 Os-191 4.76E-14 2.14E+Ol 1 0.0024 1-133 3.21E-13 l.45E+02 350 0.0001

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

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

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

VII-2

SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2019 through December 31, 2019 Environmental samples are collected two times per year at eight locations and analyzed for radioactivity. Soil and vegetation samples are also taken at each location. Water samples are taken at three locations while subsurface soil samples are taken at six locations each period. Analytical results are shown in Tables 1 and 2.

Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2019. All doses fluctuate around background except monitor number 9. This monitor is located near a loading dock area where packages containing radioactive material are loaded or traverse prior to being placed on transport vehicles. The doses recorded by this monitor are considered to be the result of exposure to packages in transit. The environmental monitoring program confirms that minimal environmental impact exists from the operation of the MURR facility.

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

TABLE 1

SUMMARY

OF ENVIRONMENTAL SET 95 - SPRING 2019 Detection Limits*

Vegetation 0.00 pCi/g 6.91 pCi/g 1.55 pCi/g 5.22 pCi/mL Soil 0.72 pCi/g 3.55 pCi/g 0.62 pCi/g NIA Water 0.78 Subsurface Soil 0.72 pCi/g Activity Levels - Vegetation JY?~ --- . ,. ,_L,__ -- _9:?L *-l--*--*---,...._ .. ..4,_,_5_,.....*..9_....3..........._ ..____...._,.............................. _<

. _MD

. __,_,_A,_.................................... <MDA 2V95 <MDA 24.14 <MDA <MDA 3V95 <MDA 24.14 <MDA <MDA 4V95 0.62 32.07 <MDA <MDA 5V95 <MDA 47.21 <MDA <MDA 6V95 0.31 30.99 <MDA <MDA 7V95 1.25 32.07 <MDA <MDA 10V95 l 0.62 46.13 <MDA <MDA Vill-1

TABLE 1 (Cont'd)

SUMMARY

OF ENVIRONMENTAL SET 95 - SPRING 2019 Activity Levels - Soil Beta},*.

(pc1J~J.

1S95 15.32 2.33 2S95 1.56 19.28 3S95 0.78 17.48 1.43 4S95 0.78 11.35 2.08

---*-*-------t------*----+--------------t------------1 5S95 0.94 6S95 0.94 9.73 1.30 7S95 1.71 34.41 2.97 10S95 0.94 20.00 2.84 Activity Levels - Water

.* ..,Beta* :i*,;,f:75

. \,~(;i/gJ::.i[l' 4W95 <MDA <MDA <MDA 6W95 <MDA <MDA <MDA <MDA 10W95 <MDA <MDA <MDA <MDA Activity Levels - Subsurface Soil

.: B'ifa

(~~i/g)*

E95 <MDA 20.06 S95 1.08 20.04 4.00 SW95 1.08 23.23 3.97 W95 1.70 23.23 4.02 N95 NE95 1.23 24.12

• 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 minimum detectable activity (MDA).

Vill-2

TABLE2

SUMMARY

OF ENVIRONMENTAL SET 96 - FALL 2019 Detection Liniits *

• 'I'J'.!ffum**'

Vegetation l 0.00 pCi/g 7.50 pCi/g 1.75 pCi/g 5.63 pCi/ml Soil -i---o:oo-pC_i/_g_ _ _ _S.58-pC_i/_g ' 0.54 pCi/g NIA Water

_________________________________________________ i

!__ 0.86 pCi/L 3.66 pCi/L

---

i 199.25 pCi/L

---

5.78 pCi/ml Subsurface Soil I 0.00 pCi/g 3.93 pCi/g 0.52 pCi/g

• NIA Activity Levels - Vegetation 1V96 0.29 36.60 <MDA 6.75 1---------------------------------------*----------------------------------------------------------*----------------------------------------1---------------------------------------------*---*-*---..*-*----**. -*-*

2V96 <MDA 24.28 <MDA <MDA 3V96 <MDA 10.21 <MDA <MDA 4V96 <MDA 36.25 _<MDA <MDA 5V96 0.29 29.21 <MDA <MDA 6V96 <MDA 12.32 <MDA <MDA 7V96 0.29 28.51 <MDA <MDA 10V96 <MDA 28.86 <MDA <MDA Activity Levels - Soil

