ML13058A025

University of Missouri, Columbia Research Reactor, 2012 Reactor Operations Annual Report

ML13058A025
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/26/2013
From:	Fruits J Univ of Missouri
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13058A025 (38)

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UNIVERSITY of MISSOURI RESEARCH REACTOR CENTER February 26, 2013 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 2012 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, 2012 through December 31, 2012.

This document is submitted to the U.S. Nuclear Regulatory Commission in accordance with the University of Missouri Research Reactor Technical Specification 6.1 .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: www.murr.missouri.edu Fighting Cancer with Tomorrow's Technology

UNIVERSITI(YOF MIISSURI UILVJER.IEY OF MESSOURE RESEARCH RIEACThIR REACTOR OPERATKENS ANNUAL REPORT m121~muoy ý, 2KI~2 - Decelber M~, 2012

UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2012 through December 31, 2012 Compiled by the Research Reactor Staff of MURR Submitted by:

// John lK. Fruits Reactor Manager Reviewed and approved by:

Ralph A. Butler, PE Director

UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2012 through December 31, 2012 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 2012. 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. l.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) implementing License Amendment No. 35 to Amended Facility License R-103, which approved the addition of an engineered safety device to the reactor protection system which increased the capacity and flexibility of the flux trap, (2) installing and placing a new Cooling Tower on service, (3) performing cleaning and replacement of the plates on primary coolant heat exchangers HX-503A and HX-503B, and (4) responding to Requests for Additional Information for the amendment to MURR Technical Specification 2.1, "Reactor Core Safety Limit." Additionally, in August 2006 MURR submitted a request i

to the NRC to renew Amended Facility Operating License R-103. Significant efforts have already been placed in responding to the Requests for Additional Information and these efforts will continue in the upcoming 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 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.

MURR also hosted the 5t' International Symposium of Material Testing Reactors (ISMTR). Since 2008, users, operators, researchers and specialists frorn Material Testing Reactors (MTR) throughout the world have gathered each year to exchange knowledge and experiences particular to the scope of their activities.

The ISMTR encourages participants to engage in teamwork and build relationships that promote the continuous development and expansion of this collaborative worldwide network of specialists, organizations and companies involved in MTR operation. The Symposium also included'the 7 th Specialist Meeting on Recycling of Irradiated Beryllium. The objective of this meeting was to exchange information on beryllium used at MTRs, especially material selection, recycling of irradiated beryllium, lifetime expansion and waste management.

Reactor Operations Management also wishes to commend the two individuals who received their Reactor Operator certifications and the two individuals who received their Senior Reactor Operator certifications from the NRC. These individuals participated in a rigorous training program of classroom seminars, self-study, and on-the-job training. The results of this training are confident, well-versed, decisive individuals capable of performing the duties of a licensed operator during normal and abnormal situations.

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TABLE OF CONTENTS Section Title Paaes

1. Reactor Operations Sum m ary ............................................................... I- I through 8 II. M U R R Procedures ................................................................................ I1-1 through 6 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 Ill. Revisions to the Hazards Summary Report .......................................... Ill-1 through 5 IV . Plant and System M odifications ........................................................... IV-I through 3 V. New Tests and Experim ents ............................................................ V-1 VI. Special Nuclear Material and Reactor Physics Activities ..................... VI-l V II. Radioactive Effl uent ............................................................................. V II- I through 2 Table I - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII. Environmental Monitoring and Health Physics Surveys ...................... VIII- I 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 Visitors ........................................ IX-I

SECTION I REACTOR OPERATIONS

SUMMARY

January I, 2012 through December 31, 2012 The following table and discussion summarizes reactor operations during the period from January I, 2012 through December 31, 2012.

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

January 548.26 261.12 73.7 82.5 February 632.19 263.77 90.8 101.8 March 679.96 283.49 91.4 102.3 April 634.70 264.68 88.2 98.9 May 658.73 274.85 88.5 99.1 June 645.22 269.08 89.6 100.5 July 667.47 278.33 89.7 100.4 August 670.50 279.18 90.1 100.9 September 657.20 274.01 91.3 102.4 October 661.70 275.93 88.9 99.6 November 645.13 269.04 89.6 100.5 December 665.64 277.57 89.5 100.2 Total for 7766.70 3271.05 88.45 % 99.09 %

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 2012 The reactor operated continuously in January with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and three unscheduled/unplanned power reductions.

On January 2, during a regularly scheduled reactor shut down with the reactor power level less than 100 kW, a "Power Level Interlock" scram was automatically initiated. The immediate actions of REP-3, "Primary Coolant System Low Pressure or Flow Scram," were performed. Investigation revealed that improper manual adjustment of primary coolant heat exchanger automatic temperature control valve S-I increased the cool down rate of the primary coolant at a rate greater than what could be automatically compensated by the pressurizer system. Control room operators were counseled on the implications of manual adjustments to components controlling the rate of cooling and the difference of effects while above or below the point of adding heat. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager following previously scheduled maintenance activities.

On January 17, with the reactor operating at 10 MW in the automatic control mode, the reactor was manually shut down after an unexplained 3% step decrease in power level indication was observed on Nuclear Instrumentation Power Range Monitor No. 5. The duty operator noted all other power level and period indications were normal. All 1-1

immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were performed.

During troubleshooting, all safety functions associated with Nuclear Instrumentation Signal Process No. 2 were verified operational. Additional efforts revealed occasional small down spikes on Nuclear Instrumentation Intermediate Range Monitor No. 3 which led to the replacement of the preamplifier, and fission chamber detector and cabling for Nuclear Instrumentation Signal Processor No. 2. 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.

On January 19, 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 shimming evolution. The reactor was shut down. An inspection of the offset mechanism pull rod and housing revealed a slight misalignment. The offset housing was realigned and the anvil and magnet were cleaned.

The control rod was satisfactorily withdrawn to the full out position as part of the retest by performing Compliance Procedure No. 10, "Rod Drop Times." The reactor was refueled and 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: placing the new cooling tower on service; performing internal cleaning and inspection of primary coolant system heat exchanger HX-503A; replacing preamplifier, fission chamber and associated cabling for Nuclear Instrument Signal Processor No. 2; loading new de-ionization bed 'R' and placing it on pool coolant system service; and refurbishing ventilation exhaust isolation valve 16B solenoid-operated air control valve A-]153.

February 2012 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 27, 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 routine movement of the startup neutron source. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The flux trap sample holder was verified to be latched to the inner reactor pressure vessel. The operators involved were counseled on the importance of proper handling techniques near the FIRST Support Rig. Permission to restart the reactor was obtained from the Reactor Manager and the reactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included: implementing Amendment No. 35 "Flux-Trap Irradiations Reactivity Safety Trip Device" to Amended Facility License R-103; completing Modification Record 11-01, "Flux-Trap Irradiations Reactivity Safety Trip (FIRST) Instrument Channels;" completing Modification Record 75-16, Addendum 4, "Reactor Safety System Monitoring Circuit (White Rat) Panel - Revision to Panel Overlays in Support of the FIRST Device;" completing Modification Record 10-02, "Addition of MURR Systems to Lab 251;"

completing Modification Record I 1-02, "Replace Cooling Tower;" 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);" and performing a reactivity worth measurement in accordance with reactor 1-2

procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-1 I(D)," in support of a Nuclear Engineering Department practicum.

