ML050610486

University of Missouri Research Reactor 2004 Reactor Operations Annual Report

ML050610486
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/28/2005
From:	Rhonda Butler, Foyto L Univ of Missouri - Columbia
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML050610486 (39)

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Research Reactor Center Research Park Columbia, MO 65211 University of Missouri-Columbia PHONE (573) 882421 1 FAX (573) 882-6360 February 28, 2005 Document Control Desk U.S. Nuclear Regulatory Commission 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 2004 Reactor Operations Annual Report I have enclosed one copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2004 through December 31, 2004.

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.

ENDORSEMENT:

Sincerely, Reviewed and Approved i &< 'A.

es Foyto Ralph A. Butler, .E.

Reactor Manager Director Enclosure cc: Mr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC

-A10 AOD' AN EQUAL oFpowm-rr/ADA INsTrr.nON

-w-UNIVERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2004 - December 31, 2004 RESEARCH REACTOR FACILITY

UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2004 through December 31, 2004 Compiled by the Research Reactor Staff Submitted February 2005 by:

P" Leslie P. Foyto Reactor Manager Reviewed and Approved by:

/G, 4 Ralph A. Butler, PE Director

UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2004 through December 31, 2004 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 world.

The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2004. 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).

ACKNOWVLEDGMENTS 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.

Senior Management wishes to thank all of its staff members for their continuing efforts in accomplishing MURR's mission of providing quality nuclear services and products. The ongoing success of the Corrective Action Program, Safety Conscious Work Environment, Renewal and Relicensing activities, Administrative 50.59 Evaluations, and Work Control is due to their hard work, dedication, and positive attitude toward these programs. They are the reason why MURR represents a major research and education resource for the University, the State of Missouri, and the nation. It is a facility which enhances the international reputation of the University, and provides the catalyst for MU to be the leader in the education of future generations of scientists, engineers and technicians engaged in nuclear science applications.

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Reactor Operations Management also wishes to commend the six individuals who received their Reactor Operator or Senior 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 I. Reactor Operations Summary . ......................................I-I through 7 II. MURR Procedures ....................................... II-I through 8 A. Changes to Reactor Operations Procedures B. Changes to the MURR Site Emergency Procedures and Facility Emergency Procedures C. Changes to Health Physics Procedures, Byproduct Material Shipping Procedures, and Preparation of Byproduct Material for Shipping Procedures III. Revisions to the Hazards Summary Report ........................................ III-I through 4 IV. Plant and System Modifications ...................................... IV-I through 3 V. New Tests and Experiments ........................................V-I VI. Special Nuclear Material and Reactor Physics Activities ..................... VI-I VII. Radioactive Effluent ....................................... VII-I through 2 Table I - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII. Environmental Monitoring and Health Physics Surveys ...................... VIII-I through 5 Table I - Summary of Environmental Set 65 Table 2 - Summary of Environmental Set 66 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 SUMNIARY January 1,2004 through December 31, 2004 The following table and discussion summarize reactor operations during the period from January 1, 2004 through December 31, 2004.

Date l FullPowerHours l MegawattDays Full Power % of Full Power % of DaeoerHur ul MgwatDasTotal Time Scheduled*

Jan 2004 687.81 286.70 92.45 103.54 Feb 2004 615.65 256.62 91.61 102.61 Mar 2004 660.93 275.52 88.83 99.49 Apr2004 646.22 269.33 89.75 100.53 May 2004 662.55 276.22 89.05 99.74 Jun 2004 641.69 267.53' 89.12 99.83 Jul2004 681.52 284.05 91.60 102.59 Aug 2004 669.83 279.36 90.03 100.83 Sep 2004 644.10 268.46 89.46 100.20 Oct 2004 662.82 276.30 89.09 99.78 Nov 2004 648.06 270.14 90.01 100.82 Dec 2004 682.70 284.56 91.76 102.77 Total for 7903.88 3294.79 90.23 % 101.06 %

theYear __ _ _ _ __ _ _ _

• MUTRR 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 2004 The reactor operated continuously in January with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On January 16, a reactor scram was manually initiated when the control room operators observed no discernable increase in pressurizer liquid level with the primary coolant charging pump P533 operating. The charging pump had automatically started in response to a pressurizer low liquid level signal generated by level controller 936. The low liquid level condition was a result of normal operating system losses. Investigation revealed that coolant charging pump suction valve 515C had been left in the shut position after a routine preventative maintenance task had been completed; thereby isolating the charging pump from its suction source of makeup water. This resulted in a deviation from Technical Specification 3.10.b, which states, "The reactor shall not be operated unless the reactor makeup water system is operable and connected to a source of at least 2,000 gallons of primary grade water." With valve 515C in the shut position, the reactor makeup water system was in a degraded state and not considered operable. Pressurizer liquid level and pressure were within their normal operating ranges at the time of shutdown. A valve line-up checksheet was performed of the pressurizer system to ensure that no other valves were out-of-position and a Standing Order was issued prior to reactor startup that requires valve line-up checksheets to be performed on all 1-1

• 1 systems as part of equipment post maintenance testing. The reactor was subsequently refueled and returned to 10 MW operation. Licensee Event Report No. 04-01, 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 01-3, Addendum 2, "Relocation of TE-980A and TE-980B Temperature Transmitters."

February 2004 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On February 5, a reactor scram was manually initiated when Nuclear Instrumentation (NI) Drawer No. I local plasma bar graph meter indications failed - remote analog meter indications on the reactor control console remained operable.

After the shutdown, the drawer's automatic scram and rod run-in functions were tested and found to meet operability requirements; thus verifying that the loss of local meter indications did not affect the safety functions of the drawer.

The spare NI drawer, which had been previously upgraded with LCD meter units, was installed and the drawer's functions were tested and found to meet operability requirements. The reactor was subsequently refueled and returned to 10 MW operation. The front panel level and period display units for the removed NI drawer will be upgraded in the future from plasma bar graphs to LCD meter units. This is an on-going modification to upgrade all of the Gamma-Metrics NI drawer local meters.

Major maintenance items for the month included: removing the X and MH-X fuel storage baskets and installing a new X fuel storage basket; performing a 1/M criticality measurement of the new X fuel storage basket to verify a Kefr of less than the Technical Specification limit of 0.9; removing the Y and MH-Y fuel storage baskets and installing a new Y fuel storage basket; replacing the NMC Model RAK stack monitor iodine channel chart motor, and loading new pool coolant system de-ionization bed 'B.'

March 2004 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and two unscheduled shutdowns.

On March 9, a reactor scram was manually initiated when the control room operators observed a faster than normal lowering of pressurizer liquid level after startup. Upon investigation, it was discovered that the water loss was through the sealing surfaces of the reactor pressure vessel top flange and vessel cover and into the reactor pool. The reactor pressure vessel cover is unbolted and removed during core refuelings. A fexitallic gasket provides the pressure seal between the vessel cover and vessel top flange. It was determined that the flexitallic gasket was damaged and the vessel cover appeared to have been unevenly tightened after refueling. The gasket was replaced and the reactor was subsequently refueled and returned to 10 MW operation.

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On March 29, a reactor scram was automatically initiated when Rod Control power fuse 2F4 opened during a demonstration of the Automatic Shim Control circuit. The circuit was activated for training purposes just prior to the normally scheduled weekly shutdowri. The 10-amp fuse blew just as the regulating blade had inserted to the 20%

withdrawn position and the Automatic Shim Control circuit engaged. During the maintenance day activities, the rod control system was inspected and tested with no apparent cause discovered. The fuse was replaced and the reactor was returned to 10 MW operation after conclusion of the maintenance day.

Major maintenance items for the month included: performing a 1/M criticality measurement of the new Y fuel storage basket to verify a Kff of less than the Technical Specification limit of 0.9; completing Modification Record 91-3, Addendum 1, "Replacement of the Existing X, Y, MH-X, and MH-Y Fuel Storage Baskets with New X and Y Baskets;" replacing the inner and outer containment airlock door signal cabling; replacing room 114 exhaust ventilation HEPA filters; and replacing a pillow-block bearing on the building ventilation supply fan SF-1.

April 2004 The reactor operated continuously in April with the following exceptions: three shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On April 12, a reactor scram was automatically initiated when Rod Control supply power fuse 2F4 opened during a demonstration of the Automatic Shim Control circuit. The circuit was activated for training purposes just prior to the normally scheduled weekly shutdown. The 10-amp fuse blew just as the regulating blade had inserted to the 20%

withdrawn position and the Automatic Shim Control circuit engaged. During the maintenance day activities, the rod control system was inspected and tested with no apparent cause discovered. The fuse was replaced and the reactor

• vas returned to 10 MW operation after conclusion of the maintenance day. After careful review of the system prints, it was determined that both rod insertion and rod withdrawal power can be applied to the control rod drive motor simultaneously, thereby creating a potential overcurrent condition. In this instance and again on March 29, a control rod was being withdrawn when the circuit activated and fuse 2F4 opened. The operators have been instructed to secure all shimming evolutions prior to initiating the Automatic Shim Control circuit for training.

