ML12059A368

University of Missouri Research Reactor 2011 Reactor Operations Annual Report

ML12059A368
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/27/2012
From:	Fruits J Univ of Missouri - Columbia
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML12059A368 (35)

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UNIVERSITY of MISSOURI RESEARCH REACTOR CENTER February 27, 2012 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

REFERENCE:

Docket 50-186 University of Missouri-Columbia Research Reactor Amended Facility License R-103

SUBJECT:

University of Missouri Research Reactor 2011 Reactor Operations Annual Report I have enclosed one copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2011 through December 31, 2011.

This document is submitted to the U.S. Nuclear Regulatory Commission in accordance with the University of Missouri Research Reactor Technical Specification 6. l.h(4).

If you have any questions regarding the contents of this report, please contact me at (573) 882-5319 or FruitsJgmissouri.edu.

Sincerely, John L. Fruits Reactor Manager JLF/djr Enclosure xc: Mr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC 1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: http://web.missouri.edu/kmurrwww Fighting Cancer with Tomorrow's Technology

UNffERSffTY OIF MESSOURI UNIVZIR§ETY ODF Mff§§DUI~ll IREACThDhR (DPEEA~f(NS ANNUAIL IREIWT7 JEnuiry 1, 20R11I - DcembeT 3119 201i)

UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2011 through December 31, 2011 Compiled by the Research Reactor Staff of MURR Submitted by:

JihnL.Fruits Reactor Manager Reviewed and approved by, Ralph A. Butler, PE Director

UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1,2011 through December 31, 2011 INTRODUCTION The University of Missouri Research Reactor (MURR) is a multi-disciplinary research and education facility providing a broad range of analytical, materials science, and irradiation services to the research community and the commercial sector. Scientific programs include research in archaeometry, epidemiology, health physics, human and animal nutrition, nuclear medicine, radiation effects, radioisotope studies, radiotherapy, and nuclear engineering; and research techniques including neutron activation analysis, neutron and gamma-ray scattering, and neutron interferometry. The heart of this, facility is a pressurized, reflected, open pool-type, light water moderated and cooled, heterogenous 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 2011. Included within this report are changes to MURR reactor operations and health physics procedures, revisions to the Hazards Summary Report, facility modifications, new tests and experiments, reactor physics activities, and environmental and health physics data.

This Report is being submitted to the U.S. Nuclear Regulatory Commission (NRC) to meet the administrative requirements of MURR Technical Specification 6.1.h (4).

ACKNOWLEDGMENTS The success of MURR and these scientific programs is due to the dedication and hard work of many individuals and organizations. Included within this group are: the University administration; the governing officials of the State of Missouri; the Missouri State Highway Patrol; the City of Columbia Police Department; the Missouri University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our Regulators; those who have provided funding including the Department of Energy (DOE) and the Department of Homeland Security (DHS); Argonne National Laboratory (ANL); Idaho National Laboratory (INL); Sandia National Laboratories (SNL); the Researchers; the Students; the Columbia Fire Department; the Campus Facilities organization; members of the National Organization of Test, Research, and Training Reactors (TRTR); and many others who have made, and will continue to make, key contributions to our overall success. To these individuals and organizations, the staff of MURR wishes to extend its fondest appreciation.

Some of the major facility projects that were supported by Reactor Operations during this calendar year included (1) responding to the Request for Additional Information regarding a License Amendment that was submitted to increase the flexibility and capacity in the center test hole, (2) preparation and installation of a new Cooling Tower that will support a power uprate to 12 MW, which is required for fuel conversion, (3) development of the necessary controls and procedures for usage of the BEA Research Reactor (BRR) spent fuel shipping package and (4) submission of a*request to the NRC to amend MURR Technical Specification.2.1, "Reactor Core Safety Limit," because of an error that was discovered in the MURR i

Safety Limit Analysis. Additionally, in .August 2006 MURR submitted a request to the NRC to renew Amended Facility Operating License R-103. Significant efforts have already been placed in responding to the Request for Additional Information and these efforts will continue in the upcoming year.

The facility continues to actively collaborate with the US-RERTR (Reduced Enrichment for Research and Test Reactors) Program and four other U.S. high-performance research 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 research 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.

Reactor Operations Management also wishes to commend the one individual who received his Reactor Operator certification from the NRC. This individual participated in a rigorous training program of classroom seminars, self-study, and on-the-job training. The results of this training is a confident, well-versed, decisive individual capable of performing the duties of a licensed operator during normal and abnormal situations.

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TABLE OF CONTENTS Section Title Pages

1. Reactor Operations Summary ............................................................... 1-1 through 8 II. M U RR Procedures ............................................................................... IL -I through 8 A. Changes to Reactor Operations Procedures B. Changes to the MURR Site Emergency Procedures and Facility Emergency. Procedures C. Changes to Health Physics Procedures, Byproduct Material Shipping Procedures, and Preparation of Byproduct Material for Shipping Procedures III. Revisions to the Hazards Summary Report .................. II-1 through 2 IV. Plant and System Modifications .......................... IV- I V. New Tests and Experiments ............................................................ V-1 VI. Special Nuclear Material and Reactor Physics Activities ....... ............. VI- 1 VII. Radioactive Effluent .......... .................................... VII-I through 2 Table I - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII. Environmental Monitoring and Health Physics Surveys ...................... VIII-l through 5 Table I - Summary of Environmental Set 79 Table 2 - Summary of Environmental Set 80 Table 3 - Environmental TLD Summary Table 4 - Number of Facility Radiation and Contamination Surveys IX. Summary of Radiation Exposures to Facility Staff, Experimenters, and V isitors ........................................................................................... IX- I

SECTION I REACTOR OPERATIONS

SUMMARY

January 1, 2011 through December 31, 2011 The following table and discussion summarizes reactor operations during the period from January 1, 2011 through December 31, 2011.

Full Power % of Full Power % of Month Full Power Hours Megawatt Days Total Time Scheduled(1.)

January 669.29 278.98 90.0 100.7 February 614.47 256.11 91.4 102.4 March 679.31 283.16 91.3 102.2 April 655.27 273.12 91.0 102.1 May 652.70 272.08 87.7 98.2 June 652.20 271.85 90.6 101.6 July 682.73 284.53 91.8 102.7 August 648.93 270.51 87.2 97.7 September 640.57 266.19 89.0 99.8 October 651.29 271.96 87.5 98.0 November 650.82 271.66 90.4 101.4 December 536.24 267.69 72.1. 80.7 Total for 7733.82 3267.84 88.33 % 98.96 %

the Year Note 1: MURR is scheduled to average at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> of full power operation per week. Total time is the number of hours in the month listed or the year.

January 2011 The reactor operated continuously in January with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and five scheduled shutdowns for physics measurements. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: performing two reactivity worth measurements in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP- I (D);" completing compliance procedure CP-29, "'Calibration of the NMC RAK Radiation Stack Monitor;" performing two reactivity worth measurements in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" and completing compliance procedure CP-3 I, "Calibration of the Eberline Radiation Stack Monitor."

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February 2011 The :reactor operated continuously in February with the. following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and one unscheduled/unplanned power reduction.

On February 14, during a reactor startup to 10 MW operation, criticality was achieved prior to the pre-calculated Estimated Critical Position (ECP). The manual I/M calculation and graph indicated that the reactor would become critical at a rod height slightly lower than the one predicted by the pre-generated ECP. The Assistant Reactor Manager- Physics was contacted and permission was given by the Reactor Manager to continue the reactor startup to criticality. Once critical rod height data was obtained at 50 kW, the reactor was shut down for further investigation.

The correct core fuel loading was confirmed by map check of the fuel storage facilities. Two of the fuel: elements (out .of the eight) that were loaded in the core had only one week of operational history; however, there was no correction used in the calculated ECP for the partial buildup of Samarium in these two elements. The sample loading in the center test hole canister was re-verified and the center test hole strainer was installed.. The reactivity, worth of the loaded center test hole canister was verified by performing reactor procedure RP-RO-20 1, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B)." It was determined that although the deviations in core reactivity and center test hole reactivity worth were independently within normal tolerances, the two combined deviations were sufficient enough to cause the overall calculated ECP to be outside the limits listed in operating procedure QP-RO-2 10, "Reactor Startup - Normal." Permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included: completing Modification Record 01-02, Addendum 5, "Intercommunication and Paging System Changes in Support of the North Office Addition Lab Space;" installing an additional facility evacuation horn in the North Office Addition in accordance with Modification Record 90-01, "Evacuation System Changes in Support of the New North Office Addition;" loading new de-ionization bed 'K' and placing it on pool coolant system service; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-20 ., '.'Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" and performing two reactivity worth measurements in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP- II(D)," in support of a Nuclear Engineering Department practicum.

March 2011 The reactor *operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and one unscheduled/unplanned power reduction. U.S. Nuclear Regulatory Commission regional inspector arrived at the facility for a routine inspection of the Radiation Protection Program and Shipping.

