ML030590078

University of Missouri Research Reactor, Annual Report for Period January 1, 2002 Through December 31, 2002

ML030590078
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/25/2003
From:	Rhonda Butler Univ of Missouri - Columbia
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML030590078 (38)

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Research Park Research Reactor Center Columbia, MO 65211 University of Missouri-Columbia PHONE (573) 882-4211 FAX (573) 882-6360 February 25, 2003 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

REFERENCE:

Docket 50-186 University of Missouri Research Reactor License R-103 Please find enclosed one copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2002 through December 31, 2002.

This document is submitted to the Nuclear Regulatory Commission in accordance with the University of Missouri Research Reactor Technical Specification 6.1.h (4)

If you have questions regarding the contents of this document, please feel free to call Leslie P. Foyto, Interim Reactor Manager at (573) 881-5176.

Sincerely, Ralph Butler Interim Director Enclosure cc: Mr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC q, 0.

AN EQUAL OPPORrTUiTY/ADA INSTITUTION

UNIVERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2002 - December 31, 2002 RESEARCH PACTOR U'ACILI PY

UN.JE2VRSITV OF'MISSOVURI RESEARCH REACTOR FACILITy REACATOR OPERJ4ATIONS ALNWUAL REPORT January 1, 2002 - December 31, 2002 Cormy Wedby the Reactor Staff SubmittedFebruary2003 by Leslie P. Foyto Interim Reactor Mlanager

(ý -A ReviewedandApproved Ralph 5A Butler, PE Interim Director Chief Oyerating Officer

UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2002 through December 31, 2002 INTRODUCTION The University of Missouri Research Reactor (MURR) is a multi-disciplinary research and education facility providing a broad range of analytical, radiographic, and irradiation services to the research commumty 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-owvned research reactor in the world.

The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2002. 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 ACIKNOWLED GMENTS 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 Missouri University Police Department; our Regulators; those who have provided funding including the U.S. Department of Energy (DOE); the Researchers; the Students; the Columbia Fire Department; the Campus Facilities organization; 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 MURR Management wishes to thank all of its staff members for their support and cooperation in a time of continuing change within our unique facility. The success of the Organizational Alignment Initiative, Corrective Action Program, Safety Conscious Work Environment, Performance Enhancement Plan, 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 neutron scientists and engineers.

Reactor Operations Management also wishes to commend the nine 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 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.

TABLE OF CONTENTS Section Page I Reactor Operations Summary .............................. I-1 through 8 H. MURR Procedures ................................................... I-1 through 3 A. Changes to Standard Operating Procedures B. Changes to MURR Site Emergency Procedures and Facility Emergency Procedures C. Changes to Health Physics Standard Operating Procedures, Byproduct Material Shipping Procedures, and Preparation of Byproduct Material for Shipping Procedures III. Revisions to the Hazards Summary Report ............................................ 111-1 through 7 IV. Plant and System M odifications ............................................................... IV -1 through 4 V. New Tests and Experiments .................................... V-1 VI. Special Nuclear Material and Reactor Physics Activities ............... VI-1 VII. Radioactive Element .................................... VI-1 through 2 VIII Environmental Monitoring and Health Physics Surveys .......................... VIII-1 through 5 IX. Personnel Radiation Exposures ........................................................... IX-1 through 2

SECTION I REACTOR OPERATIONS

SUMMARY

January 1, 2002 through December 31, 2002 The following table and discussion summarize reactor operations in the period January 1, 2002 through December 31, 2002.

Full Power % of Full Power % of Date Full Power Hours Megawatt Days Total Time Schedule*

Jan 2002 653.16 272.29 87.79 98.33 Feb 2002 575.09 239.85 85.58 95.85 Mar 2002 641.79 267.65 86.26 96.61 Apr2002 601.04 250.56 83.48 93.49 May 2002 664.78 277.11 89.35 100.08 Jun 2002 601.36 250.67 83.52 93.54 Jul2002 619.97 258.64 83.33 93.33 Aug 2002 667.63 278.30 89.74 100.50 Sep 2002 612.33 255.69 85.04 95.25 Oct2002 648.81 270.48 87.20 97.67 Nov 2002 626.70 261.20 87.04 97.49 Dec 2002 658.11 274.35 88.46 99.07 Total for The Yer 7570.77 3156.79 86.40 % 96.77 %

The Year

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

January 2002 The reactor operated continuously in January with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and two unscheduled shutdowns.