Major maintenance items for the month included: repairing the Domestic Cold WVater cooling water line to the primary coolant system pumps; replacing a windgate in the pneumatic tube system; removing secondary coolant system distribution valve S-22 for refurbishment; replacing the local readout module in the secondary coolant system radiation monitor; completing Modification Record 04-1, "Replace the General Electric Measurement and Control Type 551 Reactor Pressure Transmitter PT-943 with a Rosemount Model 1151;" reinstalling refurbished secondary coolant system distribution valve S-21; replacing NMC Model RAK stack monitor blower motor thermal overloads; and completing the biennial changeout of Control Blade "B" Offset Mechanism.

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May 2004 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and two unscheduled shutdowns.

On May 3, the reactor was manually shutdown to adjust Nuclear Instrumentation Channel 4 indication. The indication was reading low and the gain potentiometer for Signal Processor Drawer No. I was at its maximum setting. The resistance value of switch SWI, which is the course gain adjustment, was adjusted to bring the gain potentiometer to the middle of its operating range. The reactor was subsequently returned to 10 MW operation.

On May 17, a rod run-in was automatically initiated when a six-inch sample holder was removed from the graphite reflector region. The sample holder was being removed in order to activate the Automatic Shim Control circuit for training purposes just prior to the normally scheduled weekly shutdown. The sample holder was removed with the regulating blade at a height just above the Automatic Shim Control circuit set point of 20 % withdrawn (5.2 inches).

The introduction of positive reactivity prompted by the removal of the sample holder caused the regulating blade to insert to the 10% withdrawn position and initiate the rod run-in. The reactor was returned to 10 MW operation after conclusion of the maintenance day.

Major maintenance items for the month included: replacing the heaters for the thermal overloads in the NMC Model RAK stack monitor motor; reinstalling refurbished secondary coolant system flow distribution valve S-22; repairing a Domestic Cold Water leak downstream of the secondary coolant system makeup water flow meter, completing Modification Record 01-5, Addendum 1, "Replace Secondary Coolant Flow Transmitters FT-912P and FT-912Q;"

replacing the building ventilation supply fan SF-I shaft and bearings; and completing Compliance Procedure No. 26, "Containment Building Compliance Test."

June 2004 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and refueling, and two unscheduled shutdowns.

On June 3, the reactor was manually shutdown due to a sample scheduling error, which resulted in the incorrect.

sample being removed on the previous maintenance day. After the shutdown, the correct sample was pulled. The reactor was subsequently refueled and returned to 10 MW operation.

On June 16, the reactor was manually scrammed when it was discovered that the inner airlock door positioning chain had come off its sprocket due to a loose setscrew. Containment integrity was never lost since the outer airlock door remained closed and the seal inflated. The reactor was secured, and the inner airlock door set screw was replaced with a locking style set screw. The reactor was subsequently refueled and returned to 10 MW operation. The outer airlock door set screw was replaced with a locking style set screw during the next maintenance day.

Major maintenance items for the month included: reinstalling refurbished secondary coolant system flow distribution valve S-19; replacing the Domestic Cold Water cooling water line to the primary coolant system pumps; removing the X fuel storage basket for inspection; placing an epoxy-based patch on the secondary coolant side of primary coolant system heat exchanger 503A; and loading new pool coolant system de-ionization bed 'F.'

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July 2004 The reactor operated continuously in July With the following exceptions: four-shutdowns for scheduled maintenance and'or refueling. There were no unscheduled shutdowns this month.

Major maintenance items for the month included: completing Compliance Procedure No. 31, "Calibration of the Eberline Radiation Stack Monitor;" replacing the in-line secondary coolant system pH probe; relocating the Automatic Shim Control circuit as per Modification Record 04-4; completing Modification Record 95-1, Addendum IF, "Gamma-Metrics Nuclear Instrumentation Gain Potentiometer R27 Replacement;" and removing the X fuel storage basket frame for inspection.

August 2004 The reactor operated continuously in August with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown. NRC regional inspector arrived at MURR for annual Reactor Operations' inspection. Three reactor startups were performed for NRC operator licensing examinations.

On August 28, a reactor scram was automatically initiated when pool reflector differential pressure decreased below Pressure Transmitter 917 (PT-917) scram set point. PT-917 monitors differential pressure across the reactor pool reflector region, thus serving as a back-up to the pool low flow scram. The low differential pressure condition was created when multiple material irradiation sample holders were removed from the graphite reflector region concurrently during a sample handling evolution. The reactor was subsequently refueled and returned to 10 MW operation. On August 30, during the next scheduled maintenance day, a calibration check of PT-917 was performed in accordance with Compliance Procedure No. 5. Data collected indicated that transmitter calibration was just out-of-specification low in the normal operating band - high and low calibration points were in specification (Note: These are calibration data points and not Technical Specification Limiting Conditions of Operation). After verifying that the scram set point was in specification, the transmitter was spanned and all data points were in calibration. This transmitter does not have a history'of any drifting problemhs but it will be closely monitored.

Major maintenance items for the month included: re-installing the X fuel storage basket frame, Beryllium ring storage plate and X fuel storage basket; replacing the sightglass on the secondary coolant system acid addition day tank; spanning the Reflector Differential Pressure Transmitter PT-917 during calibration; and physically adjusting nuclear instrumentation channel No. 6 drywvell.

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September 2004 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On September 25, a reactor scram was automatically initiated when meter indications on Nuclear Instrumentation (NI) Signal Processor Drawer No. I pegged high, thus causing a reactor safety system trip. Troubleshooting efforts revealed a breakdown in the insulation of the signal cabling near the fission chamber detector located in the reactor pool. This type of failure is typical of NI detector cabling that has been in operation over two years. The fission detector and its associated cabling were replaced and the drawer was verified to be operable. The reactor was subsequently refueled and returned to 10 MW operation.

Major maintenance items for the month included: replacing Nuclear Instrumentation Signal Processor Drawer No. 1 power range isolator, performing a backflush on the secondary coolant side of the pool coolant system heat exchanger 521; completing Modification Record 04-4, "Relocation of Automatic Shim Control Circuit for Reactor Console Modification;" completing Modification Record 88-11, Addendum 1, "Upgrade of Uninterruptible Power Supply (UPS) Alternate Source;" replacing the cabling and fission chamber detector for Nuclear Instrumentation Signal Processor Drawer No. I; and completing Compliance Procedure No. 29, "Calibration of the NMC Model RAK Stack Monitor."

October 2004 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and refueling, and one unscheduled shutdown. Received notification from the NRC that three new Reactor Operator and three new Senior Reactor Operator licenses had been issued.

On October 8, the reactor was manually shutdown when a loss of Domestic Cold Water (DCW) supply occurred at the facility. As part of the Cooling Tower Electrical Upgrade Project, trench work was being performed in order to install a new underground primary duct bank. While a backhoe was attempting to remove a large piece of concrete from the trench, the concrete inadvertently hit an exposed section of PVC piping, causing a break in the DCW supply line. The reactor was shutdown and DCW supply to the facility was isolated. Repairs were performed and the supply line was flushed and placed back in service. The reactor was subsequently refueled and returned to 10 MW operation.

Major maintenance items for the month included: replacing Room 299 400-amp branch feeder breaker, performing a backflush on the secondary coolant side of pool coolant system heat exchanger 521; replacing the wiring for secondary coolant system pump SP-3 from the supply breaker to its motor; and completing the biennial changeout of Control Blade "D" Offset Mechanism.

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November 2004 The reactor operated continuously in November 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 fast speed contactors for building exhaust ventilation fans EF-13 and EF-14; completing Modification Record 03-3, "Installation of a Facility Fire Detection/Suppression System;" replacing a radiator hose on the 275-kW emergency diesel generator; performing a backflush on the secondary coolant side of pool coolant system heat exchanger 521; rebuilding primary coolant system demineralizer outlet valve 527F air actuator; replacing the fission chamber detector for Nuclear Instrumentation Signal Processor Drawer No. 1; and loading new pool coolant system de-ionization bed 'W.'

December 2004 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On December 20, a Nuclear Instrumentation (NI) Channel 6 High Power Rod Run-In occurred during a reactor startup. The operator had attempted to place the reactor in automatic control at 10 MWV with Channel 6 indication too close to the high power rod run-in set point of 114%. The Wide Range channel, the NI channel that provides the output signal for automatic reactor control, was indicating approximately 15% lower than Channel 6 indication. The reactor was shutdown and checks of Channel 6 were performed to verify proper operability. Actual power, as recorded by the remaining NIs and displayed by the real-time power calculator, was less than 10 MW at time of the rod run-in. The reactor was subsequently returned to 10 MW operation. The operators involved were coached on the importance of being conservative on the approach to 10 MW and placing the reactor in automatic control during this sensitive transient period.

