Text

University of Missouri Research Reactor 2005 Reactor Operations Annual Report
	ML060600437
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/27/2006
From:	Foyto L; Univ of Missouri
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML060600437 (40)
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U Research Park Research Reactor Center Columbia, MO 65211 University of Missouri-Columbia PHONE (573) 88242 11 FAX (573) 882-6360 February 27, 2006 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop 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 2005 Reactor Operations Amnual 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, 2005 through December 31, 20C'5.

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) 882-5276.

Sincerely, Les Foyto Reactor Manager Enclosure cc: Mr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC

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AN EQUAL opPoRruNrrY/ADA INSTrruTON

UNIVERSITY OF MISSOURI RE SEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2005 through December 31, 2005; Compiled by the Research Reactor Staff Submitted February 2006 by:

Leslie P. Foyto Reactor AMlanager Reviewed and Approved by:

Ralph A. Butler, PE Director

UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2005 through December 31, 2005 INTRODUCTION The University of Missouri Research Reactor (MUJRR) 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 world.

The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2005. 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 .Lh(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 Police; the City of Columbia Police Department; the Missouri University Police Department; our Regulators; those who have provided funding including the Department of Energy (DOE) and the Department of Homeland Security; 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.

In addition to the items discussed in this Report, a considerable amount of time and resources were directed this year towards the beryllium reflector replacement, and renewal and relicensing projects. Replacement of the beryllium reflector is performed every eight years, with the next replacement scheduled for January 2006. Including low power physics testing, approximately seven to eight days is required to disassemble the necessary piping and equipment, remove the old beryllium and insert the new, and then reassembly of all piping and equipment. Planning for this evolution takes approximately one year, including training, procedure writing, and the procurement of all spare parts and tools, and involves nearly every group within the facility. Additionally, in conjunction with the beryllium replacement, three beamtubes will be retracted in order to replace four graphite reflector elements.

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The facility's operating license, R-103, is due to expire on October 11, 2006. Efforts to revise and update the Safety Analysis Report for relicensing submittal are ongoing, with a considerable amount of energy focused on the necessary computer codes to support the nucleonics and accident analyses chapters.

Renewal projects are also ongoing, with the completion of two major projects this year: cooling tower electrical and radioactive liquid waste disposal system upgrades.

Reactor Operations Management also wishes to commend the three individuals who received their 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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TABLE OF CONTENTS Section Title Pages

1. Reactor Operations Summary ........................................ I-1 through 10 II. MURR Procedures ......................................... II-lthrough 9 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 2 IV. Plant and System Modifications .......................................... IV- 1 through 3 V. New Tests and Experiments ............ ............................ V-1 VI. Special Nuclear Material and Reactor Physics Activities ..................... VI-l VII. Radioactive Effluent ........................................ VII- 1 through 2 Table 1 - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII. Environmental Monitoring and Health Physics Surveys ...................... VIII- I through 5 Table 1 - Summary of Environmental Set 67 Table 2 - Summary of Environmental Set 68 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 1,2005 through December 31, 2005 The following table and discussion summarize reactor operations during the period from January 1, 2005 through December 31, 2005.

Full Power % of Full Power % of IMont Full Power Hours Megawatt Days Total Time Scheduled*

January 670.48 279.46 90.12 100.90 February 604.64 252.04 89.98 100.77 March 662.67 276.20 89.07 99.72 April 547.65 228.34 76.06 85.30 May 673.75 280.87 90.56 101.39 June 670.17 279.33 93.08 104.39 July 681.09 283.90 91.54 102.50 August 669.82 279.19 90.03 100.80 September 639.11 266.67 88.76 99.55 October 626.76 261.32 84.24 94.32 November 631.52 263.28 87.71 98.37 December 683.72 285.07 91.90 102.89 Total for 7761.38 3235.67 88.60 % 99.21 %

the _Y ear _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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

January 2005 The reactor operated continuously in January with the following exceptions: five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled shutdowns this month.

Major maintenance items for the month included: replacing the shaft keeper key on cooling tower fan CTF-3 motor coupling; completing Compliance Procedure No. 31, "Calibration of the Eberline Radiation Stack Monitor;"

adjusting the operating linkage on pool coolant system heat exchanger bypass valve S-2; replacing the filter cartridges in pool coolant demineralizer system inlet filter housing F-200; cleaning the suction strainer for secondary coolant system pump SP-3; replacing the flange gaskets, studs, and nuts, and valve diaphragms for primary coolant demineralizer system inlet filter housing F-201; and replacing the high pressure isolation valve for primary coolant system heat exchanger differential pressure transmitter DE'S-928B.

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February 2005 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On February 8, a "Rod Not In Contact With Magnet" rod run-in was automatically initiated when control blade 'D' anvil separated from its electromagnet during a routine outward shimming evolution. The reactor was shutdown, the pull rod to housing alignment was checked and verified satisfactory, and the anvil and magnet were cleaned. The control rod was withdrawn 26-inches to the full out position as part of the retest. The reactor was refueled and subsequently returned to 10 MW operation.

Major maintenance items for the month included: completing Modification Record 80-5, Addendum 1, "Removal of the Bulk Pool Lead Shield Facility;" replacing the pneumatic tube system photo sensor collar on row 2 irradiation position as part of Modification Record 05-1, "Pneumatic Tube System Photo Sensor Collar Upgrade;" completing Modification Record 04-5, Addendum 1, "Phase 1 of the Cooling Tower Electrical Upgrade Project - Installation of a New Lighting Panel LP-41;" completing Modification Record 04-5, Addendum 2, "Phase 2 of the Cooling Tower Electrical Upgrade Project - Install Independent 13.8 kV Feeder Lines to the Cooling Tower and Laboratory Building Transformers;" completing Modification Record 04-5, Addendum 3, "Phase 3 of the Cooling Tower Electrical Upgrade Project - Replacement of the 500 kVA Cooling Tower Transformer with a 1,500 kVA Transformer;"

loading new pool coolant system de-ionization bed 'P;' reinstalling refurbished secondary coolant system flow distribution valve S-17; and completing Modification Record 05-1, "Pneumatic Tube System Photo Sensor Collar Upgrade."

March 2005 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On March 10, a reactor scram was manually initiated by the control room operator when it was discovered that the containment building personnel airlock inner door-sealing gasket did not remain inflated after a door closing cycle.

This resulted in a loss of containment integrity and a deviation from Technical Specification (TS) 3.5.a.; one of two Limiting Conditions for Operation regarding containment integrity. TS 3.5.a requires that containment integrity be maintained at all times except when the reactor is secured, and irradiated fuel with a decay time less than sixty days is not being handled. One of the six conditions for reactor containment integrity to exist is "The personnel airlock door operable." This implies that one of the two personnel airlock doors must be fully closed with its gasket inflated, thus providing a satisfactory seal. Upon investigation, it was determined that the inner airlock door three-way, dual solenoid-pilot valve had not remained in the "latched" position following the door closing cycle. Once the closing solenoid de-energized, the three-way valve returned to the "unlatched" position, thereby venting air pressure from the sealing gasket resulting in a loss of containment integrity. The three-way valve bonnet and dual solenoid-pilot control assembly were replaced. The door was then cycled five times to verify proper adjustment and operability.

The reactor was subsequently refueled and returned to 10 MW operation. Licensee Event Report No. 05-01, 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: reinstalling refurbished secondary coolant system flow distribution valve S-18; performing a backflush on the secondary coolant side of pool coolant system heat exchanger HX521; 1-2

replacing the drive motor for the containment building personnel airlock outer door; reinstalling refurbished secondary coolant system flow distribution valve S-19; and completing Compliance Procedure No. 29, "Calibration of the NMC RAK Radiation Stack Monitor."

April 2005 The reactor operated continuously in April with the following exceptions: three shutdowns for scheduled maintenance and/or refueling, and three unscheduled shutdowns. NRC regional inspector arrived at MURR for routine inspection.

On April 5 during a normal reactor startup, a "Nuclear Instrumentation Channel No. 4 High Power" rod run-in was automatically initiated while proceeding from 5 to 10 /.Ws. The set point for the rod run-in is 114%, while the highest power attained was 110% - as indicated by Channel No. 4 chart recorder and the remote meter on the control console. All other Nuclear Instrumentation (NI) channel indications were normal. Troubleshooting revealed a mismatch between the remote indicators (chart recorder and console meter) and the linear bar graph display on the NI drawer. Calibration of the linear bar graph was verified in specification. The isolator module, which amplifies and isolates the drawer output signal for use by the remote indicators, was replaced and calibration between the linear bar graph and the remote indicators was verified satisfactory. Trip settings were then verified after replacement and then confirmed again during "Front Panel Checks" prior to startup. The reactor was subsequently restarted to 10 MW operation. NOTE: Trip settings are set based on drawer calibrated indication, not remote indication. No deviation from Technical Specification Limiting Conditions of Operation for high power rod run-in or reactor scram occurred.

On April 8, a "Nuclear Instrumentation Channel No. 4 High Power" rod run-in was automatically initiated while adjusting Signal Processor drawer No. 1 gain potentiometer to increase console remote meter indication to greater than 100%. This is a routine adjustment at power that is necessary to maintain Nuclear Instrumentation (NI) indications within the administrative operating range of 100 to 105%, after first verifying power by manual heat balance. At the start of the adjustment, remote meter indication was reading approximately 98.5% with a gain potentiometer setting of 369. A Senior Reactor Operator had increased the setting to 427, which caused console meter indication to increase to approximately 99.5% when the rod run-in occurred. Console meter indication was observed by two operators. Chart recorder indication was approximately 114%, the value of the rod run-in set point.