On January 20, a manual scram was initiated by the Lead Senior Reactor Operator due to erratic indication on Reactor Inlet Temperature Instrument 980B. There are two channels of reactor inlet temperature instrumentation that provide scram input signals. In accordance with Technical Specification 3.3.a, both channels are required to be operable when the reactor is operating.

On January 26, a manual scram was initiated by the Lead Senior Reactor Operator due to a recurrence of the erratic indication on Reactor Inlet Temperature Element 980B. The manual scram was initiated for the same reason as stated above. Licensee Event Report No. 02-01, providing a description of these events 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 01-09, "Installation of Emergency Lighting Panel No. 1"; loading new pool deionization bed 'P'; rebuilding primary heat exchanger 503A I-1

dram valve 515A; completing Deiomzation Tank-201 valve and flange gasket replacement; completing Modification Record 01-09, Addendum 1, "Relocation and Replacement of Emergency Lighting Panel No. 2"; replacing Reactor Inlet Temperature Instrument 980B meter relay unit, transmitter, and RTD; and completing Modification Record 01 11, "Replace K Relay Sockets with an Improved Design."

February 2002 The reactor operated continuously in February with the following exceptions: three shutdowns for scheduled maintenance and/or refueling, and six unscheduled shutdowns.

On February 16 and 17, there were five unscheduled rod run-ms and one unscheduled scram due to an intermittent faulty detector or cabling component for nuclear instrument (NI) power range monitor Channel 6. Initial attempts at determining and correcting the cause of the rod run-in actuations focused on examining and replacing components of the Channel 6 drawer after two of the events indicated Channel 6 high power on the drawer and annunciator panel.

No actual power increase was indicated on any chart recorders or any other instrumentation. Monitoring equipment was connected to the input of the rod mn-in non-coincidence logic unit (NCLU) in an effort to capture and record any electronic inputs that might be occumng faster than the response time of the installed instrumentation. The last power reduction was clearly indicated as a Channel 6 high power scram.

After eliminating other possibilities, the detector and cabling for NI Channel 6 were replaced. No further problems of this type have occurred The cause of these actuations was therefore attributed to failure of the Channel 6 detector connectors and cabling. This failure resulted in very rapid electronic spikes that were sufficient to cause the actuation, but not of sufficient duration to register on any installed instrumentation.

Major maintenance items for the month included: replacing Gamma-metrics signal processor No. 1 fission chamber detector; completing Modification Record 01-4, Addendum 5, "Replace the Current General Electric Measurement and Control Type 563 Primary Coolant System Differential Temperature Summer with a New Moore Industries Adder-Subtractor Module"; completing 529 series solenoid-operated poppet valve modifications for valves 546A and 546B in accordance with Modification Record 01-6; replacing NI Channel 6 dual trip unit; replacing NI Channel 6 drawer; replacing the rod run-in trip actuator amplifier; replacing the rod run-in NCLU; and replacing NI Channel 6 detector and cabling.

Replacing NI Channel 6 dual trip unit, NI Channel 6 drawer, rod run-in trip actuator amplifier and NCLU, and NI Channel 6 detector and cabling were sequential maintenance activities that were performed as part of troubleshooting and repair of an intermittent electromc failure that caused five automatic rod run-in actuations and one scram.

March 2002 The reactor operated continuously in March with the following exceptions: five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled shutdowns this month. Two short duration startups to 9 MW were performed for NRC operator examination Major maintenance items for the month included: completing Modification Record 01-4, Addendum 6, "Replace the General Electric Measurement and Control Type 565 Primary Coolant System Flow Square Root Converters with Moore Industries Square Root Transmitters"; replacing the pump and motor for P501B (primary coolant system 1-2

pump); completing 529 series solenoid-operated poppet valve modifications for valves 543A and 543B in accordance with Modification Record 01-6; removing, rebuilding, and reinstalling the pump for P508B (pool coolant system pump); and completing Modification Record 01-4, Addendum 3, "Replace the Current General Electric Measurement and Control Type 563 Pool Coolant System Differential Temperature Summer with a New Moore Industries Adder Subtractor Module."

April 2002 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and two unscheduled shutdowns. Received notification from the NRC that two new Reactor Operator licenses and one new Senior Reactor Operator license had been issued.