Major maintenance items for the month included: replacing the primary coolant system demineralizer inlet filters; replacing the pool coolant system skimmer filters; replacing the local "jog/stop" switch for secondary coolant system pump SP-I; realigning the emergency air compressor motor and pulley assembly; replacing the NMC model RAK stack monitor blower starter contactor; completing Modification Record 75-16, Addendum 2, "Relocation of the Reactor Safety System Monitoring Circuit Panel;" and replacing cooling tower fan CF-3 control circuit fuse.

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SECTION 11 MURR PROCEDURES January 1, 2004 through December 31, 2004 As required by administrative Technical Specification 6.1.h (4), this section of the annual report includes a summary of procedure changes. These procedure changes were reviewed by the Reactor Manager or Reactor Health Physics Manager and others to assure compliance with the requirements of 10 CFR 50.59. These procedure changes were also reviewed by the Reactor Procedure Review Subcommittee of the Reactor Advisory Committee to meet the requirements of Technical Specification 6.l.c (1).

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

There were 55 new and revised Reactor Operations procedures, forms and operator aids issued. The majority of the revisions were strictly format or editorial in nature. The following is a list of the new and revised procedures, forms and operator aids:

1,NuffberS~t -eFineU~te e~g>X'~S2mtqR v on'Dste Rf4-ev. ReVisi'h Dae__ oem t

AP-RO-110 Conduct of Operations 3 6/2/04 AP-RO-130 Crane Operation 0 3/15/04 EX-RO- 105 Reactor Irradiation Experiments 4 11/19/04 OP-RO-100 Main Air System 3 6/2/04 OP-RO-100 Main Air System 4 11/1/04 _ _

OP-RO-101 Instrument Air System 3 4/26/04 OP-RO-210 Reactor Startup - Normal 4 6/2/04 _

OP-RO-211 Reactor Startup - Hot 3 8/5/04 OP-RO-220 Reactor Shutdown or Power Reduction 3 8/5/04 OP-RO-230 Changing Reactor Power Level 2 8/5/04 OP-RO-250 In-Pool Fuel Handling 5 3/15/04 OP-RO-3 10 Nuclear Instrumentation - Signal Processor #1 3 6/2/04 OP-RO-311 Nuclear Instrumentation - Signal Processor #2 3 6/2/04 OP-RO-312 Nuclear Instrumentation Power Range Monitor - 4 6/2/04 Channel 6 _ _

OP-RO-330 Nuclear Instrumentation - Wide Range Monitor 3 6/2/04 OP-RO-340 Nuclear Instrumentation Adjustment - 3 6/2/04 OP-RO-350 Reactor Power Calculator Flow Potentiometer 2 8/5/04 Adjustment OP-RO-410 Primary Coolant System 4 4/26/04 OP-RO-460 Pool Coolant System - Two Pump Operation 4 6/28/04 OP-RO-461 Pool Coolant System - One Pump Operation 3 6/28/04 OP-RO465 Pool Level Control - Skimmer System 3 4/26/04 OP-RO-466 Pool Level Control - Pool Coolant System 3 4126/04 1 Il-I

2EarnNw:e9Qm A> Rev. Revision ate 12 I otes, OP-RO-480 Secondary Coolant System 5 11/19104 OP-RO-510 Nitrogen System 3 2/17/04 OP-RO-510 Nitrogen System 4 9/24/04 OP-RO-515 Emergency Air System 3 11/1/04 OP-RO-516 Valve Operation Air System 3 7/12/04 OP-RO-530 Deiner-alizedWater Supply System 3 7/12/04 OP-RO-530 Demineralized Water Supply System 4 11/19/04 OP-RO-531 Primary and Pool Sample Station 3 7/12/04 OP-RO-532 Drain Collection System 3 6/28/04 OP-RO-555 Fire Protection System 0 11/1/04 OP-RO-710 Radiation Monitoring - Area Monitors 2 9/24/04 OP-RO-720 Radiation Monitoring - Stack Monitor Operational 3 8/5/04

__ _____ Check OP-RO-730 Building Exhaust System Fans 6 6/28/04 OP-RO-741 Waste Tank System Operation 5 4/26/04 RM-RO400 Waste Tank System Filter Replacement 3 4/26/04 RM-RO405 Reactor Demineralizer System 4 8/5/04 RP-RO-100 Fuel Movement 2 1/21/04 RP-RO-100 Fuel Movement 3 3/15/04 RP-RO-200 Measurement of Differential Worth of a Shim Blade, 0 7/29104 Replaced RTP I l-D RTP-I I(D)

RP-RO-201 Measurement of Total Reactivity Worth of Flux 0 7/29/04 Replaced RTP- 17-B Trap Loadings, RTP-17(B)

SM-RO-300 Control Console And Instrument Panel-Securing 4 8/5/04 Power SM-RO-620 Control Blade Bubble Leak Test 1 11/19/04 FM-08 Fuel Movement Sheet 4 1/21/04 _

FM-08 Fuel Movement Sheet 5 3/15/04 FM-Il Reactor Shutdown Checksheet 1 1/21/04 FM- 16 Primary-Pool Coolant Water Analysis 3 4/26/04 OA-3 Beamport and Pool Overflow Loop Seals 1 4/26/04 OA-3 Beamport and Pool Overflow Loop Seals 2 11/19/04 OA-4 Valve Operation Air Compressor 2 11/19/04 _

OA-5 Emergency Air Compressor 2 11/19/04 OA-7 Receiving Bulk Chemicals 1 9/24/04 . .

REP-RO- 100 Reactor Emergency Procedures 1 3/15104 REP-RO-100 Reactor Emergency Procedures 2 6/2104 11-2

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.

As part of the ongoing effort to rewrite and reformat MURR procedures in accordance with the MURR Procedure Writer's Guide, the Emergency Plan Implementing Procedures were revised and reformatted in their entirety with 41 new procedures, forms and operator aids issued. The following is a list of the new procedures, forms and operator aids:

'Number- ,. He Itt* ' F Re* R evision Datel Notes -

EP-RO-001 Definitions 0 4/8/04 Replaced FEP- 10 EP-RO-002 Emergency Responsibilities 0 4/8/04 EP-RO-002 Emergency Responsibilities 1 7/14/04 EP-RO-003 Emergency Preparedness Training 0 4/8/04 Replaced SEP-7 EP-RO-004 Fire 0 4/8/04 Replaced FEP-6 EP-RO-005 Medical Emergency 0 4/8104 Replaced FEP-7 EP-RO-006 Radiological Emergency 0 4/8/04 Replaced SEP-2 EP-RO-007 Severe Natural Phenomenon 0 4/8/04 EP-RO-008 Threat To Security 0 4/8/04 Replaced FEP-9 EP-RO-009 Notification of Unusual Event 0 4/8/04 EP-RO-010 Alert 0 4/8/04 EP-RO-0 II Site Area Emergency 0 4/8/04 EP-RO-012 Reactor Isolation 0 4/8/04 Replaced FEP-4 EP-RO-013 Facility Evacuation 0 4/8/04 Replaced FEP-5 EP-RO-014 EPZ and Site Area Evacuations 0 4/8/04 EP-RO-015 Emergency Notifications 0 4/8/04 Replaced SEP-I EP-RO-016 Public Information 0 4/8/04 Replaced FEP-8 EP-RO-017 Emergency Air Sampling 0 4/8/04 Replaced SEP-3 EP-RO-018 Emergency Radiation Exposure 0 4/8/04 Replaced SEP-4 EP-RO-018 Emergency Radiation Exposure 1 7/14/04 EP-RO-019 Emergency Dosimeters 0 4/8/04 Replaced SEP-5 EP-RO-020 Emergency Equipment Maintenance 0 4/8/04 Replaced SEP-6 FM-100 Emergency Declaration 0 4/8/04 FM-101 FEO Management 0 .4/8/04 FM-102 Emergency Event Log 0 4/8/04 FM-103 Facility Status 0 4/8/04 FM-104 Emergency Call List 0 4/8/04 FM-105 Initial/Follow-up Emergency Message 0 4/8/04 FM-106 Log of Personnel Released From Site. 0 4/8/04 FM-110 Fire Flowchart 0 4/8/04 FM-I I I Medical Flowchart . 0 4/8/04, FM-1 12 Radiological Flowchart 0 4/8/04 FM-I13 Severe Natural Phenomenon Flowchart 0 4/8/04 II-3