Drawer indication was not known, as this indication is not typically viewed during adjustment. However, comparison of local and remote indications is verified prior to startup. All other NI channel indications were normal, thus indicating that no actual reactivity transient occurred. Troubleshooting efforts did not reveal any discrepancies. The NI drawer was removed and a spare drawer was installed and calibrated. The reactor was subsequently refueled and returned to 10 MW operation. The removed NI drawer will undergo further bench top troubleshooting. NOTE: A potentiometer adjustment of 100 correlates to a percent power indication change of approximately 3%. In this case, an increase in the setting of 58 would be expected to increase meter indication approximately 1 to -/2 °/0, as it did.

On April 22, a reactor scram was manually initiated by the control room operator when facility fire main pressure decreased and remained below the minimum pressure required for emergency pool fill availability. Upon investigation, the University water supply line immediately outside the facility grounds had ruptured, causing a low-pressure condition. Campus Energy Management isolated and repaired the leak. The reactor was subsequently refueled and returned to 10 MW operation.

Major maintenance items for the month included: placing an epoxy patch on the secondary coolant side of primary heat exchanger HX503A; completing Modification Record 95-3, Addendum 1, "Redesign and Replacement of the 1-3

GH Reflector Wedge;" replacing a section of emergency pool fill piping which enters the containment structure through the utility seal trench; performing a backflush on the secondary coolant side of pool coolant system heat exchanger HX521; completing the biannual cleaning of the cooling tower sump and basin; and completing the biennial changeout of control blade 'A' offset mechanism.

May 2005 The reactor operated continuously in May with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and two unscheduled shutdowns.

On May 9 during a normal reactor startup, a "Rod Not in Contact with Magnet" rod run-in was automatically initiated when control blade 'A' separated from its electromagnet while performing a shimming evolution. Initial troubleshooting efforts revealed no abnormalities. Compliance Procedure No. 10 was performed, which verified satisfactory alignment for the control blade's full travel (26-inches), and the reactor was eventually restarted to 10 MW operation. During the following scheduled maintenance day it was discovered that the allen head screw, which attaches the magnet to the drive tube, was installed backwards. The drive tube is a hollow aluminum tube that is tapped on one side and has a non-threaded hole on the other side. The screw was attached to the drive tube first through the threaded side, which allowed more "slop" between the magnet and drive tube. Additionally, the magnet cabling was pulled too tight through its securing clamp, thus not allowing sufficient freedom for the magnet to hang.

Both of these conditions caused the magnet to tilt approximately 20 degrees off vertical centerline. With the magnet not hanging freely and vertically, it had a tendency to push the anvil to one side as it engaged, thus causing the anvil to drag against the housing and the magnet to pull off. The remaining control blade magnets were also checked to ensure that they hung freely and vertically.

On May 18, the control Rod Position Indication (RPI) system remote Operator Display Assembly (ODA) display screen on the control console failed (went blank). The master local display chassis on the Instrument Panel remained operational; therefore RPI was still available to the operators. After conferring with the Reactor Manager, the Lead Senior Reactor Operator shutdown the reactor to troubleshoot the ODA. The Chief Electronic Technician determined that the ODA display control card had failed. The spare display control card was installed which returned the ODA to operation. The reactor was subsequently refueled and returned to 10 MW operation.

Major maintenance items for the month included: replacing Nuclear Instrumentation Signal Processor No. 2 drawer; replacing the batteries for the Uninterruptible Power Supply; completing Compliance Procedure No. 26, "Containment Building Compliance Test;" and completing Modification Record 95-1, Addendum ID, "Replace Existing Gamma-Metrics High Voltage Plasma Bargraphs with Liquid Crystal Displays."

June 2005 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled shutdowns this month.

On June 6 during a normally scheduled reactor shutdown, it was discovered that the head pin, which secures the hold-down rod assembly, had been improperly installed on the three-tube flux trap sample holder during the previous reactor shutdown on May 30. Failure to have the head pin properly installed resulted in a deviation from Technical Specification (TS) 3.6.e; one of fifteen (15) Limiting Conditions for Operation regarding experiments. TS 3.6.e 14

states, "Only movable experiments in the center test hole shall be removed or installed with the reactor operating. All other experiments in the center test hole shall be removed or installed only with the reactor shut dovm. Secured experiments shall be rigidly held in place during reactor operation." Additionally, TS definition 1.24 for a secured experiment states "A secured experiment is any experiment which is rigidly held in place by mechanical. means with sufficient restraint to withstand any anticipated forces to which the experiment might be subjected." Failure to have the head pin properly installed resulted in a component of a secured experiment, which was installed in the center test hole, not being rigidly held in place during reactor operation.

It should be noted that the flux trap sample holder itself was at all times rigidly held in place while inserted into the reactor. As described in the safety analysis section of the Licensee Event Report, the reactivity worth of the sample holder is approximately 75% of the total reactivity worth of the experiment. The reactivity worth of all of the samples and spacers in the holder was only 0.00114 AK - slightly greater than the TS limit for a movable experiment.

The reactivity that could have been introduced by movement of these samples and spacers in all three tubes was only 0.00037 AK, less than the limit for a movable experiment. Furthermore, any potential movement of samples or spacers was confined within the sample holder. Therefore, no reactor safety hazard existed with the flux. trap sample holder pin improperly installed during reactor operation. Licensee Event Report No. 05-02, 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: replacing the roots blower on the NMC RAK radiation stack monitor; performing a zero and span, and calibration on the pool coolant system flow transmitter FT-912D; performing a backflush on the secondary coolant side of pool coolant system heat exchanger HX521; replacing the rod run-in system trip actuator amplifier; replacing the secondary coolant system pH probe; completing Compliance Procedure No. 31, "Calibration of the Eberline Radiation Stack Monitor;" and replacing a fuse on the display control card for the Rod Position Indication system remote Operator Display Assembly.

July 2005 The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown (power reduction).

On July 8, a "Nuclear Instrumentation Channel No. 5 High Power" rod run-in was automatically initiated when a movable sample was being removed from the graphite reflector region during a routine sample handling evolution.

While pulling the sample holder out, its handling cable became entangled with an adjacent sample's cables, causing both sample holders to be withdrawn from the reflector region at the same time. The reactivity insertion caused by the removal of both samples automatically initiated the rod run-in. The rod run-in was reset, and the reactor was returned to 10 MW operation. The operators involved were counseled on the importance of ensuring only one sample is pulled from the reflector region at a time. Note: The combined reactivity effect due to the removal of both sample holders simultaneously did not exceed the Technical Specification limit of 0.001 AK for a movable experiment.

Major maintenance items for the month included: replacing the power supply for the Rod Position Indication system remote Operator Display Assembly; loading new pool coolant system de-ionization bed 'B;' replacing the air compressor for the facility instrument air system; replacing Nuclear Instrumentation Intermediate Range Channel No.

2 remote meter face; completing Modification Record 04-5, Addendum 4, "Phase 4 of the Cooling Tower Electrical Upgrade Project - Replacement of Substation 'A' and the Motor Control Centers;" completing Modification Record 04-5, Addendum 6, "Phase 6 of the Cooling Tower Electrical Upgrade Project - Replacement of the 15 kVA I-5

Transformer with a 45 kVA Transformer;" and replacing the bypass piping for the secondary coolant system auto make-up water valve.

August 2005 The reactor operated continuously in August with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On August 22 during a normal reactor startup, a "Nuclear Instrumentation Channel No. 3 Short Period" rod run-in was automatically initiated when an "Anti-Siphon Tank HI-LO Pressure" annunciator alarm occurred. The control rods had been withdrawn to a height of approximately two inches from the fully inserted position when the rod run-in occurred. Anti-Siphon System pressure had lowered to the alarm set point as a result of system cool-down prior to startup. The rod run-in was most likely caused by electrical "noise" from the annunciator alarm because the pressure switch is located immediately adjacent to the nuclear instrumentation detector. A reactor startup was subsequently performed to 10 MW operation.

Major maintenance items for the month included: replacing the logic relay in the building exhaust ventilation system fan failure circuit; transferring the old beryllium reflector and tantalum wedge from the reactor pool to a storage cask; completing Modification Record 05-3, "Electrical Distribution Modifications Associated with the New Chill Water Loop;" and installing a rebuilt cooling fan in the Instrument Panel.

September 2005 The reactor operated continuously in September with the following exceptions: three shutdowns for scheduled maintenance and/or refueling, and five unscheduled shutdowns.

Four (4) reactor loop low flow scrams occurred within a three-day period while operating at 10 MW. The following indications were common to each occurrence:

1. No indications of an actual reduction in primary coolant flow was recorded on the chart recorder;

2. No reactor loop low flow alarm was received; and

3. All lights on the "Yellow Leg" and only lights I and 2 remained lit on the "Green Leg" of the reactor scram monitoring system ("White Rat"), thus indicating that the most likely cause was the "B" loop of the primary coolant system - flow transmitter FT-912E Instrumentation String.

First Shutdown at 15:32, September 3: Suspected air bubbles in the sensing lines of flow transmitter FT-912E as the most probable cause. Transmitter high and low-pressure sides were vented and Compliance Procedure No. 4B was performed to verify scram set point and transmitter calibration - both were within specification. Permission to restart the reactor was obtained from the Reactor Manager.

Second Shutdown at 21:59, September 3: Because the above stated indications would imply that there was no actual drop in current, or signal, within the instrument loop (i.e., no corresponding low flow alarm), troubleshooting efforts were directed at components that could intermittently fail and provide only a reactor scram and annunciation: dual alarm unit EP-920C/D, scram relay K-38, and any interconnect wiring. After systematically eliminating K-38 and any interconnect wiring as the probable cause, focus was placed on the dual alarm unit. The dual alarm unit was replaced with one from spare parts. Compliance Procedure No. 4B and 7A were performed to verify scram set point 1-6

settings were satisfactory. Additionally, a multi-meter was connected to the chart recorder test points to continuously monitor the instrumentation current loop. The multi-meter was selected to the MIN function, which would record the lowest current reading during a transient. Permission to restart the reactor was obtained from the Reactor Manager.