On Apnl 4, a scram was initiated by a control room operator upon discovering there was no discemable rise in water level of the pressurizer when the charging pump was running. Investigation revealed that the Pressurizer Recirculation Valve 528 had been left open after maintenance allowing water to return to storage tank T-300 rather than flow to the pressurizer. While pressurizer level remained in the normal operating range, the open 528 valve placed the reactor makeup water system in a degraded lineup resulting in a deviation from Technical Specification 3.10.b. The valve was repositioned to allow the charging system to makeup water normally to the pressurizer and a complete valve lineup of the pressurizer system was performed. The reactor was subsequently refueled and returned to normal operation. Licensee Event Report No. 02-02, providing a description of these events and the corrective actions taken, was submitted within the Technical Specification thirty-day time requirement.

On Apnl 22, a Rod Not In Contact With Magnet Rod Run-In was automatically initiated when control blade 'B' anvil separated from its magnet during a normal reactor startup. Control Rod "B" Drive Mechanism, connectors, wiring, seating surfaces, magnet and anvil were inspected with no apparent problems detected. Control blade 'B' was withdrawn to 2 inches to verify proper magnet engagement The Control Rod Drive Mechamsm was reassembled and control blade 'B' was withdrawn to 12 inches to verify proper operation. The reactor was subsequently started up to 10 MW and operated with no other problems Major maintenance items for the month included: completing Pressurizer valve refurbishment in accordance with Work Authorization 02-13; replacing Secondary Coolant System make-up water float valve; commencing repair of the Dry Fire Main penetration through the utility entry water seal in accordance with Work Authorization 143-01; commencing installation of a 2000 kVA transformer as part of the facility electrical distribution system upgrade in accordance with Modification Record 02-1; replacing the amphenol connector for the Bridge ALARA area radiation monitoring system unit; replacing relay 1K9 for the rod run-in trip actuator amplifier; replacing the meter for PT-943 (primary pressure); and repairing a broken wire in pool isolation valve 509 control circuit.

May 2002 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On May 31, a Rod Not In Contact With Magnet Rod Run-In was automatically initiated when control blade 'D' anvil separated from its magnet during a sample handling evolution. Blade 'D' Full In light was lit so the control room operator initiated a manual scram and the reactor was shutdown It was determined that during sample handling an 1-3

operator trainee had allowed a sample holder to bump Control Blade "D" Offset Mechanism. This bump was sufficient to cause the anvil to separate from the magnet. The reactor was subsequently refueled and returned to power.

Major maintenance items for the month included- replacing Cooling Tower Fan No. 3 gearbox; replacing the control fuse and relay (CP-1) in Facility Ventilation Exhaust Fan EF-13 control circuit; and completing the biennial change out of Control Blade "B" Offset Mechanism June 2002 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns this month Major maintenance items for the month included: completing Deionization Tank-202 and resin storage tank valve and flange gasket replacement; loading new pool de-ionization bed 'E'; completing repair of the Dry Fire Main penetration through the utility entry water seal in accordance with Work Authorization 143-01; completing installation of a 2000 kVA transformer as part of the facility electrical distribution system upgrade in accordance with Modification Record 02-1; completing Modification Record 01-4, Addendum 7, "Replace the General Electric Measurement and Control Type 565 Pool Coolant System Flow Square Root Converters with Moore Industries Square Root Transmitters"; loading the CNSI-13G Waste Shipping Cask with old wedges for shipment to the Bamwell Site for disposal; and replacing the motor for P501A (primary coolant system pump).

July 2002 The reactor operated continuously in July with the following exceptions- six shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown. Received notification from the NRC that two new Reactor Operator licenses had been issued.

On July 25, a reactor scram was initiated automatically by PT-917 (reflector low AP) when the differential pressure across the pool reflector momentarily dropped below the scram set point. This set point had been changed on July 22 during the performance of CP-5. It was deterrmned that during the performance of CP-5 air in the lines from the pressure test unit had provided a false indication and had caused the operating crew to reset the set point. This change was in the conservative direction and placed the set point within close proximity of actual operating differential pressure. CP-5 was performed again after flushing the test lines and the set point was reset to allow for normal operating pressure transients without inadvertently actuating the protective function of PT-917.

Major maintenance items for the month included: replacing anti-siphon isolation valve 543B air actuator; re installing the keeper pin in the northwest Pressure Vessel tie-rod support; and replacing the control transformer for P501A (primary coolant system pump) control circuit.