.NtiMumir-Z g~g>-r~t' t~>1 :gNaine:gytf i g- Rev Ri tig of Dtet FM-1 14 Security Flowchart 0 4/8/04 FM-I 15 Plant Conditions Flowchart 0 4/8104 FM- 116 Classification Flowchart 0 4/8/04 FM- 117 Reactor Isolation Flowchart 0 4/8/04 FM- 118 Evacuation Flowchart 0 4/8/04 OA-09 Combined Emergency Flowcharts 0 4/8/04 OA-10 Fire Extinguisher Locations and Types 0 4/8/04 OA-20 Emergency Equipment 0 4/8/04 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 125 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:

o~+~mberlgtat@@>4-&-&> Nhame R lR 5Si otes~'f4 AP-HP-105 Radiation Work Permit 3 4/1/04 AP-HP- I10 Controlled Special Exposures 3 11/1/04 AP-HP-1 17 MURR Initial Radiation Worker Training 4 4/1/04 Program AP-HP- 117 MURR Initial Radiation Worker Training 5 4/23/04 Program AP-HP-120 Beamport Area 1 3/16/04 AP-HP-121 Isotope Closet I 4/1/04 AP-HP-122 Material License Projects Quarterly Review 2 6/28/04 AP-HP-123 Visitor Dosimetry - Reception Desk 2 8/13/04 AP-HP-129 Hot Cell Control 2 3/16/04 AP-HP-130 Reactor License Projects Annual Review 0 10/12/04 AP-HP-150 Source Calibration 2 4/14/04 AP-PSO-001 Preparation of Radioactive Materials for Shipping 1 4/23/04 AP-SH-001 Administrative Procedure 1 4/22/04 AP-SH-001 Administrative Procedure 2 9/13/04 BPB-SH-001 NeoRx 2. Shipping Container Leak Check 2 4/22/04 BPB-SH-001 NeoRx 2R Shipping Container Leak Check 3 11/19/04 __

BPB-SH-002 2OWC-1 Packaging and Shipment of Type B Non- 3 4/22/04 Replaced SP-SH-002 Waste Radioactive Material BPB-SH-002 2OWC-I Packaging and Shipment of Type B Non- 4 11/19/04 Waste Radioactive Material BPB-SH-003 DOT 2OWC-I Receipt and Preparation I 4/22104 _

11-4

7E bei 7NweR, Rvso Date WNotes BPB-SH-005 DOT 6M Packaging and Shipment of Type B 1 4/22/04 Replaced SAS-000I Non-Waste Radioactive Material BPB-SH-005 DOT 6M Packaging and Shipment of Type B 2 11/19/04 Non-Waste Radioactive Material BPB-SH-006 2OWC-1 Packaging and Shipment of Type B Non- 0 8/27/03 Obsolete 4/22/04 Waste Radioactive Material BPB-SH-008 Type B(U) F-327 Series Packaging and Shipment 1 4/22/04 Replaced SAS-00013 of Type B Non-Waste Radioactive Material BPB-SH-008 Type B(U) F-327 Series Packaging and Shipment 2 11/19/04 of Type B Non-Waste Radioactive Material BPB-SH-009 GB/0924BP/B(U) Packaging and Shipment of 0 4/22/04 Replaced SAS-00008 Type B(U) Non-Waste Radioactive Material (Amersham)

BP-SH-004 Packing and Shipment of Type A Non-Waste 2 8/18/03 Obsolete 4/22/04 Radioactive Material BP-SH-007 F-327 Packaging and Shipment of Type A Non- 0 4/22/04 Waste Radioactive Material BP-SH-010 Packaging and Shipment of Non-Waste 0 9/27/04 Radioactive Materials in Excepted Packages BP-SH-011 Shipment of Non-Waste USA DOT 7A Type A 0 9/27/04 (Gemstone) Radioactive Material Package BP-SH-036 Packaging of Non-Waste Radioactive Material 0 4/22/04 Replaced SP-SH-004 Using MURR MODEL 1100 BP-SH-037 Packaging of Non-Waste Radioactive Material 0 4/22/04 Replaced SP-SH-004 Using MURR MODEL 1220 BP-SH-038 Packaging of Non-Waste Radioactive Material 0 4/22/04 Replaced SP-SH-004 Using MURR MODEL 1300 BR-RRD-205 Lutetium Chloride Batch Record 1 4/27/04 BR-RRD-205 Lutetium Chloride Batch Record 2 9/27/04 FM-151 Control Checksheet for Non-Waste USA DOT 7A 0 9/27/04 Type A (Gemstone) Radioactive Material Package FM-151 Control Checksheet forNon-Waste USA'DOT 7A 1 10/11/04 Type A (Gemstone) Radioactive Material Package FM-27 In-House Radioactive Shipping Request . 3 4/22/04 FM-35 Control Checksheet for Type B USA DOT 2OWC- 5 6/11/04 1 Radioactive Materials Shipment _

FM-35 Control Checksheet for Type B USA DOT 2OWC- 6 10/11/04 I Radioactive Materials Shipment FM-35 Control Checksheet for Type B USA DOT 2OWC- 7 10/28/04 1 Radioactive Materials Shipment FM-36 Control Checksheet for USA DOT 7A- MURR 3 4/22/04 Model 1100 Series FM-36 Control Checksheet for USA DOT 7A- MURR 4 6/11/04 Model 1100 Series FM-36 Control Checksheet for USA DOT 7A- MURR 5 10/11/04 Model 1100 Series FM-37 Control Checksheet for USA DOT 7A -MURR 3 4/22/04 Model 1220 Series .

II-5

qrXlyNume n¢amessss~s~w~

fy>

Atg;a _Ri fiin.; 6A.Dt ig jHs FM-37 Control Checksheet for USA DOT 7A -MURR 4 6/11/04 Model 1220 Series FM-37 Control Checksheet for USA DOT 7A -MURR 5 10/11/2004 Model 1220 Series FM-38 Control Checksheet for USA DOT 7A MURR 3 4/22/04 Model 1300 Series FM-38 Control Checksheet for USA DOT 7A MURR 4 6/11/04 Model 1300 Series FM-38 Control Checksheet for USA DOT 7A MURR 5 10/11/04 Model 1300 Series FM-39 Control Checksheet for Excepted Package 3 6/11/04 Radioactive Materials Shipment FM-39 Control Checksheet for Excepted Package 4 9/13/04 Radioactive Materials Shipment FM-39 Control Checksheet for Excepted Package 5 10/11/04 Radioactive Materials Shipment FM-44 Request for Radioisotope Shipment 4 4/22/04 FM-74 Control Checksheet for Type B USA DOT 6M 2 6/11/04 Radioactive Materials Shipment FM-74 Control Checksheet for Type B USA DOT 6M 3 10/11/04 Radioactive Materials Shipment FM-74 Control Checksheet for Type B USA DOT 6M 4 10/28/04 Radioactive Materials Shipment FM-75 Control Checksheet for Type B(U) F-327 Series 2 6/11/04 Radioactive Materials Shipment FM-75 Control Checksheet for Type B(U) F-327 Series 3 10/11/04 Radioactive Materials Shipment FM-77 Control Checksheet for GB/0924BP/B(U) 0 4/26/04 Radioactive Materials Shipment FM-77 Control Checksheet for GB/0924BP/B(U) 1 6/11/04 Radioactive Materials Shipment FM-77 Control Checksheet for GB/0924BP/B(U) 2 10/11/04 Radioactive Materials Shipment FM-78 Lutetium Chloride Radiation Protection 1 4/27/04 Data Sheet A FM-78 Lutetium Chloride Radiation Protection 2 9/27/04 Data Sheet A FM-79 Lutetium Chloride Radiation Protection 1 4/27/04 Data Sheet B FM-79 Lutetium Chloride Radiation Protection 2 9/27/04 Data Sheet B FM-89 Control Checksheet for Type A F-327 Series 0 4/26/04 Radioactive Material Shipment FM-89 Control Checksheet for Type A F-327 Series 1 6/11/04 Radioactive Material Shipment FM-89 Control Checksheet for Type A F-327 Series 2 10/11/2004 Radioactive Material Shipment GMP-PRC-112 Holmium Chloride Process Setup in HC-03 I 12/9/03 Obsolete 7/15/04 11-6

• ube ;15Nuti e~v. Revision~t iI.~e GMP-PRC-1 13 Holmium Chloride Production in HC-03 1 12/9/03 Obsolete 7/15/04 GMP-PRC-1 14 Quartz Vial Preparation - . 4 '8/30104 ..

GMP-PRC-1 15 Holmium Chloride Process Setup in HC-02 a/b 1 3/24/04 GMP-PRC-1 15 Holmium Chloride Process Setup in HC-02 alb 2 8/18/04 GMP-PRC-1 15 Holmium Chloride Process Setup in HC-02 a/b - 3 11/23/04 .

GMP-PRC- 116 Holmium Chloride Production in HC-02 a/b 1 3/24/04 .

