ML14063A044

University of Missouri Research Reactor 2013 Reactor Operations Annual Report

ML14063A044
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/27/2014
From:	Butler R A, Fruits J L Univ of Mississippi
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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UNIVERSITY of MISSOURIRESEARCH REACTOR CENTERFebruary 27, 2014U.S. Nuclear Regulatory Commission Attention:

Document Control DeskMail Station P1-37Washington, DC 20555-0001

SUBJECT:

Docket 50-186University of Missouri-Columbia Research ReactorAmended Facility License R-103University of Missouri Research Reactor2013 Reactor Operations Annual ReportEnclosed is a copy of the Reactor Operations Annual Report for the University Reactor.

The reporting period covers January 1, 2013 through December 31, 2013.This document is submitted to the U.S. Nuclear Regulatory Commission inUniversity of Missouri Research Reactor Technical Specification 6.1 .h(4).of Missouri Researchaccordance with theIf you have any questions regarding the contents of this report, please contact John Fruits at (573) 882-5319 or FruitsJ(d@missouri.edu.

S i n c e r e l y ,John L. FruitsReactor ManagerENDORSEMENT:

Reviewed and ApprovedRalph A. Butler, P.E.DirectorJLF/jlbEnclosure xc: Mr. Alexander Adams, U.S. NRCMr. Johnny Eads, U.S. NRC1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: http://web.missouri.edu/-murrwww Fighting Cancer with Tomorrow's Technology 4-UNIVERSITY OF MISSOURIa .1UNIVERSITY REACTOR'.-:.

REACTOR OPERATIONS-,;q

.,..:...'ANNUAL".;REPORT.-

Januhary 1, 2013 .- Dec'ember.31, 20"13j..]', '.* :.

UNIVERSITY OF MISSOURIRESEARCH REACTOR FACILITYREACTOR OPERATIONS ANNUAL REPORTJanuary 1, 2013 through December 31, 2013Compiled by the Research Reactor Staff of MURRSubmitted by:John L. FruitsReactor ManagerReviewed andapproved by:a/46<Ralph A. Butler, PEDirector UNIVERSITY OF MISSOURI

-COLUMBIARESEARCH REACTORREACTOR OPERATIONS ANNUAL REPORTJanuary 1,2013 through December 31, 2013INTRODUCTION 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 researchcommunity and the commercial sector. Scientific programs include research in archaeometry, epidemiology, health physics, human and animal nutrition, nuclear medicine, radiation

effects, radioisotope

studies, radiotherapy, boron neutron capture therapy and nuclear engineering; and research techniques including neutron activation

analysis, neutron and gamma-ray scattering and neutron interferometry.

Theheart 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 calendaryear 2013. Included within this report are changes to MURR reactor operations and health physicsprocedures, 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 theadministrative 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 manyindividuals 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 PoliceDepartment; the Missou'i University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our regulators; those who have provided funding including the Department of Energy (DOE), theNational Nuclear Security Administration (NNSA) 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 otherswho 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 yearincluded (1) implementing Amendment No. 36 to Amended Facility License No. R-103, which revised theSafety Limit Curves based on newer, more accurate power peaking factors developed using a 3-dimensional diffusion code, (2) replacement of the 30-degree graphite reflector elements

'GH' and IJ' witha single 60-degree graphite reflector element 'GHIJ,' and (3) irradiating and processing a 5-gram naturaluranium target to determine the feasibility of producing molybdenum-99 using a selective gaseousextraction process.

Additionally, in August 2006 MURR submitted a request to the NRC to renewi Amended Facility License No. R-103. Significant efforts have already been placed in responding to theRequests for Additional Information and these efforts continued in this past year.The facility continues to actively collaborate with the Reduced Enrichment for Research and Test Reactors(RERTR) Program and four other U.S. high-performance research reactor facilities that use highly-enriched uranium (HEU) fuel to find a suitable low-enriched uranium (LEU) fuel replacement.

Although each oneof 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 amongall five reactors that will benefit from a coordinated, working-group effort. This past year, resources werefocused on completing Phase 1 accident analyses for the LEU conversion core.MURR also hosted the 2013 Annual Test, Research and Training Reactors Conference.

The TRTRorganization represents research reactor facilities across the nation from government, major universities, national laboratories and industry.

TRTR's primary mission is education, fundamental and appliedresearch, application of technology in areas of national concern and improving U.S. technological competitiveness around the world. TRTR membership includes managers and directors of researchreactors, educators, administrators, regulators and research scientists and engineers.

Reactor Operations Management also wishes to commend the five individuals who received their ReactorOperator certifications and the four individuals who received their Senior Reactor Operator certifications from the NRC. These individuals participated in a rigorous training program of classroom

seminars, self-study and on-the-job training.

The results of this training are confident, well-versed, decisive individuals capable of performing the duties of a licensed operator during normal and abnormal situations.

ii TABLE OF CONTENTSSection Title PagesI. Reactor Operations Sum m ary ...............................................................

I-I through 9f]. M U RR Procedures

................................................................................

Il-1 through 6A. Changes to Reactor Operations Procedures B. Changes to the MURR Site Emergency Procedures andFacility Emergency Procedures C. Changes to Health Physics Procedures, Byproduct Material Shipping Procedures, andPreparation of Byproduct Material for Shipping Procedures III. Revisions to the Hazards Summary Report ..........................................

Ill-I through 4IV. Plant and System M odifications

...........................................................

IV- 1 through 3V. New Tests and Experiments

............................................................

V-1VI. Special Nuclear Material and Reactor Physics Activities

................

VI-1VII. Radioactive Effluent

.............................................................................

VII-I through 2Table 1 -Sanitary Sewer EffluentTable 2 -Stack EffluentVIII. Environmental Monitoring and Health Physics Surveys ......................

VIII-l through 6Table I -Summary of Environmental Set 83Table 2 -Summary of Environmental Set 84Table 3 -Environmental TLD SummaryTable 4 -Number of Facility Radiation and Contamination SurveysIX. Summary of Radiation Exposures to Facility Staff, Experimenters and V isitors ...........................................................................................

IX -1 SECTION IREACTOR OPERATIONS SUMMARYJanuary 1,2013 through December 31, 2013The following table and discussion summarizes reactor operations during the period from January 1, 2013 throughDecember 31, 2013.Full Power % of Total Full Power % ofMonth Full Power Hours Megawatt Days Time Scheduled"'1 January 679.75 283.43 91.4 102.3February 589.33 245.87 87.7 98.2March 664.72 277.30 89.3 100.0April 619.93 258.61 86.1 96.6May 649.35 270.93 87.3 97.7June 633.77 264.35 88.0 98.7July 653.10 272.39 87.8 98.3August 653.01 272.41 87.8 98.3September 631.41 263.39 87.7 98.4October 672.05 280.20 90.3 101.1November 656.37 273.77 91.2 102.2December 666.32 277.85 89.6 100.3Total for 7769.11 3240.50 88.68 % 99.34 %the YearNote 1: MURR is scheduled to average at least 150 hour0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />snumber of hours in the month listed or the year.of full power operation per week. Total time is theJanuary 2013The reactor operated continuously in January 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.Major maintenance items for the month included:

replacing Reactor Pool Reflector Region Differential PressureTransmitter PT-917; 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).'"

February 2013The reactor operated continuously in February with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and two unscheduled/unplanned powerreductions.

On February 23, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not In Contact WithMagnet" rod run-in was automatically initiated when the reactor safety system yellow leg Trip Actuator Amplifier 1-1 (TAA) de-energized, causing control blades 'A' and 'B' anvils to separate from their electromagnets and drop. Amanual scram was then initiated and all immediate and subsequent actions of reactor emergency procedure REP-2,"Reactor Scram," were performed.

Investigation of all relays and wiring associated with this portion of the reactorsafety system revealed that a normally closed contact in the manual scram switch.,

1SI 0, was intermittently making apoor connection.

The contact blocks in the manual scram switch were burnished and the yellow leg TAA wasreplaced.

The system was retested satisfactorily and permission to restart the reactor was obtained from the ReactorManager.

The reactor was refueled and subsequently restarted to 10 MW operation.

On February 23, with the reactor operating at 10 MW in the automatic control mode, a reactor scram wasautomatically initiated when an interruption in electrical supply power from the University Power Plant to the facilityoccurred.

All immediate and subsequent actions of reactor emergency procedure REP-11, "Momentary Loss ofNormal Electrical Power," were performed.

Permission to restart the reactor was obtained from the Lead SeniorReactor Operator after confirmation from the power plant that the cause of the interruption in electrical power wascorrected.

A "hot reactor startup" was performed to return the reactor to 10 MW operation.

Major maintenance items for the month included:

replacing the 30-degree graphite reflector elements

'GH' and 'IJ'with a single 60-degree graphite reflector element 'GHIJ;' and replacing the pool coolant demineralizer system inletfilters.March 2013The reactor operated continuously in March with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and four unscheduled/unplanned powerreductions.

U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of theRadiation Protection Program and Shipping.

On March 4, while reviewing a list of the completed maintenance items and compliance procedures performed thatday, the Surveillance Programs System Specialist discovered that compliance procedure CP-27, "Power LevelInterlock Static Scram," was not completed within the prescribed Technical Specification (TS) periodicity.

Failure toperform the surveillance within the required time interval resulted in a deviation from TS 5.4. Licensee Event ReportNo. 13-01 was submitted to the U.S. Nuclear Regulatory Commission on April 2, 2013. The compliance procedure was performed on March 11, the next scheduled maintenance day after discovery of the error.On March 5, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible orvisual alarm occurred) rod run-in was automatically initiated.