August 2002 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and two unscheduled shutdowns.

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On August 4, a Rod Not In Contact With Magnet Rod Run-In was automatically initiated when control blade 'D' anvil separated from its magnet during a sample handling evolution. Blade 'D' Full In light was lit so the control room operator initiated a manual scram and the reactor was shutdown. It was determined that during sample handling an operator trainee had allowed a sample holder to bump Control Blade "D" Offset Mechanism. This bump was sufficient to cause the anvil to separate from the magnet. The reactor was subsequently refueled and returned to power.

On August 20, a Rod Not In Contact With Magnet Rod Run-In was automatically initiated when control blade 'A' anvil separated from its magnet during a sample handling evolution. Blade 'A' Full In light was lit so the control room operator initiated a manual scram and the reactor was shutdown. It was determined that during sample handling an operator trainee had allowed a sample holder to bump Control Blade "A" Offset Mechanism. This bump was sufficient to cause the anvil to separate from the magnet. The reactor was subsequently refueled and returned to power.

Both of these unscheduled shutdowns were the result of relatively new operators handling samples in close proximity to the reactor control blades. Operations personnel were reminded of the necessity of flawless attention to detail and to use care in sample handling.

Major maintenance items for the month included: None.

September 2002 The reactor operated continuously in September with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and four unscheduled shutdowns On September 18, a deviation from Technical Specification 3.8.c occurred when a fuel element was mis-positioned resulting in a noncompliant core configuration. During a reactor startup following refueling it was observed that there was a difference between the Estimated Critical Position (ECP) and the 1/M predicted critical position with the rods two inches below the ECP. Examination of the Source Range Instrumentation revealed no cause for the discrepancy so the startup was terminated by a manual rod run-in. Troubleshooting revealed no abnormalities with nuclear instrumentation or the rod control system. The pressure vessel head was removed and it was observed that fuel element F5 was not seated in the core. This fuel element was inspected and placed into its proper core position.

A root cause analysis determined that the fuel handling tool had not been allowed to float off the element after unlatching. The element was lifted up out of the core position, was released, and became lodged on a point of narrowing of a guide groove in the OD of the inner pressure vessel wall. Subsequent mechanical and visual inspections then failed to detect the rmis-positioned element prior to reinstalling the pressure vessel head.

Additionally, the relationship between the misplaced element and changes in several primary flow related parameters was not seen as indicative of a core discrepancy prior to the reactor startup. Licensee Event Report No. 02-03, providing a description of these events and the corrective actions taken, was submitted within the Technical Specification thirty-day time requirement.

On September 18, a manual scram was initiated when the outer airlock door failed to open. Master Control Switch IS1 was placed to the OFF position securing the reactor for airlock door repairs and limit switch adjustments. It was determined that pressure switch B on the outer door control circuit had failed. This switch was replaced and the door was cycled several times to verify proper operation. The reactor was subsequently returned to operation.

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On September 19, a reactor scram occurred when Master Control Switch 1SI was bumped by an Operator while raising power with the Power Schedule Switch It was determined that during the previous start-up the Master Control Switch was not placed fully in the ON detent position. The Master Control Switch was checked for proper engagement in all detent positions and the reactor was subsequently returned to operation On September 24, a reactor scram was automatically initiated by PT-944 (Reactor Loop Low Pressure) when the pressure on the discharge side of the core dropped below the scram set point during a scheduled reduction in power.

Power was being lowered to allow entry into Mechanical Equipment Room 114 to reposition the secondary coolant system bypass valve for S-l, the primary coolant system temperature control valve, which had been mis-positioned after corrective maintenance. With the bypass open, valve S-1 could not keep up with the temperature drop associated with the power reduction resulting in reactor loop pressure dropping below the scram set point Valve S-l bypass was repositioned, positions of the valves involved in the corrective maintenance were verified, the primary coolant system was restarted and the reactor was subsequently returned to operation.

On September 24, a deviation from Technical Specification 3.5 a occurred when a failure of the containment airlock door control circuit allowed the outer airlock door to cycle open while the inner airlock door was open resulting in a loss of Containment Integrity. Master Control Switch IS1 was immediately placed in the OFF position placing the reactor in a secured condition. It was determined that pressure switch B set point had drifted after installation. A new pressure switch was bench tested and installed. The door was cycled several times to verify proper operation.