Third Shutdown at 08:15, September 4: The multi-meter did not record any decrease in current that would have caused a reactor scram - lowest current reading correlated to a flow rate of 1880 gpm; well above the scram set point of 1725 gpm. Interconnected wiring was rechecked. Replaced primary coolant "B" loop flow scram relay K-38 and once again replaced dual alarm unit EP-920C/D with one from spare parts. Compliance Procedure Nc. 4B and 7A were performed to verify scram set point settings were satisfactory. In addition to the multi-meter thai was already connected to the chart recorder, a second multi-meter was connected to the dual alarm unit to monitor its +24V output. The multi-meter was selected to the MIN function, which would record the lowest voltage reading during a transient. By the use of the two multi-meters and the installed "White Rat," all instrumentation output signals within the FT-912E Instrumentation String were monitored. Permission to restart the reactor was obtained from the Reactor Manager.

Fourth Shutdown at 03:12, September 5: This shutdown occurred while performing Compliance Procedure No. 10, "Control Rod Drop Times," during the normally scheduled Monday morning shutdown. All indications provided by the multi-meters were normal, suggesting that no actual trip signal was generated by either the flow transmitter or the dual alarm unit. Troubleshooting efforts were again focused at the interconnect wiring between the output of the dual alarm unit and relay K-38. A more rigorous investigation of the interconnect wiring and connection points was performed including the disassembly and inspection of the "Green Leg" connector and K relay drawer. This inspection once again yielded no definitive cause. After exhausting all known options and testing, the dual alarm units for the "Green" and "Yellow Legs," EP-920C/D and EP-920A/B respectively, were swapped. If another shutdown would have occurred, this would have provided us additional troubleshooting information depending on whether the scram was generated in the "Yellow" or "Green Leg." Compliance Procedure No. 4A/B and 7A/B were performed to verify scram set point settings were satisfactory. Permission to startup the reactor was obtained from the Reactor Manager following completion of the normal maintenance day activities.

No further reactor loop low flow scrams have been received. Although no definitive cause could be found, nor could a duplication of the event be created during troubleshooting activities, the most probable cause was a loose connector that was not apparent when disconnected.

On September 13, a "Reactor Loop Low Flow" scram was automatically initiated when primary coolant system pump P-501B breaker opened while operating. The motor phase currents and resistance to ground were measured with all readings indicating nothing unusual. Both motor and pump were checked for free rotation. Additionally, vibration analysis of the motor/pump did not indicate any abnormalities. No definitive cause could be identified. An electronic data logger was connected to all three phases of the motor to record run current in the event of a similar occurrence. The primary coolant system was operated for approximately 30 minutes with no abnormal indications.

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

Major maintenance items for the month included: replacing the reactor safety system dual alarm unit EP-920C/D; replacing the primary coolant 'B' loop low flow scram relay K-38; replacing the pool coolant 'B' loop low flow scram relay K-37; replacing the sensing line piping on the high-pressure side of pool coolant system flow transmitter FT-912F; and replacing the primary coolant system temperature element TE-980B meter relay unit.

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October 2005 The reactor operated continuously in October with the following exceptions: six shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown. NRC regional inspector arrived at MURR for routine inspection. Three reactor startups were performed for NRC operator licensing examinations.

On October 6, a "Reflector HI-LOW Differential Pressure" scram was automatically initiated when a 3-inch sample holder was removed from the reactor pool reflector region during a normal sample handling evolution. Removal of the sample holder, combined with a lower than normal pool coolant flow, created a low differential pressure condition across the reflector region. Pool coolant flow had gradually decreased over the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to the shutdown for no apparent reason. During troubleshooting efforts, the pool coolant and pool coolant demineralizer system filters were removed and inspected. Fibrous material, similar to that of nylon rope, was found on the filters.

The filters were either replaced or cleaned, as applicable, and pool coolant system flows returned to normal. The most probable scenario is that a section of nylon rope, which is used to hang off items in the pool, had come loose and entered the pool coolant loop through natural convection valve 547. This valve is located near the pool bottom and is maintained open during operation. Once in the loop, the combination of gamma radiation and the pool coolants pumps had deteriorated the rope to point where it had disintegrated and collected on the filters. The reactor was refueled and subsequently returned to 10 MW operation.

Major maintenance items for the month included: completing Compliance Procedure No. 29, "Calibration of the NMC RAK Radiation Stack Monitor;" replacing the filter cartridges in pool coolant demineralizer system inlet filter housing F-200; completing the biannual cleaning of the cooling tower sump and basin; performing a backflush on the secondary coolant side of pool coolant system heat exchanger HX52 1; completing the biennial changeout of control blade 'C' offset mechanism; replacing the leadscrew assembly for control rod 'C' drive mechanism; replacing the electromagnet cabling for control rod 'C' drive mechanism; and replacing the fuses in the south roof top air handler control circuit.

November 2005 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and four unscheduled shutdowns.

On November 2, a "Rod Not In Contact With Magnet" rod run-in was automatically initiated when control blade 'C' anvil separated from its electromagnet during a routine outward shimming evolution. The reactor was shutdown and the pull rod to housing alignment was checked and verified satisfactory. During the October 31 maintenance day activities, the electromagnet cabling for control rod 'C' drive mechanism was replaced due to degradation of the cabling insulation. In comparison to the other drive mechanisms, it appeared that the new cabling was a few inches longer than the others. This may have caused the cabling to "bunch up" as the drive tube retracted into the upper housing. The cabling was shortened approximately 6-inches and the control rod was satisfactorily withdrawn to the full out position as part of the retest. The reactor was refueled and subsequently returned to 10 MW operation.

On November 6, a "Rod Not In Contact With Magnet" rod run-in was automatically initiated when control blades 'C' and 'D' separated from their respective electromagnets. It was immediately noted by the reactor operator that the trip actuator amplifier (TAA) for the "Green Leg" of the reactor safety system had tripped. Troubleshooting efforts revealed no specific cause and the condition could not be re-created. As a precaution, the TAA was replaced with I-8

one from spare parts. Further bench-top testing will be performed on the removed TAA. The reactor was refueled and subsequently returned to 10 MW operation.

On November 25, the reactor was shutdown when all four control rods automatically inserted by rod run-in for no apparent reason. Troubleshooting efforts revealed that the rod run-in trip actuator amplifier (TAA) had failed and could not be reset. Bench-top testing discovered two failed transistors. The TAA was replaced with one from spare parts and tested satisfactorily. The reactor was refueled and subsequently returned to 10 MW operation.

On November 28 during a reactor startup (the reactor was still subcritical), a "Pool Loop Valve 509 Off Open" scram was automatically initiated. Valve 509 position indication on the Instrument Panel indicated that the valve was open and the scram condition immediately cleared. Additionally, had the valve actually come off of its open seat, the pool coolant system pumps would have secured as part of the valve-pump interlock circuitry. The most probable cause was either dirt between the contact surfaces or the contact had not properly seated during system star-up causing a momentary break in connectivity. All contacts on the relay block were burnished and the relay was manually cycled to ensure freedom of movement. All retesting indicated proper operation of the relay and its contacts. The reactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included: shortening the cabling on control rod 'C' drive mechanism electro-magnet; replacing the vibration switch on cooling tower fam CTF-2; replacing the reactor safety system "Green Leg" trip actuator amplifier; loading new pool coolant system de-ionization bed 'F;' replacing the pressure switch for the facility main air compressor; completing Modification Record 05-9, "Redirect Resin Sluice Water to Waste Tanks;"

replacing the rod run-in system trip actuator amplifier; flooding Beamport 'C' with demineralized water; replacing the level control switch for waste tank No. 4; replacing the harmonic filter for secondary coolant system pump SP-1; and completing Modification Record 05-4, "Secondary Coolant System Changes in support of Upgrades to the Facility HVAC System."

December 2005 The reactor operated continuously in December with the following exceptions: eight shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On December 26 during a reactor startup, a "Nuclear Instrumentation Channel 4, 5 & 6 Hi Power" red run-in was automatically initiated when Nuclear Instrumentation (NI) Channel No. 5 exceeded its rod run-in set paint of 114%

immediately after placing the reactor in automatic control at 10 MWs. The rod run-in was reset, with Reactor Manager's approval, and the reactor was subsequently returned to 10 MW operation.

A contributor to the unscheduled shutdown was a previous action that was performed on December 12. In preparation for the upcoming beryllium change-out, Beamport 'A' was filled with demineralized water. Filling a beamport with water secures the neutron beam to its experimental apparatus. This is performed with the reactor shutdown, and in keeping with the principles of ALARA, allows the experiment and its shielding to have a sufficient period of decay before being dismantled. Filling or draining a beamport also affects neutron signal strength to NIs that are adjacent to the beamport; filling decreases signal strength whereas draining increases it. NI Channel No. 6 and the Wide Range Monitor (WRM) are adjacent to Beamport 'A.' A change in signal strength can be compensated by gain adjustment on Channel No. 6; however, the WRM does not have sufficient gain adjustment to increase meter indication to 100% with the beamport filled. The WRM, which has no reactor safety functions, provides an input signal to the Rod Control System for automatic control of reactor power. The reactor may be operated at 10 MW in 1I9

automatic control with WRM meter indication less than 100% by matching power schedule set point to WRM indication. In this instance, the unfamiliarity of placing the reactor in automatic control with WRM indication less than 100% allowed Channel No. 5 to increase to its rod run-in set point. The reactor operators have been informed to approach 10 MWs more conservatively and place the reactor in automatic control at 9 MWs and increase power from that point. Beamport 'A' will be drained after reassembly of its experiment.