-,_,,Gamma--*-

_(p<Ji(g),

1S96 <MDA 3.18 2S96 0.57 <MDA 2.19 3S96 0.86 <MDA 2.45 4S96 0.86 2.54

---

----l----------------l--------------1 5S96 0.86 2.81 6S96 0. 72 <MDA 1.80 7S96 1.29 <MDA 1.94 10S96 1.14 <MDA 2.39 Vill-3

TABLE 2 (Cont'd)

SUMMARY

OF ENVIRONMENTAL SET 96 - FALL 2019 Activity Levels - Water

• *.. iJ{11eta

fipCi/g}.:;{;\i .

4W96 <MDA 9.10 <MDA 6W96 <MDA 14.92 <MDA <MDA 10W96 <MDA 18.57 <MDA <MDA Activity Levels - Subsurface Soil Gainffii:*.*

.(pcygJi{

4.77 S96 1.39 22.08 4.48

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

0.84 23.18 4.91 1.39 18.85 4.80 1.29 18.19 4.21

. NE96 1.13 19.05 3.94

• 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.

Vill-4

TABLE3 ENVIRONMENTAL TLD

SUMMARY

'~~::t*:~,i~*11:r*1:*~*,::t/ *j:~~!tr:rl ~:irt:!!lilte1;:::**!. ~j~~:!!f,.l;l~;:::rl~?::i o* Control NIA I 1

30 32-7 33 122 1* Control NI 33 30 25 28 116 2* Control NIA 29 30 29 115 3 W 30 -2 -1 -6 -12 4 SW 59 -1 3 -1 f 17 5 ENE 110 -4 -5 -4 -15 R-9--1

-?

6 7

NNE ENE 84 55

-~ -~ -~ ~

9 8 SW 32

-,-+---------+---------------,----********~*****-***************----*??***

SSE 27 5

• • • ---*> ~ ~ ~-7-4--

10 NE 139 -4 -1 -1 -1 -7 11 N 135 -1 1 0 2 2 12 NE 284 13 NNE 305 14 s 168 15 SSE 74 16 SE 113 17 E 299 -2 -6 -4 .. _....,............ -5  :!7 18 NE 453 -5 ~5 Missing -6. -16 19

-*--*-****** f-........._*---*-!----*----*-

20 21 NE NE SSE 673 893 239

= -8

---**--..--*--**+-

-7

~

-10

~

-4

-10 W

-8

-6

-5 1

-34

-24 4

22 SE 158 -8 -9 -9 -7 -33 23

• NW I 89 -2 -2 1 6 3

-~_!__+-__:_:_--i----~--~  : __:_;__

3

-*--*-----~~ ;;

28

,  ;:~

NW

~

f--***-*--..1*-~-05-*-**---i--.--1!-*--l----:--28____

-------------i-----*-t-------i------j-------

229 1 *1 -1 f--_ _ -:_ _-l-:_._--**_***_=_E_*----*_--_

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1

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---

29 NW i 260 -1 0 -2 0 -3 30 N [ 335 -5 -5 -6 -2 -18 31 NNE I 677 -3 -1 -1 2 -3 32 NW ' 760 -3 -1 -1 -1 ' -6 33 1

34_***--+---E_NE ESE

_ _ _t--_ _5_9_6_ _ _

578 -8

, __-7______-_10_ _ _ _ _-_7_ _

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35

---

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'.:'.'.:':'_______ J...................477

.'....'....*-*-*-*--f****--*-**---:::*6...........-*,1----*-*-=********

-2 ........: ........... _-: 2 __ ...... J............ 6'.:'............. 12 36 SE 446 -5 -1 -2 -8 -16 37 . NE 732 -7 -7 i -9 -5

..............*--*-**t........ --*--*-*****._..............-1-*---***-*----..---*--+*-*------****-"*****"*****t**.................................., ........______**-*""""t"**-***..*-*"""*----*t-*---*--**-*--******--*1