The reactor was subsequently returned to operation. As a corrective action for repeated airlock door failures, all pressure switches associated with the airlock doors, both installed and spare, were checked. Licensee Event Report No. 02-04, providing a description of these events 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 91-2, Addendum 1, "Place Nitrogen Station on Emergency Lighting"; completing Modification Record 01-3, Addendum 1, "Replacement of Temperature Element 980A/B Meter Relay Units"; and loading new pool de-ionization bed 'B.'

October 2002 The reactor operated continuously in October with the following exceptions five shutdowns for scheduled maintenance and refueling, and two unscheduled shutdowns. Received notification from the NRC that five new Reactor Operator licenses and one new Senior Reactor Operator license had been issued.

On October 18, a manual scram was initiated when the outer airlock door south trolley hanger broke. Master Control Switch 1S1 was placed to the OFF position securing the reactor for airlock door repairs. It was determined the south trolley hanger had broken causing the door to be held up by only the north trolley. The pin, hanger and door spring were replaced. The airlock was tested for proper operation and the reactor was subsequently returned to operation.

On October 19, a Rod Not In Contact With Magnet Rod Run-In was automatically initiated when control blade 'B' anvil separated from its magnet during rod shimming. Blade 'B' Full In light was lit so the control room operator initiated a manual scram and the reactor was shutdown. It was determined that control blade 'B' had disengaged from its magnet when the Control Blade Selector Switch had been moved from position "A" to position "B" and the Control Blade Operate Switch moved to the Out position Control Rod "B" Drive Mechanism and magnet were inspected and tested for proper operation. A drop time test (CP-10) was performed satisfactorily on control blade 1-6

'B.' The reactor was subsequently refueled and returned to operation.

Major maintenance items for the month included: installing a new Regulating Blade Position Indication System in accordance with Modification Records 96-02 and 96-02, Addendum 1; replacing the lower springs on both the inner and outer air lock doors; replacing the outer airlock door south trolley pin, hanger, and door spring; and replacing Facility Ventilation Supply Fan SF-1 inboard fan bearing November 2002 The reactor operated continuously in November with the following exceptions: two shutdowns for scheduled maintenance and!or refueling, and four unscheduled shutdowns.

On November 10, a reactor scram was automatically initiated when the flexible motor-to-pump coupling on primary coolant system pump P501A failed resulting in a reduction in primary coolant system flow. The pump and motor were inspected and it was determined the failure was most likely due to a defective coupling flex element. The coupling flex element was replaced and P501A was tested satisfactorily. The reactor was refueled and returned to operation.

On November 10, a rod run-in was automatically initiated Investigation revealed bad contacts in the rod run-in circuit. The contacts were burnished, all connections tightened and all relays inspected and tested for operability. All scram and rod run-in signals were cleared and all relays reset normally. The failure did not recur. The reactor was subsequently returned to operation.

On November 24, a reactor scram was automatically initiated when the flexible motor-to-pump coupling on primary coolant system pump P501A failed resulting in a reduction m primary coolant system flow. The pump and motor were thoroughly inspected. A small amount of play between the shaft and pump impeller was found. The coupling flex element and pump internals were replaced and P501A was tested satisfactorily. The reactor was subsequently refueled and returned to operation. The pump's internal assembly will be overhauled.

On November 25, a reactor scram was automatically initiated when the flexible motor-to-pump coupling on primary coolant system pump P501A failed resulting in a reduction in primary coolant system flow. The pump and motor were inspected and it was determined the failure was due to a misalignment between the pump and motor. The coupling flex element was replaced and the motor re-shimmed. The realignment was verified and the pump was tested satisfactorily. The reactor was subsequently returned to operation.

Major maintenance items for the month included: replacing P501A (primary coolant system pump) coupling flex element (three times) and pump; burnishing rod run-in circuit contacts; placing the NMC Model RAK stack monitor out of service indefinitely for repairs; and refurbishing P-501B (primary coolant system pump) motor contacts.

