ML080590029

University of Missouri, Research Reactor, Transmittal of Reactor Operations Annual Report for 2007

ML080590029
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/27/2008
From:	Foyto L Univ of Missouri - Columbia
To:	Mcknight J Document Control Desk, NRC/OIS/IRSD/ISB
References
Download: ML080590029 (36)

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Research Reactor Center 1513 Research Park Drive Columbia, MO 65211 University of Missouri-Columbia PHONE 573-882-4211

FAx573-882-6360

,,v n h trp://web. missou ri .edu/~nmrri-*ww February 27, 2008 Mr. James McKnight Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop P1-37 Washington, D(C 20555-0001 K R IlýL NC1I": Docket 50-186 University of M issonri-ColIumbia Research Reactor Amiended Facility License R-103 S U13 -'.-' University of Missouri Research Reactor 2007 Reactor Operations Annual Rleport

'The Rcactor Operations Annual Report for the University of Missouri Research Reactor was sent to you via Federal Express on F'ebruarTy 26, 2008. The tracking number is.9348 0895 8602 and the package is scheduled to arrive by 3:00 p.m. today. The reporting period covers January 1, 2007 through December 31, 2007.

Ihis document is submitted to the U.S. Nuclear Regulatory Commission in accordance with the University of Missouri RcsCarch Reactor Tcchnical Spccification 6. l.h (4).

If you have any questions regarding the contents of this reporl, please contact me at (573) 882-5276.

Sincercly.

Ics P. Foyto Reactor Managcr

"-ncIos urIc xc: Nlr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC 4j~ZOA ý'"

FRAIrING CANCER ii O.1l~ws tNLG

UNIVERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2007 - December 31, 2007

UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2007 through December 31, 2007 Compiled by the Research Reactor Staff Submitted February 2008 by:

Leslie P. Foyto Reactor Manager Reviewed and Approved by:

Ralph A. Butler, PE Director

TABLE OF CONTENTS Section Title Pages I. Reactor Operations Su mma ry-........................... ........................ I -i through 7 II. M U R R Procedures ............................................................................... II-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 III. Revisions to the Hazards Summary Report .......................................... III- 1 through 4 IV. Plant and System M odifications ........................................................... IV- 1 through 3 V. New Tests and Experim ents ............................................................ V-1 VI. Special Nuclear Material and Reactor Physics Activities ............... VI- I V II. Radioactive Effl uent ............................................................................ V II-1 through 2 Table I - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII. Environmental Monitoring and Health Physics Surveys .......... VIII- I through 5 Table 1 - Summary of Environmental Set 69 Table 2 - Summary of Environmental Set 70 Table 3 - Environmental TLD Summary Table 4 - Number of Facility Radiation and Contamination Surveys IX. Summary of Radiation Exposures to Facility Staff, Experimenters, an d V isitors ......................................................... ................................ IX -1

UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2007 through December 31, 2007 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-owned research reactor in the United States.

The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2007. Included within this report are changes to MURR 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 to meet the administrative requirements of MURR Technical Specification 6.1 .h (4).

ACKNOWLEDGMENTS The success of MURR and these scientific programs is due to the dedication and hard work of many individuals and organizations. Included within this group are: the University administration; the governing officials of the State of Missouri; the Missouri State Highway Patrol; the City of Columbia Police.

Department; the Missouri University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our Regulators; those who have provided funding including the Department of Energy (DOE) and the Department of Homeland Security (DHS); the Researchers; the Students; the Columbia Fire Department; the Campus Facilities organization; members of the National Organization of Test, Research, and Training Reactors; 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 projects that were completed this calendar year by Operations included: replacement of the drive motor on primary coolant circulation pump P-501B; refurbishment of the valve actuators on primary coolant system isolation valves V507A and V507B and pool coolant system isolation valve V509; replacing certain sections of pool coolant system piping to improve system hydraulic performance; refurbishing anti-siphon system isolation valves V543A and V543B; and replacing the collimator liner on Beamport "E" in support of the Boron Neutron Capture Therapy Project.

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The facility is also actively collaborating with the US-RERTR (Reduced Enrichment for Research and Test Reactors) Program and four other U.S. high-performance research reactor facilities that use highly-enriched uranium (HEU) fuel to find a suitable low-enriched uranium (LEU) fuel replacement. Although each one

-of-the five-highlperformance research -reactors is--responsible- for -its-own feasibility- and safety studies, regulatory interactions, fuel procurement, and conversion, there are common interests and activities among all five reactors that will benefit from a coordinated, working-group effort.

Reactor Operations Management also wishes to commend the six individuals who received their Senior Reactor Operator and Reactor Operator certifications from the U.S. Nuclear Regulatory Commission.

These individuals participated in a rigorous training program of classroom seminars, self-study, and on-the-job training. The results of this training are confident, well-versed, decisive individuals capable of performing the duties of licensed operators during normal and abnormal situations.

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SECTION I REACTOR OPERATIONS

SUMMARY

January 1, 2007 through December 31, 2007 The following table and discussion summarize reactor operations during the period from January 1, 2007 through December 31, 2007.

Monhowr Fll Hurs Meawat Dys Full Power % of Full Power % of Mont PwerHous Ful Mgawtt aysTotal Time Scheduled~')

January 664.23 276.92 89.3 100.0 February 604.21 251.87 89.9 100.7 March .678.19 282.67 91.2 102.1 April 632.42 263.63 87.8 98.5 May 670.07 279.35 90.1 100.8 June 638.63 266.19 88.7 99.5 July 658.37 274.39 88.5 99.1 August 669.98 279.26 90.1 100.8 September 649.11 270.45 90.2 101.1 October 658.49 274.47 88.5 99.1 November 658.86 274.60 91.5 102.6 December 644.66 268.75 86.6 97.0 Total for 7827.22 3262.55 89.36 % 100.11 %

the YearI

(')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 2007 The reactor operated continuously in January with the following exceptions: five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: performing a back-flush on the secondary coolant side of pool coolant system heat exchanger HX-521 and primary coolant system heat exchangers HX-503A and HX-503B3; replacing the drive motor on primary coolant circulation pump P-50113; loading new pool coolant system de-ionization bed 'V;' and completing compliance procedure CP-3 1, "Calibration of the Eberline Radiation Stack Monitor."

February 2007 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled/unplanned power reduction.

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On February 8, with the reactor operating at 10 MW in the automatic control mode, a "Reactor Loop Lo Pressure Scram" was automatically initiated when primary coolant system pressure decreased below the reactor safety system low pressure set point of 63 psig. The immediate and subsequent actions of reactor emergency procedure REP-13,

-"Primary -Colant SystermL6w Pressure or Flow-Scram," were completed.

Upon investigation of mechanical equipment room 114, which contains a large portion of the cooling equipment for the reactor, coolant was found leaking from primary heat exchanger outlet valve V540B. 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 in two places. The diaphragm was replaced, the system re-filled and then leak tested satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation. Note: Failure of the valve diaphragm was discussed with the vendor to determine if a failure of this nature had previously occurred. To their knowledge, this type of failure had not occurred in the past.

Major maintenance items for the month included: replacing the diaphragm on primary heat exchanger outlet valve V540B; and performing two reactivity worth measurements in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP- 11(D)."

March 2007 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month. NRC regional inspector arrived at MURR for routine inspection of the Radiation Protection Program and Shipping.

Major maintenance items for the month included: completing Modification Record 07-1, "Installation of the Five and Six Inch Sample Diameter Irradiation Facility;" draining and back-flushing beamport 'D' with helium; performing two reactivity worth measurements in accordance with reactor procedure RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B);" flooding beamport 'D' with super-demineralized water; completing compliance procedure CP-29, "Calibration of the NMC RAK Radiation Stack Monitor;" performing a reactivity worth measurement in accordance with reactor test procedure RTP-19, "Experimental Measurement of the MURR Primary Temperature Coefficient of Reactivity;" and performing a reactivity worth measurement in accordance with reactor test procedure RTP-6, "Reactivity Worth Procedure for Flux Trap."

April 2007 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: completing Modification Record 04-1, Addendum 1, "Replace the 943 LFE Meter Relay Unit (EP-942) with a Beede Meter Relay Unit;" draining and back-flushing beamport 'D' with helium; flooding beamport 'D' with super-demineralized water; performing two reactivity worth measurements in accordance with reactor procedure RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B);" completing the biannual cleaning of the cooling tower sump and basin; completing the biennial change-out of control blade 'A' offset mechanism; and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-1I(D)."

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May 2007 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance

--a-id/0r refueling, afid ile inschfdiiled/iiplliife&d-pýV~efrreductif-n.