-28 38 NW 487 -3 1  : 0 1 -1 39 W 528 -4 -22 18 1 -7 40 N 503 -9 -5 -5 -2 -21 41 NE 161 -2 -3 -7 -5 .... -17

>---*-4-2---i-------+---------5---;-l---6--+----7---+---5--+---2-3_ _,

. *-*---* ............ In.Building---* -*-****-***-**-*!!1.-A....-----* --- . . . . . . . .L 43 In Building NIA O 0 0 4 4 44 SW 102 -1 -3 -5 0 -9 45 SE 94 9 1 i 1 16 27 46 SE 105 6 -4 1 9 12

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

VIII-5

TABLE4 NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS

• • ':i,~tiice .,gs:;

Cont;~i~~tio;~

';}:*. *lli~1t,:t:if"

",} ~< ~ '. . < M~Jerials.. *

• January 103 103 67 16 3

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • -***-********-*1-----****--*--..-*---*---*-*i******-****************-*-----*-***-*****- *-I February 85 85 52 11 5 March 91 91 58 14 8 April 106 106 66 25 9 May 86 86 68 22 5 June 97 97 62 18 6 July 100 100 63 16 7 103 66 8 13 85 51 11 6 October 104 104 52 15 8 November 84 84 42 13 4 December 105 105 32 3 7 TOTAL 1,149 1,149 679 172 81

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

• • Air samples include stack Ar-41, containment Ar-41, sump entries, and hot cell entries. This number is lower for 2019, as sampling for Ar-41 is done on a continuous basis and not reported as discreet samples.

Miscellaneous Note During calendar year 2019, MURR shipped 1,804 cubic feet of low-level radioactive waste containing 5,364 mCi of activity.

VID-6

~-------------------------------------~-----

SECTION IX

SUMMARY

OF RADIATION EXPOSURE TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS January 1, 2019 through December 31, 2019 Total Personnel Dose (mrem) by Dosimetry Group AC/PRD BCS DO FOE HC HP IRR NA NS NSP OPS QA RES RP SH SIL TEE WC Total January 128 0 0 303 193 491 0 9 18 102 1,944 70 13 16 52 207 4 0 3,550 February 59 1 0 46 132 252 0 6 69 88 1,629 79 3 5 39 187 14 0 2,609 March 79 0 0 17 185 254 0 0 312 86 2,007 76 2 4 55 175 5 1 3,258 April 53 0 14 202 190 164 0 4 203 128 2,226 84 0 7 33 236 0 0 3,544 May 230 0 0 81 172 224 9 0 149 52 1,939 51 0 8 43 219 0 6 3,183 June 58 0 0 167 121 199 0 10 2 26 1,573 51 0 0 16 114 7 0 2,344 July 162 12 44 57 187 300 6 89 156 175 1,781 107 49 79 46 236 41 6 3,533 August 213 0 2 73 200 176 0 10 59 90 1,388 26 1 7 84 212 2 18 2,561 September 91 0 0 20 287 277 0 24 74 148 982 59 0 0 30 179 0 0 2,171 October 62 2 0 73 127 140 0 12 0 82 1,144 36 13 2 19 139 0 0 1,851

~ November 86 0 9 69 210 303 0 5 69 214 1,328 36 28 6 55 88 18 0 2,524 I

December 101 3 2 39 228 332 0 4 85 169 1,125 106 55 5 68 79 0 0 2,401 Total for Year 1,322 18 71 1,147 2,232 3,112 15 173 1,196 1,360 19,066 781 164 139 540 2,071 91 31 33,529 Monthly Average 110 2 6 96 186 259 1 14 100 113 1,589 65 14 12 45 173 8 3 2,794 HighestWB 308 6 13 229 884 757 4 28 128 308 1,069 159 58 36 235 1,288 15 19 (annual)

High Extremity 5,594 123 NM 5,608 2,309 1,150 20 1,204 50 1,498 1,750 1,520 150 843 432 1,404 112 0 (annual)

AC/PRD-Analytical Chemistry/Production HP-Health Physics OPS-Operations SH-Shipping RCS-Business & Central Services IRR-Irradiations QA-Quality Assurance SIL-Silicon DO-Director's Office NA-Neutron Activation RES-Research TEE-Trace Elemental Epidemiology FOE-Shops & Support NS-Neutron Scattering RP-Radiopharmaceutical WC-Work Control HC-HotCell NSP-NorthStar Partners 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).