March 2012 The reactor operated continuously in March 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 the air actuator on Primary Coolant Demineralizer Inlet Isolation Valve 527E; refurbishing Reactor Pool Below Refuel Level Relay 2K5; 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 a reactivity worth measurement in accordance with reactor procedure RP-RO-203, "Measurement of the Primary Coolant/Moderator Temperature Coefficient of Reactivity, RTP-19," in support of a Nuclear Engineering Department practicum; and replacing the secondary coolant supply header piping from Temporary Cooling Isolation Valve S-238 to the through-wall portion of the secondary coolant pump suction piping.

April 2012 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and four shutdowns for physics measurements. There were no unscheduled/unplanned power reductions this month. U.S. Nuclear Regulatory Commission regional inspector arrived at the facility for a routine inspection of the Radiation Protection Program and Shipping.

Major maintenance items for the month included: performing four 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);" performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP- 11(D);" replacing the Regulating Blade Drive Rotary Limit Switch; and completing the biennial change-out of Control Blade 'B' Offset Mechanism and associated retesting.

May 2012 The reactor operated continuously in May with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and four unscheduled/unplanned power reductions.

On May 19, with the reactor operating at 10 MW in the automatic control mode, a manual scram was initiated when an operator discovered the drive sprocket on the regulating blade rotary limit switch assembly not rotating during a normal regulating blade movement. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Subsequent investigation discovered that the set screws that secure the drive sprocket to the drive shaft had disengaged. The regulating blade rotary limit switch drive sprocket and associated set screws were replaced. All functions initiated by the regulating blade rotary limit switch assembly were tested satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

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Failure of the regulating blade rotary limit switch assembly to be operable during reactor operation resulted in a deviation from Technical Specification 3.4.c, which states, "The reactor shall not be operated unless the/1b/lowing rod run-in ffiunions are operable. Each of the rod run-in functions shall have I/N logic where N is the number of instrument channels requiredfor the corresponding mode of operation." The two rod run-in functions associated with "Regulating Blade Position" are the "< 10% withdrawn and bottomed. " Licensee Event Report 12-01, providing a detailed description of this event and the corrective actions taken, was submitted to the U. S. Nuclear Regulatory commission with the 30-day reporting requirements.

On May 26, 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 routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The flux trap sample holder was verified to be latched to the inner reactor pressure vessel. The operators 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.

On May 27, with the reactor operating at 10 MW in the automatic control mode, a manual scram was initiated after the duty operator observed a greater than abnormal lowering of pressurizer liquid level. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Subsequent investigation discovered leakage from primary demineralizer inlet filter F-201 housing lower sealing gasket. All gaskets on the filter housing were replaced and satisfactorily leak checked. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

On May 30, 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 routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The flux trap sample holder was verified to be latched to the inner reactor pressure vessel. The operators 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.

Major maintenance items for the month included: completing Modification Record 09-03, "Lab Impex Stack Monitoring System;" completing Modification Record 09-03, Addendum 1, "Update to Lab Impex Stack Monitoring System;" completing compliance procedure CP-26, "Containment Building Compliance Test;" installing replacement plates in primary coolant heat exchanger HX-503B; loading new de-ionization bed 'L' and placing it on pool coolant system service; 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 2012 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown 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 Security and Material Control and Accountability.

On June 28, with the reactor operating at 10 MW in the automatic control mode, a manual scram was initiated after the duty operator observed a greater than normal lowering of pressurizer liquid level. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Upon investigation of Mechanical 1-4

Equipment Room 114, which contains a large portion of the cooling equipment for tile reactor, primary coolant was found leaking from primary heat coolant system exchanger HX-503A Outlet Valve 540A. The valve was isolated and that section of the primary coolant system drained in order to remove the bonnet for an internal inspection of the valve. It was discovered that the valve diaphragm had ruptured. The diaphragm was replaced, the system refilled and then leak tested satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

Major maintenance items for the month included: completing Modification Record 05-0 1, Addendum 3, "Pneumatic Tube System Changes in Lab 227;" performing a reactivity worth measurement in accordance with reactor procedure RP-RO-202, "Measurement of Reactivity Worth of Movable Samples, RTP-6;" and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP- 17(B).

July 2012 The reactor operated continuously in July with the following exceptions: five 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: 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 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 air actuator on Primary Coolant Demineralizer Inlet Valve 527E; completing Modification Record 0 1-09, Addendum 4, "Emergency Electrical Power System in Room 231;" completing Modification Record 98-02, Addendum 1, "Sulfuric Acid System Changes in Support of Cooling Tower Replacement;" completing Modification Record 03-03, Addendum 3, "Fire Protection System Changes in Support of Cooling Tower Replacement;" and replacing the diaphragm on primary coolant system heat exchanger HX-503A Outlet Valve 540B.

August 2012 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions. Additionally, two reactor startups and one reactor shutdown were performed in support of U.S. Nuclear Regulatory Commission operator licensing examinations. Received notification from the U.S. Nuclear Regulatory Commission that two new Reactor Operator and two new Senior Reactor Operator licenses had been issued.

On August 21, with the reactor operating at 10 MW in the automatic control mode, a "Power Level Interlock or FIRST" scram was automatically initiated when an operator attempted to replace a lamp in the light box of Control Rod Drive Mechanism 'A' "Power On" indication. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Further investigation determined that the new lamp had dropped from the light box into the indication housing assembly, thereby momentarily causing a short across the power supply contacts. The resultant voltage drop was sufficient to initiate a Power Level Interlock scram. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

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On August 23, 2012, with the reactor operating at 10 MW in the automatic control mode, the control room operator discovered that the automatic control switches for Pressurizer Water Drain Valve 527A were in the manual and closed positions. The automatic/manual switch for valve 527A was immediately placed in the automatic position.

This valve is required to be in the automatic position whenever the reactor is in operation. At the time, pressurizer liquid level was approximately 3.0 inches below centerline (-3), which is within the normal operating band of +4 to -7 inches. With Pressurizer Water Drain Valve 527A switch in the manual position, a valve interlock would have prevented Pressurizer Water Fill Valve 527B from opening and primary coolant charging pump P-533 from starting had pressurizer liquid level decreased to a set point of-6 inches.

Primary coolant charging pump P-533 delivers makeup water to tile primary coolant system via the pressurizer from makeup water storage tank T-300. In accordance with Technical Specification 3.10.b, "the reactor shall not be operated unless the reactor makeup water system is operable and connected to a source of at least 2,000 gallons qf primary grade water." The basis for this Technical Specification is to provide "...an adequate supply of primary grade water.i[r makeup during all modes qf'operation." With the potential of coolant charging pump P-533 not starting as required by system demand, the reactor makeup water system was in a degraded state and not considered operable. Licensee Event Report 12-02, providing a detailed description of this event and the corrective actions taken, was submitted to the U. S. Nuclear Regulatory commission with the 30-day reporting requirements.

On August 30, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact with Magnet" rod run-in automatically initiated. The duty operator noted no additional indications of a rod not in contact with its magnet and initiated a manual reactor scram. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed Troubleshooting efforts discovered that a solder connection on the magnet engaged circuit for Control Rod Drive Mechanism 'A' had failed. The connection was repaired and operation of the Control Rod Drive Mechanism retested satisfactorily. 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);" and completing compliance procedure CP-3 1, "Calibration of the Eberline Radiation Stack Monitor."

September 2012 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one scheduled shutdown for physics measurements. 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-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" performing a reactivity worth measurement in accordance with reactor procedure RP-RO-202, "Measurement of Reactivity Worth of Moveable Samples, RTP-6;" and loading new de-ionization bed 'V' and placing it on pool coolant system service.