GMP-PRC-1 16 Holmium Chloride Production in HC-02 a/b 2 .8/18/04 GMP-PRC- 116 Holmium Chloride Production in HC-02 a/b 3 11/23/04 HC-PSO-002 Hot Cell Preparation of Radioactive Material for 2 4/23/04 Shipment .

HC-PSO-002 Hot Cell Preparation of Radioactive Material for 3 9/24/04 Shipment HC-PSO-003 Hot Laboratory Preparation of Radioactive 1 4/23/04 Material for Shipment HC-PSO-003 Hot Laboratory Preparation of Radioactive - - 2 9/24/04 Material for Shipment HC-PSO-005 Hot Cell Loading of Host Cans 2 4/23/04 IC-HP-300 Calibration - Radiation Survey Instruments 2 2/17/04 IC-HP-310 Calibration - Eberline Ping Ia Stack Monitor - 2 1/23/04 Particulate Channel IC-HP-311 Calibration - Eberline Ping I a Stack Monitor - 2 1/23/04 Iodine Channel IC-HP-312 Calibration - Eberline Ping 1a Stack Monitor - Gas 2 1/23/04

__ Channel IC-HP-319 Calibration - NMC Model RAK Monitor - 2 3/16/04 Particulate Channel .

IC-HP-320 Calibration - NMC Model RAK Monitor - Iodine 2 3/16/04 Channel IC-HP-321 Calibration - NMC Model RAK Monitor - Gas 2 3/16/04 Channel IC-HP-330 Calibration - Canberra Model 2404 Swipe Counter 2 7/23/04 Obsolete 9/3/04 IC-HP-331 Calibration - Tennelec LB-5 100 Alpha/Beta . 3 4/1/04 IC-HP-333 Eberline BC-4 Beta Swipe Counter-Calibration 2 1/23/04 IC-HP-335 Calibration - Portal Monitor Gamma S/N 5 4/1/04 900644 IC-HP-337 Calibration - Portal Monitor Gamma S/N 4 4/14/04 1010 and 1011 IC-HP-341 Calibration -High Resolution Gamma 1 1/23/04 Spectroscopy Systems IC-HP-343 Calibration - Sodium Iodide Detector 2 4/1/04 IC-HP-347 Calibration - Protean Model WPC 9550 Alpha- 3 7/23/04 Beta Swipe Counter OP-HP-220 Tritium Bioassay 2 5/14/04 OP-HP-221 Environmental Sample - Analysis 2 2/17/04 OP-HP-224 Spent Fuel Shipping Cask Air Sample Analysis 1 5/14/04 OP-HP-225 Operation - Canberra Model 2404 Swipe Counter 1 8/4/03 Obsolete 9/3/04 II-7

. T 7umb. nie <77 i Re. Revision Dat "77. Nuite^

OP-HP-227 Tennelec LB-5 100 Alpha/Beta - Operation 2 3/16/04 OP-HP-230 Eberline BC-4 Beta Swipe Counter - Operation 2 1/23/04 OP-HP-348 Operation - Protean WPC-9550 Swipe Counter 1 1/23/04 OP-HP-350 Eberline Model Ping IA - Filter Change 2 4/1/04 OP-HP-352 Particulate and Iodine Filter - Analysis 1 1/23/04 OP-HP-353 Waste Tank Sample - Analysis 1 2/17/04 QA-SH-002 Sodium Iodide Spectral Analysis for Excepted, 0 9/13/04 Exempt, License-to-License, Type A, or Type B Radioactive Materials Shipments RM-HP-100 Stack Monitor Preventive Maintenance - NMC 2 3/16/04 Model RAK RM-HP-101 Stack Monitor Preventative Maintenance - 1 10/12/04 Eberline Ping IA _ _ _._._

RP-HP-110 Survey and Decontamination of Returned 2 4/1/04 Shipping Container RP-HP-130 Receipt of New Fuel Elements 2 4/1/04 RP-HP-135 Room 114 Entry - Self Monitored 1 4/14/04 RP-HP-137 Handling Radioactive Material in the Reactor Pool 2 9/24/04 RP-HP-139 Beamport Radiation Level Monitoring During 1 5/14/04 Reactor Startup SP-SH-004 Packing and Shipment of Type A Non-Waste 1 6/6/02 Obsolete 4/22/04 Radioactive Material SV-HP-1 10 Environmental Sampling 2 5/14/04 SV-HP-1 17 Secondary Coolant and Sump Water - Sampling 2 4/1/04 and Analysis SV-HP-121 Building Exhaust Stack Effluent - Ar-41 1 4/1/04 Monitoring SV-HP-131 Emergency Analysis of Environmental Samples 1 1/23/04 For Callaway Nuclear Plant WMB-SH-005 Shipment of Type B Radioactive Waste Using 2 6/28/04 Chem-Nuclear System 1- I3G Cask WM-SH-100 Radioactive Waste - Preparation and Storage 2 4/22/04 WM-SH-105 Radioactive Waste Processing 1 5/14/04 WM-SH-200 Exclusive Use Shipment of LSA or SCO 3 5/14/04 Radioactive Waste Utilizing a Broker I I WM-SH-300 MURR Exclusive Use Shipment of LSA or SCO 1 7/14/04

._ Radioactive Waste 11-8

-.SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT January 1, 2004 through December 31, 2004 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, page 7-4, Section 7.1.4 (as revised by the 1972-73, 1989-90, and 2002 Reactor Operations Annual Reports):

Add: The following to the end of the list:

"(15) Fire Protection System" Original HSR, page 7-17, Section 7.2.4 (as revised by the 1995 Reactor Operations Annual Report):

Delete: Entire section, which states:

"Fire Control System The Research Reactor Facility has eleven fire hose cabinets strategically located throughout the building. The hose cabinets are connected to a dry fire system which connects to three siamese fittings located outside the building, one each at the north, west and south entries. Fire hydrants are located outside the building in a vicinity near the external siamese connections to facilitate connecting a pumper truck between the hydrants and the hose connections on the building."

Replace with: "Fire Protection System The MURR fire protection system is designed to protect the facility and staff, and to mitigate any property loss in the event of a fire. The system provides two primary functions: (I) detection, which affords an early warning of an actual or potential fire condition by a combination of heat, smoke, and remote manual devices, and (2) suppression, which incorporates a normal sprinkler system with a pre-action system that is used in areas with sensitive electronic equipment, and a deluge, non-freezing system used in the cooling tower. It should be noted that fire protection is not required to accomplish a safe shut down of the reactor or to maintain a safe shutdown condition.

The fire detection system is' a combination of thermal, photoelectronic, and ionization-type sensors, flow switches, and manual pull stations. A central control station, located in room 204, and a repeater station, located in the reactor control room, monitors each system component. These stations will annunciate an alarm if any component is not in its normal condition:

111-li

The fire suppression system is a combination of many types of systems: a deluge system used in the cooling tower, a pre-action system used in areas that contain highly sensitive electronic equipment; a dry fire main system used in the reactor containment building; a traditional sprinkler system used throughout the rest of the laboratory building; and a damper isolation system for the facility ventilation exhaust system. The containment building fire suppression system consists of three fire hose cabinets connected to a dry fire main. Cross-connecting it to the rest of the facility's wet system by a manual isolation valve located in the laboratory basement can flood this system.

The fire protection system receives a virtually unlimited supply of water from the combination University fire and domestic cold water main. Four (4) siamese or storz hose fittings are also connected to the MURR fire main.

These fittings are located outside the facility and they facilitate connecting a pumper truck between the fittings and fire hydrants, which are located in the vicinity of the hose fittings, thus providing an additional water supply path to the fire main. In addition, fire extinguishers are strategically located throughout the facility.

The fire protection system is powered from the emergency electrical distribution system (ELP-2). The system also has a self-contained 24-hour battery backup."

Original HSR, pages 9-5 through 9-7, Table 9.1 (as revised by 1981-82, 1995, and 2001 Reactor Operations Annual Reports):

Delete:

"25 Temperature Readout Digital" Replace with:

"25 Auto Shim Engaged Light" Delete:

"59 Automatic Shim Circuit N/A N/A" Replace with:

"59 Intercom N/A N/A" Delete:

"60 Temperature Readout N/A 24 Position" Original HSR, Figure 5.1, Piping & Instrument Diagram (as revised by the 1972-73, 1973-74, 1994, 1996, 2001, 2002, and 2003 Reactor Operations Annual Reports):

Replace with: Updated Figure 5.1, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet I of 1, dated 11/16/04)

Original HSR, Figure 9.2, Control Console Layout (as revised by 1995 and 2001 Reactor Operations Annual Reports):

Replace with: Updated Figure 9.2, Control Console Layout (dated 6/29/04) 111-2

Original HSR, Figure 93, Instrument Panel Layout (as revised by 1995 and 2001 Reactor Operations Annual Report):

Replace with: Updated Figure 9.3, Instrument Cabinet (MURR Dwg No. 74, Sheet 12 of 12, dated 1/26/05)

ADDENDUM I - HAZARDS

SUMMARY

REPORT (FEBRUARY 1966)

HSR, Addendum 1, page 24, Section 3.8, paragraph 4, fourth item (as revised by the 1989-90 and 2002 Reactor Operations Annual Reports):

Add: The following bolded words to the first sentence: "...nitrogen station, fire protection system, and the evacuation alarms."