The control room operator immediately noted all fourshim control blades moving in the inward direction.

After a brief investigation was unable to determine the cause ofthe rod run-in, the rod run-in was not manually reset and the reactor was shut down. Subsequent investigation of allpower supplies, relays, switches and wiring connections associated with the rod run-in system revealed noabnormalities.

Additional troubleshooting and investigation were unable to reproduce this system response.

Operational checks of the rod run-in system were performed satisfactorily.

The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

The reactor was subsequently restarted to 10 MWoperation.

On March 5 (5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 55 minutes after the previous power reduction),

with the reactor operating at 10 MW in theautomatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated.

The control room operator immediately noted all four shim control blades moving in the inward direction.

After abrief investigation was unable to determine the cause of the rod run-in, the reactor was manually scrammed.

Theimmediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed.

Subsequent 1-2 investigation did not identify a failed component;

however, the most likely cause was a failure of either the rod run-insystem Trip Actuator Amplifier (TAA) or Non-Coincidence Logic Unit (NCLU). The rod run-in system TAA andNCLUs were replaced and operational checks of the rod run-in system were performed satisfactorily.

Permission torestart the reactor was obtained from the Reactor Manager.

The reactor was subsequently restarted to 10 MWoperation.

On March 13, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact withMagnet" rod run-in was automatically initiated when control blade 'D' anvil separated from its electromagnet duringa routine sample handling evolution.

The immediate actions of reactor emergency procedure REP-2, "ReactorScram," were performed.

The operators involved were counseled on the importance of proper sample handlingtechniques near the offset mechanisms.

Visual verification of the pull rod to housing alignment was performed.

Thereactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator.

Thereactor was subsequently restarted to 10 MW operation.

On March 20, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact withMagnet" rod run-in was automatically initiated when control blade 'A' anvil separated from its electromagnet duringa routine sample handling evolution.

The immediate actions of reactor emergency procedure REP-2, "ReactorScram," were performed.

The operators involved were counseled on the importance of proper sample handlingtechniques near the offset mechanisms.

Visual verification of the pull rod to housing alignment was performed.

Thereactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator.

Thereactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included:

completing Modification Record 13-03, "Replacement of GH andIJ Wedge with a Single 600 Wedge;" completing Modification Record 12-02, "Control Blade Fabrication Alternative Using Laser Welding;"

completing Modification Record 01-02, Addendum 9, "Intercommunication and PagingSystem Changes in Support of MURR Industrial Building (Room 299) Renovations;"

performing two reactivity worth measurements in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of FluxTrap Loadings or Individual

Samples, RTP-17(B);"

performing a reactivity worth measurement in accordance withreactor procedure RP-RO-203, "Measurement of the Primary Coolant/Moderator Temperature Coefficient ofReactivity, RTP-19,"

in support of a Nuclear Engineering Department practicum; performing a reactivity worthmeasurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a ShimBlade, RTP- II(D)," in support of a Nuclear Engineering Department practicum; and loading new de-ionization bed'F' and placing on pool coolant system service.April 2013The reactor operated continuously in April with the following exceptions:

five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and one unscheduled/unplanned power reduction.

Oneadditional reactor startup and shutdown were performed in support of NRC operator license examinations.

MURRreceived notification from the U.S. Nuclear Regulatory Commission that two new Reactor Operator and one newSenior Reactor Operator licenses had been issued.On April 30, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible orvisual alarm occurred) rod run-in was automatically initiated.

The control room operator immediately noted all fourshim control blades moving in the inward direction.

The reactor was then subsequently shut down. Subsequent investigation did not identify a failed component;

however, two resistors in the Trip Actuating Amplifier (TAA)circuit were determined to have resistance values outside their specified tolerances.

Both resistors were replaced.

1-3 Operational checks of the rod run-in system were performed satisfactorily and permission to restart the reactor wasobtained from the Reactor Manager.

The reactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included:

performing extensive troubleshooting on the rod run-in systemwiring; completing Modification Record 11-03, Addendum 1, "Addition of Blow-Down Meter to the DataAcquisition Monitoring System;"

completing Modification Record 13-02, "Replacement of Secondary Chemistry Controllers;"

replacing primary coolant circulation pump P-501A; performing a reactivity worth measurement inaccordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings orIndividual

Samples, RTP-I 7(B);" 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);" replacing the actuator for manualscram switch, I SI0; and completing the biennial change-out of Control Blade 'A' Offset Mechanism and associated retesting.

May 2013The reactor operated continuously in May with the following exceptions:

five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and three unscheduled/unplanned power reductions.

On May 7, with the reactor operating at 10 MW in the automatic control mode, a manual scram was initiated when anoperator discovered the regulating blade would not move in the inward direction.

The immediate actions of reactoremergency procedure REP-2, "Reactor Scram" were performed.

Subsequent investigation revealed the ball plungerfor the overload clutch had loosened and slightly backed out preventing the movement of the servomotor from beingtransferred to the lead screw assembly, thus preventing the regulating blade from being able to drive in the outwardand inward directions.

The overload clutch was inspected and the ball plunger was replaced.

Operational checks ofthe regulating blade were performed satisfactorily and permission to restart the reactor was obtained from the ReactorManager.

The reactor was subsequently restarted to 10 MW operation.

Failure of the regulating blade to be operable during reactor operation resulted in a deviation from Technical Specification 3.4.c. Licensee Event Report No. 13-02 was submitted to the U.S. Nuclear Regulatory Commission onJune 4, 2013.On May 8, 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 electromagnet during a routinesample handling evolution.

The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," wereperformed.

The operators involved were counseled on the importance of proper sample handling techniques near theoffset mechanisms.

Visual verification of the pull rod to housing alignment was performed.

The reactor was refueledand permission to restart the reactor was obtained from the Lead Senior Reactor Operator.

The reactor wassubsequently restarted to 10 MW operation.

On May 14, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible orvisual alarm occurred) reactor scram was automatically initiated.

Investigation revealed all monitored parameters were normal and none had trended toward an automatic scram set point or exhibited any abnormalities.

Subsequent troubleshooting efforts led to the replacement of Power Level Interlock relay I1K26. Operational checks of the PowerLevel Interlock circuit were performed satisfactorily and permission to restart the reactor was obtained from theReactor Manager.

The reactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included:

replacing Power Level Interlock relay IK26; replacing thediaphragm and inlet and outlet flange gaskets for pool coolant demineralizer pump P-513B Discharge Valve 515N;1-4 completing compliance procedure CP-26, "Containment Building Compliance Test;" and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of FluxTrap Loadings or Individual

Samples, RTP-17(B)."

June 2013The reactor operated continuously in June with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and two unscheduled/unplanned power reductions.

On June 11, 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 'A' anvil separated from its electromagnet during a routinesample handling evolution.

The reactor was manually scrammed and the immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed.

Inspection of the offset mechanism pull rod and housingrevealed a slight misalignment between the anvil and electromagnet.

The lower drive limit switch was adjusted andthe anvil and electromagnet were cleaned.

The control rod was satisfactorily withdrawn to the full out position aspart of the retest by performing compliance procedure CP-10, "Rod Drop Times." Permission to perform a "hotreactor startup" was obtained from the Reactor Manager.

While conducting the "hot reactor startup,"

the ReactorOperator noted, immediately after stabilizing reactor power level at 5 MW, that the heights of shim control blades 'B'and 'D' were at 21.90 and 23.10 inches, respectively.

This 1.20 inch difference in shim blade height created adeviation from Technical Specification (TS) 3.2.b, which states, "Above 100 kilowatts the reactor shall be operatedso that the maximum distance between the highest and lowest shim blade shall not exceed one inch." Licensee EventReport No. 13-03 was submitted to the U.S. Nuclear Regulatory Commission on July 10, 2013.On June 14, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible orvisual alarm occurred) rod run-in was automatically initiated.

The control room operator immediately noted all fourshim control blades moving in the inward direction.

The reactor was then subsequently shut down. Subsequent investigation did not identify a failed component.

Additional troubleshooting and investigation were unable toreproduce this system response.

Operational checks of the rod run-in system were performed satisfactorily.

Thereactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

The reactor wassubsequently restarted to 10 MW operation.

Major maintenance items for the month included:

performing extensive troubleshooting on the rod run-in systemwiring connections; completing Modification Record 13-04, "Rod Run-In Monitoring System;"

completing Modification Record 75-01, Addendum 3, "Rod Run-In Electronic Circuit Jumper Panel;" completing Modification Record 13-01, "Replacement of TE-980A and TE-980B Power Supply 2PS5;" performing a reactivity worthmeasurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux TrapLoadings or Individual

Samples, RTP-17(B);"

and replacing the Loss of Voltage to Magnet A and B Scram relay2K20 and the Loss of Voltage to Magnet C and D Scram relay 2K2 1.July 2013The reactor operated continuously in July with the following exceptions:

five shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions.

U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of Security and Material Control and Accountability.

The U.S. NuclearRegulatory Commission issued Amendment No. 36 to Amended Facility License No. R-103.On July 3, with the reactor operating at 10 MW in the automatic control mode, a "Power Level Interlock or FIRST"scram was automatically initiated when the FIRST Support Rig was inadvertently bumped while performing a routine1-5 sample handling evolution.

The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," wereperformed.