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October 2012 The reactor operated continuously in October with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month. U.S. Nuclear Regulatory Commission regional inspector arrived at the facility for a routine inspection of Reactor Operations and Emergency Preparedness.

Major maintenance items for the month included: performing a zero and span procedure on Pool Coolant Heat Exchanger Outlet temperature element TE-90 ID; replacing the motor for primary coolant circulation pump P-50 IA; completing Modification Record 01-02, Addendum 8, "Intercommunication and Paging System Changes in Support of the Sterility Suite Rooms 2045A and 2045B;" completing compliance procedure CP-29, "Calibration of Lab Impex Stack Monitor;" and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-20 1, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP- I7(B)."

November 2012 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, and one unscheduled/unplanned power reduction.

On November 13, with the reactor operating at 10 MW in the automatic control mode, a "Bldg Air Plenum and Bridge Hi Activity" reactor scram and containment building isolation were automatically initiated. The immediate actions of emergency procedure EP-RO-012, "Reactor Isolation," were performed. Remote monitoring (external to the reactor containment building) of all containment area radiation monitors indicated normal radiation levels with the exception of Containment Building Exhaust Plenum - No. 2 Radiation Monitor, whose indication was pegged high off scale. After re-entry into the reactor containment building, troubleshooting efforts determined that Containment Building Exhaust Plenum - No. 2 Radiation Monitor detector assembly had failed. The detector assembly and electronic control module were replaced. Proper operation was verified by performance of the applicable portions of compliance procedure CP-30, "ARMS and 16-Inch Valve Cabinet and Associated Horns and Lights." 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);" replacing the displacer cable for the anti-siphon system level controller, LC965; replacing the motor for primary coolant demineralizer pump P-513A; and performing a calibration of the iodine chart recorder for the Lab Impex Stack Monitor.

December 2012 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and three shutdowns for physics measurements. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: completing compliance procedure CP-31, "Calibration of the Eberline Radiation Stack Monitor;" completing the biennial change-out of Control Blade 'D' Offset Mechanism and 1-7

associated retesting: 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);" and perfonning three 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)."

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SECTION I1 MURR PROCEDURES January 1,2012 through December 31, 2012 As required by administrative Technical Specification 6.1.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. l.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-four (64) revisions issued to the reactor operations procedures, forms and operator aids.

Additionally, one (1) outdated procedure was 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:

• Num'ber AP-RO-10 Iic Conduct Name of Operations.............. 17 lR 2/8/2012 iski*n Di[te Notes, Minor Editorial AP-RO-l 10 lConduct of Operations 18 11/86/2012 j Minor Editorial AP-RO-135 oReactor Utilization Requests 1 2/8/2012 1 Minor Editorial AP-RO-135 ]Reactor Utilization Requests 12 10/24/2012 Minor Editorial EX-RO-105 Reactor Irradiation Experiments 16 3/5/2012 Minor Editorial EX-RO-l105 Reactor Irradiation Experiments 17 6/8/2012 Minor Editorial EX-RO- 105 Reactor Irradiation Experiments 118 12/4/2012 Minor Editorial EX-RO-120 Beamport "A" Operation 10 8/21/2012 Cover Page EX-RO-121 JBeamport "B" Operation 10 8/21/2012 1 Cover Page EX-RO-122 JBeamport "C" Operation EX-RO-123 ]Beamport "D" Operation 10T 8/21/2012

]10J 8/21/2012 T _CoverPage Cover Page EX-RO-124 JBeamport "E" Operation I 1 8/21/2012 j Cover Page EX-RO-125 JBeamport "F" Operation T 12 8/21/2012 T Cover Page EX-RO-126 ]Thermal Column Door T81 12/4/2012 Cover Page FM-I I lReactor Shutdown Checksheet I5 1/12/2012 Cover Page FM-15 10 CFR 50.59 Qualified Reviewers List j 14 T 7/31/2012 Minor Editorial .

FM-18 IDeviation From Procedure Report 6 T 12/4/2012 Cover Page FM-19 JUnscheduled Power Reduction Report I 4 1/12/2012 Cover Page FM-33 lContainment Building Restricted Materials T4T 12/4/2012 If Cover Page FM-43 INuclear and Process Data 16 3/5/2012 Minor Editorial FM-47 jDeviation From Procedure Report T6F 10/17/2012 I Minor Editorial FM-56 lReactor Routine Patrol ]15 T 3/5/2012 I Minor Editorial FM-57 JLong Form Startup Checksheet 1 1 3/5/2012 Minor Editorial FM-57 ]Long Form Startup Checksheet 19 12/4/2012 Cover Page I1-1

JNumber i Namfe~ R evy.4tvision DateI Notes~

FM-58 IShort Form Startup Checksheet 10 12/4/2012 Cover Page FM-63 IDI Water Makeup Log T 8 2/8/2012 Cover Page FM-68 ITarget Material Control Checksheet 1 10 { 8/1/2012 Minor Editorial FM-68 fTarget Material Control Checksheet I1 10/10/2012 Minor Editorial OA-4 lValve Operation Air Compressor T6 12/4/2012 Minor Editorial OA-5 ]Emergency Air Compressor T6 j 12/4/2012 T Minor Editorial OP-RO-100 IMain Air System T9 f 3/5/2012 T Minor Editorial OP-RO-101 lInstrument Air System 9 f 3/5/2012 Minor Editorial OP-RO-2 10 lReactor Startup-Normal 12 f 8/1/2012 T Minor Editorial OP-RO-211 ]Reactor Startup-Hot T f10 8/1/2012 T Minor Editorial OP-RO0212 Reactor Startup - Recovery from Temporary Power 10 8/1/20 12 Minor Editorial OP-RO-212 Reduction l0_8/ I MnrEioa OP-RO-220 [Reactor Shutdown or Power Reduction T7 6/29/2012 1 Cover Page OP-RO-230 ]Changing Reactor Power Level 7 6/29/2012 j Cover Page OP-RO-310 [Nuclear Instrumentation - Signal Processor #1 T9 6/8/2012 Minor Editorial OP-RO-311 Nuclear Instrumentation - Signal Processor #2 T10 [ 6/8/2012 Minor Editorial OP-RO-312 Nuclear Instrumentation Power Range Monitor - 1 6/8/2012 Channel 6 12 6/8/2012 Cover Page OP-RO-330 Nuclear Instrumentation - Wide Range Monitor T 9 6/8/2012 Cover Page OP-RO-340 Nuclear Instrumentation Adjustment T 9 6/8/2012 Cover Page OP-R-350Adjustment/