On March 21, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was manually initiated when the control room operators observed a faster than normal lowering of pressurizer liquid level soon after startup. Upon investigation, it was discovered that the water loss was through the reactor pressure vessel head flange and into the reactor pool. The pressure vessel head is required to be unbolted and removed during the weekly core refueling. It was determined that the pressure vessel head flange had been improperly tightened after it was reinstalled following a core refueling.. The pressure vessel head was removed, a new flexitallic gasket was installed 1-2

and the vessel head was reinstalled and tightened. The reactor returned to 10 MW operation with permission from the Reactor Manager.

Major maintenance items for the month included: replacing the +15 volt power supply for Nuclear Instrumentation Signal Processor No. 1; performing two reactor test procedures "RTP Experimental Measurement of the MIJRR Primary Temperature Coefficient of Reactivity" in support of a Nuclear Engineering Department practicum; replacing the rotary limit switch and cam follower for Regulating Blade 60% Withdrawn indication; installing the facility exhaust ventilation system isolation damper for laboratory 251; and collecting primary coolant system hydraulic data for benchmarking.

April 2011 The reactor operated continuously in April with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and two unscheduled/unplanned power reductions.

On April 7, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5 & 6 High Power" rod run-in was automatically initiated when Channel 5 power level indication increased above the rod run-in set point. Investigation revealed a momentary upward spike to 109% on Channel 5 chart recorder. All other power level indications were normal - between 100 and 105%. The specific cause of the rod run-in could not be determined. The Reactor Manager granted permission to reset the rod run-in and the reactor was returned to 10 MW operation.

During the following scheduled maintenance day activities (April II), extensive troubleshooting did not reveal a definitive cause. Historically, after various periods of service, the cabling between detectors and amplifier assemblies have caused upward spiking due to radiation induced insulation damage or breakdown. The fission chamber detector and associated cabling were replaced. An instrument channel calibration and pre-operational check were performed satisfactorily. The system was then response checked with a neutron source. No further instances of indication spiking have occurred.

On April 21, with the reactor operating at 10 MW in automatic control mode, a "Reactor Loop Low Flow" reactor scram was automatically initiated when primary coolant system flow decreased below the reactor safety system low flow scram set point of 1725 gpm. The immediate and subsequent actions of reactor emergency procedure REP-3, "Primary Coolant System Low Pressure or Flow Scram," were completed. Subsequent investigation revealed primary coolant circulation pump P-501.B thermal overloads had tripped due to a failure of relay K2 in the pump controller. The relay was replaced. the pump controller was inspected and retested satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.

Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-I 7(B);" refurbishing Regulating Blade 60% Withdrawn relay IK 10; replacing the fission chamber detector for Nuclear Instrumentation Signal Processor No. 2; replacing pump control relay K2 for primary coolant circulation pump P-5013B; and completing the biennial change-out of Control Blade 'A' Offset Mechanism and associated retesting.

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May 2011 The reactor operated continuously in May with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown forphysics measurements and one unscheduled/unplanned power reduction.

On May 13, with the reactor operating at 10 MW in the automatic control mode, a "Nuclear Instrument Anomaly" scram was automatically initiated when. Nuclear Instrumentation .Power Range Channel No. 6 self-diagnostic operation monitoring system generated a malfunction (inoperative) signal. The duty operator noted that the other two power level indications were normal - between 100 and 105% - prior to the scram. All immediate and subsequent actions of reactor emergency procedure REP-5, "Nuclear Instrument Failure," were performed. Subsequent investigation revealed .that the uncompensated ion chamber detector and associated cabling were causing excessive loading of the high voltage power supply. The uncompensated ion chamber detector and cabling and the high voltage power supply were replaced. An. instrument channel calibration and pre-operational checks were performed satisfactorily. The system was. response checked with a neutron source and permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.

.Major maintenance items for the month included: performing back flushes on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B and pool coolant system heat exchanger .HX-521; completing compliance procedure CP-26, "Containment Building Compliance Test;" replacing the trolleys for Personnel Airlock Door 276; completing compliance procedure CP-29, "LAB IMPEX Stack Monitor;" and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP- 17(B)."

June 2011 The reactor operated continuously ,in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and three unscheduled/unplanned power reductions.

.On June 6, during a reactor startup with the reactor operating at 5 MW in the manual control mode, a "Reactor Loop Hi Temp Scram" was automatically initiated when primary coolant heat exchanger outlet temperature increased above the scram set point of 148 IF. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. An insufficient configuration of the secondary coolant circulation pumps and cooling tower fans to provide adequate cooling was the cause of the scram. After verification that no Safety Limits or Limiting Safety System Settings had been exceeded, permission to restart the reactor was obtained from the Reactor Manager. The control room staff was reminded of the need to provide greater cooling prior to reaching "the point of adding heat" when outside temperature and humidity conditions are higher than normal.

On June 13, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was initiated when the control room operator noted all four shim control blades moving inward. A brief initial'investigation was unable to determine the cause of the rod run-in and the reactor was manually shutdown. Subsequent investigation of all relays, switches and wiring associated with the rod run-in system revealed no abnormalities. This instance was similar to Unscheduled Shutdown No. 1242 at which time the Non-Coincidence Logic Unit and the Trip Actuator Amplifiers were replaced. Temporary monitoring equipment was reattached to the circuit to monitor certain input signals to aid in any future troubleshooting efforts. Operational checks of the rod run-in system were performed satisfactorily and permission to restart the reactor was obtained from the Reactor Manager.

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• On June 13, with the reactor operating at 10 MW in the automatic control, mode, an unannounced (no audible or visual alarm occurred) rod run-in was initiated as the control room operator noted all four shim control blades moving inward. A brief initial investigation was unable to determine the cause of the rod run-in and the reactor was manually shutdown. The temporary monitoring equipment did not indicate that an input signal generated the rod run-in.

Additional troubleshooting and investigation were unable to reproduce this system response. The Non-Coincidence Logic Unit and the. Trip Actuator Amplifiers were replaced and operational checks of the rod run-in system were performed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager.

Major maintenance items for the month included: performing a back flush on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B and pool coolant system heat exchanger HX-52 1; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings:or Individual Samples, RTP-17(B);" completing compliance procedure CP-3 1, "Calibration of the Eberl ine Radiation Stack Monitor;" and adjusting the timing sequence between seal deflation and door actuation for Personnel Airlock Doors 276 and 277.

July 2011 The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-I I(D);" performing a zero and span procedure on Differential Pressure across the Reactor Pool Reflector Transmitter PT-917; replacing the trolley blocks on Personnel Airlock Door 276; performing back flushes on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B; performing a back flush on the secondary coolant side of pool coolant system heat exchanger HX-52 1; and repairing the wire harness on control rod 'A' drive mechanism.

August 2011 The reactor operated continuously in August with the following exceptions: five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: performing back flushes on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B and pool coolant system heat exchanger HX-52 1; loading new de-ionization bed 'S' and placing it on pool coolant system service; repairing the Fission Product Monitor; removing pneumatic tube system service from laboratory 227; and completing the biennial change-out of Control Blade 'D' Offset Mechanism and associated retesting.

September 2011 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one scheduled shutdown for physics measurements and two unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission examiner arrived at the facility to conduct operator licensingexaminations.

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On September 1, with the reactor operating at 10 MW in the automatic control mode, a manual reactor shutdown was initiated in order to investigate an abnormal lowering in Reactor Make-Up Water Storage Tank T-300 water level.

Upon investigation, it was discovered that Charging Pump Gland Cooling Solenoid Valve 515AF apparently had not fully seated following a routine charging evolution. Valve 515AF automatically opens when Primary Coolant Charging Pump P-533 starts in order to provide packing gland cooling and lubrication. The water source for both the coolant charging pump and gland cooling and lubrication is from T-300. The valve was disassembled and a small amount of debris was found on the valve disc and seating surface. The debris was removed, the valve reassembled and operationally tested satisfactorily. Inspection of the remainder of the system revealed no additional foreign material. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

On September 2, with the reactor operating, at 10 MW in the automatic control mode, a "Rod Not in Contact with Magnet" rod run-in was automatically initiated when control blade"B' anvil, separated from its electro-magnet following the completion of a routine shimming evolution. The reactor.was shut down, and an inspection of the offset mechanism and a pull rod to housing alignment were performed. Satisfactory operation of the shim rod was verified through performance of the applicable portions of compliance procedure CP-25, "Offset Removal, Installation and Control Blade Inspection;" special maintenance procedure SM-RO-625, "Measuring Control Blade Pull Weight and Blade Drop Time with the Test Magnet Assembly, RTP-21;" and compliance procedure CP-10, "Rod Drop Times." The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" updating the PLC control program for containment building Personnel Airlock Doors 276 and 277 as part of Modification Record 09-2, "Airlock Door Control;" and modifying the secondary coolant chemical addition piping and secondary coolant pH and conductivity sensing lines as part of Modification Record 09-4, "Cooling Tower Temporary Cooling."