The flux trap sample holder was verified to be positively latched to the inner reactor pressure vessel. Theoperators involved were counseled on the importance of proper handling techniques near the FIRST Support Rig.The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

The reactorwas subsequently restarted to 10 MW operation.

On July 15, during a reactor startup with the reactor subcritical, a "Rod Not in Contact with Magnet" rod run-in wasautomatically initiated when control blade 'B' anvil separated from its electromagnet during a shimming evolution.

The reactor was shut down and the immediate actions of reactor emergency procedure REP-2, "Reactor Scram," wereperformed.

The mating surfaces between the control rod drive mechanism electromagnet and pull rod anvil werecleaned and proper alignment of the offset mechanism pull rod and housing were verified.

The control rod wassatisfactorily withdrawn to the full out position as part of the retest by performing compliance procedure CP-10, "RodDrop Times." 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 withreactor procedure RP-RO-200.,

"Measurement of Differential Worth of a Shim Blade, RTP-I I(D);" performing areactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worthof Flux Trap Loadings or Individual

Samples, RTP-17(B);"

replacing Vent Tank Discharge Check Valve 550A;replacing Pool Below Refuel Level relay 2K5; replacing the chassis edge connectors for the rod run-in system and thereactor safety system Trip Actuator Amplifiers and Non-Coincidence Logic Units; and replacing the air actuator anddiaphragm on pressurizer Water Drain Valve 527A.August 2013The reactor operated continuously in August with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, one shutdown for training and fourunscheduled/unplanned power reductions.

On August 21, with the reactor operating at 10 MW in the automatic control mode, a "Reactor Loop Low Pressure" scram was automatically initiated.

All immediate and subsequent actions of reactor emergency procedure REP-3,"Primary Coolant System Low Pressure or Flow Scram," were performed.

No actual low pressure condition indication was present.

Investigation determined the most likely cause to be reactor core outlet pressure channels944A or 944B. Contacts on Reactor Pressure/Flow Interlock relays 2K32 and 2K33 were burnished, reactor coreoutlet pressure transmitters were vented and applicable sections of compliance procedure CP-22, "Pressure Transmitters PT-944A/B and PT-943,"

were completed satisfactorily.

The reactor was refueled and permission torestart the reactor was obtained from the Reactor Manager.

The reactor was subsequently restarted to 10 MWoperation.

On August 23, with the reactor operating at 10 MW in the automatic control mode, a "Reactor Loop Low Pressure" scram was automatically initiated.

All immediate and subsequent actions of reactor emergency procedure REP-3,"Primary Coolant System Low Pressure or Flow Scram," were performed.

No actual low pressure condition indication was present.

Investigation determined the cause to be an intermittent failure of reactor core outlet pressure944B meter/relay unit. The meter/relay unit was replaced and applicable sections of compliance procedure CP-22"Pressure Transmitters PT-944A/B and PT-943,"

were completed satisfactorily.

The reactor was refueled andpermission to restart the reactor was obtained from the Reactor Manager.

The reactor was subsequently restarted to10 MW operation.

1-6 On August 25, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact withMagnet" rod run-in was automatically initiated when control blade 'D' anvil was separated from its electromagnet during a routine sample handling evolution.

The immediate actions of reactor emergency procedure REP-2, "ReactorScram," were performed.

The operators involved were counseled on the importance of proper sample handlingtechniques near the offset mechanisms.

Visual verification of the pull rod to housing alignment was performed.

Thereactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

The reactor wassubsequently restarted to 10 MW operation.

On August 26, during a reactor startup with the control blades at approximately 11 inches withdrawn (subcritical),

a"Channel 2 & 3 Period" scram was automatically initiated when Nuclear Instrumentation (NI) Intermediate RangeChannel No. 2 period indication increased above the scram set point. The duty operator noted all power level andperiod indications other than those from NI Signal Processor No. 1 were normal. All immediate actions of reactoremergency procedure REP-2, "Reactor Scram," were performed.

Troubleshooting efforts led to the replacement ofNI Signal Processor No. I fission chamber and its associated cabling.

An instrument channel calibration and pre-operational checks were performed satisfactorily, including a response check using the neutron source. The reactorwas refueled and permission to restart the reactor was obtained from the Reactor Manager.

The reactor wassubsequently restarted to 10 MW operation.

Major maintenance items for the month included:

completing Modification Record 04-05, Addendum 8, "CoolingTower Electrical Arc Flash Danger Mitigation;"

completing Modification Record 12-01, "Replace PT-944A/B withRosemount Transmitters;"

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);"

performing achemical cleaning of the secondary coolant side of primary coolant heat exchanger HX-503A; loading new de-ionization bed 'D' and placing it on pool coolant system service; and replacing the fission chamber detector andassociated cabling for NI Signal Processor No. 1.September 2013The reactor operated continuously in September with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, two shutdowns for training and twounscheduled/unplanned shutdowns.

On September 16, with the reactor operating at 10 MW in the automatic control mode, a reactor shutdown wasinitiated after the duty operator observed a blown fuse indication on Annunciator Control Power Fuse 2F7,accompanied, shortly thereafter, by an Uninterruptible Power Supply (UPS) trouble alarm. All other indications for10 MW operation were normal. Further investigation revealed that the Annunciator 115VAC Supply Breaker onUPS Panel No. 2 was in the tripped condition and the Annunciator inoperable.

Troubleshooting efforts determined that the most likely cause of the blown fuse and tripped breaker was a faulty alarm module. The Annunciator alarmmodule for "Channel 4, 5, or 6 Downscale" function was replaced and an operational test of the Annunciator wascompleted satisfactorily.

Permission to the restart the reactor was obtained from the Reactor Manager.

The reactorwas subsequently returned to 10 MW operation.

On September 23, with the reactor operating at 10 MW in the automatic control mode, a reactor shutdown wasinitiated after the duty operator observed a greater than normal lowering of pressurizer liquid level of approximately 2inches per hour. This abnormal decrease in liquid level was observed shortly after a reactor startup.

A reactorrefueling had been performed earlier in the day. Subsequent investigation revealed that the source of leakage wasfrom the pressure vessel head packing gland seal, which provides the seal between the pressure vessel head and innerreactor pressure vessel. Note: The pressure vessel head is removed and then subsequently replaced and tightened 1-7 after refueling a core has been completed.

The packing gland was tightened and permission to restart the reactor wasobtained from the Reactor Manager.

The reactor was returned to 10 MW operation.

Operators were subsequently counseled on proper bolting techniques.

Major maintenance items for the month included:

completing Modification Record 01-02, Addendum 10,"Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299), Room 243,Room 246 and Room 271 Renovations;"

performing a reactivity worth measurement in accordance with reactorprocedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual

Samples, RTP-17(B);" completing a change-out of Control Blade 'A' Offset Mechanism and associated retesting; and replacing the"Channel 4, 5 or 6 Downscale" annunciator alarm module.October 2013The reactor operated continuously in October with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements.

There were no unplanned/unscheduled shutdowns this month.Major maintenance items for the month included:

completing Modification Record 04-03, Addendum 1, "LiquidRadioactive Waste System in MURR Industrial Building;"

completing Modification Record 13-06, "Modifications toMURR Industrial Building (Room 299) in Support of the NS-99 Project;"

replacing Nuclear Instrumentation PowerRange "Channel 4 Downscale (95%)" relay unit K58; flooding and draining Beamport

'D' and back filling withhelium; performing the biennial change-out of Control Blade 'C' Offset Mechanism and associated retesting; andperforming a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement ofReactivity Worth of Flux Trap Loadings or Individual

Samples, RTP-17(B)."

November 2013The reactor operated continuously in November with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and one unscheduled/unplanned powerreduction.

Three additional reactor startups and shutdowns were performed in support of NRC operator licenseexaminations.

U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection ofReactor Operations and Emergency Preparedness.

MURR received notification from the U.S. Nuclear Regulatory Commission that three new Reactor Operator and three new Senior Reactor Operator licenses had been issued.On November 11, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact withMagnet" rod run-in was automatically initiated when control blade 'D' anvil separated from its electromagnet duringa routine sample handling evolution.

The immediate actions of reactor emergency procedure REP-2, "ReactorScram," were performed.

The operators involved were counseled on the importance of proper sample handlingtechniques near the offset mechanisms.

Visual verification of the pull rod to housing alignment and operability testswere performed satisfactorily.

The reactor was refueled and permission to restart the reactor was obtained from theLead Senior Reactor Operator.

The reactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included:

performing a reactivity worth measurement in accordance withreactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP- I1(D);" and performing pre-beryllium change-out center test hole flux profile measurements.

1-8 December 2013The reactor operated continuously in December with the following exceptions:

five shutdowns for scheduled maintenance and one shutdown for physics measurements.

There were no unscheduled/unplanned power reductions this month.Major maintenance items for the month included:

completing Modification Record 13-05, "T-300 and T-301 LevelSensing System;"

performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual

Samples, RTP-17(B);"

loading new de-ionizing bed 'R' and placing on pool coolant system service; and performing a chemical cleaning of the secondary coolant side of pool coolant system heat exchanger HX-52 1.1-9 SECTION I!MURR PROCEDURES January 1, 2013 through December 31, 2013As required by administrative Technical Specification 6.l.h (4), this section of the Annual Report includes asummary of procedure changes.