OP-RO-350 Reactor Power Calculator Flow Potentiometer 6 86202ovrag 8/16/2012 Cover Page OP-RO-410 [Primary Coolant System T10 11/16/2012 Minor Editorial OP-RO-461 Pool Coolant System - One Pump Operation 13 6/29/2012 1 Minor Editorial OP-RO-480 ISecondary Coolant System T15 8/1/2012 1 Minor Editorial OP-RO-480 Secondary Coolant System 16 j 12/4/2012 1 Minor Editorial OP-RO-515 Emergency Air System T8 10/24/2012 1 Cover Page OP-RO-520 JEmergency Diesel Generator T10 10/24/2012 1 Cover Page OP-RO-525 ]Chill Water System _6__ 6/8/2012 Minor Editorial OP-RO-530 IDemineralized Water Supply System T12 { 8/16/2012 Minor Editorial OP-RO-531 jPrimary and Pool Sample Station T10 6/29/2012 Minor Editorial OP-RO-555 IFire Protection System T9 2/8/2012 Minor Editorial OP-RO-710 lRadiation Monitoring - Area Monitors T7 8/16/2012 Minor Editorial OP-RO-720 Radiation Monitoring - Stack Monitor Operational 3/5/2012 Minor RCheck _________ i Editorial OP-RO-720 adiation Monitoring - Stack Monitor Operational 10 6/29/2012 Minor Editorial REP-RO-100 lReactor Emergency Procedures 1'41 2/15/2012 Minor Editorial REP-RO- 100 [Reactor Emergency Procedures 15 9/11/2012 Minor Editorial RP-RO-100 [Fuel Movement 11 9/19/2012 Minor Editorial RP-RO-2102 RP-RO-202 Measurement of Reactivity Worth of Movable Samples, RTP-6

[ 6/8/2012 3I6/8/2012 iMinor Editorial Editorial Draining and Filling the Primary Coolant Side of 2/7/2012 Minor Editorial SM-RO-l00 Primary Coolant System Heat ExchangersI 2/7/2012_ I MinorEditorial Replace Primary and Pool Coolant System Heat SM-RO-105 1 2/7/2012 Cover Page

,Exchangers and Piping 11-2

,:.Number JName Revý.. Revision Date Notes SM-RO-625 Measuring Control Blade Pull Weight and Blade 2 10/24/2012 Cover Page Drop Time with the Test Magnet Assembly, RTP-2 2 SM-RO-650 Cleaning the Acid Day Tank Sight Glass 1 4/15/2011 Obsoleted SM-RO-660 IReplacement of Inner and Outer Pressure Vessels 2/7/2012 1 Minor Editorial 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 eight (8) 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:

Numiber. J .Name Rev. Revision Date .,Notes.

EP-RO-015 /Emergency Notifications 8 10/30/2012 Minor Editorial FM-104 ]Emergency Call List __19 I 1/20/2012. Minor Editorial  !

FM-104 Emergency Call List T-20 6/12/2012 Minor Editorial FM-104 Emergency Call List T T 21 10/30/2012 Minor Editorial OA-10 OA-20

]Fire Extinguisher Locations and Types Emergency Equipment T [ 8 12 12/28/2012 1/20/2012 Minor Editorial Minor Editorial OA-20 Emergency Equipment j 13 9/19/2012 j Minor Editorial OA-20 Emergency Equipment j 14 12/28/2012 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 Health Physics Manager reviewed the procedures for radioactive materials handling, shipping, and preparation for shipping of byproduct materials.

There were fifty-one (5 I) 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, and eight (8) 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:

JsNumnber~ "'Name << -(Rev. Revision Date NotcN A AP-HP-I 19 High Radiation AreaAccess 4 5/31/2012 Minor Editorial i AP-HP-120 Beamport Area 5 11/23/2010 Obsoleted AP-HP-121 Isotope Closet 1 5 1 12/30/2010 J Obsoleted AP-HP-123 Visitor Dosimetry - Reception Desk 8 1/12/2012 j Cover Page ........

AP-HP-125 Review of Unplanned Radiation Exposure 4 2/22/2012 Minor Editorial In-House Radioactive Shipping Request Form AP-SH-002 I 9/19/2012 Minor Editorial Instructions 11-3

u____-___

___N____be__ ____ I Rev . eston Datel, Notes 20WC- I Packaging and Shipment of Type B Non-] - r~

BPB-SH-002 PB-S-0 Packaging Waste Radioactive Material of Type B No11 0 I 7/25/2012 Minor Editorial DOT 6M Packaging of Type B Non-Waste BPB-SH-0205 31/29/2012 Minor Editorial Bai B Material nsRadioactive ckn" 0aaT IReceipt Inspection Of Type B Byproduct MaterialI BPB-SH-020 nont aine 3 12/5/2012 Minor Editorial BPB-SH-02o5 BP-H02 Type B(U) ZA/NNR 1005 (Beatrice) Packagingo nContainers uve B Non-Waste

_Type Dcnamnt~n° P1 etreShipping Radioactive Material Type B(U) F-327 Series Packaging of Type B I 01NePrcde I

I l

1/4/20-12 Minor Editorial BPB-SH-026 Mateln 1ontadioaci 9/19/2012 Minor Editorial BPBSH027

]Survey and Decontamination of Returned

~Shipping Containers 1018221 I_ _ _

e rcdr BPB-SH-028 ~oTYPE B(U) USA/93a37/B (U)-96 (LS) Packaging aiatv aeilj0 12/12/2012 jNew Procedure Nocagn-Wandste Radioactive Material mnt BP-SH052 BPB-SH-027 Radioactive Material Shipment S8crtkSrie Rual Package1yeA 0sn 1 8/202TMioEdtra

/12/2012 Noew Procedr jDocumentation and LabelingI I_______________

Radioactive Pakgn nMaterial Shipment Package Radioactive hpetof BP-SH-052 Docen and L Material I 10/2/2012 Minor Editorial BP-SH-052 BP-SH-059 eual Packaging and Shipment of Radioactive Material Using Spectratek Services Reusable Type yeA4 e3 A 8sn Ii 1/12/2012 8pcrtkSrie 6/12/2012 Minor Editorial Cover Page Package I Packaging and Shipment of Radioactive Material i BP-SH-C-059 Using Spectratek Services Reusable Type A 4 12/12/2012 Minor Editorial PackageI__I_ _ _ __ _ _ _

BP-SH-099 Packaging of Radioactive Material Using MURR Moe310 3 1/4/2012

/ 2T Minor Editorial FM-17 on Work Permit eminorEditorial 1 2 0 T FM-27 In-House Radioactive Shipping Request Form 1[ 9/19/2012 Minor Editorial FM-39 Control Checksheet for Excepted Package 1 //01 io dtra Radioactive Materials Shipment Control Checksheet for Documentation and1 FM-l o a 1M/2/a2012 Minor Editorial Control Checksheet for Spectratek Services FM-59 Reusable Type A Package Radioactive Materials 5 3/9/2012 Cover Page

____________Shipment_________________

Control Checksheet for Spectratek Services FM-59 Reusable Type A Package Radioactive Materials 6 12/12/2012 Minor Editorial

____________Shipment ____________________

FM-125_____

FM-79

[Lutetium Chloride Radiation Protection Data Sheet Bj 27

-1

//2012 1 Minr 0 e

io Control Checksheet for Type A F-327 Series 1 1/4/2012 CoverPage FM-91 [Declaration of Pregnancy 4 2/22/2012 Cover Page FM- 120 l1ndividual Type B QA Training Certification 14 1/4/2012 Cover Page FM- 125 [Lutetium Chloride Process Notification 121 3/22/2012 1 Cover Page FM-135 Control Checksheet for Type B(U) ZA/NNR 1005

______________(Beatrice) Radioactive Materials ShipmentI 1 1392 2 1 CvrPg FM-137 Type B Qualified Shipper List 0 12/12/2012 New Form 11-4