On May 16, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5, or 6 Downscale" annunciator alarm was received. Investigation as to the cause of the alarm revealed that the regulating blade would not function in the inward or outward direction in either the automatic or manual control modes. The reactor was then shutdown by manual scram. Failure of the regulating blade to be operable during reactor operation resulted in a deviation from Technical Specification (TS) 3.2.a, which states, "All control blades, including the regulating blade, shall be operable during reactor operation." Additionally, with the regulating blade in an inoperable state, a deviation from TS 3.4.c occurred. TS 3.4.c specifies that the two (2) rod run-in functions associated with the regulating blade must be operable when the reactor is in operation.

After the reactor was shutdown and secured, the regulating blade drive mechanism was removed and taken to the Electronic Technician Shop for troubleshooting. Upon disassembly, it was discovered that the stainless steel roll pin that connects the servomotor driveshaft to the drive plate had backed out to a point where it was no longer engaged in the driveshafi. In addition, a setscrew, which acts as a secondary means to secure the drive plate to the shaft, had loosened and backed out also allowing the drive plate to slip on the servomotor driveshaft. A new 1/16-inch roll pin was inserted into the servomotor driveshaft and drive plate, and Loctite adhesive was applied to the setscrew. The drive mechanism was bench tested satisfactorily in the Electronic Technician Shop and then reinstalled and tested over its full range of travel during reactor startup checks. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.

The most probable cause of this event was a failure to renew the roll pin the last time the semi-annual preventative maintenance (PM) was performed. Repeated use of a roll pin causes it to lose its ability to be pressed tightly within a hole; therefore increasing the probability that it will become disengaged from a rotating coupling. The semi-annual PM procedure has been revised such that the roll pin will be replaced each time it is removed, as well as a note to apply Loctite adhesive to the setscrew. Licensee Event Report No. 07-01, providing a detailed description of this event and the corrective actions taken, was submitted within the Technical Specification thirty-day time requirement.

Major maintenance items for the month included: completing Modification Record 07-2, "Installation of Circuitry to Indicate a Loss of the Main Annunciator;" replacing the wear ring on the three-barrel center test hole canister in accordance with Modification Record 06-3, "Replace Flux Trap Holder Wear Ring;" replacing the non-compensated ion chamber detector and cabling for nuclear instrumentation channel No. 6; draining and back-flushing beamport

'D' with helium; flooding beamport 'D' with super-demineralized water; and completing compliance procedure CP-26, "Containment Building Leak Test."

June 2007 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled/unplanned power reduction. Additionally, two shutdowns were performed for NRC operator licensing examinations. NRC examiner arrived at MURR for operator licensing examinations.

On June 14, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact with Magnet Rod Run-In" annunciator alarm was received. Investigation as to the cause of the alarm revealed that control blade 1-3

'A' anvil had separated from its electro-magnet when a sample handling rod inadvertently struck the control blade arm during a routine sample handling evolution. The reactor was shutdown and the control blade was satisfactorily withdrawn to the full out position as part of the retest using compliance procedure CP-10, "Rod Drop Times."

-Pef-i-s-ni--t-to resita thde reaictbo was 6obtiiiicd'rornithe React6r Mmingef.' The reacto'-w--fifuleda restarted to 10 MW operation.

Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B);"

draining and back-flushing beamport 'D' with helium; flooding beamport 'D' with super-demineralized water; and conducting a facility-wide electrical outage in support of installing the new 13.8 kV facility electrical feeder breaker.

July 2007 The reactor operated continuously in July with the following exceptions: five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month. Received notification from the NRC that two new Senior Reactor Operator licenses and two Reactor Operator licenses had been issued.

Major maintenance items for the month included: replacing the wear ring on the six-barrel center test hole canister to complete Modification Record 06-3, "Replace Flux Trap Holder Wear Ring;" replacing the vibration switch on cooling tower fan No. 1 as part of Modification Record 07-3, "Replace Cooling Tower Fan Vibration Switches;"

completing compliance procedure CP-31, "Calibration of the Eberline Radiation Stack Monitor;" performing a reactivity worth measurement in accordance with RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B);" draining and back-flushing beamport 'D' with helium; flooding beamport 'D' with super-demineralized water; loading new pool coolant system de-ionization bed 'B;' and completing the annual facility emergency preparedness drill.

August 2007 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and two unscheduled/unplanned power reductions.

On August 8, with the reactor operating at 10 MW in the automatic control mode, a "Bldg Air Plenum and Bridge Hi Activity Scram" and containment building isolation were automatically initiated when radiation levels at the reactor pool surface increased above the alarm set point. Immediate actions of emergency procedure EP-RO-012, "Reactor Isolation," and reactor emergency procedure REP-2, "Reactor Scram," were performed. Routine sample handling activities were in progress at the time of the event and investigation to the cause revealed that a failure of a sample can lid resulted in an activated section of aluminum foil floating to the pool surface. After radiation levels had sufficiently decreased, Operations and Health Physics personnel re-entered the containment building to retrieve the foil. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.

On August 24, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was manually initiated when a sustained firemain low pressure condition occurred. The low pressure condition was confirmed by the University power plant, which in turn informed the facility that the cause was due to a piping rupture on campus near the MU Hospital. Immediate and subsequent actions of reactor emergency procedures REP- 13, "Firemain Low 1-4

Pressure," and REP-2, "Reactor Scram," were performed. University personnel were able to isolate the section of damaged piping and eventually return firemain supply pressure to normal. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.

Major maintenance items for the month included: completing Modification Record 90-1, Addendum 1, "Evacuation System Changes ,in Support of the New North Office Addition;" replacing the detector cabling for nuclear instrumentation signal processor drawer No. 2; refurbishing the valve actuator for pool coolant system isolation valve V509; refurbishing the valve actuator for primary coolant system isolation valve V507A; adjusting the blade pitch on cooling tower fans No. 1, 2 and 3; back-flushing beamport 'D' with helium; and replacing the filter cartridges in pool coolant demineralizer system outlet filter housing F-204.

September 2007 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two scheduled shutdowns for reactivity measurements, and one unscheduled/unplanned power reduction.

On September 11, with the reactor operating at 10 MW in the automatic control mode, a manual reactor scram was initiated when control rod 'D' did not respond to a routine outward shim command. The immediate and subsequent actions of reactor emergency procedure REP-8, "Control Rod Drive Mechanism Failure or Stuck Rod," were performed. Investigation determined that relay K2, which controls outward shim motion, was not fully seated within its socket. The relay was properly seated and the control blade was satisfactorily withdrawn to the full out position as part of the retest using compliance procedure CP-10, "Rod Drop Times." Permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation. Note: Relay K2 is not a part of the reactor safety system. The ability to manually or automatically scram the reactor or shim the control rod in the inward direction always remained functional.

Major maintenance items for the month included: completing Modification Record 05-6, "Replace Pool Pump Piping;" replacing the vibration switch on cooling tower fan No. 3 as part of Modification Record 07-3, "Replace Cooling Tower Fan Vibration Switches;" installing a fiber optic sensor in row one of the pneumatic tube system as part of Modification Record 05-1, Addendum 1, "Upgrade Pneumatic Tube System Photo Sensor Collar and Counting Circuit;" performing two reactivity worth measurements in accordance with reactor procedure RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B);" refurbishing the valve actuator for primary coolant system isolation valve V507B; and removing beamport 'E' vestibule shutter box to perform modifications in support of the Boron Neutron Capture Therapy project.

October 2007 The reactor operated continuously in October with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and one scheduled shutdown for a reactivity measurement. There were no unscheduled/unplanned power reductions this month. NRC regional inspector arrived at MURR for routine inspection of Operations and Emergency Planning.

Major maintenance items for the month included: replacing the vibration switch on cooling tower fan No. 2 to complete Modification Record 07-3, "Replace Cooling Tower Fan Vibration Switches;" energizing the 120/208V I-5

transformer and distribution center No. 2 to complete Modification Record 01-14, Addendum 1, "120/208V Electrical Distribution System Upgrade;" installing a fiber optic sensor in row two of the pneumatic tube system to complete Modification Record 05-01, Addendum 1, "Upgrade Pneumatic Tube System Photo Sensor Collar and Counting

-Ciricuit-;" ierf6riiiig a -reactivity -worthf- ins6iernet-itni-acc6rddaiic --,iith- reactor ediiwe-RPROR201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B);" performing an "end-of-life" inspection on two spent fuel elements; replacing pool coolant system flow rate chart recorder EP No. 915C/D; replacing the graphite element in reflector tank position No. 6; collecting pool coolant system single-pump operational data; adjusting the mechanical seal ring on primary coolant circulation pump P-501B; completing the biennial change-out of control blade 'C' offset mechanism; completing the biannual cleaning of the cooling tower sump and basin; and performing a reactivity worth measurement in accordance with RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP- I1(D)."