These procedure changes were reviewed by the Reactor Manager or Reactor HealthPhysics Manager, as applicable, and others to assure compliance with the requirements of 10 CFR 50.59. Theseprocedure changes were also reviewed by the Reactor Procedure Review Subcommittee of the Reactor AdvisoryCommittee to meet the requirements of Technical Specification 6.1.c (1).A. CHANGES TO REACTOR OPERATIONS PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Reactor Operations Procedures and found them to be adequate for the safe and reliable operation of the facility.

There were sixty-two (62) revisions issued to the reactor operations procedures, forms and operator aids. Themajority of the revisions were strictly format or editorial in nature, such as cover page changes.

The following is alist of the new and revised procedures, forms and operator aids:~Ntinier~

Name Rev Aevision Dte NotesAP-RO-130 Crane Operation 16 3/29/2013 Cover PageAP-RR-003 10 CFR 50.59 Evaluations 8 6/5/2013 Minor Editorial EX-RO-105 Reactor Irradiation Experiments 119 5/22/2013 Minor Editorial Type B Shipment of spent Fuel Using the BEA IFB-SH- I10 e 4/16/2013 Minor Editorial Research Reactor PackageIFB-SH- 110 ~Type B Shipment of spent Fuel Using the BEA 5/14/2013 Full ReviewResearch Reactor PackageFM- 1 Reactor Shutdown Checksheet 6 12/20/2013 Cover PageFM-15 110 CFR 50.59 Qualified Reviewers List 15 6/5/2013

.Minor Editorial FM-15 10 CFR 50.59 Qualified Reviewers List 16 12/19/2013 Minor Editorial FM-21 ARMS Trip Setpoints 9 6/6/2013 Minor Editorial FM-33 Containment Building Restricted Materials 5 12/9/2013 Cover PageFM-43 Nuclear and Process Data 17 3/29/2013 Cover PageFM-43 Nuclear and Process Data 18 10/17/2013 Minor Editorial FM-55 jStartup Nuclear Data Sheet 7 3/29/2013 Minor Editorial FM-56 lReactor Routine Patrol 16 3/29/2013 Minor Editorial FM-57 Long Form Startup Checksheet 20 5/2/2013 Minor Editorial FM-57 Long Form Startup Checksheet 21 10/31/2013 Minor Editorial FM-58 .Short Form Startup Checksheet

.11 10/31/2013 Minor Editorial

.FM-63 .DI Water Makeup Log 19 1/31/2013 Cover Page.Customer Sample Pre-Encapsulation Evaluation 7 1 6/10/2013 MinorFM-66 7W6/0/213eino Editorial

__________

Worksheet FM-68 Target Material Control Checksheet 12 J 6/10/2013 Minor Editorial FM-93 .Post Maintenance Valve Line-up Checksheet 5 6/10/20 1.3 Cover PageIRR-PSO-111 ICustomer Sample Pre-Encapsulation Evaluation I -6/10/2013 Minor Editorial 11-1 Nu~mber Na~me Rgy. Revision Dite j No9tesOP-RO-100 Main Air System j.10 3/29/2013 Minor Editorial OP-RO-101 Instrument Air System J 10 3/29/2013 Minor Editorial OP-RO-210 Reactor Startup-Normal 113 5/22/2013 3 Cover PageOP-RO-211 Reactor Startup-Hot 11 ] 6/25/2013 3 Minor Editorial OP-RO-211 lReactor Startup -Hot 1 12 8/22/2013 3 Minor Editorial Reactor Startup -Recovery from Temporary Power 1 1OP-RO-212 Reduction 12/9/2013 Cover PageOP-RO-220 Reactor Shutdown or Power Reduction 81 6/25/2013 Minor Editorial OP-RO-230 Changing Reactor Power Level 8 6/25/2013 Minor Editorial OP-RO-310

_Nuclear Instrumentation

-Signal Processor

1. 1 310 5/22/2013 Cover PageOP-RO-311 TNuclear Instrumentation

-Signal Processor

1. 2 11 5/22/2013 Cover PageOP-RO-312 Nuclear Instrumentation Power Range Monitor -13OPhannOe316 13 52/03 Cover PageOP-RO-330 Nuclear Instrumentation-Wide Range Monitor 1 13 5/22/2013 Cover PageOP-RO-340 Nuclear Instrumentation Adjustment

.103 5/22/2013 Cover PageReactor Power Calculator Flow Potentiometer OP-RO-350 Adjustment 9/24/2013 Cover PageOP-RO-410

]Primary Coolant System .l.1i 5/2/2013 Minor Editorial OP-RO-420 3Primary and Pool Water Analysis 161 9/24/2013 j Cover PageOP-RO-460 3Pool Coolant System -Two Pump Operation 314..3 9/24/2013 Minor Editorial OP-RO-461 JPool Coolant System -One Pump Operation 14T 9/24/2013 Minor Editorial OP-RO-465 3Pool Level Control -Skimmer System 18 3/29/2013 Minor Editorial OP-RO-480 3Secondary Coolant System 17 9/24/2013 Minor Editorial OP-RO-480 3Secondary Coolant System 18 12/9/2013 Minor Editorial OP-RO-510 Nitrogen System 37. 5/2/2013 3 Minor Editorial OP-RO-515 Emergency Air System J9 9/24/2013 f Minor Editorial OP-RO-516 Valve Operation Air System1 9 1 8/22/2013 1 Cover PageOP-RO-525 Chill Water System 17 6/25/2013 Minor Editorial OP-RO-530 Demineralized Water Supply System IT13 8/22/2013 Cover PageOP-RO-531 Primary and Pool Sample Station I1 9/24/2013 Cover PageOP-RO-555 Fire Protection System .10 1/31/2013 Minor Editorial OP-RO-555 Fire Protection System 311 11/19/2013 Minor Editorial OP-RO-710 Radiation Monitoring

-Area Monitors 181 8/22/2013 Cover Page .OP-RO_720 jRadiation Monitoring

-Stack Monitor Operational 1 6 1OPhROec20 11 6/25/2013 Minor Editorial OP-RO-730 Facility Exhaust System 14 3/29/2013 Minor Editorial OP-RO-741 Waste Tank System Operation 13 5/2/2013 Minor Editorial OP-RO-741 Waste Tank System Operation 14 12/19/2013 Minor Editorial POL-20 Special Nuclear Materials Manual 13 3/3/8/2013 Minor Editorial REP-RO-100 IReactor Emergency Procedures 3161 1/31/2013 Cover PageRM-RO-400 Waste Tank System Filter Replacement 373 3/29/2013 Minor Editorial

Receipt, Inspection and Accounting of Unirradiated 5/1nEo-RO-00 5/22/2013 Minor Editorial SM-RO-200 Manual Operation of Airlock doors 276 and 277 2 5/7/2013 Minor Editorial lControl Console And Instrument Panel -Securing SM-RO-301 3Power11-2109/24/2013 Cover Page 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 PlanImplementing Procedures and found them to be adequate for the safe and reliable operation of the facility.

There were thirteen (13) revisions issued to the emergency procedures, forms and operator aids. The majority of therevisions were strictly format or editorial in nature. The following is a list of the revised procedures, forms andoperator aids:Number~ Name R1ev. fRevision Datej Not~esEP-RO-002 Emergency Responsibilities 4 5/7/2013 Minor Editorial EP-RO-006 Radiological Emergency 5 5/7/2013 Minor Editorial EP-RO-013 Facility Evacuation

.5 15/7/23 Minor Editorial EP-1R-0 15 Emergency Notifications 9 4/4/2013 Minor Editorial.

EP-RO-0 15 Emergency Notifications 10 5/7/2013 Minor Editorial EP-RO-0 15 Emergency Notifications I 1 10/29/2013 Minor Editorial EP-RO-0 18 Emergency Radiation Exposure 5 5/7/2013 Minor Editorial FM-104 JEmergency Call List 22 4/4/2013 Minor Editorial FM-i 10 Fire Flowchart 4 5/7/2013 Minor Editorial OA-09 Combined Emergency Flowcharts 5 7/8/2013 1 Minor Editorial OA-10 jFire Extinguisher Locations and Types ' 9 12/12/2013 Minor Editorial OA-20 jEmergency Equipment

.15 7/8/2013 Minor Editorial OA-20 JEmergency Equipment 1612/12/2013 Minor Editorial C. CHANGES TO HEALTH PHYSICS PROCEDURES, BYPRODUCT MATERIAL SHIPPINGPROCEDURES, and PREPARATION OF BYPRODUCT MATERIAL FOR SHIPPINGPROCEDURES As required by the MURR Technical Specifications, the Reactor Health Physics Manager reviewed the procedures for radioactive materials

handling, shipping, and preparation for shipping of byproduct materials.

There were eighty-four (84) revisions issued to the health physics, radioactive materials

shipping, and preparation for shipping procedures and forms. Additionally, three (3) new forms and four (4) new procedures were issued.The majority of the revisions were strictly format or editorial in nature. The following is a list of the revisedprocedures and forms:Naniber JName Rev. ~Revision Date ~ NotestMURR Initial Radiation Worker TrainingAP-HP- 117 ]Mrral 11 3/22/2013 Minor Editorial

~Program I_________________

AP-HP- 119 IHigh Radiation Area Access 5 1/3/2013 Minor Editorial

..... .rAP-HP-123 IVisitor Dosimetry

-Reception Desk 19 4/29/2013 Minor Editorial 123 .V~isitor

-'rReception Desk ... .........

..!0......

8/5/(2.013

..........