Major maintenance items for the month included: cleaning the high and low level probes in the drain collection tank; flooding Beamport 'C' with demineralized water; replacing the test and feedback module for nuclear instrumentation channel No. 6; replacing the pool and primary coolant system differential temperature meters; performing a flux profile measurement of the flux trap region; completing Compliance Procedure No. 31, "Calibration of the Eberline Radiation Stack Monitor;" and replacing the power supply for the primary power calculator.

1-10

SECTION II MURR PROCEDURES January 1, 2005 through December 31, 2005 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 93 new and revised Reactor Operations procedures, forms and operator aids issued. 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:

OP-RO-212 Reactor Startup - Recovery from Temporary Power 3 2/11/2005 Cover Page Reduction EX-RO-120 Beamport "A" Operation 2 8/15/2005 Cover Page EX-RO-121 Beamport "B" Operation 2 8/15/2005 Cover Page EX-RO-123 Beamport "D" Operation 2 8/15/2005 Cover Page EX-RO-124 Beamport "E" Operation 2 8/15/2005 Cover Page EX-RO-125 Beamport "F" Operation 2 8/15/2005 Cover Page EX-RO-126 Thermal Column Door 2 10/20/2005 Cover Page FM-08 Fuel Movement Sheet 6 9/15/2005 Cover Page FM- 18 Deviation From Procedure Report 3 10/20/2005 Cover Page FM-19 Unscheduled Power Reduction Report 2 12/14/2005 Cover Page FM-20 Waste Tank Sample Report 6 6/9/2005 Cover Page FM-2 1 ARMS Trip Setpoints 3 6/30/2005 Cover Page FM-23 MURR Tag Out Index Record 3 8/18/2005 Cover Page FM-24 MIJRR Tag Out Sheet 4 8/18/2005 Cover Page FM-25 MURR Tag Out Monthly Audit 3 8/18/2005 Cover Page FM-55 Startup Nuclear Data Sheet 3 4/18/2005 Cover Page FM-57 Long Form Startup Checksheet 5 2/11/2005 COVET Page FM-57 Long Form Startup Checksheet 6 10/20/2005 Cover Page FM-58 Short Form Startup Checksheet 3 2/11/2005 Cover Page FM-58 Short Form Startup Checksheet 4 10/20/2005 CovCr Page j FM-64 DI Resin Log 3 9/15/2005 Cover Page FM-65 Filter Status Log 3 9/15/2005 Cover Page

____ _____________ _ a _ _____

FM-68 Toarget aterial Control Checksheet 3 41/21/2005 Cover Page 11-1

FM-71 Pneumatic Tube User Approval 1 6/9/2005 Cover Page GS-RA-100 MURR Equipment Tag Out 4 8/18/2005 Cover Page OA-1 Facility Exhaust Fans EF-13 and EF-14, EF-13 3 10/20/2005 Cover Page Running OA-2 Facility Exhaust Fans EF-13 and EF-14, EF-14 3 10/20/2005 Cover Page Running OA-3 Beamport and Pool Overflow Loop Seals 3 10/20/2005 Cover Page OA-4 Valve Operation Air Compressor 3 10/20/2005 Cover Page OA-5 Emergency Air Compressor 3 10/20/2005 Cover Page OP-RO-211 Reactor Startup - Hot 4 8/15/2005 Cover Page OP-RO-212 Reactor Startup - Recovery from Temporary Power 4 9/15/2005 Cover Page Reduction__ _ _ _ _ _ _ _

OP-RO-220 Reactor Shutdown or Power Reduction 4 8/15/2005 Cover Page OP-RO-350 Reactor Power Calculator Flow Potentiometer 3 8/15/2005 Cover Page Adjustment OP-RO420 Primary and Pool Water Analysis 2 8/15/2005 Cover Page OP-RO-460 Pool Coolant System-Two Pump Operation 5 6/9/2005 Cover Page OP-RO-516 Valve Operation Air System 4 8/15/2005 Cover Page OP-RO-520 Emergency Diesel Generator 4 9/15/2005 Cover Page X OP-RO-53 1 Primary and Pool Sample Station 4 6/30/2005 Cover Page OP-RO-532 Drain Collection System 4 6/9/2005 Cover Page OP-RO-533 Skimmer System 3 8/15/2005 Cover Page OP-RO-710 Radiation Monitoring - Area Monitors 3 8/15/2005 Cover Page RM-RO405 Reactor Demineralizer System 6 9/15/2005 Cover Page RP-RO-200 RTP-1ID Measurement of Differential Worth of a 1 8/15/2005 New Procedure

_ _ Shim Blade AP-RO-1 10 Conduct of Operations 4 3/28/2005 Full Review EX-RO-105 Reactor Irradiation Experiments 5 5/3/2005 Full Review EX-RO-105 Reactor Irradiation Experiments 6 8/15/2005 Full Review FB-SH-005 Type B Shipment of Spent Fuel Using the BMI-1 0 6/1/2005 New Procedure I _ 4Shipping Cask FM-66 Customer Sample Pre-Encapsulation Evaluation 0 3/16/2005 Full Review

.__._Worksheet OP-RO-250 In-Pool Fuel Handling 7 8/15/2005 Full Review OP-RO480 Secondary Coolant System 6 8/15/2005 Full Review OP-RO-730 Facility Exhaust System 8 12/14/2005 Full Review REP-RO-100 Reactor Emergency Procedures 4 6/24/2005 Full Review AP-RO-1 10 Conduct of Operations 5 10/20/2005 Minor Editorial EX-RO-105 Reactor Irradiation Experiments 7 10/20/2005 Minor Editorial EX-RO-122 Beamport "C" Operation 2 9/15/2005 Minor Editorial FM-33 Containment Building Restricted Materials 2 10/20/2005 Minor Editorial FM-41 Fuel Shipping Drum Return Inspection Form 2 5/18/2005 Minor Editorial FM-56 Reactor Routine Patrol 8 3/28/2005 Minor Editorial FM-56 Reactor Routine Patrol 9 5/18/2005 Minor Editorial Water Makeup Log 6/9/2005 Minor Editorial 11-2

FM-66 Customer Sample Pre-Encaptsulation Evaluation 1 7/26/2005 Minor Editorial Worksheet FM-93 Post-Maintenance Valve Lineup Checksheet 2 5/18/2005 Minor Editorial GS-RA-100 MURR Equipment Tag Out 5 9/16/2005 Minor Editorial OA-7 Receiving Bulk Chemicals 2 8/15/2005 Minor Editorial OP-RO-100 Main Air System 5 3/28/2005 Minor Editorial OP-RO-101 Instrument Air System 4 3/28/2005 Minor Editorial OP-RO-210 Reactor Startup-Normal 5 3/28/2005 Minor Editorial OP-RO-210 Reactor Startup-Normal 6 5/3/2005 Minor Editorial OP-RO-230 Changing Reactor Power Level 3 6/30/2005 Minor Editorial OP-RO-250 In-Pool Fuel Handling 6 6/9/2005 Minor Editorial OP-RO-310 Nuclear Instrumentation - Signal Processor #1 4 5/18/2005 Minor Editorial OP-RO-311 Nuclear Instrumentation - Signal Processor #2 4 5/18/2005 Minor Editorial OP-RO-312 Nuclear Instrumentation Power Range Monitor - 5 5/18/2005 Minor Editorial Channel 6 OP-RO-330 Nuclear Instrumentation - Wide Range Monitor 4 5/18/2005 Minor Editorial OP-RO-340 Nuclear Instrumentation Adjustment 5 6/9/2005 Minor Editorial OP-RO-340 Nuclear Instrumentation Adjustment 6 8/15/2005 Minor Editorial l OP-RO-461 Pool Coolant System-One Pump Operation 4j 6/9/2005 Minor Editorial j OP-RO-480 Secondary Coolant System 7 10/20/2005 Minor Editorial X OP-RO-515 Emergency Air System 4 9/15/2005 Minor Editorial OP-RO-530 Demineralized Water Supply System J 5 6/9/2005 Minor Editorial OP-RO-555 Fire Protection System 1 12/14/2005 Minor Editorial OP-RO-720 Radiation Monitoring - Stack Monitor Operational 4 6/9/2005 Minor Editorial Check[___ _ _

OP-RO-730 Building Exhaust System Fans 7 3/28/2005 Minor Editorial OP-RO-741 Waste Tank System Operation 6 3/28/2005 Minor Editorial REP-RO- 100 Reactor Emergency Procedures 3 5/24/2005 Minor Editorial REP-RO-100 Reactor Emergency Procedures 5 12/14/2005 Minor Editorial RM-RO-405 Reactor Demineralizer System 5 2/11/2005 Minor Editorial RM-RO-405 Reactor Demineralizer System 7 12/14/2005 Minor Editorial RM-RO-470 Sulfuric Acid System 4 8/15/2005 Minor Editorial RP-RO-100 Fuel Movement 4 5/18/2005 Minor Editorial RP-RO-201 RTP- 17B Measurement of Total Reactivity Worth of 1 8/15/2005 Minor Editorial Flux Trap Loadings FM-152 Spent Fuel Element Inspection 0110/20/2005 New Form 11-3

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 44 revisions issued to the emergency 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:

EP-RO-003 Emergency Preparedness Training 2 7/19/2005 Cover Page EP-RO-004 Fire 1 7/19/2005 Cover Page EP-RO-005 Medical Emergency 1 7/19/2005 Cover Page EP-RO-006 Radiological Emergency 1 7/19/2005 Cover Page EP-RO-007 Severe Natural Phenomenon 1 7/19/2005 Cover Page EP-RO-008 Threat To Security 1 7/19/2005 Cover Page EP-RO-009 Notification of Unusual Event 1 7/19/2005 Cover Page EP-RO-Ol 1 Site Area Emergency 1 7/19/2005 Cover Page EP-RO-012 Reactor Isolation 1 7/19/2005 Cover Page EP-RO-013 Facility Evacuation 1 7/19/2005 Cover Page EP-RO-014 EPZ and Site Area Evacuations 2 7/19/2005 Cover Page EP-RO-016 Public Information 1 7/19/2005 Cover Page EP-RO-017 Emergency Air Sampling 1 7/19/2005 Cover Page EP-RO-018 Emergency Radiation Exposure 2 7/19/2005 Cover Page EP-RO-019 Emergency Dosimeters 1 7/19/2005 Cover Page FM-102 Emergency Event Log 1 7/19/2005 Cover Page FM-103 Facility Status 117/19/2005 Cover Page FM-105 Initial/Follow-Up Emergency Message 1 7/19/2005 Cover Page FM-106 Log of Personnel Released From Site 1 7/19/2005 Cover Page FM-I 10 Fire Flowchart 1 7/19/2005 Cover Page FM-l1l Medical Flowchart 1 7/19/2005 Cover Page l FM-1 12 Radiological Flowchart 1 7/19/2005 Cover Page FM-1 13 Severe Natural Phenomenon Flowchart 1 7/19/2005 Cover Page FM-1 15 Plant Conditions Flowchart I 7/19/2005 Cover Page FM-1 16 mClassificationFlowchart 1 7/19/2005 Cover Page EP-RO-O10 Alert 1 7/19/2005 Cover Page FM-iO Emergency Declaration _1 7/19/2005 Cover Page FM-101 FEO Management 1 7/19/2005 Cover Page OA-10 Fire Extinguisher Locations and Types 1 7/19/2005 Full Review OA-20 Emergency Equipment 1 7/19/2005 Full Review EP-RO-001 Definitions 1 2/17/2005 Minor Editorial EP-RO-001 Definitions 2 7/19/2005 Minor Editorial EP-RO-002 Emergency Responsibilities 2 7/19/2005 Minor Editorial EP-RO-003 Emergency Preparedness Training 1 2/17/2005 Minor Editorial P-RO-014 andSite Area Evacuations a 2/17/2005 MinorE 11-4

EP-O 5 Emergeny N os2gg/17/00 M dito EP-RO-015 Emergency Notifications 1 2/17/2005 Minor Editorial EP-RO-015 Emergency Notifications 2 7/19/2005 Minor.-Editorial EP-RO-020 Emergency Equipment Maintenance 1 7/19/2005 Minor Editorial FM-i04 Emergency Call List 1 2/17/2005 Minor E rial FM-104 Emergency Call List 2 7/19/2005 Minor Editorial FM- 104 Security Flowchart 1 7/19/2005 Minor Editorial FM-1 17 Reactor Isolation Flowchart 1 7/19/2005 Minor Editorial FM-1 18 Evacuation Flowchart 1 7/19/2005 Minor Editorial OA-09 Combined Emergency Flowcharts 1 7/19/2005 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 109 new and revised health physics, radioactive materials shipping, and preparation for shipping procedures and forms issued. The majority of the revisions were strictly format or editorial in nature. The following is a list of the new and revised procedures and forms:

INN . .. . NO... .. 9 R.............

AP-HP-105 Radiation Work Permit 4 10/21/2005 Cover Page AP-HP- I10 Controlled Special Exposures 4 10/21/2005 Cover Page AP-HP-1 17 MURR Initial Radiation Worker Training 6 2/4/2005 Minor Editorial Program AP-HP-123 Visitor Dosimetry - Reception Desk 3 2/4/2005 Cover Page AP-BP-125 Review Of Unplanned Radiation Exposure 1 6/2/2005 Minor Editorial AP-HP-129 Hot Cell Control 3 5/6/2005 Cover Page AP-PSO-001 General Requirements for Preparation of 2 11/9/2005 Cover Page Radioactive Materials for Shipping AP-SH-001 Administrative Procedure, Radioactive Materials 3 4/4/2005 Minor Editorial Shipping BPB-SH-001 2R Shipping Container Leak Check 4 11/30/05 Minor Editorial BPB-SH-002 2OWC-1 Packaging and Shipment of Type B Non- 5 11/30/05 Minor Editorial Waste Radioactive Material BPB-SH-005 DOT 6M Packaging and Shipment of Type B 3 11/30/05 Minor Editorial Non-Waste Radioactive Material BPB-SH-008 Type B(U) F-327 Series Packaging and Shipment 3 10/20/2005 Minor Editorial of Type B Non-Waste Radioactive Material BPB-SH-009 GB/0924BP/B(U) Packaging and Shipment of 1 6/1/2005 Minor Editorial Type B(U) Non-Waste Radioactive Material BP-SH-007 F-327 Packaging and Shipment of Type A Non- 1 6/1/2005 Minor Editorial Waste Radioactive Material BP-SH-010 Packaging and Shipment of Non-Waste 1 11/30/05 Minor Editorial Radioactive Materials in Excepted Packages ___ _ _

11-5

BP-SH-01 1 Shipment of Non-Waste USA DOT 7A Type A 1 10/20/2005 Minor Editorial (Gemstone) Radioactive Material Package_

BP-SH-012 DOT-7A Package Certification 0 2/28/2005 New Procedure BP-SH-013 Packaging and Shipment of Radioactive Materials 0 2/28/2005 New Procedure Using MURR Reusable Type A Package ____

BP-SH-036 Packaging of Non-Waste Radioactive Material 1 6/1/2005 Minor Editorial Using MURR MODEL 1100 BP-SH-037 Packaging of Non-Waste Radioactive Material 1 6/1/2005 Minor Editorial Using MURR MODEL 1220 BP-SH-038 Packaging of Non-Waste Radioactive Material 1 6/1/2005 Minor Editorial Using MURR MODEL 1300 BP-SH-099 Packaging of Radioactive Material Using MURR 0 10/20/2005 New Procedure Model 1500 BP-SH-302 Packaging and Shipment of Radioactive Material 0 8/16/2005 New Procedure Using MURR Models 6 and 12 _ _

FB-SH-005 Type B Shipment of Spent Fuel Using the BMI-I 0 6/1/2005 New Procedure Shipping Cask FM-09 Gemstone Irradiation Sheet 3 5/24/2005 Minor Editorial FM-12 Gemstone Loading Sheet 3 10/26/05 Minor Editorial FM- 151 Control Checksheet for Non-Waste USA DOT 7A 2 10/20/2005 Minor Editorial Type A (Gemstone) Radioactive Material Package _

FM-17 Radiation Work Permit 4 10/21/2005 Minor Editorial FM-27 In-House Radioactive Shipping Request Form 4 4/4/2005 Minor Editorial FM-28 Controlled Special Exposure Authorization 3 10/21/2005 Minor Editorial FM-29 Initial Radiation Worker Training Packet 4 2/4/2005 Minor Editorial FM-35 Control Checksheet for Type B USA DOT 2OWC- 8 4/4/2005 Minor Editorial 1 Radioactive Materials Shipment FM-35 Control Checksheet for Type B USA DOT 2OWC- 9 10/20/2005 Minor Editorial

[ Radioactive Materials Shipment FM-36 Control Checksheet for USA DOT 7A- MURR 6 10/20/2005 Minor Editorial Model 1100 Series FM-37 Control Checksheet for USA DOT 7A -MURR 6 10/20/2005 Minor Editorial Model 1220 Series FM-38 Control Checksheet for USA DOT 7A MURR 6 10/20/2005 Minor Editorial

__________ Model 1300 Series FM-39 Control Checksheet for Excepted Package 6 10/20/2005 Minor Editorial Radioactive Materials Shipment FM-44 Request for Radioisotope Shipment 5 6/1/2005 Minor Editorial FM-62 Radiation Instrument Certificate of Calibration 3 6/28/2005 Cover Page FM-69 Control Checksheet for MURR Reusable Type A 0 2/28/2005 New Form Radioactive Materials Shipment FM-69 FM-74 Control Checksheet for MURR Reusable Type A Radioactive Materials Shipment Control Checksheet for Type B USA DOT 6M I 1 5

6/1/2005 4/4/2005 Minor Editorial Minor Editorial Radioactive Materials Shipment FM-74 Control Checksheet for Type B USA DOT 6M 6 10/20/2005 Cover Page Radioactive Materials Shipment II-6

FM-75 Control Checksheet for Type B(U) F-327 Series 4 4/4/2005 Minor Editorial Radioactive Materials Shipment _

FM-75 Control Checksheet for Type B(U) F-327 Series 5 10/20/2005 Minor Editorial Radioactive Materials Shipment _

FM-76 Personnel Contamination Log 1 6/2/2005 Cover Page FM-77 Control Checksheet for GB/0924BP/B(U) 3 4/4/2005 Minor Editorial Radioactive Materials Shipment FM-77 Control Checksheet for GB/0924BP/B(U) 4 6/1/2005 Cover Page

_ _ Radioactive Materials Shipment FM-89 Control Checksheet for Type A F-327 Series 3 4/4/2005 Minor Editorial Radioactive Material Shipment _____

FM-98 Control Checksheet for MURR Shipment Using 0 8/16/2005 New Procedure USA DOT 7A MURR Model 6 or 12 FM-99 Packaging of Radioactive Material Using MURR 0 10/20/2005 New Procedure

_____________ Model 1500 Checksheet HC-PSO-002 Hot Cell Preparation of Radioactive Material for 4 11/9/2005 Cover Page Shipment HC-PSO-003 Hot Laboratory Preparation of Radioactive 3 11/9/2005 Cover Page Material for Shipment HC-PSO-005 Hot Cell Loading of Host Cans 3 11/9/2005 Minor Editorial IC-HP-300 Calibration - Radiation Survey Instruments 3 3/3/2005 Minor Editorial