HSR, Addendum 1, page 25a, Figure 3.8.1, Emergency Generator Load Diagram (as revised by the 1989-90 and 2002 Reactor Operations Annual Reports):

Replace with: Updated Figure 3.8.1, Electrical Distribution Elem. Diagram (MURR Dwg No. 2272, Sheet I of 1, dated 8/20/04)

HSR, Addendum 1, page 104, Figure 3.22.2, Ventilation Air Flow Diagram for the East Tower (as revised by 1995 Reactor Operations Annual Report):

Replace with: Updated Figure 3.22.2, MURR Supply Air Schematic (MURR Dwg No.

1125, Sheet 2 of 3, dated 10/25/04)

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, and 2003 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.2, Secondary Cooling System (MURR Dwg No. 502, Sheet I of 1, dated 2/12/04)

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

Replace with: Updated Figure 2.3.a, Electrical Distribution (MURR Dwg No. 522, Sheet I of 3, dated 11/16/04)

III-3

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

Replace with: Updated Figure 2.3.b, Electrical Distribution (MURR Dwg No. 522, Sheet 2 of 3, dated 11/16/04)

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

Add new figure: Figure 2.3.c, Electrical Distribution (MURR Dwg No. 522, Sheet 3 of 3, dated 11/16/04)

ADDENDUM 4 - HAZARDS

SUMMARY

REPORT (OCTOBER 1973)

HSR, Addendum 4, page A-29, Figure A.2, Piping and Instrument Diagram (as revised by the 1995, 2001, 2002, and 2003 Reactor Operations Annual Reports):

Replace with: Updated Figure A.2, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet I of 1, dated 11/16/04)

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

Replace with: Updated Figure A.4.a, Reactor Control System (MURR Dwg No. 42, Sheet I of 2, dated 10/13/04)

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

Replace with: Updated Figure A.4.b, Reactor Control System (MURR Dwg No. 42, Sheet 2 of 2, dated 7/14/04)

HSR, Addendum 4, page A-33a, Figure A.6.a, 10 IMV Process Instrumentation Control & Interlock (as added by the 2001 Reactor Operations Annual Report):

Replace with: Updated Figure A.6.a, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 4 of 4, dated 5/18/04) 111-4 I

ADDENDUM 5 - HAZARDS SUMINIARY REPORT (JANUARY 1974)

HSR, Addendum 5, page 4, Section 2.2, third paragraph, second item (as revised by the 1989-90 Reactor Operations Annual Report):

Add: The following bolded words to the first sentence: "...intercommunication system, nitrogen station, fire protection system, and the reactor evacuation and isolation alarms."

HSR, Addendum 5, page 12, Section 2A.1 (as revised by the 1989-90 and 2002 Reactor Operations Annual Reports):

Add to end of list: "(15) Fire Protection System Normal supply power would be lost to the fire detection system.

However, the system is equipped with a battery backup that would provide power for the entire system for a period of twenty-four (24) hours. Additionally, fire protection is not required to accomplish a safe shut down of the reactor or to maintain a safe shutdown condition."

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

Replace with: Updated Figure 2.1, Electrical Distribution (MURR Dwg No. 522, Sheet I of 3, dated 11/16/04)

III-5

SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2004 through December 31, 2004 For each facility modification described below, MURR has on file the safety evaluation as well as the documentation of review in accordance with 10 CFR 50.59.

Modification 75-16, Addendum 2:

Relocation of the Reactor Safety System Monitoring Circuit Panel This addendum to modification record 75-16; "Portable White Rat for Safety System," documents the relocation of the reactor safety system monitoring circuit display panel from the right side of the control room Instrument Panel to the left side of the panel. This modification will allow the new Secondary Coolant Pump variable speed controller circuit control switches and meters, which are part of the Cooling Tower Electrical Upgrade Project (Modification Record 04-5), to be mounted on a panel in this freed position. This location was preferred since it'is adjacent to the Secondary Coolant Flow and Temperature Chart Recorder.

Modification 88-11, Addendum 1:

Upcrade of the Uninterruptible Power Suppl' (UPS) Alternate Source This addendum to modification record 88-11, "Reactor Control Power Upgrade," documents the upgrade in the load carrying capacity of the UPS Alternate Source. The alternate source, with a previous maximum load capacity of 50 amps, was undersized in relationship to the UPS. -This modification upgraded the alternate source wiring to 125 amps and replaced the 15 kVA, 3 phase, 480-208/120V step-down transformer with a new low-impedance isolation transformer line conditioner., Installation of a combination transformer/line conditioner allowed the removal of the 2.5 kVA Elgar; a 40-year old line conditioner that had not been placed in service for over fifteen years. In addition to its unknown reliability and functional utility, transfer of supply power to the Elgar had to be performed while the reactor was shutdown and secured. Installation of a line conditioner on the alternate source should increase operational reliability and flexibility in that if a failure of the UPS would occur while the reactor is operating, the alternate source will provide regulated and filtered AC output voltage to the reactor Instrumentation and Control Systems without an interruption in power.

Modification 91-3, Addendum 1:

Replacement of the Existine X. Y. MH-X. and MH-Y Fuel Storace Baskets with New X and Y Baskets This addendum to modification record 91-3, "Temporary Additional In-Pool Fuel Storage Baskets,"

documents the replacement of the X, Y, MH-X, and MH-Y fuel storage baskets with two'new fuel baskets.

The MH-X and MH-Y baskets were installed in 1991 as additional temporary fuel storage locations during a period when the facility was unable to ship fuel because two spent fuel shipping casks that were certified to transport MURR fuel were removed from service. The additional storage locations were needed to ensure that no interruption-to MURR's operating schedule would be experienced. The MH-X and MH-Y baskets were designed and built for the MH IA shipping cask and were not intended for long-term everyday use that they had endured at MURR. The new baskets are designed and constructed for everyday use, similar to that of the original X, Y, and Z storage baskets.

IV-I

Modification 95-1, Addendum IF:

Gamma-Metrics Nuclear Instrumentation Gain Potentiometer R27 Replacement This addendum to modification record 95-1, "Replacement of Nuclear Instruments," documents the replacement of the 20 K-ohm Gain Potentiometer R27 with a 50 K-ohm gain potentiometer in each Gamma-Metrics Nuclear Instrumentation (NI) drawer Squaring Amplifier. The 20 K-ohm potentiometer limited the NI adjustment range to approximately 15% at full power. If an adjustment was required outside of this range, the reactor had to be shutdown and the resistance value of switch SWI changed.

Replacement of the 20 K-ohm gain potentiometer with a 50 K-ohm potentiometer provides a greater adjustment range while operating.

Modification 01-3, Addendum 2:

Relocation of TE-980A and TE-980B Temperature Transmitters This addendum to modification record 0 1-3, "Replacement of the 980A/B Temperature Transmitters, Meter Relay Units, and RTDs," documents the relocation of the Primary Coolant System Temperature Transmitters for TE-980A and TE-980B from their previous location in Room 114 - a high radiation area at operation - to immediately outside of its entrance. These transmitters, replaced in March 2001 because of their age and unavailability of replacement pails, had experienced periodic drifting/erratic behavior since their installation. This modification was in response to the Manufacturer's (Rosemount Nuclear) recommendation of relocating the transmitters to a lower radiation field. The manufacturer believed that the driftinglerratic behavior of the temperature instruments was attributed to the high radiation field that the transmitters were mounted in. Since relocation, the transmitters have not experienced any more problems.

Modification 01-5, Addendum 1:

Replace Secondary Coolant Flow Transmitters FT-9 12P and FT-9 120 This addendum to modification record 01-5, "Upgrade Secondary Coolant System Flow and Temperature Measurement System," documents the replacement of the Rosemount Model 1151DP4J22B1 differential pressure transmitters for Secondary Coolant Flow Transmitters FT-912P and FT-912Q with Rosemount Model 1151DP4E22B2 transmitters. The Rosemount Model 1151DP4J22BI transmitters were unique in that they were the only Rosemount differential pressure transmitters at MURR that had the circuitry to perform the necessary square root function to determine flow built within the transmitter, and hence located in Room 114 (a high radiation area at operation). All other transmitters, which support process recorders that require a square root input, have the square root converters located in the reactor control room. FT-912P and FT-912Q had historically been problematic in that the "zero" and "span" settings routinely drifted, usually requiring adjustments during calibration. All other Rosemount Model 1151 transmitters in Room 114 had not experienced this same type of problem. A recent modification (Modification Record 01-3, Addendum 2) was performed in which the temperature transmitters for TE-980A and TE-980B were relocated from inside Room 114 to immediately outside its entrance. By relocating the temperature transmitters to a much lower radiation field, these instruments have not experienced any of the previous drifting problems. One of the many features of the Yokogawa Chart Recorder, which provides an indication of flow for FT-912P and FT-912Q, is the ability to take the square root of an input signal and provide a linear output signal; consequently no additional square root converters needed to be installed.