Mino°r.E~ditori~al

.AP-HP-129 Hot Cell, HC-01 Control 9 ] 2/7/2013 Minor Editorial AIn-House Radioactive Shipping Request FormAP-SH-002

]Isrcin .2 6/18/2013 Minor Editorial AP-SH-002 In-House Radioactive Shipping Request FormInstructions 11-339/17/2013 Minor Editorial

~'Number jName Rev. Rievision Date] NotesSAP-SH-002 jIn-House Radioactive Shipping Request Form 4 12/19/2013 Minor Editorial

_Instructions

...................

DOT 6M Packaging of Type B Non-Waste 1 T 10/9/2013 Minor Editorial BPB-S-005_

~Radioactive MaterialReceiptlnspection Of Type B Byproduct Material 4 4/29/2013 MinorBPB-SH-020 Shipping Containers BPB-SH-023 jType B Equipment Calibration 121 12/20/2013

.Minor Editorial TypeB(U)

F-458 Series Packaging of Type BBPB-SH-024 Non-Waste Radioactive Material Editorial Type B(U) ZA/NNRI005 (Beatrice)

Packaging of IBPB-SH-021 2 10/9/20 13 Minor Editorial BP-SH-025_

gType B Non-Waste Radioactive MaterialBPB-SH-026 Type B(U) F-327 Series Packaging of Type B 1Non-Waste Radioactive Material 1h nC.BPB-SH-027 Survey and Decontamination of Returned 1 iShipingConainrs7 1 10/9/2013 Minor Editorial BTYPE B(U) USA/0656/B(U)-96 (Ganuk) 0BPB-SH-029 0Pcaigo aiatv aeilf 11/5/2013 New Procedure jPackaging of Radioactive MaterialBP-SH-016

~Packaging and Shipment of Radioactive Material 3 10/9/2013 Minor Editorial Using USA DOT 7 A Model H or I PackageBP-SH-017 Packaging and Shipment of Radioactive Material 0 7/18/2013 New Procedure Using Tracerco LS-6 Reusable Type A Package IRadioactive Material Shipment PackageBP-SH-052 Douetto n aeig10 2/6/2013 Minor Editorial

• _ _ I~Documentation and Labeling_

___BRadioactive Material Shipment PackageBP-SH-052 IouettonadLbln 11 7/26/2013 Minor Editorial

.I~~ ~Documentation and Labeling

_ _Type B Shipment of spent Fuel Using the BEA 2 4/16/2013 Minor Editorial FB-SH- 110 ]Research Reactor Package ..........

/Type B Shipment of spent Fuel Using the BEAFB-SH- 1I0 R a Reactor Package 3 5/13/2013 Full ReviewBP-SH-099 jPackaging of Radioactive Material Using MURR 3 1/4/2012 Minor Editorial Model 1500FM-17 Radiation Work Permit i11 11/19/2013 Minor Editorial FM-27 In-House Radioactive Shipping Request Form 12 9/17/2013 Minor Editorial Control Checksheet for Documentation and 1iLabeling of Radioactive Material Shipment 11 __2/6/2013 MinorEditorial Control Checksheet for Documentation and 1121 7/26/2013 MinorFM-52__ Labeling of Radioactive Material Shipment

..... Editorial FM-62 Radiation Instrument Certificate of Calibration 171 7/11/2013 Cover PageControl Checksheet for Reusable Type AFM-69 Radioactive Materials Shipment (5 to 30 Gallon 8 10/11/2013 Minor Editorial Drums)FControl Checksheet for Tracerco LS-6 Reusable 78 1 1 eFFM-70 _ IType A Package Radioactive Materials Shipment 7/8/01 NewFormFControl Checksheet for Type B USA DOT 6M 10iFM-74 RaiatvMaeilShp nt14 10/9/2013 Minor Editorial Radioactive Materials Shipment111_____

________FM-91 jDeclaration of Pregnancy 51 ] 8/5/2013 Cover PageFM-94 lExclusive Use Shipment Controls 41 2/6/2013 Minor Editorial FM-94 Exclusive Use Shipment Controls j 5 4/29/2013 J Minor Editorial FM-94 jExclusive Use Shipment Controls11-467/26/2013 1 Minor Editorial Number Name JRev eis~ion'fDate NFM-99 ModlControl checkshees for USA DOT 7A MURR 7112/19/201!

MinorEditorial Model 1500 Series....

FM- 129 Control Checksheet for Receipt and Inspection of 3 4/16/2013 Minor Editorial Type B Byproduct Material Shipping Containers_

Control Checksheet for Type B(U) ZA/NNR 1005FM-135 (Beatrice)

Radioactive Materials Shipment I /821 io dtraFM-137 Type B Qualified Shipper List 1 4/29/2013 Minor Editorial FM- 149 Personnel Radiation Dose Estimate 0o 2/7/2013 New FormFControl Checksheet for USA DOT 7A Type A 55- T i____ 151 Gallon Radioactive Material Package 812/19/2013 MinorFM- 154 Control Checksheet for USA DOT 20WC-1 3 4/29/201 Cover PageOverpack Rod Replacement 013FM-155 *Quality Assurance Control Checksheet Exterior4/

013 CovePagPainting of USA DOT WC-I, Type B Overpack

...Required Documentation for Non-MURR Owned 'FM-156 Type B Shipping Containers 7/26/2013 Minor Editorial RT ive Mate Ship ment6/18/201 Control Checksheet for Type B(U) F-458 Series 2 MFM- 15.7 2. 6/18/2013 MinorEditorial Control Checksheet for Type B(U) F-327 SeriesFM- 160 1 10/9/2013 Minor Editorial Radioactive Materials Shipment..

Control Checksheet for Type B(U) IFM- 163 USA/9337/B(U)-96 (LS) Packaging of 1 3/22/2013 Minor Editorial Radioactive Material

..Control Checksheet for Type B(U)FM-167 USA/0656/B(U)-96 (Ganuk) Radioactive 0 11/5/2013 New FormMaterials Shipping

.....HC-PSO-002 Hot Cell Preparation of Radioactive Material for 9/11/2013 Minor Editorial ShipmentHC-PSO-005 Hot Cell Loading of Host Cans 111. 9/11/2013 j Minor Editorial IC-HP-300 Calibration

-Radiation Survey Instruments 77 7/11/2013 Cover PageIC-HP-305 Calibration

-Electrostatic Discharge Dosimeter 8 8/2/2013 Cover PageCalibration

-Eberline Ping IA Stack Monitor-4/9/2013 MIC-HP-3 11 Ioin Channel013 Minor Editorial Iodine ChannelCalibration

-Protean Model WPC 9550 Alpha- 7 0e*IC-HIP-347 BeaSieCutr9 7/11/2013 Cover PageIC-H-347 Beta Swipe CounterCalibration

-Canberra S5XLB-G & TennelecSeries 4 with Gamma, & Tennelec Series 3 .. ... PageICalibration

-Lab Impex Stack Monitor-Particulate IC-HP-349 I~anl.4 7/11/20 13 Cover PageChannel]Calibration

-Lab Impex Stack Monitor-Iodine IIC-HP-350

[Channel 2 8/2/2013 Minor Editorial

• IC-HP-35 1 Calibration

-Lab Impex Stack Monitor-Gas 2 7/11/2013 Cover PageChannelIC-HP-352

~Calibration

-Lab Impex Stack Monitor-Flow IC-ibr-35o 3 7/11/2013 Cover PageIRR-PSO-1 12 Preparing Shipping Paperwork 17 8/13/2013 Minor Editorial OP-HP-200 Air Sampling-Containment Building Tritium 6 1 8/2/2013 f Cover PageOP-HP-220 Tritium Bioassay98/5/2013 j Minor Editorial Il-5 Number ::Name Rev.

Date Notes__:::___:__:_

OP-HP-222 Air Sampling

-Containment Building Ar-41 6 2/7/2013 Minor Editorial OP-HP-348 Operation

-Protean WPC-9550 Swipe Counter 4 7/11/2013 Cover PageOperation

-Lab Impex Stack Monitor -FilterOP-HP-356 Changepand Source4checks 8/5/2013 I Cover PageQAB-SH-002 jProcurement of Type B Packages 2" 2/6/2013 Cover PageQAB-SH-003 Material Control for Type B Shipping Program 3 5/14/2013 Minor Editorial QAB-SH-004 Type B Program Vendor Qualification 3 1 5/14/2013 Cover PageQAB-SH-005 Type B QA Personnel Training 3 .2/6/2013 Minor Editorial QAB-SH-006

, Type.B Shipping Program ,Quality Audits 1 2/6/2013

...Minor Editorial...

QAB-SH-009 jPre-Shipment leak Testing of the Ganuk ShippingContainer 0 11/5/2013 New Procedure Stack Monitor Preventive Maintenance

-LabRM-HP- 102 m 7/11/2013 Cover PageImpexRP-HP-100 Contamination Monitoring

-In Facility

16. 4/3/2013 Minor Editorial RP-HP-105 Transfer of Radioactive Material

-In Facility

.71 4/3/2013 Minor Editorial RP-HP-120 IPersonnel Radioactive Contamination 7 4/29/20 13 Minor Editorial RP-HP-120 Personnel Radioactive Contamination 8 8/5/2013 Minor Editorial RP-HP- 125 Radiation Monitoring

-Performing andRP-HP....