November 2007 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two scheduled shutdowns for operator training, and one unscheduled/unplanned power reduction.

On November 26, during a reactor startup with the control rods at less than 5 inches withdrawn (subcritical), a "Channel 4, 5 & 6 High Power Scram" was automatically initiated by the nuclear instrumentation (NI) system. The immediate actions of reactor emergency procedure REP-5, "Nuclear Instrument Failure," were performed. The control room console remote meter and local drawer indications for power range monitor No. 6 were greater than 125%, with the high power rod run-in and scram outputs tripped. Additionally, an NI anomaly annunciator alarm was also energized. All other NI channel indications were normal.

Troubleshooting efforts by the Electronic Technicians did not reveal a definitive cause, nor could the condition be recreated; however, because an NI anomaly alarm accompanied the trip the most probable cause was the high voltage power supply module. A spare module was tested satisfactorily and placed in service. A full instrument channel calibration and pre-operational check were performed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager.

Major maintenance items for the month included: completing Modification Record 07-4, "Interfacing MURR Systems with the North Office Addition;" completing Modification Record 01-2, Addendum 2, "Intercommunication and Paging System Changes in Support of the New North Office Addition;" completing Modification Record 07-5, "Beamport E Changes to Replace Collimator Liner in Support of Boron Neutron Capture Therapy (BNCT) Project;"

cleaning the secondary coolant system pump suction strainers; completing repairs to the upper wood decking of cooling tower cells No. 1, 2 and 3; test fitting the saddle shield block on beamport 'E' in support of the Boron Neutron Capture Therapy Project; completing an integrity test of anti-siphon system isolation valves V543A and V543B; draining and back-flushing beamport 'E' with helium; and flooding beamport 'E' with super-demineralized water.

December 2007 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one scheduled shutdown for a reactivity measurement, and two unscheduled/unplanned 1-6

power reductions. Additionally, one shutdown was performed for NRC operator licensing examinations. NRC examiner arrived at MURR for operator licensing examinations.

• D-eceiiibe-r1 2,--wih-i-the- react-or 6*per-atinig-ait 1-0 MW-iii-the-Fiiitoffmati -c bhti5-ftio-de,-- "Rtd-Nbtin Ccrtlmtw-ith-On-D Magnet Rod Run-In" annunciator alarm was received. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Investigation as to the cause of the alarm revealed that control blade 'D' anvil had separated from its electro-magnet when a sample handling rod inadvertently struck the offset mechanism counter balance arm during a routine sample handling evolution. The operators involved were counseled on the importance of proper sample handling techniques. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.

On December 28, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not in Contact with Magnet Rod Run-In" annunciator alarm was received when control blades 'A' and 'B' disengaged from their respective electro-magnets. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Investigation as to the cause of the rod run-in revealed that the reactor safety system "Yellow Leg" trip actuator amplifier (TAA) was found in the tripped condition. Additionally, a strong burning smell was present in the vicinity of the TAA. Troubleshooting efforts by Electronics Shop personnel discovered a failed resistor (R-14) and two failed transistors (Q4 and Q5) in the bi-stable driver amplifier of the TAA. More than likely one of the components had failed, causing a high current condition, which in turn caused the other two components to fail. A spare TAA, which had been tested satisfactorily, was installed and verified operational. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.

Major maintenance items for the month included: completing Modification Record 90-1, Addendum 1, "Evacuation System Changes in Support of the New North Office Addition;" replacing the glass wool filter material and the anion and cation resins in the exchange columns of the primary coolant system fission product monitor; refurbishing anti-siphon system isolation valves V543A and V543B; replacing in-pool heat exchanger inlet temperature element TE-950A; zeroing, spanning and calibrating pool coolant system flow transmitter FT-912F; zeroing, spanning and calibrating primary coolant system flow transmitter FT-912G; zeroing, spanning and calibrating primary coolant system flow transmitter FT-912H; loading new de-ionization bed 'W' and placing on primary coolant system service; transferring primary de-ionization bed 'S' to pool coolant system service; replacing the filter cartridges in pool coolant demineralizer system inlet filter housing F-200; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B);"

and replacing the scintillation detector in the primary coolant system fission product monitor.

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SECTION II MURR PROCEDURES January 1, 2007 through December 31, 2007 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 6.1 .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 eighty (80) revisions issued to the reactor operations procedures, forms and operator aids. The majority of the revisions were strictly format or editorial in nature, such as cover page changes. The following is a list of the revised procedures, forms and operator aids:

AP-RO-I 10 IConduct of Operations " 10 3/6/2007 Minor Editorial 1 AP-RO-1 10 lConduct of Operations 11 11/26/2007 Minor Editorial AP-RO- 115 [Modification Records 1 3 I10/18/2007 Minor Editorial AP-RO-135 [Reactor Utilization Requests 0 9/27/2007 New Procedure jAP-RR-026 lEvent Review - 3 [5/8/2007 T Minor Editorial

.EX'R.01105 Reactor Irradiation Experiments 1 9 [ 6/28/2007 TFUll Review EX-RO-105 Reactor Irradiation Experiments J10 11/26/2007 Cover Page I EX-RO-120 jBeamport "A" Operation 1 5 1 11/1/2007 Minor Editorial EX-RO-121 Beamport "B" Operation 5 1 11/1/2007 Minor Editorial EX-RO-122 EX-RO-123 Beamport "C" Operation ........

Beamport "D" Operation

(( 4 [

_ 11/1/2007 f..Minor Editorial 1/1/200.. Minor Editorial EX-RO-123 Beamport "D" Operation 5 [_11/26/2007 Minor Editorial EX-RO-124 1Beamport "E" Operation . ' 5 [__ 11/1/2007 1 Minor Editorial EX-RO-124 Beamport "E" Operation [ f 6 11/26/2097 1 Minor Editorial j EX-RO-125 ]Beamport "F" Operation

[ 1 5 3/6/2007

.. 11//2007 1Minor Editorial MinorEditorial IFEX-RO-125 _Beamport "IF"' Operation EX-RO-125 1Beamport "F" Operation 7 1 11/26/2007 Minor Editorial EX-RO-126 Thermal Column Door T4 1 11/26/2007 CoverPage FM-152 .Fuel Element Inspection T1 7/9/2007 Minor Editorial FM-18 Deviation From Procedure Report 4 T 11/1/2007 J Cover Page FM-21 .ARMS Trip Setpoints 4

4. T 6/28/2007 JMinor Editorial I FM-23 MURR Tag Out Index Record 4 7/19/2007 Cover Page FM-24 .IMURR Tag Out Sheet 5 7/19/2007 Minor Editorial

~FM-25 MURR Tag Out Monthly Audit 4 7/19/2007 Minor Editorial 11-1

unibv T- alu Nts~nKJ r FM-33 fContainment Building Restricted Materials ]3 1 1/1/2007 Minor Editorial FM-40 lEvent Review Report 2 1 5/8/2007 J Minor Editorial FM-43 INuclear and Process Data 1 9 1 3/6/2007 [ Minor Editorial FM-43 Nuclear and Process Data 10 10/18/2007 [ Minor Editorial FM-55 . Startup Nuclear Data Sheet 4 3/6/2007 [ Minor Editorial FM-56 lReactor Routine Patrol 11 3/6/2007 [ Minor Editorial FM-57 ]Long Form Startup Checksheet 1 10 1 3/6/2007 [ Minor Editorial FM-57 Long Form Startup Checksheet I II 5/11/2007 [ Minor Editorial FM-58 .- Short Form Startup Checksheet 5 5/11/2007 [ Minor Editorial FM-93 jPost-Maintenance Valve Lineup Checksheet [ 3 .1.6/28/2007 f Cover Page FM-97 Operations and Facility Infrastructure Drawing 7/31/2007 I Cover

_ _ Revision Tracking Form Page ORunFain Fans EF-13 and EF-14, EF-13 11/26/2007 Cover OA- ci'4 1126/207 CverPage Running OA2 Facility Exhaust Fans EF- 13 and EF- 14, EF-14

___ [Running 4 11/26/20071 Cover Page OA-21 .MUIRR Maintenance Guidelines T 4 7/31/2007 CoverPage OA-3 Beamport and Pool Overflow Loop Seals 4 1_ 11/1/2007_ MinorTEditorial OA-4 Valve Operation Air Compressor 41 [ 11/1/2007 f Minor Editorial F