I -Number Name - Re& Revision

. DateN Control Checksheet for Leak Testing of the LS FM-138 Shipping Container Using the CALT 9 Leakage 0 12/12/2012 New Form Testing Device Required Documentation for Non-MURR Owned 7/25/2012 Minor Editorial FM- 156 FM-T158 Type B Shipping Containers NOA Waste Tank Sample Analysis _2 7 - Minor Editorial FM-158 [NOA Waste Tank Sample Analysis 1 2 7/25/2012 [ Minor Editorial FM-I162 Mo-99 Process HP Check Sheet 0 6/7/2012 [ New Procedure Control Checksheet for Type B(U)

FM-163 USA/9337/B(U)-96 (LS) Packaging ofj 0 12/12/2012 New Form Radioactive Material HC-PSO-002 Hot Cell Preparation of Radioactive Material for Shipment 11 12/10/2012 12/10/2012 Minor Editorial Glove Box Preparation of Radioactive Material for HC-PSO-003 9 12/10/2012 Minor Editorial Shipment o HC-PSO-005 Hot Cell Loading of Host Cans 90 1/19/2012 Minor Editorial HC-PSO-005 Hot Cell Loading of Host Cans [ 10 ]12/10/2012 Minor Editorial IC-HP-300 ICalibration - Radiation Survey Instruments 6 3/7/2012 Minor Editorial IC-HP-305 ICalibration - Electrostatic Discharge Dosimeter 171 1/13/2012 J Cover Page NMC Model RAK Stack Monitor / 0s IC-HP-318 Offsets/Multipliers/High Voltages Determination IC-HP-319 Calibration - NMC Model RAK Monitor -

Pa Iti Channel 1 4/4/2007 Obsoleted Calibration - NMC Model RAK Monitor - Iodine IC-HP-320 Channel 4/4/2007 Obsoleted Calibration - NMC Model RAK Monitor - Gas 1 IC-HP-321 Channe 4/18/2007 Obsoleted Calibration - Lab Impex Stack Monitor-Particulate IC-HP-349 [Channel 3 12/26/2012 Minor Editorial Calibration - Lab Impex Stack Monitor-Flow IC-HP-352 Calibration 2 5/31/2012 Minor Editorial IC-HP-353 IRR-PSO- 112 Calibration - Lab Impex Monitor - DP2001 Preparing Shipping Paperwork 161 1 12/26/2012 10/10/2012 1 Minor Editorial Minor Editorial OP-HP-200 Air Sampling- Containment Building Tritium 1 1/13/2012 Minor Editorial OP-HP-220 Tritium Bioassay j 8 8/2/2012 Cover Page OP-HP-355 INOA Waste Tank System Operation 1ii 1/13/2012 1 Minor Editorial Operation - Lab Impex Stack Monitor - Filter I T OP-HP-35O6 an a 2 2/22/2012 Minor Editorial

________Change and Source Checks__ _ _ _ _ _ _ _ _

Operation - Lab Impex Stack Monitor - Filter 3 0 OP-HP-356 i3 10/15/2012 Minor Editorial Change and Source Checks OP-HP-400 lGemstone Shipping Barrel Analysis 8 4/12/2012 Cover Page OP-HP-400 fGemstone Shipping Barrel Analysis 9 10/15/2012 1 Minor Editorial Sodium Iodide Spectral Analysis for Excepted, QA-SH-002 License-to-License, Type A, and Type B 5 4/20/2012 Minor Editorial Radioactive Materials Shipments QAB-SH-004 'Type B Program Vendor Qualification 2 1 3/29/2012 [ Minor Editorial "AB -H-007 ]Leak Testing of the LS Shipping Container Using 0 12/12/2012 New Procedure

• the CALT 9 Leakage Testing Device I-5

Number> Name ReiinDt Notes

! Stack Monitor Preventive Maintenance - NMC RM-HP-_00 S o ntainer 4 4/4/2007 Obsoleted R- I Survey and Decontamination of Returned 1 SRP-HP- 110 Sipn otie 5 4/27/2011l Obsoleted Beamport Radiation Level Monitoring During 8 Cover Page RP-HP-139 iReactor Stu8/2/2012 SV-HP-130 Emergency Air Sampling of Exhaust Plume 6 7/25/2012 Cover Page Exclusive Use Shipment of LSA or SCO WM-SH-300 10 9/19/2012 Minor Editorial Radioactive Waste 11-6

SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT January 1,2012 through December 31, 2012 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 Specificaiions. These changes have all been reviewed in accordance with 10 CFR 50.59.

HAZARDS

SUMMARY

REPORT (ORIGINAL JULY 1, 1965)

Original HSR, page 5-8, Section 5.4.3 (as revised in the 1970-1971, 1973-1974 and 1996 Reactor Operations Annual Reports):

Delete: The entire paragraph under Section 5.4.3.

Replace with: "The cooling tower is a stainless steel, induced-draft, cross-flow type, with three cells and two-speed fan assemblies for each cell. The tower is designed to cool 5,400 gallons (20,440 liters) of water per minute to a temperature of 85 'F (29.4 C) from an initial temperature of 115 'F (46.1 C) at a maximum wet bulb temperature of 80 'F (26.7 C). Vibration and low oil cutout switches are mounted on each fan assembly to secure the associated fan motor to prevent damage to the fan or cooling tower structure should an imbalance or low oil level condition develop. The number of fans and fan speed is configured as required to provide sufficient cooling for 10-MW operation."

Original HSR, page 5-10, Section 5.4.6 (as revised in the 1967-1968 and 1972-1973 Reactor Operations Annual Reports):

Delete: "A gravity feed, solenoid valve controlled acid addition line has been provided to serve this purpose."

Replace with: "A metering pump injection system has been provided to serve this purpose."

Original HSR, page 7-17, Section 7.2.4 (as revised by the 1995 and 2004 Reactor Operations Annual Reports):

Delete: ", and a deluge, no-freezing system used in the cooling tower" and "a deluge system used in the cooling tower;"

Original HSR, page 7-21, Section 7.2.9, Table 7.2, (as revised by the 1995, 2001, 2007, 2009 and 2011 Reactor Operations Annual Reports):

Add: The following after "Room 2041":

"Room 2045A Room 20451B" 111-1

Original HSR, page 8-2, Section 8.2, (as revised in the 1967-1968, 1972-1973, 1996 and 2000 Reactor Operations Annual Reports):

Delete: "Consequently, use of this facility will be subject to a high degree of administrative control to minimize the possibility of inserting or removing a sample with high reactivity worth during reactor operation."

Replace with: "Consequently, use of this facility will be interlocked with the Reactor Safety System to ensure that the reactor will scram should the center test hole canister be removed during reactor operation. The facility will also be subject to a high degree of administrative control to minimize the possibility of inserting or removing a sample with high reactivity worth during reactor operation."

Delete: "A latching device located at the top of the canister positively determines the canister position."

Replace with: "A latching device located at the top of the canister positively determines the canister position and two Reactor Safety System instrument channels positively sense the canister position during reactor operation."

Original HSR, page 8-10, Section 8.5 (as revised in the 1996 and 2001 Reactor Operations Annual Reports):

Delete: "Currently, only two reactor terminals and three sending -receiving stations are in use."

Replace with: "Currently, only two reactor terminals and two sending-receiving stations are in use."