.... Documenting.a.Survey 0 8/5/20.13 New Procedure RP-HP-135 Room 114 Entry -.Self Monitored 6 5/22/2013 Minor Editorial RP-HP-137 Handling Radioactive Material in the Reactor Pool I1 8/5/2013 Cover PagejPost-Irradiation Processing:

Exported FloodedMioEdtra SI-PSO-008 6Silicon Cans 6M12/11/201 EdiSV-HP- I 10 Environmental Sampling 5 6/21/2013 Minor Editorial SV-HP- 121 I Building Exhaust Stack Effluent

-Ar-41 5 8/2/2013 Minor Editorial

...............

...... M on itoring ......TPZ-PSO-002 lrradiation of Gemstone Irradiation Containers 6 12/11/2013 Minor Editorial TPZ-PSO-003 Loading Gemstone Irradiation Containers 5 12/11/2013 Minor Editorial TSP-02 ITransportation Security Plan 5 12/19/2013 Minor Editorial WM-SH-100 Radioactive Waste -Preparation and Storage 7 7/26/2013 Cover PageWM-SH-105 Radioactive Waste Processing 8 2/6/2013 I Minor Editorial WM-SH-105 Radioactive Waste Processing

.. 9 7/26/2013 Cover PageExclusive Use Shipment of LSA or SCO 11lT 6/18/2013 Minor Editorial WRadioactive Waste ..........

_WM-SH-300 lExclusive Use Shipment of LSA or SCORadioactive Waste1211/20/2013 Cover PageI1-6 SECTION IIIREVISIONS TO THE HAZARDS SUMMARY REPORTJanuary 1, 2013 through December 31, 2013These changes were approved by the Reactor Manager and reviewed by licensed staff and members of theReactor 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, pages 3-11, Figure 3.2, Grade Level Plan (as revised by the 1972-1973, 1979-1980, 1990-1991, 1995, 1996 and 2012 Reactor Operations Annual Reports):

Replace with: Updated Figure 3.2, Grade Level Plan (MURR Dwg No. 1145, Sheet 2 of 5)Original HSR, pages 7-19, Section 7.2.7 (as revised by the 1974-75, 1989-1990 and 1995 ReactorOperations Annual Reports):

Delete: "...beamport ventilation air, air which is drawn from the surface of the pool andexhaust from the film irradiator shield box."Replace with: "...beamport ventilation air and air which is drawn from the surface of thepool."Original HSR, pages 7-20, Section 7.2.9, Table 7.1 (as revised by the 1974-75, 1995, 2001, 2002, 2007and 2008 Reactor Operations Annual Reports):

Delete: The following from Table 7.1 under Staff Stations:

"Room 288 Health Physics Office"Add: The following to Table 7.1 under Staff Stations:

"Room 271B Health Physics Office"Original HSR, pages 7-21, Section 7.2.9, Table 7.2 (as revised by the 1995, 2001, 2007, 2009. 2011 and2012 Reactor Operations Annual Reports):

Add: The following after "Room 299":"Corridor C299DRoom 299NRoom 299PRoom 299Q"Original HSR, pages 9-7 through 9-9, Table 9.2 (as revised by the 1981-82, 1985-86, 1995, 2000, 2001,2002. 2006 and 2007 Reactor Operations Annual Reports):

Add: "137 Isolated Power Supply (EP 91 IC) -TE-980 A/B"III-I Add:Add:"138 Rod Run-In System Monitoring Circuit""139 T-300 & T-301 Water Level Display"Original HSR, Figure 9.3, Instrument Panel Layout (as revised by 1995, 2001, 2004 and 2006 ReactorOperations Annual Reports):

Replace with: Updated Figure 9.3, Instrument Cabinet (MURR Dwg No. 74, Sheet 12 of 12)Original HSRI Figure 9.5, Rod Run-In System (as revised by 1995 and 2001 Reactor Operations AnnualReports):

Replace with:Updated Figure 9.5, Rod Run-In System (MURR Dwg #140, Sheet 1 of 1, dated9/10/13)ADDENDUM 3 -HAZARDS SUMMARY REPORT (AUGUST 1972)HSR, Addendum 3, page 15, Figure 2.2.b, Secondary Coolant System (as added by the 2012 ReactorOperations Annual Report):Replace with: Updated Figure 2.2.b, Secondary Cooling System (MURR Dwg No. 502, Sheet2 of 3, dated 4/24/13)HSR, Addendum 3, page 18, Figure 2.3.a, Electrical Distribution (as revised by the 1989-90, 1990-91,1995, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011 and 2012 Reactor Operations AnnualReports):

Replace with:Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR DwgNo. 522, Sheet 1 of 5, dated 8/20/13)HSR, Addendum 3, page 23b, Figure 2.3.b, Electrical Distribution (as added by the 1995 and revisedby the 2001, 2002, 2003, 2004, 2005, 2007, 2009, 2010, 2011 and 2012 Reactor Operations AnnualReports):

Replace with:Updated Figure 2.3.b, Electrical Distribution North Office Addition (MURRDwg No. 522, Sheet 2 of 5, dated 10/4/13)HSR, Addendum 3, page 23c, Figure 2.3.c, Electrical Distribution (as added by the 2004 and revised bythe 2005, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.c, Electrical Distribution Reactor/Laboratory Panels (MURRDwg No. 522, Sheet 3 of 5, dated 8/27/13)HSR, Addendum 3, page 23d, Figure 2.3.d, Electrical Distribution (as added by the 2007 and revisedby the 2008, 2009, 2010, 201 land 2012 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 8/27/13)111-2 HSR, Addendum 3, page 23e, Figure 2.3.e, Electrical Distribution (as added by the 2007 and revised bythe 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.e, Electrical Distribution North Office Addition Panels(MURR Dwg No. 522, Sheet 5 of 5, dated 10/7/13)ADDENDUM 4 -HAZARDS SUMMARY REPORT (OCTOBER 1973)HSR, Addendum 4, page A-22, Figure A.4.a, Reactor Control System -10 MW (as revised by 1995,2001, 2004, 2006 and 2007 Reactor Operations Annual Reports):

Replace with: Updated Figure A.4.a, Reactor Control System (MURR Dwg No. 42, Sheet 1 of2, dated 8/22/13)HSR, Addendum 4, page A-25, Figure A.6, 10 MW Process Instrumentation Control & Interlock (asrevised by the 1995, 2001, 2002, 2003, 2005 and 2006 Reactor Operations Annual Reports):

Replace with: Updated Figure A.6, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 2 of 4, dated 8/22/13)HSR, Addendum 4, page A-26, Figure A.7, Annunciator Control 10 MW (as revised by the 1995, 2001,2002, 2005, 2006, 2007, 2008 and 2012 Reactor Operations Annual Reports):

Replace with: Updated Figure A.l, Annunciator Control 10 MW (MURR Dwg No. 138, dated9/11/13)HSR, Addendum 4, page A-29, Figure A.I1, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (as revised by the 1995, 2002, 2005, 2009, 2010, 2011 and 2012 ReactorOperations Annual Reports):

Replace with: Updated Figure A. 11, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (MURR Dwg No. 1125, Sheet 1 of 4, dated8/19/13)ADDENDUM 5 -HAZARDS SUMMARY REPORT (JANUARY 1974)HSR, Addendum 5, page 15, Figure 2.1, Electrical Distribution (as revised by the 1989-90, 2001, 2002,2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR DwgNo. 522, Sheet I of 5, dated 8/20/13)111-3 As a result of the issuance of Amendment No. 36 to Amended Facility License No. R-103 on July 8, 2013,the following changes to the MURR Hazards Summary Report and its addenda were performed:

ADDENDUM 3 -HAZARDS SUMMARY REPORT (AUGUST 1972)HSR, Addendum 3, Section 3.3, Evaluation of Peaking Factors in the MURR 6.2 Kg CoreDelete:Entire section.Replace with:Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR,as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 11).ADDENDUM 4 -HAZARDS SUMMARY REPORT (OCTOBER 1973)HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURRDelete: Entire section.Replace with:Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR,as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 11).HSR, Addendum 4, Appendix H, Bases for Limiting Safety System Settings for Modes I and I!Operation Delete:Entire section.Replace with: Revised HSR, Addendum 4, Appendix H, Bases for Limiting Safety SystemSettings for Modes I and II Operation, as submitted with the application toamend Amended Facility License No. R-103, dated August 19, 2011(Attachment 12).ADDENDUM 5 -HAZARDS SUMMARY REPORT (JANUARY 1974)HSR, Addendum 5, Section 6, Addendum to the Safety Limit Analysis for the MURRDelete:Entire section.Replace with: Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR,as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 1I).111-4 SECTION IVPLANT AND SYSTEM MODIFICATIONS January 1, 2013 through December 31, 2013For each facility modification described below, MURR has on file the safety screen or evaluation, as wellas the documentation of review, performed in accordance with 10 CFR 50.59.Modification 11-03, Addendum 1:Addition of Blow-Down Meter to the Data Acquisition Monitoring SystemThis addendum to modification record 11-03, "Data Acquisition and Monitoring System for Secondary Coolant System" documents the installation of an additional component to the Data Acquisition andMonitoring System for the Secondary Coolant System. A secondary coolant blow-down transmitter andassociated indication were installed to assist in monitoring the amount of secondary coolant that is requiredto be discharged to the sanitary sewer in order to maintain appropriate Secondary Coolant Systemchemistry control.Modification 12-01:Replace PT-944A/B with Rosemount Transmitters This modification record documents the replacement of two pressure transmitters, PT-944A and PT-944B,which sense reactor core outlet pressure in the Primary Coolant System. The previous pressure transmitters could not be directly replaced due to obsolescence of both the transmitters and repair parts. Thereplacement pressure transmitters meet or exceed the performance specifications of the previoustransmitters.