Since replacement, the new transmitters have not experienced any more problems.

IV-2

Modification 03-3:

Installation of a Facility Fire Detection/Suppression System This modification record documents the installation of a new Fire Detection/Suppression System in the facility. The new system, as its name implies, provides two functions: (l) a Detection System that provides an early warning of an actual or potential fire condition by a combination of heat, smoke, and remote manual devices, and (2) a Suppression System that incorporates a normal sprinkler system with a pre-action system used in areas with sensitive electronic equipment, and a deluge, non-freezing system used in the Cooling Tower. All of these systems and devices combine to form a complete Fire Detection/Suppression System for MURR.

Modification 04-1:

Replace the General Electric Measurement and Control Type 551 Reactor Pressure Transmitter PT-943 with a Rosemount Model 1151 This modification record documents the replacement of the General Electric Measurement and Control (GE/MAC) Type 551 Pressure Transmitter for Reactor Pressure Transmitter PT-943 with a Rosemount Model 1151 Pressure Transmitter. Because of its age and the inability to purchase replacement parts, the GE/MAC Type 551 Pressure Transmitter had become obsolete. In addition to their known reliability, replacement of the GE/MAC transmitters with Rosemount Model 1151's will help standardize all reactor plant pressure transmitters.

Modification 04-4:

Relocation of Automatic Shim Control Circuit for Reactor Console Modification This modification record documents the relocation of the Automatic Shim Control circuit from the sloping face section of the reactor control console to a panel behind the north most console access door. Relocation of this circuit freed up sufficient space that allowed the Master Control Switch, IS], to be relocated higher and away from the writing surface, thereby lessening the chance that ISI could inadvertently be bumped and cause a shutdown of the reactor. Additionally, the old Regulating Rod Position Indication panel was removed and a new panel, which only houses the regulating rod indicating lights and manual pushbuttons, was mounted in its place.

IV-3

SECTION V NEW 'TESTS AND EXPERIMENTS January 1, 2004 through December 31, 2004 New tests or experiments developed during this period are as follows:

RUR 219, as amended: Ytterbium Metal and Oxide (Natural and Enriched)

Description:

This amended RUR authorizes the irradiation of natural and enriched ytterbium metal and ytterbium oxide for use in research and development activities.

RUR 276, as amended: Natural Iridium

Description:

This amended RUR authorizes the irradiation of natural iridium for use in research and development activities.

RUR 407: Enriched Calcium Carbonate

Description:

This RUR authorizes the irradiation of enriched calcium carbide for use in research and development activities.

RUR 409, as amended: Xenon Targets - Modified Encapsulation Design

Description:

This amended RUR authorizes the irradiation of xenon targets with a modified encapsulation design for use in research and development activities.

RUR 411: Enriched Gadolinium Nitrate

Description:

This RUR authorizes the irradiation of enriched gadolinium nitrate for use in research and development activities.

Project Authorization RL-64: Irradiation of Electronic Components in the Thermal Column

Description:

This Project Authorization authorizes the irradiation of electronic components in the thermal column port of the reactor.

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-64, the Isotope Use Subcommittee also reviewed the project.

V-l

SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1,2004 through December 31, 2004 Inspections:

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

Reactor Characteristic Measurements:

Sixty (60) refueling evolutions were completed in 2004. Excess reactivity verification was performed for each refueling. The largest measured excess reactivity was 2.95%. MURR Technical Specification 3.1(f) requires that the excess reactivity be less than 9.8%.

Reactivity Measurements:

Ten (10) measurements were made to determine the reactivity worth of several samples that are irradiated in either the flux trap or reflector regions and that of the total flux trap loading.

Eight (8) differential blade-worth measurements and one primary coolant temperature coefficient measurement were also performed.

VI-1

SECTION VII RADIOACTIVE EFFLUENT January 1, 2004 through December 31, 2004 TABLE I SANITARY SEWER EFFLUENT January 1, 2004 through December 31, 2004 Descending Order of Activity Released for Nuclide Totals > 1.OOOE-05 Ci Nuclide Activity (Ci)

H-3 1.029E-01 S-35 - 1.345E-03 Lu-177 5.384E-04 Co-60 5.237E-04 Cr-51 1.476E-04 Ca-45 1.245E-04 Lu-177m 1.145E-04 1-131 2.621E-05 TI-201* 1.885E-05 Zn-65 1.700E-05 Ag-110m l-1.615E-05 Mn-54 1.591E-05 Cu-67 1.170E-05 Total H-3 1.029E-01 Total Other 1.086E-01 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."

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

VII-1

-1 TABLE 2 STACK EFFLUENT January 1, 2004 through December 31, 2004 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration pCilml Total Release Ci TS Limit Multiplier  % TS Ar-41 2.85E-06 1.32E+03 350 81.5061 C-14 2.48E-11I 1.13E-02 I 0.830 Co-60 3.97E-14 1.84E-05 1 0.0794 1-131 1.49E-13 6.89E-05 I 0.0743 H-3 1.88E-08 8.70E+00 350 0.0537 1-125 7.00E-14 3.25E-05 I 0.0233 Cd-109 1.16E-14 5.36E-06 1 0.0165 Ti-51 3.83E-11 1.78E-02 350 0.0110 W-188 1.78E-13 8.27E-05 1_ 0.0089 Sr-85 1.97E-14 9.1 IE-06 I 0.0010 Cs-137 1.50E-15 6.97E-07 I 0.0008 Sc-46 2.05E-15 9.50E-07 1 0.0007 Hf-181 2.75E-15 1.28E-06 1 0.0005 Se-75 3.50E-15 1.62E-06 1 0.0004 Os-191 7.84E-15 3.63E-06 1 0.0004 Ru-103 1.911E-15 8.84E-07 1 0.0002 1-133 4.51E-13 2.09E-04 350 0.0001 Xe-135m 1.74E-11 8.05E-03 350 0.0001 S-35 3.72E-15 1.72E-06 1 0.0001 Sn-113 9.05E-16 4.19E-07 I 0.0001 Hg-203 1.04E-15 4.81 E-07 I 0.0001 As-77 2.37E-12 1.IOE-03 350 0.0001 Co-58 6.39E-16 2.96E-07 I 0.0001 Be-7 1.81E-14 8.38E-06 I 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 ENVIRONNIENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1,2004 through December 31, 2004 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 2004. All doses are about 25 mRemlyear 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 trzansit. The environmental monitoring program confirms that no environmental impact exists from the operation of the MURR facility.

The number of radiation and contamination surveys performed each month is provided in Table 4.

TABLE I Summary of Environmental Set 65 May 2004 Detection Limits*

Matrix Alpha Beta Gamma Tritium Water 1.82 pCi/L 10.19 pCi/L 288.16 pCi/L 3.76 pCi/mL of sample Soil 1.49 pCi/,g 10.06 pCi/g 1.32 pCi/g N/A Vegetation 3.65 pCi/g 19.73 pCi/g 2.84 pCi/g 3.81 pCi/mL of distillate

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

Activitv Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/0) Gamma (pCi/g) H-3 (pCi/mL)

IV65 < 3.65 <19.73 < 2.84 <3.81 2V65 < 3.65 31.54 < 2.84 <3.81 3V65 < 3.65 21.92 < 2.84 <3.81 4V65 < 3.65 29.94 < 2.84 ' <3.81 5V65 < 3.65 24.06 <2.84 <3.81 6V65 < 3.65 20.32 < 2.84 <3.81' 7V65 < 3.65 24.06 < 2.84 <3.81 10V65 < 3.65 22.99 < 2.84 <3.81

I -1 TABLE 1 (Cont'd)

Summary of Environmental Set 65 May 2004 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g)

I S65 < 1.49 10.43 3.09 2S65 1.60 14.44 < 1.32 3S65 1.60 <10.06 < 1.32 4S65 < 1.49 <10.06 < 1.32 5S65 < 1.49 17.11 2.92 6S65 < 1.49 10.43 < 1.32 7S65 < 1.49 11.23 < 1.32 10S65 < 1.49 16.04 7.48 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W65 < 1.82 < 10.19 < 288.16 < 3.76 6W65 < 1.82 < 10.19 < 288.16 <3.76 10W65 < 1.82 14.03 824.86 <3.76

• Sample 10W65 was found to have gamma activity above MDA. Sample was counted on a HPGE detector and Tc-99m was identified as the only isotope above background levels. This isotope is routinely used for medical treatment and has historically been found at this sample location.