OA-5 Emergency Air Compressor 4 [1/1/2007 Minor Editorial OP-RO-100 IMain Air System T 1 4/19/2007 1 7 Minor Editorial OP-RO-!01[Instrument Air System 6 14/19/2007 1 Minor Editorial OP-RO-211 Reactor Startup - Hot T.. 6. 7/9/2007 Minor Editorial OP-R-212Reduction Reactor Startup - Recovery from Temporary Power 5 1/620 11/26/2007 io Minor dtra OP-RO-250 In-Pool Fuel Handling _ ' T8 8/30/2007 Cover Page OP-RO-460 Pool Coolant System - Two Pump Operation Pool Coolant System - Two Pump Operation T__8 1-f-- 6/28/2007 7/31/2007 Cover Page Minor Editorial 1OP-RO-460 r--OP-RO-460 Pool Coolant System - Two Pump Operation 110 } 10/18/2007 Minor Editorial IOP-RO-461 Pool Coolant System - One Pump Operation 1 7 T10/18/2007 Minor Editorial OP-RO-461 Pool Coolant System - One Pump Operation 17 f 10/18/2007 Minor Editorial F OP-RO-465 jPool Level Control - Skimmer System 15 ] 5/11/2007 J Cover Page OP-RO-466 . Pool Level Control - Pool Coolant System -- -5]-- 4/6/2007 { Cover Page FOP-RO-466 ]Pool Level Control - Pool Coolant System 1 6 1 11/1/2007 Minor Editorial 6

OP-R0-5 15 Emergency Air System 6 1 10/8/2007 [ Minor Editorial FOP-RO-516 IValve Operation Air System 6 1 7/9/2007 [ Cover Page OP-RO-525 lChill Water System _4/6/2007 Full Review

] OP-RO-530 IDemineralized Water Supply System 1 6 7/9/2007 [ Cover Page

[ P-R°-532 jDrain Collection System . . 5.. 6/28(2007 [ Cover Page OP-RO-533 ISkimmer System 4 7/31/2007 ] Cover Page OP-RO-710 ]Radiation Monitoring - Area Monitors J4 {7/31/2007 ] CoverPage OP-RO072(0 Radiation Monitoring- Stack Monitor Operational 6/28/2007 Minor Editorial OP-RO-720__ lCheck Radiation Monitoring - Stack Monitor Operational OP-RO-720 6 7/9/2007 Full Review Check 11-2

Numýber am/y<uJ[j.~KV11UJvsjk t _

OP-RO-730 JFacility Exhaust System [9 4/6/2007 Minor Editorial FiiP-RO-100 IReactor Emergency Procedures F 6 4/10/2007 1 Minor Editorial REP-RO-100 ]Reactor Emergency Procedures . [ 4/11/2007 T Minor Editorial

[RiEP-RO-100 jReactor Emergency Procedures r 8 5/11/2007 1 Full Review TRM-RO-405 jReactor Demineralizer System [.9 f9 7/31/2007 1 Minor Editorial RP-RO-100 JFuel Movement f f 7 6/28/2007 1 Minor Editorial RTP-1 1D Measurement of Differential Worth ofa RP-RO-200 Shim Blade 3 7/31/2007 1 Minor Editorial RP-RO-201 RRTP-17B Measurement of Total Reactivity Worth of-2i rpLaig 2Fu 8 0i 8/30/2007 t Minor Editorial lFlux Trap LoadingsI -__

RP-RO-202 Measurement of Reactivity Worth of Movable ISamples, RTP-6 0 1 4/19/2007 4/19/2007 Full Review F Review i SM-RO-635 IRetracting and Reinserting Beamport'A' Liner [1 1 . 4/6/2007 1 Minor Editorial I SM-RO-636 Retracting and Reinserting Beamport'B' Liner I 1 4/6/2007 1 Minor Editorial SM-RO-637 lRetracting and Reinserting Beamport'C' Liner [ 1 4/6/2007 1 Minor Editorial I SM-RO-638 lRetracting and Reinserting Beamport'D' Liner 2 1 4/6/2007 Minor Editorial I.SM-RO-639 Retracting and Reinserting Beamport'E' Liner F 2 J 4/6/2007 Minor Editorial SM-RO-640 fRetracting and Reinserting Beamport 'F' Liner 3 4/6/2007 Minor.Editorial SM-RO-660 IRemoval of Pressure Vessel _1 T 4/6/2007 1 Minor Editorial i GS-RA-100 IMURR Equipment Tag Out J 6 4/4/2007 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:

EP-RO-004 ire 2 1 8/10/2007 J Minor Editorial Severe NaturaPhenomenon jEP-RO-007 1 2 1 8/10/2007 { Minor Editorial FEP-RO-013 Facility Evacuation 12 1 8/10/2007 Minor Editorial FEP-RO-014 jEPZ and Site Area Evacuations 1 3 1 8/10/2007 J Minor Editorial I EP-RO-017 JEmergency Air Sampling . _2_ 8/10/2007 [ Minor Editorial FM-1 ._ ire. E ncyCallList Types.1 1 6 8/10/20_07. Minor Editorial I OA-10 IFire Extinguisher Locations and Types 3 8/10/2007 [ Minor Editorial I OA-20 JEmergency Equipment 13 1 8/10/2007 1 Minor Editorial 11-3

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 eighty-five (85) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures and forms:

AP-HP- 105 [Radiation Work Permit _ 6J 8/21/2007 Minor Editorial AP-HP-105 Radiaion Work Permit MURR Initial Radiation Worker Training 1--7-T 11/8/2007 T Minor Editorial AP-HP-1 17 Program 4/18/2007 Minor Editorial AP-HP-117 ProgramInitial Radiation Worker Training MURR 9 ....-1 1 1/207 MioEdtra Minor AP-HP-120 1Beamport Area 13 1 4/4/2007 1 Cover Page AP-HP-121 Isotope Closet 3 4/4/2007 -f Cover Page I AP-HP-125 AP-HP-!129-- -]Hot Review of Unplanned Radiation Exposure

....Cell Control Conro6.... . .....

• 2 5

4/18/2007 6/6/2007 T Minor Cover Page Editoriali AP-SH-001 Administrative Procedure, Radioactive Materials 5 2/16/2007 Full Review IShipping

[

APS-00l-U* .. 2/16/2007.Full.Review DOT 6M Packaging of Type B Non-Waste 5 12/7/2007 Minor Editorial BPB-SH-005 Radioactive MaterialI 5 12/7/2007_ MinorEditorial BPSH0 F-327 Packaging and Shipment of Type A Non- I I BWaste Radioactive Material I 5/24/2007 BP-SH-012 IDOT-7A Package Certification 2 5/24/2007 Cover Page

,P . Packaging and Shipment of Radioactive Materials 2 5 I 1Using MURR Reusable Type A Package .

_ 5/24/2007 BP-SH.014 Packaging and Shipment of Radioactive Material 1 4/020 CoeIPg lUsing an Overpack .

Radioactive Material Shipment Package 1 I

1 Documentation and Labeling 9/112007 Cover Page B

BP-SH-052 Radioactive Material Shipment Package Documentation and Labeling 21i 12/7/2007 Minor Editorial BP-SH059 Packaging and Shipment of Radioactive Material Using Reusable DOT 7A Type A Package 1 12/7/2007_ iMinor Editorial f

Editorial BP-SH-099.

BPackaging of Radioactive Material Using MURR I i jModel 1500 2/16/2007 Minor Editorial

-.... -0. .. uPnirradiated Using DOT 6M..

Fuel Shipment.......... Ful Rview Fu ll....