Modification 12-02:Control Blade Fabrication Alternative Using Laser WeldingThis modification record documents a fabrication alternative for construction of the control blades. Anassembly method using laser welding on the edge channels required a change in the edge channel alloy. Amore streamlined connection between the top mounting plate and the BORALC absorber plate was alsodocumented.

Modification 13-01:Replacement of TE-980A and TE-980B Power Supply 2PS5This modification record documents replacement of the power supplies for the temperature instrument channels on Primary Heat Exchanger outlet temperatures, TE-980A and TE-980B.

The previous powersupply, 2PS5, was obsolete and unavailable for purchase.

The replacement power supply EP-91 IC meetsor exceeds the performance specifications of the previous power supplies, and was relocated from behindthe Instrument Cabinet to the former General Electric Measurement and Control (GE/MAC) rack on theInstrument Cabinet face.IV-I Modification 04-03, Addendum 1:Liquid Radioactive Waste System In MURR Industrial BuildingThis addendum to modification record 04-03, "Liquid Radioactive Waste Modification" documents thechanges required to incorporate the MURR Industrial Building (MIB) Liquid Radioactive Waste (LRW)system into the existing facility LRW system.Modification 75-01, Addendum 3:Rod Run-In Electronic Circuit Jumper PanelThis addendum to modification record 75-01, "Electronic Circuits Jumper Panel" documents theinstallation of a jumper panel dedicated to the rod run-in system. This jumper panel supports the use of therod run-in system monitoring circuit installed under Modification Record 13-04.Modification 13-04:Rod Run-In Monitoring SystemThis modification record documents the implementation of a passive monitoring circuit on the rod run-insystem to improve troubleshooting capabilities for rod run-in signals that are too short in duration to detectwith the annunciator system. The monitoring circuit works in conjunction with a new jumper paneldedicated to the rod run-in system, and provides additional unused monitoring capacity for futuretroubleshooting expansion.

The monitoring circuit was constructed in a manner similar to the reactorscram system monitoring circuit.Modification 13-02:Replacement of Secondary Chemistry Controllers This modification record documents the replacement of the Secondary Coolant System pH and conductivity controllers.

The previous model controllers had become obsolete and repair parts were no longer available.

The replacement controllers meet or exceed the performance specifications of the existing controllers.

Modification 13-03:Replacement of the GH and IJ Wedge with a Single 60-Degree WedgeThis modification record documents the redesign and replacement of the 30-degree "GH" and "IJ" graphitereflector elements with a single 60-degree graphite reflector element (GHIJ). The new reflector elementaccommodates a 6-inch irradiation position as well as a 3-inch, two 2-inch and two 1-inch irradiation positions designated G-6, B-3, B-2 and R-2, G-I and H-I, respectively.

The 6-inch irradiation position isdesigned such that a sleeve insert with nickels bands may be installed to allow for manipulation of the fluxprofile.

This insert is bolted securely to the element cover plate, and is inserted and/or removed only whenthe reactor is shutdown.

The reflector element is constructed of aluminum 6061-T6 with graphite in thevoid area.Modification 04-05, Addendum 8:Cooling Tower Electrical Arc Flash Danger Mitigation This addendum to modification record 04-05, "Cooling Tower Electrical Upgrade Project" documents thechanges to Motor Control Center 1 in order to provide for improved arc flash protection and subsequent classification reduction of the cooling tower motor control center.IV-2 Modification 01-02, Addendum 9:Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299)Renovations This addendum to modification record 01-02, "Installation of a New Reactor Facility Intercommunication and Paging System" documents changes to the facility Intercommunication and Paging System that willenhance communications in Rooms 299M, N and 0.Modification 01-02, Addendum 10:Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299),Room 243, Room 246 and Room 271 Renovations This addendum to modification record 01-02, "Installation of a New Reactor Facility Intercommunication and Paging System" documents changes to the facility Intercommunication and Paging System that willenhance communications in MURR Industrial Building (Room 299), Room 243, Room 246 and Room271B. It also documents the relocation of the Health Physics Office staff station from Room 288 to Room271B.Modification 13-05:T-300 & T-301 Level Sensing SystemThis modification to the Reactor Plant Make-Up Water Storage Tank System documents the replacement ofthe previous level sensing and annunciating instrument channels with current loop transmitters that alsodisplay the tank levels in the Control Room.Modification 13-06:Modifications to MURR Industrial Building (Room 299) in Support of the NS-99 ProiectThis modification record documents the remodeling of portions of the MURR Industrial Building (Room299) to provide the necessary space needs and services required to support the dispensing system for theNS-99 Project.IV-3 SECTION VNEW TESTS AND EXPERIMENTS January 1, 2013 through December 31, 2013New tests and experiments approved during this period under a Reactor Utilization Request (RUR) orReactor License (RL) Project are as follows:RUR 441: Natural Uranium Oxide Irradiation

==

Description:==

This RUR authorizes the irradiation of up to 5.0 grams of natural UraniumOxide in the reflector region of the reactor in support of research anddevelopment activities for medical applications.

RUR 271, as amended:

Yttrium Microspheres:

==

Description:==

This RUR was amended twice during calendar year 2013. The first amendment authorizes the use of quartz as a primary encapsulation and removed therequirement for the secondary encapsulation of aluminum for the microsphere targets.

A second amendment to RUR 271 authorizes the use of discs, adifferent physical form of the same target material for irradiation.

RL-80: Selective Gaseous Extraction of Fission ProductsDescription:

This RL authorizes the processing of up to 5.0 grams of natural Uranium Oxideto investigate Selective Gaseous Extraction as a novel separation process forproducing radioisotopes from the fission of uranium.Each of these tests or experiments has a written safety evaluation on file and a 10 CFR 50.59 Screen, ifapplicable, to assure that the test or experiment is safe and within the limits of the Technical Specifications.

The safety evaluations have been reviewed by the Reactor Manager, Reactor Health Physics Manager,Assistant Reactor Manager-Physics, and the Reactor Safety Subcommittee, as applicable.

V-1 SECTION VISPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2013 through December 31, 2013Inspections:

There was one NRC inspection reviewing Special Nuclear Material (SNM) activities.

All records andactivities were found to be in compliance with NRC rules and regulations.

No violations were noted.Reactor Characteristic Measurements:

Sixty-six (66) refueling evolutions were completed in 2013. Excess reactivity verification was performed for each refueling.

The largest measured excess reactivity was 3.32%. MURR Technical Specification

3. 1(f) requires the excess reactivity to be less than 9.8%.Reactivity Measurements:

Differential blade-worth measurements of three (3) shim control blades were performed following either aplanned replacement of a control blade or characterization of the bum-in effect of a new control blade.Six (6) reactivity measurements were performed to determine the reactivity worth of all 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 cansirradiated in the flux trap region, including the worth of an empty sample holder.Two (2) measurements were performed to determine the reactivity worth of the newly constructed GHIJ60-degree graphite reflector element and the target irradiation positions associated with the new reflector element.In support of the Nuclear Engineering student labs, one (1) differential blade-worth measurement and one(1) primary coolant temperature coefficient measurement were also performed.

VI-I SECTION VIIRADIOACTIVE EFFLUENTJanuary 1, 2013 through December 31, 2013TABLE 1SANITARY SEWER EFFLUENTJanuary 1, 2013 through December 31, 2013Descending Order of Activity Released for Nuclide Totals > 1.000E-05 CiNuclideH-3S-35Lu-177Co-60Ca-45P-32Mo-99Zn-65W-181Cr-51Ag-110mSc-46Tc-99m1-131As-76Total H-3Total OtherActivity (Ci)9.816E-02 7.312E-03 6.619E-03 2.256E-03 1.558E-03 1.384E-03 9.858E-04 6.517E-04 3.125E-04 5.560E-05 3.384E-05 3.075E-05 2.664E-05 1.592E-05 1.052E-05 9.816E-01 2.128E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."

VII-1 TABLE 2STACK EFFLUENTJanuary 1,2013 through December 31, 2013Ordered by % Technical Specification (TS) LimitIsotope Average Concentration Total Release TS Limit Multiplier

% TS(pCi/ml)

(Ci)Ar-41 2.73E-06 1.22E+03 350 78.1054H-3 2.21E-08 9.89E+00 350 0.0633Kr-79 6.72E-09 3.OOE+00 350 0.02741-131 3.38E-14 1.51E-05 1 0.0169K-40 6.02E-14 2.69E-05 1 0.0100C-14 2.48E-11 1.13E-02 1 0.0083Co-60 2.70E- 15 1.21E-06 1 0.00541-125 1.12E-14 4.99E-06 1 0.0037Sn- 113 2.55E-15 1.14E-06 1 0.0003Xe-135m 1.94E- 11 8.65E-03 350 0.0001Os-191 2.04E- 15 9.12E-07 1 0.00011-133 1.96E- 13 8.76E-05 350 0.0001Note: C-14 activity is calculated based on the ratio of argon to nitrogen in the air and the (n,p) reaction crosssections for the activation of N-14 to C-14.Isotopes observed at < 0.0001% Technical Specification limit are not listed.Stack Flow Rate = -30,000 cfmStack effluent releases are in compliance with University of Missouri-Columbia Research

Reactor, License R-103Technical Specifications.

VII-2 SECTION VIIIENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYSJanuary 1, 2013 through December 31, 2013Environmental samples are collected two times per year at eight (8) locations and analyzed for radioactivity.