Original HSR, page 9-7, Table 9.1 (as revised by the 1995, 2001, 2004, 2008 and 2009 Reactor Operations Annual Reports):

Add: "61 FIRST "Off-Bypass" 2 Pos. Key Lock" "62 FIRST "Off-Bypass" 2 Pos. Key Lock" Original HSR, page 9-28, Figure 9.2, Control Console Layout (as revised by the 2009 Reactor Operations Annual Report):

Replace with: Updated Figure 9.2, Control Console Layout Drawing (dated 2/20/12)

Original HSR, page 9-30, Figure 9.4, Safety System (as revised by the 2009 Reactor Operations Annual Report):

Replace with: Updated Figure 9.4. Safety System (MURR Dwg No. 139 dated 3/14/12)

Original HSR, page 9-22, Section 9.7.3, (as revised by the 1980-1981 and 1999 Reactor Operations Annual Reports):

Delete: The entire paragraph under Section 9.7.3 Replace with: "The Off-Gas Radiation Monitoring system consists of a three-channel radiation detection system designed to measure the airborne concentrations of radioactive particulate, iodine, and noble gas in the exhaust air which is sampled by an isokinetic probe located in the ventilation exhaust plenum. The radiation 111-2

detection equipment is an integrated component unit consisting of a fixed particulate filter monitored by either a scintillation or solid-state detector, a charcoal cartridge monitored by a lead-shielded scintillation detector, and a gas chamber monitored by a lead-shielded scintillation detector. The output from each radiation detector is displayed on a local meter, and on a strip-chart, three-pen recorder mounted in the Reactor Control Room. An audible and visual alarm alerts the operator to high activity or abnormal air flow. Minimum concentrations of radioactive wastes are ensured by continuously monitoring the gasses leading to the exhaust stack, and by ensuring maximum dilution of the potentially contaminated air with uncontaminated air."

Original HSR, page 9-26, after section 9.8.3.2 add new section:

Add: "9.9 Center Test Hole Instrumentation The center test hole instrument channels, called the Flux-Trap Irradiations Reactivity Safety Trip (FIRST), detect the position of the center test hole canister, or strainer, when installed. If these channels do not detect that the center test hole canister, or strainer, is in the secured and latched position, a scram is initiated."

ADDENDUM 3 - HAZARDS

SUMMARY

REPORT (AUGUST 1972)

HSR, Addendum 3, page 15, Figure 2.2, Secondary Coolant System (as revised by the 1989-1990, 1990-1991, 1194, 1995, 2001, 2002, 2003, 2004, 2005 and 2006 Reactor Operations Annual Reports):

Replace with: New Figure 2.2.a, Secondary Cooling System (MURR Dwg No. 502, Sheet I of 3, dated 2/28/12)

New Figure 2.2.b, Secondary Cooling System (MURR Dwg No. 502, Sheet 2 of 3, dated 4/26/12)

New Figure 2.2.c, Secondary Cooling System (MURR Dwg No. 502, Sheet 3 of 3, dated 4/10/12)

HSR, Addendum 3, page 23a, Figure 2.3.a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010 and 2011 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of 5, dated 3/20/12)

HSR, Addendum 3, page 23b, Figure 2.3.b, Electrical Distribution (as added by the 1995 and revised by the 2001, 2002, 2003, 2004, 2005, 2007, 2009, 2010 and 2011 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 11/21/12)

HSR, Addendum 3, page 23c, Figure 2.3.c, Electrical Distribution (as added by the 2004 and revised by the 2005, 2007, 2009, 2010 and 2011 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.c, Electrical Distribution Reactor/Laboratory Panels (MURR Dwg No. 522, Sheet 3 of 5, dated 11/12/12) 111-3

HSR, Addendum 3, page 23d, Figure 2.3.d, Electrical Distribution (as added by the 2007 and revised by the 2008, 2009, 2010 and 2011 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 5/9/12)

HSR, Addendum 3, page 23e, Figure 2.3.e, Electrical Distribution (as added by the 2007 and revised by the 2009, 2010 and 2011 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 11/21/12)

ADDENDUM 4 - HAZARDS

SUMMARY

REPORT (OCTOBER 1973)

HSR, Addendum 4 page A-10, after section A.3.3.14 add new section:

Add: "A.3.3. 15 "Center Test Hole Scram" Protection against an excessive reactivity step insertion in the Flux Trap region is achieved by two independent position sensing switches mounted on a removable support rig at the top of the pressure vessel head. In the event the Center Test Hole Canister leaves its secured and latched position, a reactor scram is initiated by either or both of these sensing switches, which actuate auxiliary relays K61 and K62, which in turn interrupt logic unit inputs E4A and E3B respectively."

HSR, Addendum 4, page A-14, Section A.3.10, Capability for Sensor Checks after "(unmonitored level controller):

Add: "Center Test Hole Canister position (limit switches).

HSR, Addendum 4, page A-15, Section A.3.14, Indication of Bypasses:

Delete: "Bypass switches are utilized to change the protective system to correspond to the three modes of operation (50 kW, 5 MW, or 10 MW)."

Replace with: "Bypass switches are utilized to change the protective system to correspond to the three modes of operation (50 kW, 5 MW, or 10 MW), and to bypass the center test hole instrument channels."

HSR, Addendum 4, page A-19, Figure A.1, Safety Systems (as revised by the 1995, 2001, 2002, 2003, 2006, 2007 and 2009 Reactor Operations Annual Reports):

Replace with: Updated Figure A. 1, Safety System (MURR Dwg No. 139, dated 3/14/12)

HSR, Addendum 4, page A-26, Figure A.7, Annunciator Control 10 MW (as revised by the 1995, 2001, 2002, 2005, 2006, 2007 and 2008 Reactor Operations Annual Reports):

Replace with: Updated Figure A.1, Annunciator Control 10 MW (MURR Dwg No. 138, dated 4/18/12) 111-4

HSR, Addendum 4, page A-29, Figure A.11, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (as revised by the 1995, 2002, 2005, 2009, 2010 and 2011 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 10/19/12)

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 and 2011 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet I of 5, dated 3/20/12) 111-5

SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2012 through December 31, 2012 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 11-01:

Flux-Trap Irradiation Reactivity Safety Trip (FIRST) Instrument Channels This modification record documents the addition of the FIRST device to the Reactor Safety System that ensures that the Center Test Hole Canister and its contents remain in place during reactor operation. The change is authorized by issuance of License Amendment No. 35 to Amended Facility License R-103.

Installation of the FIRST device allows a change in the methodology that was previously used to calculate the reactivity contribution of samples loaded in the flux trap region.

Modification 75-16, Addendum 4:

Reactor Safety System Monitoring Circuit (White Rat) Panel - Revision to Panel Overlays in Support of FIRST Device This modification record documents a revision to the Reactor Safety System Monitoring Circuit ("White Rat") Panel. New overlays reflect the addition of a series of contacts in both the "green leg" and "yellow leg" of the Reactor Safety System. The new contacts provide a SCRAM function from the Flux-Trap Irradiations Reactivity Safety Trip (FIRST) instrument channel. This modification did not change the function of the "White Rat" Panel itself.

Modification 10-02:

Addition of MURR Systems to Lab 251 This Modification Record documents the conversion of Room 251 to a laboratory (lab) space outfitted for the safe disposal of acids. Room 251 was not originally fitted as a lab space. Therefore all major lab utilities, save Natural Gas and Vacuum, were routed to this space. These include Facility Air, Deionized Water, Domestic Cold Water, Domestic Hot Water, Normal Electrical Power, Exhaust Ventilation, and Radioactive Liquid Waste.