.. p ackag e FM-107 lControl Check Sheet for Overpack Shipment J_[2 I 4/20/2007 1 Cover Page

_ FM-10'8'-- Container Leak Check Data Sheet [.1 [ 4/20/2007 1 Cover Page FM-27 lIn-House Radioactive Shipping Request Form - 6 [ 2/16/2007 Minor Editorial I FM-27 In-House Radioactive Shipping Request Form F7 r 12/7/2007 Minor Editorial FM-68 jTarget Material Control Checksheet 6 [ 8/22/2007 1 Minor Editorial FM-39 lControl Checksheet for Excepted Package 9 2/16/2007 Minor Editorial 11-4

V.1111 r it> ý Notes I7

[Radioactive Materials Shipment ]_ [ _

FM-44 Request for Radioisotope Shipment J 7 [ 9/11/2007 Cover Page Control Checksheet for Documentation and 2 2/16/2007 Minor Edito a FM-52 Labeling of Radioactive Material Shipment TM52

.Control Checksheet for Documentation and Labeling of Radioactive Material Shipment3

........ 11/707 M Editorial MioEdtra FM-54 [Report of Personnel Contamination "5 6/6/2007 Full Review FControl Checksheet for Reusable Type A Package 1 12 FM-59 Radioactive Materials Shipment 1 12/7/2007 Full Review FM-62 [Radiation Instrument Certificate of Calibration J 4 [ 4/18/2007 Full Review P

Control Checksheet for MURR Reusable Type A FM-69 Radioactive Materials Shipment (5 and 10 Gallon 5 5/24/2007 Full Review Drums)

Control Checksheet for Type B USA DOT 6M I FM-74 Radioactive Materials Shipment 9 12/7/2007 Minor Editorial Control Checksheet for Type B(U) F-327 Series 8 12/7/2007 Minor Editorial

............. . [Radioactive Materials Shipment .... 12/7/2007...Minor.Ed.torial FM-76 Personnel Contamination Log [2 9/10/2007 [ Full Review FM 1-89 Control Checksheet for Type A F-327 Series 6 4/12/2007 Minor Editorial

______ Radioactive Material Shipment I 6 I 4/_20 I MnrEioa FM-89

[Control Checksheet for Type A F-327 Series jRadioactive Material Shipment 7

7 7/17 7/17/2007 I Full Review

.FM-94 Exclusive Use Shipment Controls [ 1 [4/20/2007 { Full Review FM-98 FM-98 Control Checksheet for MURR Shipment Using IUSA DOT7A MURR Model 6 or 12 3 2/16/2007 1 Cover Page FM-99 [Control Checksheet for USA DOT 7A MURR 2 4/12/2007 Minor Editorial FM-99__ _ .IMo.del 1500 Series . . ._ 2 4/12/2007 MinorEditorial Hot Cell Preparation of Radioactive Material for 6 4/6/2007 Minor Editorial HC-PSO-002 Shipment I 4/6/2007 1 MinorEditorial HC-PSO-002

-Hot Cell Preparation of Radioactive Material for Shipment 7

7I.

12/7/2007 T

{ Page Cover Page HC-PSO-003 Shipment Box Preparation of Radioactive Material for[ 5 F3/14/2007 Cover Page HC-PSO-003 Glove Box Preparation of Radioactive Materialfor Shipment 6 1I2/72007 I Minor ditorial HC-PSO-005 lHot Cell Loading of Host Cans [ 4 [ 3/14/2007 1 Minor Editorial HC-PSO-005 lHot Cell Loading of Host Cans [ 5 1 12/7/2007 1 Cover Page IC-HP-319 Calibration - NMC Model RAK Monitor - 4 4/4/2007 1 Cover Page CP1articulate Channel _4 ______ CoverPage Calibration - NMC Model RAK Monitor - Iodine 4 4/4/2007 Minor Editorial IC-HP-320 IChannel 4 4 0 M d IC-HP-321 IC-u-HP 31I Calibration - NMC Model RAK Monitor - Gas ChannelJ 4 ..

T 4/18/2007 Minor Editorial IC.HP-.341 Calibration -High Resolution Gamma 1 3/12/2007 Minor Editorial CSpectroscopy Systems 3/12/2007 I MinorEditorial IC-HP-343 ]Calibration - Sodium Iodide Detector 1 4 ] 4/4/2007 Minor Editorial I IC-HP-347 lCalibration - Protean Model WPC 9550 Alpha- 1 7 1 8/21/2007 J Minor Editorialj 11-5

Nuinikrj_60i- Name WI R .]Ravision DaiW.e Notes W jBeta Swipe Counter i 1 _

.IC.HP.348

. . - Calibration - Canberra S5XLB-G & Tennelec 3 616/207 i

.... sie4_.it__G i_....... -- . MinorEdit

_IRR-PSO-112

[OP-HP-221 IPreparing Shipping Paperwork

"[Environmental Sample - Analysis 11 1 5

3/14/2007 6/6/2007 Minor Editorial

-[MinorEditorial OP-HP-222 jAirSampling - ContainmentBuilding Ar-41 __3 1 3/12/2007 Minor Editorial OP-HP-223 ISpent Fuel Shipping Cask Water Sample Analysis 3-1 7/19/2007 T Minor Editorial OP-HP-224 ISpent Fuel Shipping Cask Air Sample Analysis 13 T 9/10/2007 T Cover Page OP-HP-306 Ibaily Facility Checks I 1 11/8/2007 Minor Editorial OP-HP-353 IWaste Tank Sample - Analysis 4 1 11/8/2007 Minor Editorial I .OP-HP-505

. Emergency Stack Monitor Filter Analysis- 1 1 9/10/2007 Cover Page POL-03 fRadiation Protection Program 17 1 9/20/2007 [ Minor Editorial 1

F Stack Monitor Preventive Maintenance - NMC Model R .4 Stack Monitor Preventative Maintenance -

4 4/4/2007 Cover Page RM-HP-101 Eberline PingI A __ ______ ______

RP-HP-105 ITransfer of Radioactive Material - In Facility 4 3/12/2007 Minor Editorial RP-HP-105 JTransfer of Radioactive Material - In Facility 5 8/21/2007 Minor Editorial RP-HPI 10 Survey and Decontamination of Returned 4 4/18/2007 Cover Page Shipping Container _ 4 _1820 Coverage RP-HP- 120 iPersonnel Radioactive Contamination 5 1 6/6/2007 J Cover Page RP-HP-130 IReceipt of New Fuel Elements 141 4 4/18/2007 T Cover Page RP-HP-135 ]Room 114 Entry - Self Monitored 1 3 I 7/19/2007-1 Cover Page I RP-HP-137 lHand!ing.RadioactiveMaterial in the Reactor Pol 5- 8/21/2007 1 Minor Editorial RP-HP-137 ]Handling Radioactive Material in the Reactor Pool 6 ] 11/8/2007 [ Minor Editorial SV-HP-105 ISealed Calibration Source - Leak Check 16 12/28/2007__ Minor Editorial Secondary Coolant and Sump Water - Sampling I4 6 SV-HP-117 land Analysis 4 6/6/2007 Cover Page SV-HP-130 Emergency Air Sampling of Exhaust Plume , 3 17/19/2007 - Cover Page

.SV-HP-135 .Containment Air - Emergency Remote Sampling 4 1 12/28/2007 T Cover Page TPZ-PSO-001 IReceiving Gemstone Irradiation Shipping Drums 14 1 12/7/2007 T Minor Editorial WMB-SHO005 IShipment of Type B Radioactive Waste Using /12/2007 Full Review Chem-Nuclear System I-13G Cask _ 4/12/2007 __FullRev i WM-SH-100 lRadioactive Waste - Preparation and Storage [4 [4/20/2007 1 Minor Editorial WM-SH-105 lRadioactive Waste Processing 13 17/17/2007T Minor Editorial Exclusive Use Shipment of LSA or SCO 4 5/24/2007 Minor Editorial

'.WM-SH-300 Radioactive Waste iWM-SH-30 Exclusive Use Shipment of LSA or SCO 5 81/07 Minor Editorial WM-...... Radioactive Waste F

SFB-SH-001 H0 PUnirradiated acag Fuel Shipment Using DOT 6M 0 7/17/2007 Full Revie I IacIag IRR-PSO-106 ITarget Material Control Checks I 4 1 1/31/2007 Minor Editorial IR.R-PSO- 106 ITarget Material Control Checks 5'~~-8/22/2007 Minor Editorial 11-6

SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT January 1, 2007 through December 31, 2007 These changes were approved by the Reactor Manager and reviewed by licensed staff and members of the Reactor Safety Subcommittee and have been determined not to involve a change to the Technical Specifications. These changes have all been reviewed in accordance with 10 CFR 50.59.