October 2011 The reactor operated continuously in October with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and one unscheduled/unplanned power reduction. U.S. Nuclear Regulatory Commission regional inspector arrived at the facility for a routine inspection of Reactor Operations and Emergency Preparedness.

On October 7, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was automatically initiated when a momentary interruption in electrical supply power from the University Power Plant to the facility occurred. All immediate and subsequent actions of reactor emergency procedure REP-1 1, "Momentary Loss of Normal Electrical Power," were performed. Permission to restart the reactor was obtained from the Reactor Manager after confirmation from the University Power Plant that the cause of the interruption in electrical power was corrected. The reactor was refueled and subsequently restarted to 10 MW operation.

Major maintenance items for the month-included: replacing-detector cabling on the Reactor Bridge ALARA module of the Area Radiation Monitoring System; completing Modification Record 09-04, "Cooling Tower Temporary.

Cooling;" completing Modification Record 01-02, Addendum 6, "Intercommunication and Paging System Changes in Support of the North Office Addition Classroom Space, Laboratory Break Room and Laboratory Basement;"

-repairing rod drop timer contacts on "Loss of Voltage to Magnet C and D Scram". relay; performing back flushes on 1-6

the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B and pool coolant system heat exchanger HX-521; and replacing the suction piping expansion boot for secondary coolant circulation pump SP-2.

November 2011 The reactor operated continuously in *November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month. Received notification from the U.S. Nuclear Regulatory Commission that one new Reactor Operator license had been issued.

Major maintenance items for the month included: performing back flushes on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B and pool coolant system heat exchanger HX-521; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP- 17(B);" replacing the suction piping expansion boot for secondary coolant circulation pump SP-I; and refurbishing the ventilation exhaust isolation valve 16B solenoid-operated air control valve A- 150.

December 2011 The reactor operated continuously in December with the following exceptions: -four shutdowns for scheduled maintenance and five unscheduled/unplanned power reductions.

On December 3, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact with Magnet" rod run-in was automatically initiated when control blade 'D' anvil separated from its electro-magnet during a routine sample handling evolution. The immediate actions of REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator.

On December 6, with the reactor operating at 10 MW in the automatic control mode, the reactor was manually shut down. Following routine scheduled calibration activities .on the iodine channel of the Eberline PING stack monitor, the control room operators observed a higher than normal indication on the chart recorder when returning the monitor to service. Confidence in the monitor's performance was in question and the reactor was immediately shut down as required by Technical Specification 3.4.a. Investigation revealed some Iodine-13 1 contamination on or in the iodine detector area which had most likely occurred during the calibration procedure. Decontamination efforts proved successful with an iodine indication slightly higher than pre-calibration levels. After consultation with the Reactor Health Physics Manager, the Reactor Manager determined that the reactor could be refueled and restarted.

On December 13, with the reactor operating at 10 MW in the automatic control mode, the reactor was manually shut down because of difficulties in maintaining primary coolant system temperatures in .their normal operating bands..

While operating on the temporary cooling towers during installation of the new cooling towers, efficiency of the secondary coolant side of the primary coolant heat exchangers had declined due to difficulties in maintaining secondary coolant water chemistry and the buildup.of foreign material from the temporary cooling, towers. The unseasonably high outside temperatures coupled with the reduced performance of the heat exchangers precluded 10 1-7

MW operation. Following back flushes on the secondary coolant side of the primary coolant heat exchangers, the Reactor Manager directed control room personnel to operate the reactor at a reduced power level, as necessary, in order to maintain proper primary coolant system temperatures. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

On December 20, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5 & 6High Power" rod run-in was automatically initiated. The duty operator noted all reactor power level indications were.

normal. All immediate and subsequent actions of reactor emergency procedure REP-5, "Nuclear Instrument Failure,"

were performed. Troubleshooting efforts lead to the replacement of the fission chamber detector and associated cabling for Nuclear Instrumentation Signal Processor No. 2. An instrument channel calibration, nuclear instrument response check and pre-operational checks were performed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

On December 25; with the reactor operating at 9.5 MW in the automatic control mode, a reactor scram was automatically initiated when an interruption in electrical supply power from the University Power Plant to the facility occurred. All immediate and subsequent actions of reactor emergency procedure REP-I 1, "Momentary Loss of Normal Electrical Power," were performed. After the cause of the momentary loss of electrical power was confirmed and corrected by the University Power Plant, permission to refuel and restart the reactor was obtained from the Reactor Manager.

Major maintenance items for the month included: performing back flushes on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B and pool coolant system heat exchanger HX-521; completing compliance procedure CP-3 1, "Calibration of the Eberline Radiation Stack Monitor;" refurbishing control blade selector switch IS3; electrically connecting the new cooling tower fans to Motor Control Center No. 1; and completing the biennial change-out of Control Blade 'C' Offset Mechanism and associated retesting.

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SECTION !1 MURR PROCEDURES January 1, 2011 through December 31, 2011 As required by administrative Technical Specification 6. .h (4), this section of the Annual Report includes a summary of procedure changes. These procedure changes were reviewed by the Reactor Manager or Reactor Health Physics Manager and others to assure compliance with the requirements of 10 CFR 50.59. These procedure changes were also reviewed by the Reactor Procedure Review Subcommittee of the Reactor Advisory Committee to meet the requirements of Technical Specification 6.] .c (1).

A. CHANGES TO REACTOR OPERATIONS PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Reactor Operations Procedures and found them to be adequate for the safe and reliable operation of the facility.

There were one hundred and one (101) revisions issued to the reactor operations procedures, forms and operator aids. Additionally, two (2) new procedures were issued and six (6)'outdated procedures were obsoleted. The majority of the revisions were strictly format or editorial in nature, such as cover page changes. The following is a list of the new and revised procedures, forms and operator aids:

Number Name Revsio nDateJ Notes:

AP-RO- I10 ,Conduct of Operations 16 12/9/2011 Minor Editorial AP-RO- 15 Records 7 11/17/2011 Minor Editorial AP-RO-130 Crane Operation J 5 6/14/2011 Minor Editorial EX-RO-105 Reactor Irradiation Experiments 15 11/17/2011 Minor Editorial EX-RO-120 Beamport "A" Operation J 9 10/13/2011 Minor Editorial EX-RO- 121 EX-RO-122 Beamport "B" Operation Beamport "C" Operation 99 10/13/2011 10/13/2011 T Minor Editorial Minor Editorial EX-RO-123 Beamport "D" Operation 9 10/13/2011 Minor Editorial EX-RO-124 Beamport"E" Operation 10 9 T 10/13/2011 Minor Editorial EX-RO-I251 Beamport "F" Operation 1i 10/13/2011 1 Minor Editorial EX-RO- 126 Thermal Column Door 7 11/17/2011 Minor Editorial FB-SH-001 Unirradiated Fuel Shipment Using the 110- Gallon 8/1 soee USA DOTFB-H-0 6M Type B Package 0 8/1/2011 Obsleted FB-SH-005 FType B Shipment of Spent Fuel Using the BMI- T 8/11/2011 Obsoleted Shipping Cask FB-SH-F-I 10 B Shipment oType Reco0B) f Spent Fuel Using the BEA akg Research Reactor (BRR) Package o 8 2e 8/17/2011 iNew Procedured FB-SH-120 lAnnual Inspection and Preventive Maintenance 5l/0 Obsoleted

ýBMI-1 Shipping Cask FB-SH-125 !Biennial Inspection and Preventive Maintenance 0 3/11/2011 Obsoleted iBMI-I Shipping Cask FB-SH-130 Test and Calibration Procedure BMI-I Shipping 0 3/11/2011 Obsoleted FCask ._ 0 31/1 Obsoete FB-SH-200 JO-RingFabrication BMl-1 Shipping Cask 101 5/11/2011 Obsoleted FM-08 IFuel Movement Sheet 7 11/17/2011 Minor Editorial 11-1

Number +/-Name Rev R~evisionDate ~ Notes FM-16 . Primary-Pool Coolant Water Analysis 16 3/15/2011 Minor Editorial FM-18 Deviation From Procedure Report 15 11/17/2011 Minor Editorial FM-20 FM:20 IWaste Tank Sample Report IWaste Tank Sample Report 9 4/14/2011 Minor Editorial

]o0{ 6/14/2011 Minor Editorial FM-21 ARMS Trip Setpoints . 7 f 7/26/2011 Cover Page F .. ARMS Trip Setpoints 181 11/17/2011* Minor Editorial FM-43 Nuclear and Process Data 141 7/26/2011 Cover Page FM-43 . Nucear and Process Data ... 5 11/17/2011 Minor Editorial FM-55 Startup Nuclear Data 5 J 3/31/2011 Cover Page FM-55 IStartup Nuclear Data 6 11/17/2011 Cover Page FM-56 Reactor Routine Patrol 1141 3/31/2011 . Cover Page FM-57 Long Form Startup Checksheet 17 11/17/2011 Cover Page FM-58 Short Form Startup Checksheet 191 11/17/2011 Cover Page FM-64 DI Resin Log .5 9/9/2011 Cover Page FM-65 IFilter Status Log 5 9/9/2011 Cover Page FM-71 IPneumatic Tube User Approval .. 3 6/14/201 Cover Page FM-93 iPost-Maintenance Valve Lineup Checksheet 41 7/26/2011 Cover Page FM-.152 Fuel Element Inspection 2 12/9/2011 1 Cover Page .