Soiland vegetation samples are also taken at each location.

Water samples are taken at three (3) of the eight (8)locations.

Subsurface soil monitoring commenced in 2013 with six (6) samples taken 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 2013. Alldoses are approximately 20 mRem/year or less, except monitor numbers 9 and 15. These monitors are located nearloading dock areas where packages containing radioactive material are loaded on transport vehicles.

The dosesrecorded by these monitors are considered to be the result of exposure to packages in transit.

Additionally, during2013, six (6) monitoring sites around the reactor facility were chosen for subsurface soil monitoring.

The subsurface results are presented along with the traditional monitoring locations and results.

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 1SUMMARY OF ENVIRONMENTAL SET 83Spring 2013Detection Limits]MatrixWaterSoilVegetation Subsurface SoilAlpha0.00 pCi/L0.58 pCi/g0.00 pCi/g1.00 pCi/gBeta3.14 pCi/L3.47 pCi/g8.94 pCi/g3.32 pCi/gGamma189.00 pCi/L0.61 pCi/g1.53 pCi/g0.57 pCi/gTritium5.26 pCi/mL of sampleN/A6.33 pCi/mL of distillate N/AActivity Levels -Vegetation SampleI V832V833V834V835V836V837V8310V83Aloha (oCi/g)0.350.350.000.350.000.701.380.70Beta (pCi/g)42.7830.5323.1336.5432.5032.4025.1646.64Gamma (pCi/g)2.522.25< 1.53< 1.53< 1.532.29< 1.532.97H-3 (pCi/mL)< 6.33< 6.33< 6.33< 6.33< 6.33< 6.33< 6.33<6.33VIII-I TABLE 1 (Cont'd)SUMMARY OF ENVIRONMENTAL SET 83Spring 2013Activity Levels -SoilSampleIS832S833S834S835S836S837S8310S83Alpha (pCi/g)1.47<0.58<0.581.152.031.671.15<0.58Beta (pCi/g)21.8519.1016.5021.1623.0414.9827.9126.60Gamma (pCi/g)3.460.972.641.721.092.211.962.29Activity Levels -WaterSample4W836W8310W83Alpha (pCi/L)1.060.180.35Beta (pCi/L)3.754.1212.36Gamma (pCi/L)< 189.00< 189.00< 189.00H-3 (pCi/mL)< 5.26< 5.26< 5.26Activity Levels -Subsurface SoilSamplePSS83NESS83NSS83WSS83ESS83SSS83Alpha (1Ci/2)1.501.501.501.50< 1.001.32Beta (pCi/g)26.8825.0027.8122.3821.2618.82Gamma (pCi/g)3.955.513.183.644.185.81Note 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-2 TABLE 2SUMMARY OF ENVIRONMENTAL SET 84Fall 2013Detection Limits'MatrixWaterSoilVegetation Subsurface Alpha0.00 pCi/L0.73 pCi/g2.53 pCi/g0.82 pCi/gBeta3.64 pCi/L3.98 pCi/g7.98 pCi/g4.35 pCi/gGamma222.00 pCi/L0.55 pCi/g1.56pCi/g 0.62 pCi/gTritium5.68 pCi/mL of sampleN/A5.21 pCi/mL of distillate N/AActivity Levels -Vegetation Sample1 V842V843V844V845V846V847V8410V84Alpha (oCi/,)< 2.53< 2.53< 2.53<2.53< 2.53< 2.53<2.532.84Beta (pCi/g)33.8839.6417.2621.1927.7212.9139.3231.95Gamma (pCi/g)2.511.862.811.97< 1.56< 1.56< 1.56< 1.56H-3 (pCi/mL)< 5.21< 5.21< 5.21< 5.21< 5.21< 5.21< 5.21< 5.21Activity Levels -SoilSample1S842S843S844S845S846S847S8410S84Alpha (pCi/g)< 0.73< 0.73< 0.73< 0.73< 0.73< 0.731.771.26Beta (pCi/g)20.1810.3517.9310.7121.5213.1117.1321.68Gamma (pCi/g)3.322.442.762.794.532.934.573.52VIII-3 TABLE 2 (Cont'd)SUMMARY OF ENVIRONMENTAL SET 84Fall 2013Activity Levels -WaterSample4W846W8410W84Alpha (pCi/L)0.630.160.00Beta (pCi/L)6.52< 3.6410.11Gamma (pCi/L)< 222.00< 222.00< 222.00H-3 (pCi/mL)<5.68< 5.68< 5.68Activity Levels -Subsurface SoilSamolePSS84NESS84NSS84WSS84ESS84SSS84Alpha (VCi/g)1.070.871.570.881.062.14Beta (pCi/g)22.5122.6226.1521.1621.9123.46Gamma (pCi/g)6.234.244.473.164.765.48Note 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-4 TABLE 3ENVIRONMENTAL TLD SUMMARYJanuary 1, 2013 through December 31, 2013Badge Direction Map Distance from 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.Number From MURR MURR Stack 2013 2013 2013 2013(meters)

Net mR Net mR Net mR Net mRTotal2013Net mR1234*5*6789101112131415161718192021222324252627282930313233343536373839404142*43*444546Control 0Control 1Control 2WSWN/A1660016600N/ANNESWSNENWENENNESSSEENENNENESEESENWSSWSSWSWWSWWNWNWNNWNNWNNWEENESSESENENWWNNNESpareSE3457272714914930131615665107293476606907236168110328480301141210255328671724671587499419690556491541137N/A657028.027.024.00.00.04.06.022.00.00.00.00.00.019.00.00.00.00.00.00.00.00.00.00.00.00.00.02.00.00.00.00.00.05.00.00.00.00.00.00.00.07.00.023.023.022.00.01.02.04.020.00.00.02.00.03.015.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.05.00.00.00.00.00.00.0missing4.00.025.024.024.00.05.05.03.015.00.02.03.00.00.014.00.00.00.00.00.00.00.00.00.03.00.00.03.04.00.00.01.00.00.02.00.00.01.00.00.00.0missing6.00.033.032.031.00.09.01.02.026.00.00.02.00.00.017.00.00.00.00.00.01.00.03.00.00.00.00.01.00.00.00.00.00.00.04.00.00.00.00.00.00.00.03.00.0109.0106.0101.00.015.012.015.083.00.02.07.00.03.065.00.00.00.00.00.01.00.03.00.03.00.00.04.06.00.00.01.00.00.016.00.00.01.00.00.00.00.020.00.0*These badge numbers are no longer used.VIII-5 TABLE 4NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYSJanuary 1,2013 through December 31, 2013Radiation JanuaryFebruaryMarchAprilMayJuneJulyAugustSeptember OctoberNovemberDecemberTOTALS9460976187979497801018574Surface Contamination*

94609761879794978010185741027Air Samples**

594445433649626362664511585RWPs107988471086109961027In 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 NotesNathan Hogue resigned as Assistant Health Physics Manager in August 2013.During calendar year 2013, MURR shipped 554 cubic feet of low-level radioactive waste containing 1.205 mCi of activity.

VIII-6 SECTION IXSummary of Radiation Exposure to Facility Staff, Experimenters and VisitorsJanuary I, 2013 through December 31, 2013TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUPJanuaryFebruaryMarchAprilMayJuneJulyAugustSeptember OctoberNovemberDecemberAC1218391415301507221BCS237010061321328DO1000000010447FOE HC/SH HP IRR4 419 128 76 346 90 617 534 121 30 450 207 130 414 109 37 434 219 00 340 89 93 335 122 75 310 II1 23 348 146 78 411 178 02 282 101 5NA NS OPS PRO QA RES lIP SIL TEE WC Total6 52 1443 121 29 10 47 140 0 27 24579 62 1169 72 8 37 13 107 0 121 206711 34 1371 77 25 24 35 87 0 99 248411 22 1352 109 7 4 48 *86 5 254 25822 21 1612 127 65 2 22 78 0 19 24994 84 1995 109 63 100 38 177 4 38 327512 1 1651 153 42 11 25 168 0 16 252315 54 2042 139 82 6 44 224 4 17 312327 42 1598 129 47 4 246 137 8 39 270722 62 1666 130 85 9 65 94 2 101 276421 112 1865 117 21 2 28 411 0 37 321942 58 1725 171 32 7 30 114 2 23 2630Total for Year 146Monthly Avg 1266 26 55 4623 1621 6262 5 385 135 5182 604 19489 1454 506 216 641 1823 2515 50 1624 121 42 18 53 152 264 212 1236 407 154 144 311 998 82929 370 1556 5524 513 538 1832 1237 168791 3233066 2694Highest WB 31 26 6 25 1565 425 57(annual)High EXT 479 58 NR NR 3397 866 NR(annual)241893AC -Analytical Chemistry BCS -Business

& Central ServicesDO -Director's OfficeFOE -Shops & SupportHC/SH -Hot Cell/Shipping HP -Health PhysicsIRR -Irradiations NA -Nuclear AnalysisNS -Neutron Scattering OPS -Operations PRO -Isotope Processing QA -Quality Assurance RES -ResearchRP -Radiopharmaceutical SIL -SiliconTEE -Trace Elemental Epidemiology WC -Work ControlWB = Whole BodyEXT = Extremities M = MinimalNR = None ReportedAnalysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA.Radiation workers who are not full time staff members have radiation exposures which are generally lower than full time radiation workers.NOTES:Dosimetry services are provided by Mirion Technologies (except self reading dosimetry).