HAZARDS

SUMMARY

REPORT (ORIGINAL JULY 1, 1965)

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

Replace with: Updated Figure 5. 1, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet 1 of 1, dated 10/l/07)

Original HSR, page 7-20, Section 7.2.9, Table 7.1 (as revised by the 1974-75, 1995, 2001 and 2002 Reactor Operations Annual Reports):

Add: The following to Table 7.1 under Staff Stations:

Corridor C2002 Cyclotron Suite Corridor C2000 Exit to Lobby Room 2041 Laboratory Area" Original HSR, page 7-21, Section 7.2.9, Table 7.2 (as revised by the 1995 and 2001 Reactor Operations Annual Reports):

Delete: Entire Table 7.2, which states:

"Room 101 (3) Room 216 Containment Building Grade Level (2) Room 218 Containment Building Third Level Room 224 Containment Building Fourth Level Room 227 Cooling Tower Grade Level Room 232B Room 103 Room 238 RoomlIlIl Room 231 Main Lobby Room 23 1A Outside Room 114 Room 23 1B Outside Room 214A Room 23 1C Outside Room 224 Room 241 Outside Room 228 Room 251 Outside Room 241 Room 251 Outside Room 244 Room 257 Outside Room 258 Room 259 Outside Room 264 Room 262 Outside Room 288 Room 267A Outside Room 293 Room 271 Room 212 Room 278 Room 215A Room 288" 111-1

Replace with: " Containment Building Room 101 (3) Containment Building Third Level Containment Building Grade Level (2) Containment Building Fourth Level Reactor Laboratory Building Cooling Tower Grade Level Room 241 Room 103 Room 242 Room Ill Room 244 Outside Room 114 Room 245 Outside Room 214A Room 247 Outside Room 224 Room 251 Outside Room 228 Room 255 Outside Room 241 Room 257 Outside Room 244 Room 258 Outside Room 258 Room 259 Outside Room 264 Room 260 Outside Room 288 Room 262 Outside Room 293 Room 267A Room 202 Room 271 Room 210, Lobby Room 273 Room 212 Room 278 (2)

Room 215A Room 280 Room 216 Room 281 Room 218 Room 288 Room 224 Room 299 Room 227 TOB-1 Room 232B TOB-2 Room 238 TOB-3 Room 231 TOB-4 Room 231A TOB-5 Room 231C North Office Addition Corridor C2000 Room 2008C Corridor C2002 (2) Room 2009 Room 2005 Room 2009A Room 2006 Room 2011 Room 2007 Room 2015 (17)

Room 2008 Room 2041 Room 2008A" Original HSR, page 8-18, Figure 8.4, MURR 3 Tube Flux Trap (as added by the 1972-73 Reactor Operations Annual Report):

Replace with: New Figure 8.4, Flux Trap: 3-Barrel Assembly View (MURR Dwg No. 2505, Sheet I of 3, dated 4/17/07)

Original HSR, page 8-19, Figure 8.5, Flux Trap: 6-Barrel Assembly View (as added by the 2000 Reactor Operations Annual Report):

Replace with: Updated Figure 8.5, Flux Trap: 6-Barrel Assembly View (MURR Dwg No.

2528, Sheet 1 of 3, dated 4/17/07) 111-2

Original HSR, pages 9-7 through 9-9, Table 9.2 (as revised by the 1981-82, 1985-86, 1995, 2000, 2001, 2002 and 2006 Reactor Operations Annual Reports):

Add:.

... . --. -135--- ---.- Radioactive-L-iquid--Waste System-Alarn-Panel-'."- ............... ....--

Add: "136 Fire Protection System Alarm Panel" Original HSR, Figure 9.4, Safety System 10 MW (as revised by the 1995, 2001, 2002, 2003 and 2006 Reactor Operations Annual Reports):

Replace with:. Updated Figure 9.4, Safety System (MURR Dwg No. 139, Sheet I of 1, dated 4/9/07)

Original HSR, page 9-15, Section 9.4.3:

Add: The following sentence to the end of the second paragraph:

"To ensure that the annunciator panel remains operable, an out of normal or loss of power condition is indicated on the auxiliary annunciator."

ADDENDUM 3 - HAZARDS

SUMMARY

REPORT (AUGUST 1972)

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 and 2006 Reactor Operations Annual Reports):

Replace with: New Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg No.

522, Sheet I of 5, dated 11/28/07)

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

Replace with: New Figure 2.3.b, Electrical Distribution North Office Addition (MURR Dwg No. 522, Sheet 2 of 5, dated 11/28/07)

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

Replace with: New Figure 2.3.c, Electrical Distribution Reactor/Laboratory Panels (MURR Dwg No. 522, Sheet 3 of 5, dated 11/28/07)

HSR, Addendum 3, page 23d, Figure 2.3.d, Electrical Distribution:

Add: New Figure 2.3.d, Electrical Distribution Reactor/Laboratory Panels-2 (MURR Dwg No. 522, Sheet 4 of 5, dated 11/28/07)

HSR, Addendum 3, page 23e, Figure 2.3.e, Electrical Distribution:

Add: New Figure 2.3.e, Electrical Distribution North Office Addition Panels (MURR Dwg No. 522, Sheet 5 of 5, dated 11/28/07) 111-3

ADDENDUM 4 - HAZARDS

SUMMARY

REPORT (OCTOBER 1973)

HSR, Addendum 4, page A-28, Figure A.1, Safety System 10 MW (as revised by the 1995, 2001, 2002,

_2003_and_20.06.ReactorQp-eration Annual Reports): .. ..

Replace with: Updated Figure A.1, Safety System (MURR Dwg No. 139, Sheet 1 of 1, dated 4/9/07)

HSR, Addendum 4, page A-29, Figure A.2, Piping & Instrument Diagram (as revised by the 1972-73, 1973-1974, 1994, 1996, 2001, 2002, 2003, 2004 and 2006 Reactor Operations Annual Reports):

Replace with: Updated Figure A.2, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet I of 1, dated 10/1/07)

HSR, Addendum 4, page A-30, Figure A.3, 10 MW Process Instrumentation Control & Interlock (as revised by 1995, 1998, 2001, 2004, 2005 and 2006 Reactor Operations Annual Reports):

Replace with: Updated Figure A.3, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 3 of 4, dated 4/9/07)

HSR, Addendum 4, page A-31a, Figure A.4.a, Reactor Control System - 10 MW (as revised by 1995, 2001, 2004 and 2006 Reactor Operations Annual Reports):

Replace with: Updated Figure A.4.a, Reactor Control System (MURR Dwg No. 42, Sheet I of 2, dated 5/8/07)

HSR, Addendum 4, page A-34, Figure A.7, Annunciator Control 10 MW (as revised by the 1995, 2001, 2002, 2005 and 2006 Reactor Operations Annual Reports):

Replace with: Updated Figure A.7, Annunciator Control 10 MW (MURR Dwg No. 138, Sheet I of 1, dated 5/8/07)

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 and 2006 Reactor Operations Annual Reports):

Replace with: New Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No.

522, Sheet 1 of 5, dated 11/28/07) 111-4

SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2007 through December 31, 2007 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 90-1, Addendum 1:

Evacuation System Changes in Support of the New North Office Addition This addendum to modification record 90-1, "Evac Horn," documents changes to the facility evacuation system in support of the facility's new North Office Addition (NOA). The manual actuation switch was relocated and additional horns and lights were added to the facility evacuation system in order to safely occupy the new building addition.

Modification 01-2, Addendum 2:

Intercommunication and Paging System Changes in Support of the New North Office Addition 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 are in support of the facility's new North Office Addition (NOA). Additional intercom staff stations and paging speakers were added in order to safely occupy the new building addition.

Modification 01-14, Addendum 1:

120/208V Electrical Distribution System Upgrade This addendum to modification record 01-14, "Installation of a 300 kVA Transformer," documents the upgrade of the facility's 120/208V electrical distribution system. Modification record 01-14 documented the installation of a new 300-kVA transformer to help increase the facility's overall 120/208V load capacity while reducing the load on the current 120/208V distribution center. This upgrade included installation of a new 300-kVA transformer to eventually replace the existing 120/208V distribution center transformer, and to power both 300-kVA transformers via a new 480/277V high voltage panel which is fed from the laboratory building 2,000-kVA transformer.

Modification 04-1, Addendum 1:

Replace the 943 LFE Meter Relay Unit (EP-942) with a Beede Meter Relay Unit This addendum to modification record 04-1, "Replace the General Electric Type 551 Reactor Pressure Transmitter PT-943 with a Rosemount Model 1151," documents the replacement of the LFE Model 195 meter relay unit for primary coolant system pressure transmitter PT-943 with a Beede Model MR4 meter relay unit. Replacement of the LFE meter relay unit was necessary because the instrument could no longer satisfactorily pass calibration and this particular make and model was no longer commercially available.

Modification 05-1, Addendum 1:

Upgrade Pneumatic Tube System Photo Sensor Collar and Counting Circuit This addendum to modification record 05-1, "Pneumatic Tube System Photo Sensor Collar Upgrade,"

documents the replacement of the pneumatic tube system photo sensor collars with a new, standardized IV- 1

version that supports the new fiber optic connections. This modification record also documents the replacement of the photo sensor relays with fiber optic photo relays.