OA- I AFacility Exhaust Fans EF-13 and EF-14, EF-3 61 12/9/2011 6R12/9/201 M Minor Editorial d

0A2O- iRunning ......

Facility Exhaust Fans EF-13 and EF-141 EF-14 .... 6 292 1 12/9/2011 io Editorial Minor dtra OA-3 . Beamport and Pool Overflow Loop Seals 6 2/18/2011 J Minor Editorial OA-3 Beamport and Pool Overflow Loop Seals 7 11/17/2011 Cover Page OA-4 Valve Operation Air Compressor 5 11/17/2011 Cover Page OA-5 Emergency Air Compressor 5 11/17/2011 Cover Page OA-7 fReceiving Bulk Chemicals 41 9/9/2011 Cover Page OP-RO- 100 ]Main Air System . 8 3/31/2011 .Cover Page OP-RO-101 ]instrument Air System . 18 3/31/2011 Cover Page OP-RO-21 0 Reactor Startup-Normal . 11 6/14/2011 Minor Editorial OP-RO-211 fReactor Startup - Hot 19 7/26/201 ! . Cover Page OP-RO-212 Reactor Startup - Recovery from Temporary Power 9 11/17/20

• Pa ORP -2 2 iR ed u ction 9 1 /1 / 0 1C o ver P ag e OP-RO-220 ]Reactor Shutdown or Power Reduction 6 1 7/26/2011 Cover Page OP-RO-230 Changing Reactor Power Level 1 6 1 7/26/2011 Cover Page OP-RO-250 In-Pool Fuel Handling 141 9/9/2011 Minor Editorial OP-RO-250 In-Pool Fuel Handling 15 11/17/2011 Minor Editorial OP-RO-310 ]Nuclear Instrumentation - Signal Processor #1 181 6/14/2011 Minor Editorial OP-RO-311 'Nuclear Instrumentation - Signal Processor #2 91 6/14/2011 ] Minor Editorial OP-RO-312 Nuclear Instrumentation 61 Power Range Monitor - ICane 6/14/2011 Minor Editorial OP-RO-330 ]Nuclear Instrumentation - Wide Range Monitor 18 7/11/2011 Minor Editorial OP-RO-340 iNuclear Instrument Adjustment 88. . 6/14/2011 1 Minor Editorial RReactor Power Calculator Flow Potentiometer OP-RO-350 Adjustment5 9/9/2011 Cover Page OP-RO-4 10 jPrimary Coolant System 1 3/15/2011 Minor Editorial 11-2

Numnber- ...........

~Namne =Rev. Revision Date NoteN .....'i OP-RO-420 IPrimary and Pool Water Analysis 5 10/13/2011 Minor Editorial j OP-RO-460 IPool Coolant System - Two Pump Operation 13 8/12/2011 Minor Editorial OP-RO-461 IPool Coolant System - One Pump Operation 11 2/7/2011 Minor Editorial OP-RO-461 Pool Coolant System - One Pump Operation 12 J 8/12/2011 Minor Editorial OP-RO-465 iPool Level Control - Skimmer System 171 6/14/2011 Minor Editorial OP-RO-466 iPool Level Control - Pool Coolant System 1101 6/14/2011 Minor Editoria!

OP-RO-480 ]Secondary Coolant System 14 1 7/11/2011 Minor Editorial OP-RO-5l10 Nitrogen System .6 6/14/2011 Minor Editorial OP-RO-515 lEmergency Air System 1 7 11/17/2011 Minor Editorial OP-RO-516 lValve Operation Air System 18 9/9/2011 Minor Editorial j OP-RO-520 lEmergency Diesel Generator ]9 11/17/2011 Minor Editorial J OP-RO-525 IChill Water System 4 6/14/2011 Minor Editorial OP-RO-525 JChill Water System 5 7/11/2011 Minor Editorial OP-RO-530 jDemineralized Water Supply System I!1 9/9/2011 Minor Editorial OP-RO-531 lPrimary and Pool Sample Station 9 7/26/2011 J Minor Editorial OP-RO-532 iDrain Collection System 8 7/26/2011 J Minor Editorial OP-RO-533 ISkimmer System _ 61 10/13/2011 Minor Editorial OP-RO-710 Radiation Monitoring - Area Monitors 6 10/6/2011 . Minor Editorial**

]Radiation Monitoring Stack Monitor Operational 8 9 OP-RO-720 Check8 9/9/2011 Minor Editorial OP-RO-730 IFacility Exhaust System 13 6/14/2011 Cover Page OP-RO-741 iWaste Tank System Operation 1 11 6/14/2011 J Minor Editorial OP-RO-741 IWaste Tank System Operation 1121 11/17/2011 Minor Editorial REP-RO- 100 Reactor Emergency Procedures 12 2/17/2011 Cover Page REP-RO- 100 IReactor Emergency Proceduresj 13 7/6/2011 Minor Editorial RM-RO-400 jWaste Tank System Filter Replacement ]6 3/31/2011 Cover Page RM-RO-405 iReactor Demineralizer System 12 10/6/201 1 Minor Editorialj RM-RO-470 ISulfuric Acid System 161 3/31/2011 Minor Editorial RM-RO-470 'Sulfuric Acid System 7 9/9/2011 Minor Editorial RP-RO- 100 Fuel Movement 10 6/14/2011 Minor Editorial RP-RO-200

'Measurement of Differential Worth of a Shim Blade, RTP- 1 (D) 1 5 9/9/2011 Minor Editorial RMeasurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B) 4 9/9/2011 cover Page RMeasurement of Reactivity Worth of Movable 2 RP-RO-202 Samples, RTP-6 /14/2011 Cover Page RP-R 0-203 Measurement of Primary Coolant/Moderator 0 11 New P Temperature Coefficient of Reactivity, RTP- 19 7/26/201 Procedure RP-RO300 RP-RO-300 Fuel*2 Receipt, Inspection and Accounting of Unirradiated 2 6921 6/9/2011 io Editorial Minor dtra SM-RO-0 IIBeryllium Reflector Replacement 121 2/15/2011 Cover Page 1 SM-RO-200 jManual Operation of Airlock Doors 276 and 277 1 10/6/2011 Minor Editorial SM-RO-300 Control Console And Instrument Panel-Securing j9 9PowerOi 10/6/2011 Minor Editorial SMý-RO-420 tPressurizer Operation - Maintenance & Test ]4 9/15/2011 Minor Editorial SM-RO-620 iControl Blade Leak Test 4 12/9/2011 Cover Page 11-3

6Measuring Control Blade Pull Weight and Blade

_____-____-_ Drop Time with the Test Magnet Assembly, RTP-21 9/15/2011 Minor Editorial SM-RO-630 Removing and Reinstalling Reflector Elements in 1 7/5/2011 Minor Editorial SM-RO-635 the GH and No. 9 Positions Retracting and Reinserting Beamport'A' Liner 4 r 2/15/2011 Minor Editorial SM-RO-636 Retracting and Reinsertin* Beamport 'B' Liner 41 2/15/2011 j Minor Editorial SM-RO-637 Retracting and Reinserting Beamport'C'Liner 14 2/15/2011 Minor Editorial SM-RO-638 Retracting and Reinserting Beamport 'D' Liner 15s 2/15/2011 Minor Editorial SM-RO-639 ]Retracting and Reinserting Beamport 'V'Liner 4 1/31/2011 Minor Editorial SM-RO-640 Retracting and Reinserting Beamport 'F' Liner 5 7/5/2011 Minor Editorial SM-RO-650 Cleaning the Acid Day Tank Sight Glass ,1i 4/15/2011 Minor Editorial iPool Coolant Hold-Up Tank Welding Repair Cover Page SM-RO-661 12/9/2011 Instructions B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Emergency Plan Implementing Procedures and found them to be adequate. for the safe and reliable operation of the facility.