TABLE 2 Summary of Environmental Set 66 October 2004 Detection Limits**

Matrix Alpha Beta Gamma Tritium Water 0.72 pCi/L 4.50 pCi/L 200.82 pCi/L 4.08 pCi/mL of sample Soil 0.88 pCi/g 2.35 pCi/g 0.71 pCi/g N/A Vegetation 1.44 pCi/g 3.93 pCi/g 1.69 pCi/g 4.02 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 66 October 2004 i L -

Activitv Levels - Veizetation Sample Alpha (pCi/g) Beta (pCikg) Gamma (pCi/g) H-3 (pCi/mL) 1V66 < 1.44 13.19 < 1.69 < 4.02 2V66 < 1.44 13.45 < 1.69 < 4.02 3V66 < 1.44 20.76 < 1.69 < 4.02 4V66 < 1.44 12.40 < 1.69 < 4.02 5V66 < 1.44 27.03 < 1.69 < 4.02 6V66 < 1.44 21.80 < 1.69 <4.02 7V66 < 1.44 31.21 < 1.69 < 4.02 10V66 < 1.44 19.19 < 1.69 <4.02 Activity Levels - Soil Sample Alpha (pCilp) Beta (pCi/g) Gamma (pCik) 1S66 < 0.88 15.54 4.20 2S66 1.01, 11.88 3.03 3S66 < 0.88 16.19 3.57 4S66 < 0.88 8.23 2.84 5S66 < 0.88 14.36 3.93 6S66 < 0.88 7.18 1.24 7S66 1.01 12.14 2.60 10S66 1.16 16.45 4.08 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L Gamma (pCi/L) H-3 (pCi/mL) 4W66 <0.72 9.66. < 308.29 < 4.08 6W66 <0.72 6.27 < 308.29 < 4.08 10W66 <0.72 < 4.50 < 308.29 < 4.08 VIII-3

'I I

TABLE 3 Environmental TLD Summary January 1, 2004 through December 31, 2004 Badge Direction Map Distance from Ist Qtr. 2nd Qtr. - 3rd Qtr. 4th Qtr. Total Number From MURR MURR Stack 2004 2004 2004 2004 2004 i

(meters) Net mR Net mR Net mR Net mR Net mR Control N/A -1.4 0.2 -1.1 -0.7 -3.0 2 Control N/A -6.0 -0.4 -0.1 -0.4 -6.9 3 WSW N/A 2.8 0.7 0.0 1.4 4.9 4 Spare N/A 6.0 3.1 2.2 4.3 15.6 5 Spare N/A 2.3 2.6 2.4 1.3 8.6 6 N 34 1.0 -0.2 1.9 -2.0 0.7 7 NE 57 2.0 1.1 -1.3 -0.4 1.4 8 SW 27 -6.8 -3.5 -0.9 0.8 -10.4 9 S 27 23.7 31.1 22.8 22.9 100.5 10 NE 149 -5.0 -7.1 0.7 -4.5 -15.9 I NW 149 absent -4.5 -5.6 -6.1 -16.2 12 ENE 301 8.3 0.9 2.5 2.2 13.9 13 NNE 316 -0.2 2.3 -1.4 -0.7 0.0 14 S 156 2.3 -0.4 0.5 0.3 2.7 15* S 65 28.6 28.6 18.7 22.3 98.2 16 SE 107 -3.0 -6.5 -2.7 -4.0 -16.2 17 E 293 -3.7 -5.8 -1.5 -4.2 -15.2 18 NE 476 -2.1 -6.8 -3.0 -4.9 -16.8 19 NNE 606 -16.1 -12.4 -6.8 -7.7 -43.0 20 NE 907 -6.0 -10.0 -5.5 -8.1 -29.6 21 SE 236 1.3 -3.0 0.2 -3.0 -4.5 22 ESE 168 absent -5.8 absent -0.8 -6.6 23* NW 110 8.8 -0.6 1.9 0.4 10.5 24 SSW 328 -5.3 -2.2 0.0 absent -7.5 25 SSW 480 -1.9 -1.3 1.9 -2.2 -3.5 26 SW 301 -5.7 -4.6 0.4 -3.3 -13.2 27 WSW 141 -6.9 -11.1 -4.7 -8.1 -30.8 28** WNW 210 absent absent absent absent 0.0 29* NW 255 9.0 9.0 1.4 -3.9 15.5 30 NNW 328 absent -9.1 -0.9 -6.0 -16.0 31 NNW 671 -4.0 -2.9 -1.3 -0.8 -9.0 32 NNW 724 -6.4 -0.7 1.0 -3.0 -9.1 33 E 671 -8.3 absent -3.9 -7.1 -19.3 34* ENE 587 7.9 -9.7 -3.2 -8.9 -13.9 35 SSE 499 -4.2 -8.5 -4.5 -6.3 -23.5 36 SE 419 absent -6.4 0.0 2.6 -3.8 37 NE 690 -4.5 -6.6 -2.1 -4.7 -17.9 38 NW 556 absent -2.6 absent -2.0 -4.6 39 W 491 absent -9.2 0.0 -0.4 -9.6 40 N 514 -5.2 -6.1 1.3 -5.9 -15.9 41 NNE 137 -4.0 -10.0 -1.6 -7.4 -23.0 42 In Building N/A -2.1 1.1 -0.7 -0.4 -2.1 43 In Building N/A 4.1 0.8 4.8 5.7 15.4 44 Spare N/A 4.6 0.1 -13.5 2.1 -6.7 45 S 65 -3.5 -5.5 0.7 -1.4 -9.7

• TLD No. 23 and 34 left at site 4th quarter 2003 and I st quarter 2004, total dose is divided between the two quarters. TLD No. 15 and 29 left at site I st and 2nd quarter 2004, total dose divided between the two quarters.

• • TLD No. 28 has been moved to a different tree at the same location to prevent it from being absent so often.

V111-4

TABLE 4 Number of Facility Radiation and Contamination Surveys January 1,2004 through December 31, 2004 Radiation Surface Contamination* Air Samples** RWP's January 57 57 63 4 February 44 44 62 6 March 58 58 64 4 April 57 56 63 7 May 54 52 60 4 June 75 73 66 5 July 40 39 60 6 August 62 62 61 5 September 42 42 46 7 October 53 52 56 5 November 44 44 55 4 December 59 59 64 5 TOTALS 645 638 720 62

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

• • Air samples include stack Ar41, containment Ar-41, sump entries, and hot cell entries.

Miscellaneous Notes Rob Taylor was promoted to Health Physicist in August 2004.

Matt Ballew was promoted to Health Physics Technician II in February 2004.

During 2004, MURR shipped 828 cubic feet of low level radioactive waste.

VIII-5

SECTION IX

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS January 1,2004 through December 31, 2004 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP Month AC DO FSO HC RAG IRR NA NS OPS PRO RP SH SIL Total January 35 35 65 149 99 15 19 20 1117 103 69 50 40 1816 February 54 80 242 202 198 15 66 66 1824 174 86 83 64 3154 March 54 21 176 212 198 41 5 76 1332 102 75 50 117 2459 April 54 7 90 150 221 51 30 86 1489 90 106 64 54 2492 May 113 2 121 120 117 50 53 28 1307 89 56 58 59 2173 June 104 6 167 177 209 71 92 93 1756 66 105 63 57 2966 July 64 3 86 88 128 28 29 55 967 85 92 107 33 1765 August 35 5 55 125 137 76 7 124 1069 91 20 94 37 1875 September 17 15 35 125 163 71 8 40 1385 61 28 103 48 2099 October 7 5 29 232 250 38 10 31 1472 45 29 76 31 2255 November 5 8 29 165 103 59 18 12 1133 37 44 89 35 1737 December 17 0 211 138 121 62 14 22 1351 86 74 94 49 2239 Total to Date 559 187 1306 1883 1944 577 351 653 16202 1029 784 931 624 27030 Monthly Ave 47 16 109 157 162 48 29 54 1350 86 65 78 52 2253 Highest WB 22 34 107 83 81 48 19 35 133 48 33 76 103 Highest EXT 450 50 2450 500 390 120 230 70 290 1520 958 480 270 AC-Analytical Chemistry RAG-Health Physics NS-Neutron Scattering RP-Radiophariceutical DO-Director's Office IRR-lrradiations OPS-Operations SH-Shipping 0 FSO-Shops NA-Nuclear Analysis PRO-Isotope Production SIL-Silicon

-I' HC-Hot Cell WB=W'hole 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