Modification 11-02:

Replace Cooling Tower This Modification Record documents the replacement of the existing Cooling Tower. The replacement of the Cooling Tower consisted of the demolition of the existing wood structure, removal of an asbestos containing basin liner, conversion of the existing basin to a structural slab, installation of a steel elevating structure, installation of three (3) current generation stainless steel modular towers, installation of associated piping and electrical components and supporting instrumentation, as well as repairs to the existing mechanical building.

IV- I

Modification 09-03:

Lab Impex Stack Monitoring System This Modification Record documents the installation of a Lab Impex Stack Monitoring System which provides Off-Gas Radiation Monitoring capability as required by the Hazards Summary Report (HSR) and its addenda. This system replaced a Nuclear Measurements Corporation (NMC) RAK Stack Monitoring System, including the function of release integration, which had reached the end of its operational lifetime.

Modification 09-03, Addendum 1:

Update to Lab Impex Stack Monitoring System This Modification Record documents an update to the installation of a Lab Impex Stack Monitoring System which provides Off-Gas Radiation Monitoring capability as required by the Hazards Summary Report (HSR) and its addenda. This system was previously installed to replace the existing Nuclear Measurements Corporation (NMC) RAK Stack Monitoring System, including the function of release integration. This addendum contains additional information and documents changes performed since initial installation.

Completion of these changes allows the Lab Impex Stack Monitor to be commissioned as a licensed system, subject to surveillance requirements of the Technical Specifications, and relied upon for use in both emergency response and effluent reporting roles.

Modification 05-01, Addendum 3:

Pneumatic Tube System Changes in Lab 227 This Modification Record documents the removal of the Pneumatic Tube (P-Tube) System from Lab 227.

The master control station for Labs 218 and 227 were removed from Lab 227. A new simplified control station is now located in Lab 218. Also, the existing transfer valve for Labs 218 and 227 were replaced with a section of tubing that directs Row 2 to Lab 218.

Modification 01-09, Addendum 4:

Emergency Electrical Power System in Room 231 This Modification Record documents the transfer of loads on the Emergency Electrical Power System in Room 231. The change consisted of transferring the one remaining load from Emergency Lighting Panel Number IA (ELP-IA) to the Diesel Generator Room Distribution Panel which allowed the removal of ELP- IA.

Modification 98-02, Addendum 1:

Sulfuric Acid System Changes in Support of Cooling Tower Replacement This Modification Record documents the reconfiguration of the existing Sulfuric Acid System due to replacement of the Cooling Tower cells. The replacement of the Cooling Tower removed the original open sump, resulting in a need to convert the Sulfuric Acid System from a gravity drip system to an injection system. The reconfiguration consisted of demolition of the existing gravity day tank along with the associated transfer equipment and controls, installation of an injection metering pump and piping injector, and installation of supporting piping, electrical power and controls.

Modification 03-03, Addendum 3:

Fire Protection System Changes in Support of Cooling Tower Replacement This Modification Record documents the removal of the Deluge System in the Cooling Tower due to the replacement of the Cooling Tower cells. Replacement of the Cooling Tower cells, as documented in Modification Record 11-02, provided an all-stainless steel structure and significant reduction of potential IV-2

fire loading, resulting in a Factory Mutual (FM) rating for the new Cooling Tower cells. This removed the need for the existing non-freezing deluge system.

Modification 01-2, Addendum 8:

Intercommunication and Pacinc System Changes in Support of the Sterility Suite Rooms 2045A and 2045B 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 sterility suite in the North Office Addition to ensure a prompt and effective response from facility staff to an emergency or abnormal condition.

4/-.

IV-3

SECTION V NEW TESTS AND EXPERIMENTS January 1,2012 through December 31, 2012 New tests or experiments approved during this period under a Reactor Utilization Request (RUR) or Reactor License (RL) Project are as follows:

RUR 270, as amended: Palladium

Description:

This RUR authorizes an increase in the enrichment of Palladium- 110 to 100% in support of research and development activities.

RUR 292: Barium Carbonate

Description:

MURR previously irradiated natural barium carbonate, however due to lack of active use, this RUR was placed in an inactive status. This RUR is being reactivated and authorizes the irradiation of up to 200 grams of natural barium carbonate in support of research and development activities.

RUR 420, as amended: Antimony Oxide

Description:

This RUR authorizes an increase to the allowable antimony component of the ceramic material from 8% to 10%. The mass and activity limits for the ceramic target material remain unchanged.

RUR 436, as amended: Hydroxyapatite

Description:

This RUR authorizes an increase in the allowable mass of hydroxyapatite up to 10 grams and removes the requirement for secondary encapsulation in quartz.

Both of these changes are authorized for reflector irradiation only and are 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-1

SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2012 through December 31, 2012 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-three (63) refueling evolutions were completed in 2012. Excess reactivity verifications were performed for each refueling. The largest measured excess reactivity value was 3.3 1%. MURR Technical Specification 3. 1(f) requires excess reactivity to be less than 9.8%.

Reactivity Measurements:

Differential blade-worth measurements of three (3) 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.

Nine (9) 'reactivity measurements were performed to determine the reactivity worth of all the samples, including the sample holder, loaded in the flux trap region.

Nine (9) 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, one (1) differential blade-worth measurement and one (1) primary coolant temperature coefficient measurement were also performed.

VI-I

SECTION VII RADIOACTIVE EFFLUENT January I, 2012 through December 3 1, 2012 TABLE I SANITARY SEWER EFFLUENT January 1, 2012 through December 3 1, 2012 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide Activity (Ci)

H-3 1.621E-0I S-35 4.839E-03 Co-60 2.722E-03 Lu-177 2.567 E-03 P-32 1.162E-03 Zn-65 1.145E-03 Ca-45 8.902E-04 Tc-99m 1.702E-04 Sc-46 1.322E-04 Mo-99 1.302E-04 Cr-51 1.1 81E-04 Lu-177m 6.508E-05 Fe-59 5.956E-05 Mn-54 2.989E-05 Total H-3 1.621E-01 Total Other 1.403E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."

VIl-I

TABLE 2 STACK EFFLUENT January 1,2012 through December 3 1, 2012 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration Total Release TS Limit Multiplier 'Yo TS (QCi/ml) (Ci)

Ar-41 2.38E-06 1.21E+03 350 68.0000 C-14 2.17E-II 1.03E-02 1 0.7230 1-131 1.OIE-13 5.1 IE-05 1 0.0503 Kr-79 1. 18E-08 6.OOE+00 350 0.0482 H-3 1.49E-08 7.58E+00 350 0.0426 Co-60 2.47E- 15 1.25E-06 1 0.0049 Sb-125 7.69E- 14 3.90E-05 1 0.0026 Os-191 6.09E- 15 3.09E-06 1 0.0003 Au- 196 1.01E-15 5.14E-.07 350 0.0003 Hf- 181 9.78E- 16 4.97E-07 1 0.0002 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, 2012 through December 3 1, 2012 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 2012. All doses are approximately 14 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 81 Spring 2012 Detection Limits1 Matrix Alpha Beta Gamma Tritium Water 3.18 pCi/L 5.32 pCi/L 201.21 pCi/L 5.42 pCi/mL of sample Soil 1.01 pCi/g 4.52 pCi/g 0.75 pCi/g N/A Vegetation 3.51 pCi/g 10.18 pCi/g 1.78 pCi/g 5.36 pCi/mL of distillate Activitv Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL)