There were forty-five (45) revisions issued to the emergency procedures, forms and operator aids. The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures, forms and operator aids:

Numtber Name Reis a Del Nottesý EP-RO-001 Definitions ]i3. 5/25/2011 Cover Page EP-RO-002 Emergency Responsibilities 13] 5/25/2011 1 Cover Page EP-RO-003 *Emergency Preparedness Training 141 5/25/2011 Cover Page EP-RO-004 IFire ]s5 5/25/2011 Cover Page EP-RO-005 'Medical Emergency J2] 5/25/2011 Minor Editorial EP-RO-006 jRadiological Emergency 141 5/25/2011 Minor Editorial EP-RO-007 :jSevere Natural Phenomenon 1 1 4 5/25/2011 Cover Page EP-RO-008 ]Threat to Security ] 2 ] 5/25/2011 Cover Page EP-RO-009 jotification of Unusual Event J 2.J 5/25/2011 Cover Page EP-RO-O1O 'Alert ]2] 5/25/2011 Cover Page EP-RO-011 Site Area Emergency 2 5/25/2011 Cover Page EP-RO-012 IReactor Isolation . 31 5/25/2011 Cover Page EP-RO-013 lFacility Evacuation ]41 5/25/2011 Minor Editorial EP-RO-014 JEPZ and Site Area Evacuations 171 5/25/2011 Cover Page EP-RO-015 I Emergency Notifications 61 5/25/2011 Cover Page EP-RO-015 lEmergency Notifications 17 11/7/2011 Minor Editorial EP-RO-016 FPublic Infonnation 2 J 5/25/2011 Cover Page EP-RO-017 JEmergency Air Sampling 161 5/25/2011 Cover Page EP-RO-018 lEmergency Radiation Exposure 141 5/25/2011 1 Cover Page EP-RO-019 Emergency Dosimeters , 2 j 5/25/2011 ] Cover Page EP-RO-020 Emergency Equipment Maintenance 5j1 5/25/2011 Cover Page 11-4

Nun.b.. Nainc me Dat L < 'eRevision Notes FM- 100 Emergency Declaration 2 5/25/2011 Cover Page FM-101 .FEO Management 2 5/25/2011 Cover Page FM-102 .Emergency Event Log 121 5/25/2011 Cover Page FM-103 Facility Status . 2 1 5/25/2011 Cover Page FM-104 Emergency Call List 16 J 3/23/2011 Minor Editorial FM-i 04 Emergency Call List 17 5/25/2011 Cover Page FM-104 Emergency Call List 18 11/07/2011 Minor Editorial FM-l105 Initial/Follow-Up Emergency Message 2 5/25/2011 Cover Page

.FM-106 ]Log of Personnel Released From Site .2 5/25/2011

• CoverPage FM-I 10 IFire Flowchart 3 5/25/2011 Cover Page SFM-Il 1 Medical Flowchart 2 5/25/2011 Cover Page FM- 112 ]Radiological Flowchart 2 5/25/2011 1 Cover Page FM-I13 Severe Natural Phenomenon Flowchart 21 5/25/2011 Cover Page

=FM- 114 Security Flowchart 1 2 5/25/2011 Cover Page FM- 115 :Plant Conditions Flowchart 12 5/25/2011 . Cover Page FM-I 16 Classification Flowchart 2 5/25/2011 1 Cover Page FM-I17 ;Reactor Isolation Flowchart 1 2 5/25/2011 Cover Page FM- 118 jEvacuation Flowchart 14 5/25/2011 Cover Page O.

OA-09 ICombined Emergency Flowcharts 44 5/25/2011 Cover Page OA-10 IFire Extinguisher Locations and Types 6 5/25/2011 Cover Page OA-10 JFire Extinguisher Locations and Types 7 10/12/2011 Minor Editorial OA-20 'Emergency Equipment 1 9 I 5/25/2011 Cover Page

• OA-20 :Emergency Equipment 10 7/21/2011 1 Minor Editorial OA-20 Emergency Equipment ll 10/12/2011 1 Minor Editorial C. CHANGES TO HEALTH PHYSICS PROCEDURES, BYPRODUCT MATERIAL SHIPPING PROCEDURES, and .PREPARATION OF BYPRODUCT MATERIAL FOR SHIPPING PROCEDURES As required by the MURR Technical Specifications, the Reactor Healih Physics Manager reviewed the procedures for radioactive materials handling, shipping, and preparation for shipping of byproduct materials.

There were eighty-five (85) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. Additionally, two (2) new forms and two (2) new procedures were issued, and two (2) outdated procedures were obsoleted. The majority of the revisions were strictly format or editorial in nature.

The following is a list of the revised procedures and forms:

Number ~Namne - -kv uiinDate lNutes MURR Initial Radiation Worker Training AP-HP-1 17 10 1/11/2011 Minor Editorial

___________Program_______________

AP-HP-! 19.Hot Cell, HC-0I Control 17 4/27/2011 Minor Editorial*

AP-HP- 119 Hot Cell, H-C-01 Control 8 12/9/2011 Minor Editorial.

AP-SH-001 Administrative Procedure, Radioactive Materials 7T 3/11/2011 Cover Page IShipping 3 AP-SH-002 In-House Radioactive ShpigRqetFrI Shipping Request Fom 10 5/18/201 1 New Procedure 11-5

Number Name Re, lRey isiqu Date Notes P20WC-1 Packaging and Shipment of Type B Non- 1 i

_ _BPB-SH-002 Waste Radioactive MaterialMinor Editorial_.......

BPB-SH- WastRadioactive Material MnrE t DOT 6M Packaging ffType B Non-Waste 5/18/2011 toria i" ]~Radioactive Mwaterial .

BPi -2 Receipt Inspection of Type B Byproduct Material 2 8 BPB-SH-020 SipnCotnes2I 8/11/2011* Minor Editorial

____________Shipping ContainersI _______ _________

BPB-SH-021 20 WC- I All-Thread Rod Replacement 2 9/29/2011 Minor Editorial BPB-SH-022 Painting USA DOT 20 WC-1 Overpack 2 8/11/2011 Minor Editorial BType B(U) F-327 Series Packaging of Type B I I i BPB-SH-024 Nbn-W aste Radioactive M aterial ~ 9/29/2011

.. 1~nWseRdocieMtra jMinor Editorial BPB-SH-0260 Type B(U) ZAiNNR1005 (Beatrice) Packaging of6/7/2011 6721 ulRve Full Review

___ _ Type B Non-Waste Radioactive Material F-327 Packaging and Shipment of Type A BP-SH-007 Radioactive Material 7 4/6/2011 Obsoleted BP-SH-010 Packaging Radioactiveand Shipment Materials of Non-Waste in Excepted Packages .... 12/5/2011 Shipment of Non-Waste USA DOT 7A Type A 5 12/5/2011 Minor Editorial BP-SH-0 55-Gallon Radioactive Material Package BP-SH-012 DOT-7A Package Certification 5 4/6/2011 Cover Page BP-SH-0 1.3 Packaging and Shipment of Radioactive Materials 3/24/2011 Page Using MURR Reusable Type A Package Packaging and Shipment of Radioactive Material U

I _4/0 4/6/2011

_M oEti Minor Editorial BP-SH-014 Using an Overpack BP-SH-015 Packaging and Shipment of Radioactive Material using a USA DOT 7A Model 30 I _ _ i _ _ _

iBP-SH-016 'Packaging and Shipment of Radioactive Material 22 9/16/2011 Cover Page

I using a USA DOT 7A Model H or I Package BP-SH-052

~Radioactive R7 Material Shipment Package 74/22/2011 Minor Editorial Documentation and Labeling BP-SH-302 Packaging and Shipment of Radioactive Material Using MURR Models 6 and 12 I6/ Minor Editorial FM-09 Gemstone Irradiation Sheet 5-1 12/22/2011 Cover Page FM-10 MURR Sample Log 4 12/22/2011 Cover Page J FM-I12 Gemstone Loading Sheet 5 12/22/2011 Cover Page FM-13 Receipt of Radioactive Material 6 1/14/2011 Minor Editorial J FM-17 IRadiation Work Permit 9 11/23/2010 Cover Page FM-27 . in-House Radioactive Shipping Request Form 19 5/18/2011 Minor Editorial

...M-35 iControl Checksheet for Type B USA DOT 20WC- 9 I- Radioactive Materials Shipment 14 9/16/2011 CoverPage FControl Checksheet for Type B USA DOT 20WC- 1 1 FM-35 11aiatveMtras5hpetI I

Radioactive Materials Shipment 12/5/2011 Minor Editorial Control Checksheet for Documentation and FM-52 8 2/17/2011 Minor Editorial Labeling of Radioactive Material Shipment Control Checksheet for Documentation and FM-52 9 4/22/2011 Minor Editorial Labeling of Radioactive Material Shipment FM-60 FControl Check Sheet for MURR Shipment Using JUSA DOT 7A Model 30 12 19/16/2011 Cover Page S

FM-60 Control Check Sheet for MURR Shipment Using FM-60 .JUSA DOT 7A Model 30 3 12/5/2011 Minor Editorial 11-6

Numiber Namv . Rev. Rev'ision Date Notes FM-62 . Radiation insitument Certification of Calibration . 6 6/22/2011 Minor Editorial iReceipt of Radioactive Gemstone Shipping I FM-67 IContainers 6 5/11/2011 Cover Page Control Checksheet for MURR Reusable Type A I2oI FM-69 Radioactive Materials Shipment

• FM-74 !Control Checksheet for Type B USA DOT 6M I 13 9/16/2011 Cover Page F 74 Radioactive Materials Shipment FM-94