Modification 05-6: - -

Replace Pool Pump Piping This modification record documents the replacement of certain sections of pool coolant system piping in order to reduce operational system head losses and therefore increase available system flow. This modification, in conjunction with the replacement of pool coolant heat exchanger HX-521 (performed under modification record 94-4, addendum 1), returned pool coolant system flow rate to design values.

Modification 06-3:

Replace Flux Trap Holder Wear Ring This modification record documents the replacement of the center test hole experimental sample holder wear ring with an improved design which helps to further ensure that the experimental contents of the sample holder remain secured during reactor operation. This improved design was a corrective action for Licensee Event Report No. 05-02.

Modification 07-1:

Installation of the Five and Six Inch Sample Diameter Irradiation Facility This modification record documents the replacement of the bulk pool sample irradiation facility with a new three-position irradiation facility of improved design and capacity. The new design incorporates an increased number of self-powered detectors, an underwater rotating mechanism, and stabilizing legs for additional support.

Modification 07-2:

Installation of Circuitry to Indicate a Loss of the Main Annunciator This modification record documents the installation of circuitry that provides a visual and audible alarm to the control room operator in the event of a loss of power or any other abnormal condition in the main annunciator panel.

Modification 07-3:

Replace Cooling Tower Fan Vibration Switches This modification record documents the replacement of the cooling tower fan vibration switches with an improved design. The new switches offer the following three improvements: (1) the existing switches were originally mounted near the fan gearbox and then relocated to the motor baseplate where fan vibration levels are significantly damped while the set point was not changed, (2) an ongoing effort is being made throughout the facility, where possible, to replace switches that contain mercury, and (3) the old enclosures no longer provided adequate weather protection to prevent corrosion of the internal electrical connections.

Modification 07-4:

Interfacing MURR Systems with the North Office Addition This modification record was used as the initiating document to ensure that all systems related to emergency response have been identified and modified prior to safely occupying the facility's ncw North Office Addition (NOA). Actual modifications to these systems - facility evacuation, fire protection, intercommunication and paging, and emergency electrical power - were performed under addendums to previously approved modification records.

IV-2

Modification 07-5:

Beamport 'E' Changes to Replace Collimator Liner in Support of Boron-Neutron Capture Therapy (BNCT)

Project This-modification--r&-cor d iiWifi- -fel~ceiit-fB-6iff-rffp-'E'- -re-v-able-ollimator-liner-with a new design, and the associated piping changes necessary for its utilization. The replacement collimator liner is a combined liner and filter cavity which utilizes as much of the 8-inch diameter portion of the collimator liner in order to accommodate as much neutron and gamma filter material as possible. Due to this larger diameter filter material, no provisions can be made in the collimator liner for the helium and water connections, or concrete shielding annulus.

IV-3

SECTION V NEW TESTS AND EXPERIMENTS January 1, 2007 through December 31, 2007 New tests or experiments developed during this period under a Reactor Utilization Request (RUR) or reactor project are as follows:

RUR 428: Bismuth Oxide

Description:

This RUR authorizes the irradiation of up to 60.0 grams of bismuth oxide (Bi 2 0 3) for use in research and development activities.

RUR 429: Krypton Gas

Description:

This RUR authorizes the irradiation of up to 12.5 milliliters (or 0.200 grams) of enriched krypton gas (Kr-78) for commercial applications.

Flux Characterization

Description:

Flux Measurements were performed on Beamport 'B' in support of the Boron Neutron Capture Therapy Project planned for Beamport 'E,' which is expected to commence during calendar year 2008.

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

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

V-I

SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2007 through December 31, 2007 Inspections:

There was one NRC inspection which reviewed Special Nuclear Material activities. All records and activities were found to be in compliance with NRC rules and regulations. No violations were noted.

Reactor Characteristic Measurements:

Sixty (60) refueling evolutions were completed in 2007. Excess reactivity verifications were performed for each refueling. The largest measured excess reactivity value was 3.42%. MURR Technical Specification

3. 1(f) requires excess reactivity to be less than 9.8 %.

Reactivity Measurements:

Differential blade-worth measurements of four (4) 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.

One (1) reactivity measurement was made to characterize the reactivity worth of a new sample irradiation facility, which is installed on the bulk pool side of the reflector tank.

Four (4) reactivity measurements were made to determine the reactivity worth of all samples, including the sample holder, loaded in the flux trap region.

Three (3) reactivity measurements were made to determine the reactivity worth of a new style sample container irr adiated in the flux trap region.

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

VI- I

SECTION VII RADIOACTIVE EFFLUENT January 1, 2007 through December 3.1, 2007 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2007 through December 31, 2007 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide Activity (Ci)

H-3 9.986E-02 S-35 9.328E-03 Co-60 3.115E-03 Lu- 177 1.854E-03 Sc-46 7.011 E-04 Ca-45 6.223E-04 Zn-65 5.596E-04 P-32 5.042E-04 Cr-51 2.540E-04 Lu-177m 2.468E-04 Mn-54 1.961E-04 Sb- 124 1.648E-04 Fe-59 1.039E-04 W-181 5.168E-05 Ag- 110m 5.001 E-05 Sm-153 3.593E-05 Re-186 2.880E-05 Co-58 1.530E-05 Total H-3 9.986E-02 Total Other 1.783E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."

v1I-1

TABLE 2 STACK EFFLUENT

_ _January!l, 2007 through December 31, 2007 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration Total Release TS Limit Multiplier  % TS (PCi/ml) (Ci)

Ar-41 2.74E-06 1.27E+03 350 78.3592 C-14 2.38E-11 1.08E-02 1 0.7930 Co-60 1.69E-13 7.79E-05 1 0.3372 Ce-144 2.33E-14 1.08E-05 1 0.1165 H-3 1.70E-08 7.84E+00 350 0.0485 1-131 8.01E-14 3.70E-05 1 0.0401 Sc-46 7.89E-14 3.65E-05 1 0.0263 K-40 5.58E-14 2.58E-05 1 0.0093 Os-191 1.33E-13 6.13E-05 1 0.0066 Fe-59 1.90E-14 8.79E-06 1 0.0038 Zn-65 1.05E-14 4.83E-06 1 0.0026 Cs-137 1.27E-15 5.87E-07 1 0.0006 Au- 196 1.43E-15 6.61E-07 350 0.0004 Nb-95 6.46E- 15 2.98E-06 1 0.0003 Hg-203 2.32E-15 1.07E-06 1 0.0002 Ce-141 1.39E-15 6.41E-07 1 0.0002 1-133 3.92E- 13 1.81E-04 350 0.0001 Mn-54 1.12E-15 5.17E-07 1 0.0001 Note: C-14 activity is calculated based on the ratio of argon to nitrogen in the air and the (n,p) reaction cross sections for the activation of N-14 to C-14.

Isotopes observed at < 0.0001% TS limit are not listed.

Stack Flow Rate = 30,500 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, 2007 through December 31, 2007 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 1 and 2.

Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2007. All doses are approximately 40 tnRem/year or less, except monitor numbers 9 and 15. These monitors are located near the loading dock 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 1 Summary of Environmental Set 72 Spring 2007 Detection Limits*

Matrix Alpha Beta Gamma Tritium Water 0.29 pCi/L 0.81 pCi/L 214 pCi/L 5.93 pCi/mL of sample Soil 0.63 pCi!g 2.56 pCi/g 0.69 pCi/g N/A Vegetation 0.00 pCi/g 1.83 pCi/g 1.34 pCi/g 5.45 pCi/mL of distillate

• Gamma and tritium analyses are based on wet weights while alpha and beta analyses are based on dry weights.

Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL)

IV72 0.06 3.01 < 1.34 < 5.45 2V72 0.08 3.39 < 1.34 < 5.45 3V72 0.05 2.69 < 1.34 < 5.45 4V72 0.11 2.71 < 1.34 < 5.45 5V72 0.00 3.09 < 1.34 < 5.45 6V72 0.13 4.10 < 1,34 < 5.45 7V72 0.05 4.68 < 1.34 < 5.45 10V72 0.13 2.89 < 1.34 < 5.45 VIII-1

TABLE 1 (Cont'd)

Summary of Environmental Set 72 Spring 2007 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1S72 < 0.63 <2.56 4.08 2S72 <0.63 < 2.56 3.14 3S72 < 0.63 <2.56 3.22 4S72 < 0.63 < 2.56 1.41 5S72 <0.63 <2.56 3.64 6S72 < 0.63 < 2.56 1.95 7S72 < 0.63 <2.56 2.92 10S72 < 0.63 < 2.56 3.70 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W72 < 0.29 < 0.81 .< 214 < 5.93 6W72 < 0.29 <0.81 <214 < 5.93 10W72 < 0.29 1.21 <214 < 5.93 TABLE 2 Summary of Environmental Set 71 Fall 2007 Detection Limits**

Matrix Alpha Beta Gamma Tritium Water 0.20 pCi/L 0.85 pCi/L 286 pCi/L 4.74 pCi/mL of sample Soil 0.16 pCi/g 0.45 pCi/g 0.68 pCi/g N/A Vegetation 0.50 pCi/g 2.66 pCi/g 2.13 pCi/g 7.01 pCi/mL of distillate

• • Gamma and tritium analyses are based on wet weights while alpha and beta analyses are based on dry weights.