- --------.-.= -I1 IC-HP-305 Calibration - Electrostatic Discharge Dosimeter 2 2/10/2005 Minor Editorial IC-HP-3 10 Calibration - Eberline Ping I a Stack Monitor - 3 3/3/2005 Minor Editorial Particulate Channel IC-HP-311 Calibration - Eberline Ping I a Stack Mlonitor - 3 3/3/2005 Minor Editorial Iodine Channel _ . _._

IC-HP-312 Calibration - Eberline Ping 1a Stack Monitor - Gas 3 3/3/2005 Minor Editorial Channel IC-HP-318 NMC Model RAK Stack Monitor 3 2/10/2005 Minor Editorial Offsets/Multipliers/High Voltages Determination IC-HP-333 Eberline BC-4 Beta Swipe Counter-Calibration 3 2/4/2005 Minor Editorial IC-HP-341 Calibration -High Resolution Gamma 2 2/10/2005 Minor Editorial Spectroscopy Systems IC-HP-341 Calibration -High Resolution Gamma 3 12/19/2005 Minor Editorial

_ Spectroscopy Systems IC-HP-343 Calibration - Sodium Iodide Detector 3 6/2/2005 Minor Editorial IC-HP-347 Calibration - Protean Model WPC 9550 Alpha- 4 8/18/2005 Cover Page Beta Swipe Counter IC-HP-348 Calibration - Canberra SSXLB-G 0 5/6/2005 New Procedure IC-HP-348 Calibration - Canberra S5XLB-G & Tennelec 1 8/18/2005 Minor Editorial

____ _ WSeries 4 with Gamma ____ _ _

IRR-PSO-103 Receipt of Radioactive Material for Irradiation 3 11/9/2005 Minor Editorial IRR-PSO-112 Preparing Shipping Paperwork 0 6/29/2005 New Procedure OP-HP-220 Tritium Bioassay 3 8/18/2005 Cover Page OP-HP-221 Environmental Sample - Analysis 3 2 10/2005 Minor Editorial OP-HP-222 Air Sampling - Containment Building Ar-41 2 12/19/2005 Cover Page EnI-7o OP-BP-223 ISpent Fuel ampe /18/2005 Minor Editorial II-7

OP-HP-224 Spent Fuel Shipping Cask Air Sample Analysis 2 6/28/2005 Minor Editorial OP-BP-353 Waste Tank Sample - Analysis 2 2/10/2005 Minor Editorial OP-HP-353 Waste Tank Sample - Analysis 3 9/16/2005 Minor Editorial OP-HP-400 Gemstone Shipping Barrel Analysis 5 12/19/2005 Minor Editorial OP-HP-420 Decontamination of Enclosed Processing Units 1 10/21/2005 Cover Page OP-HP-505 Emergency Stack Monitor Filter Analysis 2 6/28/2005 Cover Page OP-HP-600 Europium Source Creation 2 9/16/2005 Cover Page QA-SH-002 Sodium Iodide Spectral Analysis for Excepted, 1 10/20/2005 Minor Editorial Exempt, License-to-License, Type A, or Type B Radioactive Materials Shipments RM-HP-100 Stack Monitor Preventive Maintenance - NMC 3 6/2/2005 Minor Editorial Model RAK RM-HP-101 Stack Monitor Preventative Maintenance - 2 10/21/2005 Cover Page

.. __._ ._Eberline Ping IA RP-HP-100 Contamination Monitoring - Performing a Swipe 3 2/4/2005 Minor Editorial RP-HP-100 Contamination Monitoring - Performing a Swipe 4 12/19/2005 Minor Editorial RP-HP-105 Transfer of Radioactive Material - In Facility 3 12/19/2005 Cover Page RP-HP- 10 Survey and Decontamination of Returned 3 5/6/2005 Cover Page Shipping Container RP-HP-130 Receipt of New Fuel Elements 3 5/6/2005 Minor Editorial RP-HP-135 Room 114 Entry - Self Monitored 2 5/6/2005 Cover Page RP-HP-137 Handling Radioactive Material in the Reactor Pool 3 9/16/2005 Minor Editorial RP-HP-139 Beamport Radiation Level Monitoring During 2 6/2/2005 Cover Page Reactor Startup __

SI-PSO-008 Post-Irradiation Processing: Exported Flooded 3 6/29/2005 Minor Editorial

_ _ Silicon Cans SV-HP-100 Reactor Chemistry Isotope Counter Trending and 3 2/4/2005 Cover Page I

Investigative Level Determination SV-HP-100 Reactor Chemistry Isotope Counter Trending and 4 12/19/2005 Cover Page Investigative Level Determination SV-HP-105 Sealed Calibration Source - Leak Check 4 2/4/2005 Minor Editorial SV-HP- 105 Sealed Calibration Source - Leak Check 5 6/2/2005 Minor Editorial SV-HP-1 15 Building Exhaust Stack Effluent - Tritium 2 2/10/2005 Minor Editorial

_ _ Monitoring SV-HP-130 Emergency Air Sampling of Exhaust Plume 2 6/2/2005 Cover Page SV-BP-131 Emergency Analysis of Environmental Samples 2 9/16/2005 Cover Page For Callaway Nuclear Plant SV-HP-135 Containment Air - Emergency Remote Sampling 2 12/19/2005 Cover Page TPZ-PSO-001 Receiving Gemstone Irradiation Shipping Drums 2 4/21/2005 Minor Editorial TPZ-PSO-002 Irradiation of Gemstone Irradiation Containers 2 4/21/2005 Minor Editorial TPZ-PSO-003 Loading Gemstone Shipping Drums 2 4/21/2005 Minor Editorial WMB-SH-005 Shipment of Type B Radioactive Waste Using 3 8/16/2005 Minor Editorial

_Chem-Nuclear System -13G Cask_

WM-SH-011 Shipment of Radioactive Material n.o.s., Waste 1 2/28/2005 Cover Page For Hot Cell Host Cans WM-SH-100 Radioactive Waste - Preparation and Storage 3 6/1/2005 Minor Editorial 11-8

g0S~~~~~~~.. G.00 ......... ...gl5

.$>l2lBlg ....

WM-SH-105 Radioactive Waste Processing 2 6/20/2005 Cover Page WM-SH-200 Exclusive Use Shipment of LSA or SCO 3 8/16/05 Obsolete 8/16/05 Radioactive Waste Utilizing a Broker WM-SH-300 MURR Exclusive Use Shipment of LSA or SCO 2 8/16/2005 Minor Editorial Radioactive Waste 11-9

SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT January 1, 2005 through December 31, 2005 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.

ADDENDUM 3 - HAZARDS

SUMMARY

REPORT (AUGUST 1972)

HSR, Addendum 3, page 20, Figure 2.2, Secondary Cooling System (as revised by the 1989-90, 1990-91, 1994, 1995, 2001, 2002, 2003, and 2004 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.2, Secondary Cooling System (MURR Dwg No. 502, Sheet 1 of 1, dated 10/24/05)

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

Replace with: Updated Figure 2.3.a, Electrical Distribution (MURR Dwg No. 522, Sheet I of 3, dated 8/4/05)

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

Replace with: Updated Figure 2.3.b. Electrical Distribution (MURR Dwg No. 522, Sheet 2 of 3, dated 8/8/05)

HSR, Addendum 3, page 23c, Figure 2.3.c, Electrical Distribution (new print added by the 2004 Reactor Operations Annual Report):

Replace with: Updated Figure 2.3.c, Electrical Distribution (MURR Dwg No. 522, Sheet 3 of 3, dated 8/8/05)

ADDENDUM 4 - HAZARDS

SUMMARY

REPORT (OCTOBER 1973)

HSR, Addendum 4, page A-30, Figure A.3, 10 MWX Process Instrumentation Control & Interlock (as revised by 1995, 1998, 2001, and 2004 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 7/13/05)

HSR, Addendum 4, page A-32, Figure A.5, 10 MWl Process Instrumentation Control & Interlock (as revised by 1995 and 2001 Reactor Operations Annual Reports):

Replace with: Updated Figure A.5, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41. Sheet 1 of 4, dated 4/16/02)

I][I-1

HSR, Addendum 4, page A-33, Figure A.6, 10 MW Process Instrumentation Control & Interlock (as revised by the 1995, 2001, 2002, and 2003 Reactor Operations Annual Reports):

Replace with: Updated Figure A.6, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 2 of 4, dated 12/20/05)

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

Replace with: Updated Figure A.7, Annunciator Control 10 MW (MURR Dwg No. 138, Sheet 1 of 2, dated 3/25/04)

HSR, Addendum 4, page A-38, Figure A.11, Schematic Diagram of Laboratory and Containment Buildings Ventilation System (as revised by the 1995 and 2002 Reactor Operations Annual Reports):

Replace with: Updated Figure A. 11, Schematic Diagram of Laboratory and Containment Buildings Ventilation System (MURR Dwg No. 1125, Sheet 1 of 3, dated 12/15/04)

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, and 2004 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.1, Electrical Distribution (MURR Dwg No. 522, Sheet 1 of 3, dated 8/4/05)

III-2

SECT]ION IV PLANT AND SYSTEM MODIFICATIONS January 1,2005 through December 31, 2005 For each facility modification described below, MIJRR has on file the safety evaluation as well as the documentation of review in accordance with 10 CFR 50.59.

Modification 80-5, Addendum 1:

Removal of the Bulk Pool Lead Shield Facility This addendum to modification record 80-5, "Bulk I'ool Lead Shield," documents the removal of the bulk pool lead shield (BPLS) facility from service to support installation of the new GH position graphite reflector element. The BPLS facility was an aluminum box, which contained a series of lead slabs and an irradiation position, attached to the reflector tank and supported vertically by two long legs. Inadiation services using the BPLS were relocated to the graphite reflector region.