• Exclusive Use Shipment Controls 3 4/6/2011 Cover Page FM-98 U Checksheet for MURR Shipment Using DControl 6 9/16/2011 Cover FM-99 M DOT USA l s 7AS MURR Model 6 o 10 2* 9/15/2011 Cover Page FM-99 Control Checksheet Model 1500 Series. for USA DOT 7A MURR 12/5/20t I _CoverPage__

FM- 107 Control Check Sheet for Overpack Shipment 4 1/31/2011 Cover Page FM-107 Control Check Sheet for Overpack Shipment 5 4/6/2011 Cover Page FM-120 Individual Type B QA Training Certification 3/11/2011 Cover Page Documentation of Compliance for DOT-7A FM- 126 Shipping Container4/6/2011 Cover Page 1Control Check Sheet For MIURR Shipment Using II FM-128 IUSA DOT 7A MURR Model H or II 2 9/16/2011 CoverPage Control Checksheet for Receipt Inspection of 2 Type B Byproduct Material Shipping Containers __12/5/2011 MinorEditorial FM- 150 Statement of Training and Experience J3 12/29/2011 Minor Editorial FM-S 15 Control Checksheet for Non-Waste USA DOT 7A 6 /31/2011 Cover Page Type A 55-Gallon Radioactive Material Package FM- 151 Control Checksheet for Non-Waste USA DOT 7A 7 12/5/2011 Cover Page, Type A 55-Gallon Radioactive Material Package *__

FControl Checksheet for USA DOT 20 WC-1 Minor Overpack Rod Replacement 1 Required Documentation for Non-MURR Owned / 1r Type B Shipping Containers 1 FM-15;7 Control Checksheet for Type B(U) F-458 Series Radioactive Materials Shipment Radioactive Materials Shipment 11 1 2/11/2011 iMinor Editorial Control Checksheet for Health Physics Review of 4/22/2011 Full Review FM-159 Radioactive Materials Shipment Documentation MaterialsforShipment Control Checksheet Radioactive Health Physics Review of Documentation J6J1i 6 Minor Editorial FM-160 jControl Checksheet for Type B(U) F-327 Series Jo 6/7/201i 1 FullReview Radioactive M aterials Shipment ...... ........

HC-PS-002 HC-PSO-002 Shipment.......

Ht Cell Preparatin of Radioactive Material for 10 12/15/2011 Minor Editorial HC-PSO-005 Hot Cell Loading of Host Cans 81 1/7/2011 1 Minor Editorial

! IC-P-310 Calibration- Eberline Ping Ia Stack Monitor-Particulate Channel IC-HP-3 10 ~ l hne 6 10/6/201 1 Minor Editorial i 1C-P-311 Calibration - Eberline Ping Ia Stack Monitor -

Iodine Channel 1C-HP-311 IdieCane 6 10/6/2011 Minor Editorial ICCalibration IC-HP-312 I Gas Channel

- Eberline Ping Ia Stack Monitor - 66 10/6/2011 10/6/2011 iMinor Editorial Editorial Calibration - Canberra S5XLB-G & Tennelec 12/9/2011 Minor Editorial IC-HP-348 Series 4 with Gamma, & Tennelec Series 3 5 11-7

Nuniber Ic-HP-49 Calibration Channel Name Lab Impex Stack Monitor-Particulate 2 12/9/2011 Rev. lRevision Date1 oe Minor Editorial Calibration - Lab Impex Stack Monitor Iodine IC-HP-350 Channel 12/9/2011 Minor Editorial IC-HP-351 ICalibration - Lab lImpex Stack Monitor - Gas Channel r 1 12/9/2011 Minor Editorial

-Calibration-

'-------- Lab Impex Stack Monitor- .

IC-HP-352 1Particulate Channel 17 12/9/2011 Minor Editorial IC-HP-353 Calibration -Lab Impex Monitor- DP2001 01 2/24/2011 Full Review IRR-PSO-l 12 Preparing Shipping Paperwork 5 8/16/2011 Cover Page OP-HP-200 .Air Sampling - Containment Building Tritium 4 3/16/2011 Cover Page OP-HP-220 OPHP-222 ..........

Tritium. Bioassay Air Sampling - Containment Building Ar-41 .

1 17 5

5/19/2011 3*1* 201 Minor Editorial Cover Pe1 OP-HP-227 Tennelec LB-5 100 Alpha/Beta - Operation I 4 6/22/2011 Obsoleted OP-HP-353 OP-H-356 Waste Tank Sample - Analysis Operation - Lab Impex Stack Monitor - Filter Change and Source Checks I 7

.6/24/2011 6/22/2011 Minor Editorial Minor Editorial POL-03 Radiation Protection Program 10 1/7/2011 Minor Editorial POL-03 . Radiation Protection Program 11 10/10/2011 Minor Editorial QAB-SH-002 jProcurement of Type B Packages 1 2/11/20 11 **Cover Page QAB-SH-003 Material Control for Type B Shipping Program 1 2/11/2011 Cover Page

.QAB-SH-003 Material Control for Type B Shipping Program 1 2 9/29/2011 1 Minor Editorial QAB-SH-004 Type B Program Vendor Qualification 1. 2/11/2011 Cover Page QAB-SH-005 JType B QA Personnel Training 2 12/5/2011 Minor Editorial RP-HP-105 jTransfer of Radioactive Material - In Facility. 6 3/16/2011 Cover Page RP-HP- -110 0I.1. Survey and Decontamination of Returned 5 4/27/2011 Cover Page Shipping Container S1-PS

-008 Post-Irradiation Silicon C ans Processing: Exported Flooded

........................ 177 5/12/2011 Cover Page SV-HP-1 19 Property Release 5 6/24/20111 Minor Editorial TPZ-PSO-00 I Receiving Gemstone Irradiation Shipping Drums 161 4/14/2011 Cover Page TPZ-PSO-002 Irradiation of Gemstone Irradiation Containers 151 4/14/2011 Cover Page. J TPX-PSO-003 Loading Gemstone Shipping Drums.4 4/14/2011 Cover Page WM-SH-100 jRadioactive Waste - Preparation and Storage 16 12/5/2011 Cover Page WM-SH-1105 lRadioactive Waste Processing T7 12/5/2011 1 *MinorEditorial Exclusive RadioactiveUse Shipment of LSA or SCO Waste 9 12/5/2011 Cover Page 11-8

SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT January 1,2011 through December 31, 2011 These changes were approved by the Reactor Manager and reviewed by licensed staff and members of the Reactor Safety Subcommittee and have been determined not to involve a change to the Technical Specifications. These changes have all been reviewed in accordance with 10 CFR 50.59.

HAZARDS

SUMMARY

REPORT (ORIGINAL JULY 1, 1965)

Original HSR, Section 7.2.9, Table 7.2, page 7-21 (as revised by the 1.995, 2001, 2007 and 2009 Reactor Operations Annual Reports):

Add: The following after "Room 2041":

"Room 2046 Room 2047A Room 2048" Add: The following after "Room 103":

"Room 110" Add: The following after "Room 267A":

"Room 269" Original HSR, Figure 5.1, Piping & Instrument Diagram (as revised by the 1972-73, 1973-74, 1994, 1996, 2001, 2002, 2003, 2004, 2006, 2007, 2009 and 2010 Reactor Operations Annual Reports):

Replace with: Updated Figure 5.1, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet I of 1; dated 7/1/11)

ADDENDUM 3 - HAZARDS

SUMMARY

REPORT (AUGUST 1972)

HSR, Addendum 3, Figure 2.3.a, page 23a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009 and 2010 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet I of 5, dated 10/6/11)

HSR, Addendum 3, Figure 2.3.b, page 23b, Electrical Distribution (as added by the 1995 and revised by the 2001, 2002, 2003, 2004, 2005, 2007, 2009 and 2010 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.b, Electrical Distribution North Office Addition (MURR Dwg No. 522, Sheet 2 of 5, dated 6/28/11) 1II-1

HSR, Addendum 3, Figure 2.3.c, page 23c, Electrical Distribution (as added by the 2004 and revised by the 2005, 2007, 2009 and 2010 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.c, Electrical Distribution Reactor/Laboratory Panels (MURR Dwg No. 522, Sheet 3of 5, dated 11/16/11)

HSR, Addendum 3, Figure 2.3.d, page 23d, Electrical Distribution (as added by the 2007 and revised by the 2008, 2009 and 2010 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.d, Electrical Distribution Reactor/Laboratory Panels-2 (MURR Dwg No. 522, Sheet 4 of 5, dated 12/1/10)

HSR, Addendum 3, Figure 2.3.e, page 23e, Electrical Distribution (as added by the 2007 and revised by the 2009 and 2010 Reactor Operations Annual Report):

Replace with: Updated Figure 2.3.e, Electrical Distribution North Office Addition Panels (MURR Dwg No. 522, Sheet 5 of 5, dated 6/28/1l)

ADDENDUM 4 - HAZARDS

SUMMARY

REPORT (OCTOBER 1973)

HSR, Addendum 4, Figure A.2, page A-20, Piping & Instrument Diagram (as revised by the 1995, 2001, 2002, 2003, 2004, 2006, 2007, and 2009 Reactor Operations Annual Reports):

Replace with: Updated Figure A.2, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet 1 of 1, dated 7/1/!11)

HSR, Addendum 4, Figure A.11, page A-29, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (as revised by the 1995, 2002, 2005, 2009 and 2010 Reactor Operations Annual Reports):

Replace with: Updated Figure A. 11, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (MURR Dwg No. 1125, Sheet I of 4, dated 9/11/ l)

ADDENDUM 5 - HAZARDS

SUMMARY

REPORT (JANUARY 1974)

HSR, Addendum 5, Figure 2.1, page 15, Electrical Distribution (as revised by the 1989-90, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009 and 2010 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet I of 5, dated 10/6/1I) 111-2

SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1,2011 through December 31, 2011 For each facility modification described below, the MURR has on file the safety screen or evaluation, as well as the documentation of review, performed in accordance with .10 CFR 50.59.