VIII-2

TABLE 2 (Cont'd)

Summary of Environmental Set 71 Fall 2007 Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL) 1V71 <0.50 < 2.66 <2.13 <7.01 2V71 <0.50 < 2.66 <2.13 <7.01 3V71 <0.50 < 2.66 <2.13 < 7.01 4V71 < 0.50 < 2.66 <2.13 < 7.01 5V71 < 0.50 < 2.66 <2.13 < 7.01 6V71 <0.50 < 2.66 <2.13 < 7.01 7V71 <0.50 < 2.66 6.77 14.79 10V71 <0.50 < 2.66 8.20 < 7.01 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/)

1S71 <0.16 1.27 4.25 2S71 <0.16 2.15 1.94 3S71 <0.16 1.92 3.13 4S71 <0.16 1.48 2.58 5S71 <0.16 1.61 2.80 6S71 <0.16 1.78 2.44 7S71 <0.16 2.22 2.51 10S71 <0.16 1.77 2.86 Activity Levels - Water Sample Alpha (PCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W71 < 0.20 <0.85 1988 < 4.74 6W71 < 0.20 1.16 < 286 < 4.74 10W71 < 0.20 <0.85 5105 < 4.74 Note: Increased gamma levels indicated in sample 10W71 were attributed to isotopes used in nuclear medicine studies originating from local hospitals.

VIII-3

TABLE 3 Environmental TLD Summary January 1, 2007 through December 31, 2007 Badge Direction Map Distance from 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total

-Number-- -From-MURR- ---.. MURR-Stack --.----. -2007-. -- 2007---. -- 200-7--- ---- 200-7 -- 200-7---

(meters) Net mR Net mR Net mR Net mR Net mR I Control N/A 4,2 0.8 0.0 2.0 7.0 2 Control N/A 2.5 0.0 0.0 6.9 9.4 3 WSW N/A 1.7 0.0 0.0 0.7 2.4 4* Not used N/A 5** Not used N/A 6 N 34 2.9 0.0 0.0 0.0 2.9 7 NE 57 5.0 2.4 0.0 0.5 7.9 8 SW 27 5.7 0.0 0.0 0.0 5.7 9 S 27 28.1 20.8 25.9 20.3 95.1 10 NE 149 0.6 0.1 0.0 0.0 0.7 11 NW 149 0.3 0.3 0.0 0.0 0.6 12 ENE 301 5.8 5.4 4.3 2.7 18.2 13 NNE 316 7.6 0.0 2.0 0.0 9.6 14 S 156 3.8 0.0 1.0 0.0 4.8 15 S 65 19.2 18.3 28.7 16.8 83.0 16 SE 107 0.0 0.0 0.0 0.6 0.6 17 E 293 absent 0.0 0.0 0.0 0.0 18 NE 476 5.6 0.0 0.0 0.0 5.6 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 0.4 0.0 7.0 0.0 7.4 22 ESE 168 0.0 0.0 0.0 0.0 0.0 23 NW 110 0.0 0.0 0.0 0.2 0.2 24 SSW 328 1.9 0.0 0.0 0.0 1.9 25 SSW 480 1.9 0.0 0.0 1.1 3.0 26 SW 301 2.5 0,0 0.0 0.0 2.5 27 WSW 141 0.0 0.0 0.0 0.0 0.0 28 WNW 210 4.2 0.0 0.0 0.0 4.2 29 NW 255 5.5 3.0 0.0 0.0 8.5 30 NNW 328 35.0 10.3 no report 0.0 45.3 31 NNW 671 absent 8.1 0.0 0.0 8.1 32 NNW 724 2.4 6.7 0.0 0.0 9.1 33 E 671 0.0 3.2 0.0 0.0 3.2 34 ENE 587 0.0 0.0 0.0 0.0 0.0 35 SSE 499 absent 3.7 0.0 0.0 3.7 36 SE 419 0.9 0.0 0.0 0.0 0.9 37 NE 690 0.0 3.9 0.0 0.0 3.9 38 NW 556 2.5 4.5 2.1 2.9 12.0 39 W 491 0.0 8.2 0.0 0.0 8.2 40 N 514 0.1 4.5 no report 1.8 6.4 41 NNE 137 0,0 4.7 0.0 1.9 6.6 42 In Building N/A 4.7 29.2 3.4 21.4 58.7 43 In Building N/A absent 7.9 0.0 2.0 9.9 44 Spare N/A 4.5 0.7 0.0 0.8 6.0 45 S 65 3.1 0.3 0.0 1.1 4.5

• TLD No. 4 moved from spare to fence outside shipping area.

• • TLD No. 5 moved from spare to outside wall of shipping area.

VIII-4

TABLE 4 Number of Facility Radiation and Contamination Surveys

. Jia*nu 2007 Ihro-uglDecem-T3l-12007 ..........

1ylK1 Radiation Surface Contamination* Air Samples** RWP's January 85 85 47 10 February 82 82 48 10 March 71 71 48 14 April 88 88 51 8 May 84 84 63 9 June 85 85 51 4 July 50 50 32 12 August 42 42 55 7 September 49 49 19 9 October 71 71 49 7 November 49 49 51 3 December 57 57 48 7 TOTALS 813 813 562 100

• 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 Tim Bussey transferred from Reactor Operations to Health Physics as a Health Physics Technician in Feb. 2007.

Shaun Kelly transferred from Health Physics to the Quality Assurance Group in Feb. 2007 upon completion of his degree in Biochemistry.

Jason Mitchell was hired as a Health Physics Technician in May 2007.

During calendar year 2007, MURR shipped 818 cubic feet of low-level radioactive waste containing 7360 mCi of activity.

VIII-5

SECTION IX

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF,

.............................. E-XPERIM EN-TERS-AND -V-ISI-TORS .......................

January 1, 2007 through December 31, 2007 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP Month AC DO FSO HC/SH RAG IRR NA NS OPS PRO RP SIL Total January 23 47 207 420 244 32 10 21 1593 93 62 172 2924 February 19 12 113 314 191 7 16 92 1247 154 62 106 2333 March 19 26 198 237 159 11 14 56 1298 131 24 119 2292 April 274 26 141 326 111 34 33 77 1535 112 41 167 2877 May 29 6 50 331. 213 9 12 185 1220 111 39 105 2310 June 32 6 36 461 163 34 17 135 1422 98 58 102 2564 July 65 26 70 426 284 35 48 71 1305 101 55 112 2598 August 74 7 184 402 198 104 54 117 1612 126 63 108 3049 September 138 62 183 335 244 4 38 67 1676 68 72 125 3012 October 152 97 246 400 239 29 68 138 1859 144 154 139 3665 November 37 13 104 324 208 17 27 79 1397 154 54 116 2530 December 51 8 57 451 203 5 26 51 2284 131 29 126 3422 Total to Date 913 336 1589 4427 2457 321 363 1089 18448 1423 713 1497 33576 Monthly Ave 76 28 132 369 205 27 30 91 1537 119 59 125 2798 Highest WB 146 18 52 177 100 77 18 65 210 70 24 103 Highest EXT 730 M 860 860 240 300 560 190 360 818 430 220 AC - Analytical Chemistry RAG - Health Physics OPS - Operations DO - Director's Office IRR - Irradiations PRO - Isotope Production FSO - Shops NA - Nuclear Analysis RP - Radiophariceutical HC/SH - Hot Cell/Shipping NS - Neutron Scattering SIL - Silicon WB = Whole Body EXT = Extremities M = Minimal Dosimetry services are provided by R.S. Landauer Jr. & Company (except self-reading dosimetry).

Analysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA. Radiation workers who are not full time staff members have radiation exposures which are generally lower than full time radiation workers.

Note: The Hot Cell and Shipping Groups were combined in 2007.