Modification 95-1, Addendum iD:

Replace Existing Gamma-Metrics High Voltage Plasma Bargranhs with Liquid Crystal Displays This addendum to modification record 95-1, "Replacement of Nuclear Instruments," documents the conversion from linear plasma bargraphs to liquid crystal display (LCD) units on all Gamma-Metrics nuclear instruments. The plasma bargraphs were overly sensitive to high humidity conditions and suffered gradual degradation during normal operation. Garnma-Metrics recognized the problems and deficiencies associated with the plasma bargraphs and initiated an upgrade which involved LCD unit replacements.

Modification 95-3, Addendum 1:

Redesign and Replacement of the GH Reflector Wedo; This addendum to modification record 95-3, "P-Tube Relocation from North Side to South Side of Pool (to Wedge 3)," documents the redesign and replacement of the GH position reflector wedge. The old wedge configuration accommodated the following five irradiation positions and sample diameters: two 3-inch, two 2-inch, and one 1-inch. Due to a change in programming needs, the new reflector wedge was designed to accommodate the following four irradiation positions and diameters: one 5-inch, and three 1-inch.

Modification 04-5, Addendum 1:

Phase I of the Cooling Tower Electrical Upgrade Proiect - Installation of a New Lighting Panel LP-41 This addendum to modification record 04-5, "CoolirLg Tower Electrical Upgrade Project," implements the first phase of the cooling tower electrical upgrade project and documents the transfer of electrical loads from existing lighting panels LP-41 and LP-41A to a newly installed single panel that is also designated LP-41. The new panel has a larger load carrying capacity which now supports the electrical loads from both the old panels while also providing for any future expansion.

Modification 04-5, Addendum 2:

Phase 2 of the Cooling Tower Electrical Upgrade Project - Install Independent 13.8 kV Feeder Lines to the Cooling Tower and Laboratory Building Transformers This addendum to modification record 04-5, "Cooling Tower Electrical Upgrade Project," implements the second phase of the cooling tower electrical upgradle project and documents the installation of Iwo new BT-1

independent 13.8 kV feeder lines to the cooling tower and laboratory building transformers. Independent feeder lines were required in order to support the future upgrade of the cooling tower transformer from 500 to 1,500 kVA.

Modification 04-5, Addendum 3:

Phase 3 of the Cooling Tower Electrical Upgrade Proiect - Replacement of the 500 kVA Cooling Tower Transformer with a 1,500 kVA Transformer This addendum to modification record 04-5, "Cooling Tower Electrical Upgrade Project," implements the third phase of the cooling tower electrical upgrade project and documents the replacement and upgrade of the existing 500 kVA cooling tower transformer with a new 1,500 kVA transformer. The new transformer was installed on a concrete pad external to the cooling tower building, thus reducing the heating load within the building.

Modification 04-5, Addendum 4:

Phase 4 of the Cooling Tower Electrical Upgrade Project - Replacement of Substation "A" and the Motor Control Centers This addendum to modification record 04-5, "Cooling Tower Electrical Upgrade Project," implements the fourth phase of the cooling tower electrical upgrade project and documents the replacement and upgrade of substation "A" and motor control centers 1, 2A and 2B with a new supply switch and motor control center which supports all of the electrical loads from the old motor control centers.

Modification 04-5, Addendum 6:

Phase 6 of the Cooling Tower Electrical Upgrade Project - Replacement of the 15 kVA Transformer with a 45 kVA Transformer This addendum to modification record 04-5, "Cooling Tower Electrical Upgrade Project," implements the sixth and final phase of the cooling tower electrical upgrade project and documents the replacement of the existing 15 kVA transformer with a new 45 kVA transformer. The new transformer supports the existing electrical loads from lighting panel LP-41 while also providing for any future expansion.

Modification 05-1:

Pneumatic Tube System Photo Sensor Collar Upgrade This modification record documents the upgrade and standardization of the pneumatic tube system photo sensor collars. Previously, two different collar designs were utilized. One collar had an open optical path such that removal of the photo sensor collar required that containment integrity, in accordance with Technical Specification 3.5.a, be met. The other collar had a transparent acrylic insert that served as both the optical path and pressure boundary. The new collars are designed similar to the one which had the acrylic insert, thus allowing greater flexibility in maintenance, troubleshooting and repairs.

Modification 05-3:

Electrical Distribution System Modifications Associated with the New Chill Water Loop This modification record documents the installation of electrical equipment in support of upgrades to the chill water system. Previously, the electrical distribution system provided electrical power to the following components of the chill water system: the 241-ton LiBr absorption unit, the 100-ton vapor compression unit, and the north and south chill water pumps. Due to the removal of the LiBr absorption unit, and the installation of a research park chill water loop, modifications were made which included disconnecting electrical power to the LiBr absorption unit and providing power to a new variable speed, 30 HP chill water booster pump and emergency chiller unit.

IV-2

Modification 054:

Secondary Coolant System Changes in Support of Upgrades to the Facility HVAC System This modification record documents changes to the secondary coolant system that are in support of upgrades to the facility heating, ventilation and air conditioning system. Specifically, the removal of portions of the secondary coolant system piping that is no longer needed to supply cooling water to the 241-ton LiBr absorption unit. The LiBr absorption unit was removed as part of modification record 05-3.

Modification 05-9:

Redirect Resin Sluice Water to Waste Tanks This modification record documents the changes required to ensure that resin transfer evolutions can be performed with minimal delays, without the risk of spreading contamination, and adhering to the principles of ALARA. The reactor demineralizer system is equipped with the means to transfer resin beds to and from various tanks as needed to facilitate replacement of resin beds. Certain of these transfer evolutions require draining waste water at high flow rates (up to 50 gpm) into a floor drain. Du. to the implementation of Modification Record 04-3, "Radioactive Liquid Waste," this floor drain no longer has the capacity to accept these high flow rates. A new alternate path, which allows the waste water to go directly into waste tank No. 2, has been installed.

IV-3

SECTION V NEW TESTS AND EXPERIMENTS January 1, 2005 through December 31, 2005 New tests or experiments developed during this period are as follows:

RUR 219, as amended: Germanium

Description:

This amended RUR authorizes the irradiation of up to 150 grams of high purity germanium for use in research and development activities.

RUR 409, as amended: Enriched Xenon

Description:

This amended RUR authorizes the irradiation of enriched xenon seeds for use in therapeutic applications.

RUR 413: Dysprosium Nitrate

Description:

This RUR authorizes the irradiation of up to 5 milligrams of enriched dysprosium nitrate for use in research and development activities.

RUR 414: Enriched Barium Carbonate

Description:

This RUR authorizes the irradiation of up to 75 grams of enriched barium carbonate for use in medical applications.

Project Authorization RL-65: Prompt-Gamma Activation Analysis of BoroBond Samples

Description:

This Project Authorization authorizes the use of a Pu-Be neutron source to characterize the boron content of shield materials used in commercial applications.

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. In the case of RL-65, the Isotope Use Subcommittee also reviewed the project.

V- 1

SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2005 through December 31, 2005 Inspections:

There were two 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 (66) refueling evolutions were completed in 2005. Excess reactivity verifications were performed for each refueling. The largest measured excess reactivity value was 3.62%. MURR Technical Specification 3.1(f) requires excess reactivity to be less than 9.8%.

Reactivity Measurements:

Two (2) reactivity measurements were made to determine the reactivity worth of all samples loaded in the flux trap region experimental sample holder.

Nine (9) measurements were made to determine the reactivity worth of several different types olf sample materials irradiated in either the flux trap or graphite reflector regions.

One (1) measurement was made to characterize the reactivity worth of two new graphite reflector elements installed in the GH and No. 9 positions.

Four (4) differential blade-worth measurements and one (1) primary coolant temperature coefficient measurement were also performed.

VI-I

SECT1[ON VII RADIOACTIVE EFFLUENT January 1, 2005 through December 31, 2005 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2005 through December 31, 2005 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide Activity (Ci)

H-3 9.287E-02 S-35 6.646E-03 Lu-177 2.480E-03 Ca-45 1.365E-03 Co-60 1.360E-03 Zn-65 5.848E-04 Ag-110m 3.715E-04 As-77 3.574E-04 Lu-177m 3.146E-04 Tl-201* 1.669E-04 Cr-51 1.405E-04 W-181 9.180E-05 Mn-54 7.363E-05 Re-188 4.026E-05 P-32 3.718E-05 Sc-46 1.848E-05 Total H-3 9.287E-02 Total Other 1.405E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."

T1-201 effluents comply with Missouri Department of Health, Division 10; Chapter 20 regulations.

VII-i

TABLE 2 STACK EFFLUENT January 1, 2005 through December 31, 2005 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration jLCi/ml Total Release Ci TS Limit Multiplier % TS Ar-41 2.68E-06 1.24E+03 350 76.6876 C-14 2.33E-11 1.06E-02 1 0.7770 I-131 1.84E-13 8.54E-05 1 0.0921 Co-60 4.26E-14 1.98E-05 1 0.0853 H-3 2.56E-08 1.l9E+01 350 0.0732 1-125 6.44E-14 2.98E-05 1 0.0215 Os-191 2.25E-14 1.05E-05 I 0.0011 Cs-137 1.35E-15 6.28E-07 1 0.0007 Zn-65 2.06E-15 9.54E-07 1 0.0005 Se-75 3.98E-15 1.85E-06 1 0.0005 Au-196 1.60E-15 7.43E-07 350 0.0005 Hf- 181 2.45E-15 1.14E-06 1 0.0004 Ce-141 2.53E-15 1.17E-06 1 0.0003 1-133 1.06E-12 4.92E-04 350 0.0003 Hg-203 2.41E-15 1.12E-06 1 0.0002 Br-82 3.20E-12 1.48E-03 350 0.0002 Ce-139 1.26E-15 5.85E-07 1 0.0001 Ru-103 4.69E-16 2.17E-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 cfin 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, 2005 through December 31, 2005 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 2005. All doses are approximately 20 mRem/year or less, except monitor numbers 9 and 15. These monitors aret 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 confinrs 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.