Modification 01-2, Addendum 5:

Intercommunication and Paging System Changes in Support of the North Office Addition Lab Space This addendum to modification record .01-2, "Installation of.a New Reactor Facility Intercommunication and Paging System," documents changes to the facility intercommunication and paging system that were necessary in order to safely occupy the new laboratory space in the North Office Addition (NOA). To ensure a prompt and effective response from facility staff to an emergency or abnormal condition, the intercommunication and paging system was extended into the NOA laboratory space.

Modification 01-2, Addendum 6:

Intercommunication and Pagini System Changes in Support of the North Office Addition Classroom Space, Laboratory Break Room and Laboratory Basement This addendum to modification record 01-2, "Installation of a New Reactor Facility Intercommunication and Paging System," documents changes to the facility intercommunication and paging system that were necessary in order to safely occupy thenew classroom space in the North Office Addition (NOA) and provide additional coverage within NOA. To ensure a prompt and effective response from facility staff to an emergency or abnormal condition, the intercommunication and paging system was extended into the NOA classroom space, NOA break room and NOA basement.

Modification 09-04:

Cooling Tower Temporary Cooling This modification record documents the changes to the Secondary Coolant and Normal Electrical Power Systems to allow connection of temporary cooling to the existing system. The existing cooling towers cells were approaching the end of their operational lifetime due to the degrading integrity of wooden structure members as well as steel fan support members. The planned replacement of these cells required several weeks to complete. To ensure continued reactor operation at 10 MW for the duration of the maintenance, rental cooling towers were connected to provide a means of cooling the Secondary Coolant System.

IV- I

SECTION V NEW TESTS AND EXPERIMENTS January 1,2011 through December 31, 2011 New tests or experiments approved during this period under a Reactor Utilization Request (RUR) or Reactor License (RL) Project are as follows:

RUR 219, asamended: Irradiations

Description:

This RUR authorizes an unrestricted fluence on the irradiation of silicon.

Silicon spacer material has been irradiated for long periods of time without complications.

RUR 231, as amended: Produce Semiconductor Materials

Description:

This RUR authorizes an unrestricted fluence on the irradiation of silicon.

Silicon spacer material has been irradiated for long periods of time without complications.

RUR 439: Molybdenum (Mo)

Description:

This RUR authorizes the irradiation of up to 480.0 grams of molybdenum, natural or enriched up to 95% in the isotope Mo-98, in support of research and development activities.

Each of these tests or experiments has a written safety evaluation on file, and a 10 CFR 50.59 Screen if applicable, to assure that the test or experiment is safe and within the limits of the Technical Specifications.

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-I

SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2011 through December 31, 2011 Inspections:

There was one NRC inspection reviewing SNM activities. All records and activities were found to be in compliance with NRC rules and regulations. No violations were noted.

Reactor Characteristic Measurements:

Sixty-two (62) refueling evolutions were completed in 2011. Excess reactivity verifications were performed for each refueling. The largest measured excess reactivity value was 3.68%. MURR Technical Specification 3.1 (f) requires excess reactivity to be less than 9.8%.

Reactivity Measurements:

Differential blade-worth measurements of six (6) shim control blades were performed following either a planned replacement of a control blade or characterization of the bum-in effect of a new control blade.

Five (5) reactivity measurements were performed to determine the reactivity worth of all the samples, including the sample holder, loaded in the flux trap region.

Four (4) reactivity measurements were performed to determine the reactivity worth of various sample cans irradiated in the flux trap region, including the worth of an empty sample holder.

In support of the Nuclear Engineering student labs, two (2) differential blade-worth measurements and two (2) primary coolant temperature coefficient measurements were also performed.

VI- I

SECTION VII RADIOACTIVE EFFLUENT January 1, 2011 through December 31,2011 TABLE I SANITARY SEWEREFFLUENT January 1, 2011 through December 31, 2011 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide Activity (Ci)

H-3 9.802E-02 S-35 2.482E-02 Lu- 177 9.168E-03 P-32 5.175E-03.

Co-60 2.589E-03 Zn-65 7.669E-04 Ca-45 6.199E-04 Sc-46 1.348E-04 Re- 188 6.633E-05 Sb- 124 6.141 E-05 Mn-54 3.182E-05 Na-22 3.059E-05 1-131 3.045E-05 Ag-I 10m 2.323E-05 Co-57 1.237E-05 Total H-3 9.802E-02 Total Other 4.353E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."

VII- I

TABLE 2 STACK EFFLUENT January 1, 2011 through.December 31, 2011 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration Total Release (PCi/ml) (Ci) TS Limit Multiplier  % TS Ar-41 1.58E-06 7.97E+02 350 45.1400 C- 14 1.43E- 11 6.80E-03 1 0.4770 1-131 1.0 IE- 13 5.12E-05 1 0.0506 H-3 1.74E-08 8.80E+00 350 0.0496 Cs-137 2.39E-15 1.21E-06 1 0.0012 Zn-65 3.54E-15 1.79E-06 1 0.0009 Os191 1.55E-14 7.85E-06 1 0.0008 Zr-95 2.08E- 15 1.06E-06 1 0.0005 Pa-233 2.59E-15 1.3 1E-06 1 0.0003 Cu-67 5.41E- 12 2.74E-03 350 0.0003

• Co-58 2.42E- 15 1.22E-06 1 0.0002 S-35 5.96E-15 3.02E-06 1 0.0002 Hf-175 1.18E-15 5.99E-07 1 0.0001 1-133 2.09E- 13 1.06E-04 350 0.0001 Note: C-14 activity is calculated based on the ratio of argon to nitrogen in the air and the (n,p) reaction cross sections for the activation of N-14 to C-14.

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

Stack Flow Rate -34,000 cfm Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, License R-103 Technical Specifications.

VII-2

SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2011 through December 31, 2011 Environmental. samples are collected two times per year at eight (8) locations and analyzed for radioactivity. Soil and. vegetation samples are taken at each location. Water samples are taken at three (3) of the eight (8) locations.

Analytical results are shown in Tables I and 2.

Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2011. All doses are approximately'16 mRem/year or less, except monitor numbers 9 and 15. These monitors are located near loading dock areas .where packages containing radioactive material are loaded on transport :vehicles. The doses recorded by these monitors are considered to be the result of exposure to packages in transit. The environmental monitoring program confirms that no 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 I Summary of Environmental Set 79 Spring 2011 Detection Limits' Matrix Alpha Beta Gamma Tritium Water 0.73 pCi/L 3.26 pCi/L 200.40 pCi/L 3.89 pCi/mL of sample Soil 0.00 pCi/g 2.78 pCi/g 0.52 pCi/g N/A Vegetation 1.01 pCi/g 5.01 pCi/g 1.42 pCi/g 3.74 pCi/mL of distillate Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL) 1V79 < 1.01 19.71 < 1.42 < 3.74 2V79 < 1.01 21.65 <1.42 < 3.74 3V79 < 1.01 12.33 < 1.42 < 3.74 4V79 < 1.01 18.19 S< 1.42 < 3.74 5V79 < 1.01 23.86 < 1.42 < 3.74 6V79" < 1.01 21.13 < 1.42 < 3.74 7V79 *1.10 17.13 < 1.42 < 3.74 10V79 < 1.01 22.94 < 1.42 < 3.74 VIlI-1

TABLE I (Cont'd)

.Summary of Environmental Set 79 Spring 2011 Activity Levels - Soil Sample Alpha (pCi/g) *Beta (VC i/g) Gamma (pCi/g)

.1S79 0.63 12.37 2.19 2S79 0.30 11.12 2.88 3S79 0.00 10.10 1.92 4S79 0.65 12.25 13.61 5S79 2.21 15.70 3.06 6S79 1.25 12.97 2.25 7S79 1.06 8.94 1.96 10S79 1.41 .13.37 2.91 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W79 < 0.73 < 3.26 < 200.40 < 3.89 6W79 < 0.73 < 3.26 < 200.40 < 3.89 10W79 < 0.73 3.27 < 200.40 < 3.89 Note 1: Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.

HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity.