I V81 <3.51 30.03 < 1.78 <5.36 2V81 < 3.51 26.81 < 1.78 < 5.36 3V81 <3.51 22.43 < 1.78 < 5.36 4V81 < 3.51 29.74 < 1.78 <5.36 5V81 < 3.51 30.56 < 1.78 < 5.36 6V81 <3.51 49.28 < 1.78 <5.36 7V81 <3.51 38.90 < 1.78 < 5.36 10V81 <3.51 41.40 < 1.78 < 5.36 VIII- 1

TABLE 1 (Cont'd)

Summary of Environmental Set 81 Spring 2012 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/k) 1S81 2.00 25.28 4.01 2S81 1.07 13.55 1.06 3S81 1.40 19.59 < 0.75 4S81 1.66 12.40 4.05 5S81 1.51 20.04 3.47 6S81 2.00 12.82 3.99 7S81 1.36 18.85 3.67 10S81 1.54 19.05 3.66 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W81 <3.18 < 5.32 < 201.21 < 5.42 6W81 <3.18 <5.32 < 201.21 < 5.42 10W81 <3.18 6.36 < 201.21 < 5.42 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 82 Fall 2012 Detection Limits' Matrix Alpha Beta Gamma Tritium Water 0.00 pCi/L 4.44 pCi/L 193.16 pCi/L 5.68 pCi/mL of sample Soil 2.32 pCi/g 4.61 pCi/g 1.63 pCi/g N/A Vegetation 2.81 pCi/g 10.84 pCi/g 1.61 pCi/g 6.24 pCi/mL of distillate VIII-2

TABLE 2 (Cont'd)

Summary of Environmental Set 82 Fall 2012 Activity Levels - Veaetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL) 1V82 <2.81 29.72 < 1.61 < 6.24 2V82 <2.81 46.06 2.44 < 6.24 3V82 <2.81 18.91 < 1.61 < 6.24 4V82 <2.81 37.65 1.74 < 6.24 5V82 <2.81 28.09 < 1.61 < 6.24 6V82 <2.81 29.24 1.64 < 6.24 7V82 < 2.81 32.13 2.43 < 6.24 10V82 <2.81 50.13 2.02 < 6.24 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1S82 <2.32 13.54 7.27 2S82 <2.32 18.73 9.37 3S82 4.76 18.73 5.93 4S82 <2.32 15.46 12.49 5S82 < 2.32 21.95 10.12 6S82 <2.32 18.17 10.33 7S82 <2.32 17.39 9.71 10S82 2.82 20.04 8.38 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W82 0.18 16.29 225.25 < 5.68 6W82 0.00 < 4.44 < 193.16 < 5.68 10W82 0.35 8.24 < 193.16 22.85 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, 2012 through December 3 1, 2012 Badge Direction Map Distance from 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total Number From MURR MURR Stack 2012 2012 2012 2012 2012 (meters) Net mR Net mR Net mR Net mR Net mR Control 0 N/A 35.0 26.0 25.0 29.0 115.0 1 Control 1 16600 31.0 24.0 24.0 28.0 107.0 2 Control 2 16600 33.0 25.0 24.0 28.0 110.0 3 WSW N/A 0.0 0.0 0.0 0.0 0.0 4*

5*

6 N 34 0.0 1.0 3.0 0.0 4.0 7 NE 57 0.0 0.0 4.0 4.0 8.0 8 Sw 27 3.0 1.0 3.0 7.0 14.0 9 S 27 19.0 17.0 16.0 18.0 70.0 10 NE 149 0.0 0.0 0.0 0.0 0.0 II NW 149 0.0 0.0 2.0 1.0 3.0 12 ENE 301 0.0 2.0 0.0 0.0 2.0 13 NNE 316 0.0 0.0 0.0 0.0 0.0 14 S 156 0.0 0.0 4.0 0.0 4.0 15 S 65 11.0 14.0 14.0 15.0 54.0 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 1.0 3.0 4.0 22 ESE 168 0.0 0.0 0.0 0.0 0.0 23 NW 110 0.0 0.0 3.0 0.0 3.0 24 SSW 328 0.0 0.0 2.0 0.0 2.0 25 SSW 480 0.0 0.0 1.0 0.0 1.0 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 1.0 2.0 1.0 4.0 29 NW 255 0.0 0.0 3.0 1.0 4.0 30 NNW 328 0.0 0.0 0.0 0.0 0.0 31 NNW 671 0.0 0.0 0.0 absent 0.0 32 NNW 724 0.0 0.0 1.0 0.0 1.0 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 2.0 4.0 5.0 11.0 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 absent 0.0 0.0 0.0 0.0 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 0.0 0.0 42*

43*

44 Spare N/A 0.0 0.0 1.0 0.0 1.0 45 S 65 0.0 0.0 1.0 0.0 1.0 46 E 70 4.0 3.0 2.0 1.0 10.0

• These badge numbers are no longer used.

VIII-4

TABLE 4 Number of Facility Radiation and Contamination Surveys January 1, 2012 through December 3 1, 2012 Radiation Surface Contamination* Air Samples** RWP's January 72 72 47 13 February 67 67 57 11 March 73 73 53 7 April 72 72 54 8 May 72 72 35 9 June 77 77 22 9 July 65 65 50 7 August 77 77 62 8 September 70 70 46 4 October 47 47 53 6 November 63 63 49 1 December 56 56 51 5 TOTALS 811 811 579 66

• 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 Chris Schnieders was hired as a Health Physics Technician in January 2012.

Eric Graham was hired as a Health Physics Technician in June 2012.

During calendar year 2012, MURR shipped 703 cubic feet of low-level radioactive waste containing 3,097 mCi of activity.

VII-5

SECTION IX Summary of Radiation Exposure to Facility Staff, Experimenters and Visitors January 1, 2012 through December 31, 2012 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 20 9 6 235 354 217 5 52 53 2437 205 48 76 17 104 4 143 3985 February 8 22 6 15 316 252 5 35 31 1088 143 75 54 32 102 I 35 2220 March 0 21 4 9 285 99 5 30 28 998 119 31 7 21 82 8 16 1763 April Is 16 1 6 502 167 14 18 29 1533 207 43 85 60 142 25 96 2959 May 1 7 0 8 413 161 0 12 12 1536 152 64 22 12 90 0 85 2575 June 4 18 2 7 324 216 3 85 57 1439 176 26 94 13 151 0 24 2639 July 32 24 2 0 379 177 4 55 18 1305 172 52 31 26 73 0 23 2373 August 9 3 0 0 284 161 5 17 28 1150 228 20 9 33 107 5 26 2085 September 1 0 0 15 297 163 4 16 15 1092 243 36 2 22 95 1 20 2022 October 5 10 0 11 417 130 13 39 38 1091 226 51 7 21 93 6 394 2552 November 10 0 0 0 231 98 0 24 26 746 98 37 32 34 118 15 24 1493 December 8 0 0 0 318 140 0 6 31 1451 76 15 28 68 68 2 135 2346 Total for Year 113 130 21 306 4120 1981 58 389 366 15866 2045 498 447 359 1225 67 1021 29012 Monthly Avg 9 11 26 343 165 5 32 31 1322 170 42 37 30 102 6 85 2418 Highest NVB 27 86 6 72 981 468 58 118 216 1275 516 109 112 87 842 17 292 (annual)

High EXT 343 343 NR 100 2525 834 NR 3466 509 3122 5361 629 1385 1995 1333 182 5272 (annual)

AC - Analytical Chemistry BCS - Business & Central Services HP - Health Physics OPS - Operations RlP - Radiopharnmaceutical 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 NR = None Reported 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:

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