TA13LE 1 Summary of Environmental Set 67 May 2005 Detection Limits*

Matrix Alpha Beta Gamma Tritium Water 0.15 pCi/L 1.74 pCi/L 177.58 pCi/L 5.61 pCi/mL of sample Soil 0.70 pCi/g 1.64 pCi/g 0.86 pCi/g N/A Vegetation 0.30 pCi/g 3.07 pCi/g 1.80 pCi/g 5.65 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/rnIL) 1V67 < 0.30 16.97 < 1.80 < 5.65 2V67 < 0.30 10.98 < 1.80 <5.65 3V67 < 0.30 14.97 < 1.80 < 5.65 4V67 < 0.30 13.73 < 1.80 < 5.65 5V67 < 0.30 28.20 < 1.80 < 5.65 6V67 0.60 16.22 <1.80 < 5.65 7V67 0.60 20.46 <1.80 < 5.65 10V67 < 0.30 26.70 <1.80 < 5.65 V[II-l

TABLE 1 (Cont'd)

Summary of Environmental Set 67 May 2005 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/R) Gamma (pCi/a) 1S67 0.90 15.97 4.54 2S67 <0.70 15.35 4.71 3S67 1.05 18.47 4.27 4S67 <0.70 7.49 2.01 5S67 1.35 17.22 5.25 6S67 < 0.70 11.23 2.48 7S67 < 0.70 11.98 4.31 10S67 0.90 19.72 5.03 Activity Levels - Water Sample Alpha (pCi/U Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W67 < 0.15 4.49 < 177.58 <5.61 6W67 0.15 4.49 < 177.58 < 5.61 10W67 <0.15 20.46 < 177.58 <5.61 TABLE 2 Summary of Environmental Set 68 October 2005 Detection Limits**

Matrix Alpha Beta Gamma Tritium Water 0.15 pCi/L 2.37 pCi/L 178 pCi/L 5.29 pCi/mL of sample Soil 0.15 pCi/g 2.51 pCi/g 0.77 pCi/g N/A Vegetation 0.30 pCi/g 4.58 pCi/g 1.76 pCi/g 5.42 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 68 October 2005 Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/p') H-3 (pCi/ml, 1V68 <0.30 8.14 < 1.76 < 5.42 2V68 < 0.30 8.65 < 1.76 < 5.42 3V68 < 0.30 10.18 <1.76 <5.42 4V68 < 0.30 8.14 < 1.76 < 5.42 5V68 < 0.30 6.11 < 1.76 < 5.42 6V68 < 0.30 5.09 < 1.76 < 5.42 7V68 < 0.30 5.60 < 1.76 < 5.42 10V68 < 0.30 6.11 < 1.76 < 5.42 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1S68 0.80 14.25 3.13 2S68 0.53 15.27 4.15 3S68 0.53 19.85 3.84 4S68 0.27 12.47 2.26 5S68 1.07 15.52 5.30 6S68 0.27 9.42 4.85 7S68 1.34 14.89 3.70 10S68 0.27 21.12 5.70 Activity Lgvels - Water Sample Alpha (pCi/L) Beta (pCi/L! Gamma (pCi/L) H-3 (pCi/<5 4W68 0.27 6.87 < 178 < 5.29 6W68 0.27 8.65 < 178 < 5.29 10W68 0.27 22.40 <178 < 5.29 VIII-3

TABLE 3 Environmental TLD Summary January 1, 2005 through December 31, 2005 Badge Direction Map Distance from 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total Number From MURR MURR Stack 2005 2005 2005 2005 2005 (meters) Net mR Net mR Net mR Net mR Net mR I Unassigned N/A N/A N/A N/A N/A N/A 2 Unassigned N/A N/A N/A N/A N/A N/A 3 WSW N/A 2.4 -1.3 -7.1 -5.9 0.0 4* Unassigned N/A N/A N/A N/A N/A N/A 5** Unassigned N/A N/A N/A N/A N/A N/A 6 N 34 2.1 0.8 -4.1 -3.1 0.0 7 NE 57 4.1 2.6 -0.3 -2.8 3.6 8 SW 27 1.1 3.5 5.4 7.2 17.2 9 S 27 23.0 19.6 26.9 25.9 95.4 10 NE 149 0.1 -2.3 -4.7 -7.6 0.0 11 NW 149 -0.8 -2.7 -2.8 -4.5 0.0 12 ENE 301 5.1 3.9 2.7 -1.6 10.1 13 NNE 316 2.3 -0.5 -2.3 -4.3 0.0 14 S 156 1.4 3.1 -1.7 -1.4 1.4 15 S 65 18.5 19.9 19.9 13.2 71.5 16 SE 107 absent absent -6.4 -7.4 0.0 17 E 293 -3.4 -5.2 -6.0 -8.7 0.0 18 NE 476 -1.8 -5.3 -6.0 -7.3 0.0 19 NNE 606 -5.8 -7.1 -9.5 -9.8 0.0 20 NE 907 -5.8 -8.5 absent -11.2 0.0 21 SE 236 -1.2 -1.1 -1.9 -4.3 0.0 22 ESE 168 absent -3.9 -5.9 -8.0 0.0 23 NW 110 1.7 0.7 -0.4 -4.2 0.0 24 SSW 328 -2.7 -5.5 -7.3 absent 0.0 25 SSW 480 -0.5 -2.8 -1.7 -5.6 0.0 26 SW 301 0.1 -0.2 -3.1 -6.7 0.0 27 WSW 141 -3.7 -5.7 -8.9 -11.2 0.0 28 WNW 210 0.2 1.4 absent absent 1.6 29 NW 255 0.6 0.2 -0.6 -1.2 0.0 30 NNW 328 -2.2 -5.2 -5.1 -10.5 0.0 31 NNW 671 1.7 0.3 -0.7 -4.7 0.0 32 NNW 724 -0.8 -0.9 -2.3 -6.3 0.0 33 E 671 -2.4 -9.4 -7.3 -10.9 0.0 34 ENE 587 -5.3 -7.4 absent -12.4 0.0 35 SSE 499 -2.6 -5.1 -7.7 -7.7 0.0 36 SE 419 0.4 -1.4 -2.6 -7.8 0.0 37 NE 690 -0.5 -3.1 -9.8 -7.5 0.0 38 NW 556 0.7 -2.0 -2.6 -7.2 0.0 39 W 491 -3.0 absent -7.9 -9.0 0.0 40 N 514 -3.3 -0.8 absent absent 0.0 41 NNE 137 -3.3 -5.8 -5.5 -8.4 0.0 42 In Building N/A 3.9 3.1 0.4 -3.0 4.4 43 In Building N/A 5.9 6.1 6.2 0.3 18.5 44 Spare N/A 4.1 3.8 -0.8 -0.6 6.5 45 S 65 -16.9 1.1 -1.6 -3.1 0.0

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 January 1, 2005 through December 31, 2005 Radiation Surface Contamination* Air Samples** RWP's January 50 50 49 8 February 61 61 50 6 March 45 45 57 6 April 77 77 53 15 May 58 58 57 9 June 57 57 59 3 July 35 35 51 8 August 49 49 54 10 September 43 43 58 8 October 57 57 52 13 November 83 83 53 10 December 48 48 57 7 TOTALS 663 663 650 103

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

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

Miscellaneous Notes Manual Diaz was hired as a Health Physics Technician in February 2005.

Dan Nickolaus was promoted to Health Physics Technician in June 2005.

Shaun Kelley was promoted to Health Physics Technician II in June 2005.

During calendar 2005, MURR shipped 737.55 cubic feet of low-level radioactive waste.

VIII- 5

SECTION IX

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS January 1, 2005 through December 31, 2005 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP Month AC DO FSO HC RAG IRR NA NS OPS PRO RP SH SIL rCI Total January 38 2 355 262 157 51 15 32 1607 47 96 76 44 0 2782 February 34 12 146 153 130 72 10 27 1366 49 110 109 78 18 2314 March 10 11 133 169 165 45 8 33 1374 106 63 76 45 7 2245 April 13 1 447 158 208 51 10 40 1455 88 24 119 51 0 2665 May 11 8 294 235 173 72 15 20 1282 67 58 148 52 2 2437 June 6 74 40 221 179 58 6 21 1282 72 61 115 128 0 2263 July 77 4 95 290 175 82 12 12 1442 75 95 127 81 0 2567 August 14 16 112 290 279 86 14 31 1748 47 38 138 93 0 2906 September 30 19 112 346 257 100 4 39 1465 38 85 189 102 3 2789 October 14 19 251 245 299 119 16 7 2070 37 47 150 73 0 3347 November 8 7 120 224 129 173 12 17 1413 31 66 200 65 4 2469 December 14 34 60 188 220 33 16 20 1683 50 43 255 207 1 2824 Total to Date 269 207 2165 2781 2371 942 138 299 18187 707 786 1702 1019 35 31608 Monthly Ave 22 17 180 232 198 79 12 25 1516 59 66 142 85 3 2634 Highest WB 49 28 128 201 115 146 7 40 275 37 21 101 124 18 Highest EXT 200 100 2210 660 150 270 260 100 1490 970 490 220 450 60 AC - Analytical Chemistry RAG - Health Physics OPS - Operations SIL - Silicon DO - Director's Office IRR - Irradiations PRO - Isotope Production TCI - Special Project FSO - Shops NA - Nuclear Analysis RP - Radiophariceutical HC - Hot Cell NS - Neutron Scattering SH - Shipping WB = Whole Body EXT = Extremities NOTE: 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.

IX-1

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