TABLE 2 Summary of Environmental Set 80 Fall 2011 Detection Limits' Matrix Alpha Beta Gamma Tritium Water 1.03 pCi/L 2.98 pCi/L 207.40 pCi/L 6.03 pCi/mL of sample Soil 0.00 pCi/g 3.08 pCi/g 0.60 pCi/g N/A Vegetation 1.32 pCi/g 6.14 pCi/g 1.63 pCi/g 5.70 pCi/mL of distillate VIII-2

TABLE 2 (Cont'd)

Summary of Environmental Set 80 Fall 2011 Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL) 1V80 < 1.32 16.37 < 1.63 < 5.70 2V80 < 1.32 14.06 3.34 23.88 3V80 < 1.32 <6.14 5.57 < 5.70 4V80 < 1.32 20.79 4.04 < 5.70 5V80 < 1.32 19.80 19.36 < 5.70 6V80 < 1.32 6.66 17.62 28.09 7V80 < 1.32 16.57 12.27 <5.70 10V80 < 1.32 30.55 4.24 < 5.70 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1S80 1.37 .11.92 3.60 2S80 1.24 9.71 3.16 3S80 0.77 10.39 2.22 4S80 0.63 6.44 3.49 5S80 1.24 14.90 3.53

.6S80 1.55 9.12 3.80 7S80 0.92 55.63 3.86 10S80 1.70 10.69 3.22 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W80 < 1.03 5.64 < 207.40 < 6.03 6W80 < 1.03 3.37 < 207.40 < 6.03 1OW80 < 1.03 10.69 < 207.40 < 6.03 Note 1: Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights, HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity.

VIII-3

TABLE 3 Environmental TLD Summary January 1, 2011 through December 31, 2011 Badge Direction Map Distance from Ist Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total Number From MURR MURR Stack 2011 2011 2011 2011 2011 (meters) Net mR Net mR Net mR Net mR Net mR Control 0 N/A 32.0 30.0 22.0 28.0 112.0 I Control 1 16600 28.0 25.0 25.0 28.0 .106.0 2 Control 2 16600 24.0 25.0 24.0 30.0 103.0 3 WSW N/A 0.0 0.0 0.0 1.3 1.3 4*

5*

6 N 34 0.0 0.0 0.2 5.3 5.5 7 NE 57 0.0 0.0 0.0 1.3 1.3 8 SW 27 4.3 2.3 3.3 6.3 16.0 9 S 27 21.3 27.3 11.3 20.3 80.0 10 NE 149 0.0 0.0 0.0 0.0 0.0 I1 NW 149 2.3 0.0 0.2 0.2 2.7 12 ENE 301 0.0 0.0 2.3 7.3 9.5 13 NNE 316 1.3 0.0 0.0 0.0 1.3 14 S 156 0.0 0.0 1.3 4.3 5.5 15 S 65 13.3 13.3 11.3 19.3 57.0 16 SE 107 0.0 0.0 0.0 0.0 0.0 17 E 293 0.0 0.0 0.0 0.0 0.0

18. NE 476 0.0 0.0 0.0 0.0 0.0 19 NNE 606 0.0 0.0 0.0 0.0 0.0 20 NE 907 0.0 0.0 0.0 0.0 0.0 21 SE 236 0.0 0.0 0.2 1.3 1.5 22 ESE 168 0.0 0.0 0.0 0.0 0.0 23 NW 110 0.0 0.0 0.0 2.3 2:3 24 SSW 328 0.0 0.0 0.0 0.2 0.2 25 SSW 480 0.0 0.0 0.2 1.3 1.5 26 SW 301 .0.0 0.0 0.0 0.0 0.0 27 WSW 141 0.0 0.0 0.0 0.0 0.0 28 WNW 210 0.0 0.0 0.0 1.3 1.3

.29 NW 255 0.0 0.0 0.0 5.3 5.3 30 NNW 328 0.2 0.0 0.0 0.0 0.2 31 NNW 671 0.2 0.0 0.2 0.2 0.7 32 NNW 724 0.0 0.0 0.0 0.0 0.0 33 E 671 0.0 0.0 0.0 0.0 0.0 34 ENE 587 0.0 0.0 0.0 0.0 0.0 35 SSE 499 0.0 absent 0.2 5.3 5.5 36 SE 419 0.0 0.0 0.0 0.0 0.0 37 NE 690 0.0 0.0 0.0 0.0 0.0 38 NW 556 0.0 0.0 0.0 2.3 2.3 39 W .491 0.0 0.0 0.0 0.0 0.0 40 N 541 0.0 0.0 0.0 0.0 0.0 41 NNE 137 0.0 0.0 0.0 0.2 0.2 42*

43*

44 Spare N/A 0.0 0.0 0.0 4.3 4.3 45 S 65 0.0 0.0 0.0 0.2 0.2 46 E 70 4.3 0.2 0 4.3 8.7

• These badge numbers are no longer used..

VIII-4

TABLE 4 Number of Facility Radiation and Contamination Surveys January 1, 2011 through December 31, 2011 Radiation Surface Contamination* Air Samples"* RWP's January 67 67 45 8 February 75 75 54 2 March 115 115 71 9 April 53 53 62 10 May 78 78 62 8 June 74 74 54 5 82 53 7 July 82 August 37 37 58 8 September 79 79 56 12 October 81 81 51 5 November, 58 58 46 5 December 64 64 54 8 TOTALS 863 863 666 87

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

• • Air samples include exhaust stack Ar-41, containment building Ar-41, sump entries, and hot cell entries.

Miscellaneous Notes Nathan Hogue was promoted to Health Physicist in August 2011.

Jason Mitchell and Dan Nickolaus were promoted to Health Physics Technician II in October 2011.

During calendar year 2011, MURR shipped 711.3 cubic feet of low-level radioactive waste containing 5,503 mCi of activity.

VIII-5

SECTION IX Summary of Radiation Exposure to Facility Staff, Experimenters and Visitors January 1, 2011 through December 31, 2011 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP AC BCS DO FOE HC/SH HP IRR NA NS OPS PRO QA RES RP. SIL TEE WC Total January 88 N/A 203 256 455 283 40 147 120 1382 143 N/A 161 199 138 N/A N/A 3615 February 33 N/A 21 74 559 362 9 44 23 1024 103 N/A 71 88 94 N/A N/A 2505 March 14 N/A 41 89 435 262 10 1.9 21 1298 118 N/A 56 109 162 N/A N/A 2634 April 30 N/A 7 132 258 164 9 21 24 1070 125 N/A 13 82 117 N/A N/A 2052 May 39 N/A 121 168 227 382 17 80 116 1162 108 N/A 172 224 122 N/A N/A 2938 June 64 N/A 68 126 329 598 27 133 139 1246 252 N/A 199 233 188 N/A N/A 3602 July 53 56 20 41 431 203 16 101 154 1403 290 82 266 114 177 N/A 87 3494 August 47 3 2 12 442 179 6 39 82 1852 239 44 512 36 165 N/A 106 3766 September 60 13 2 2 538 227 0 72 36 1361 213 66 132 27 131 N/A 103 2983 October 20 9 i0 13 245 200 9 30 72 1307 165 21 11 37 106 3 97 2355 November 68 34 0 13 252 212 3 8 79 1383. 141 57 24 97 154 27 112 2664 December 24 23 0 7 232 153 3 4 29 1567 95 42 21 70 126 18 101 2515 Total for Year 540 138 495 933 4403 3225 149 698 895 16055 1992 312 1638 1316 1680 48 606 35123 Monthly Avg 45 23 41 78 367 269 12 58 75 1338 166 52 137 110 140 16 101 2927 Highest WB 126 60 34 52 1253 1248 60 103 278 1010 536 183 212 199 579 94 305 (annual)

High EXT 1751 91 M 51 3209 1609 36 1430 574 2895 2887 668 260 1326 1208 742 2903 (annual)

AC - Analytical Chemistry BCS - Business & Central Services HP - Health Physics OPS - Operations RP - Radiopharmaceutical DO - Director's Office IRR - Irradiations PRO - Isotope Processing SIL - Silicon FOE - Shops & Support NA - Nuclear Analysis QA - Quality Assurance TEE - Trace Elemental Epidemiology HC/SH - Hot Cell-Shipping NS - Neutron Scattering RES - Research WC - Work Control WB = Whole Body EXT = Extremities M = Minimal Dosimetry services are provided by Mirion Technologies (except self reading dosimetry).

Analysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA.

Radiation workers who are not full time staff members have radiation exposures which are generally lower than full time radiation workers.

NOTES:

Due to splitting of groups, some annual WB and EXT numbers may reflect dose received prior to that person moving from one group to another.

BCS members were split off from the DO Group to better reflect their activities related to radiation exposure potential.

QA members were split off from the old Regulatory Assurance Group (now HP) to better reflect their job functions and radiation exposure potential.

TEE members were split off from the RES Group to better reflect their job functions and radiation exposure potential.

WC members were split off from the FO Group (now FOE) to better reflect their job functions and radiation exposure potential.