December 2002 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On December 16, a reactor scram was manually initiated during a reactor startup to perform RTP-17B (Flux Trap 1-7

Loading Reactivity Worth) when the measured reactivity of the flux trap sample holder and samples appeared to be in excess of the limit stated in Technical Specification 3.1.h. The flux trap sample loading was verified to be correct and RTP-1 1D (Differential Control Rod Reactivity Worth) was performed on control blade 'B' to verify its worth because it was the blade being used to determine the flux trap reactivity. RTP-1 1D revealed a change in control blade

'B' worth since its installation as a new blade in May of 2002. This change is due to normal bum up of the control blade while in operation. The reactivity worth of the flux trap was re-measured using the corrected control blade 'B' rod worth and it was determined that the flux trap reactivity was well withm Technical Specification lihmts. The reactor was subsequently returned to full power operation Major maintenance items for the month included: completing the biennial change out of Control Blade "D" Offset Mechanism.

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SECTION II MURR PROCEDURES January 1, 2002 through December 31, 2002 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 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.

As part of the ongoing process of revising and reformatting Reactor Operations Procedures in accordance with the MURR Procedure Writer's Guide, 75 new and revised procedures were issued. The majority of these procedural changes were strictly format or editorial in nature with the following significant exceptions:

AP-RO-100 MURR Equipment Tag Out AP-RO-110 Conduct of Operations AP-RO-015 Modification Records OP-RO-250 Fuel Handling and RP-RO-100 Fuel Movement All mechanical system operating procedures:

The valve line-ups in these procedures were modified to add the requirement for Independent Verification.

B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES As required by 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. One revision was issued, Revision No. 34, dated June 24, 2002, which updated Figure FEP-1, "Evacuation Routes, Research Reactor Facility," because of the addition of the MURR Industrial Building.

As part of the ongoing effort to rewrite and reformat MURR procedures in accordance with the MURR Procedure Writer's Guide, draft revisions of the Emergency Plan Implementing Procedures are currently being reviewed by Operations and Health Physics Staff. After review by staff members, the draft procedures will be reviewed by the Reactor Procedure Review Subcommittee for approval. Prior to the issuance of the approved procedures, training will be conducted for Facility Emergency Orgamzation members and Non-Facility Emergency Organization members.

II-1

C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES As required by MUJRR Technical Specifications, the Reactor Health Physics Manager reviewed vITURR procedures for radioactive materials handling, shipping, and preparation for shipping of byproduct materials. As part of the ongoing process of revising and reformatting the procedures in accordance with the MURR Procedure Writer's Guide, 81 new and revised procedures were issued The majority of these procedural changes were strictly format or editorial in nature. However, several procedures were made obsolete by the process.

The following HP SOPs were deleted in the year 2002, either obsolete or replaced by new format procedures, as noted:

I. ADMINISTRATIVE CONTROL HP/I-1 Request for Radiation Safety Evaluation Obsolete HP/I-5 MURR Indoctrination Traimng Program Replaced with AP-HP-l117 HP/I-8 Performance of Quarterly Review of Materials License Projects Replaced with AP-HP-122 II. PERSONNEL MONITORING HP/II-3 Report of Personnel Contarmnation Replaced with RP-HP-120 HP/II-5 Tritium Bioassay Replaced with OP-HP-220 HP/II-6 Containment Ar-41 Grab Sample Procedure Replaced with OP-HP-222 III. INSTRUMENTATION HP/IlI-I Calibration of Radiation Survey Instruments Replaced with IC-HP-300 HP/III-2 Self-Reading Dosimeter Calibration Replaced with IC-HP-305 HP/III-3 Calibration of Stack Particulate Channel- Eberline PING 1A Replaced with IC-HP-3 10 HP/III-4 Calibration of Stack Iodine Channel. Eberlme PING IA Replaced with IC-HP-311 HP/III-5 Calibration of Stack Gas Channel: Eberlme PING IA Replaced with IC-HP-312 HP/III-6 Stack Monitor Preventive Maintenance: NMC Model RAK Replaced with RM-HP-100 HP/III-7 Calibration of Stack Monitor System: NMC Model RAK Replaced with IC-HP-318 HP/III-8 Calibration of Stack Particulate Channel. NMC Model RAK Replaced with IC-HP-319 HP/III-9 Calibration of Stack Iodine Channel- NMC Model RAK Replaced with IC-HP-320 HP/III-10 Calibration of Stack Gas Channel- NMC Model RAK Replaced with IC-HP-321 HP/III-i 1 Calibration and Operation of Canberra Model 2404 Replaced with IC-HP-330 Alpha/Beta/Gamma System and IC-HP-347 HP/III-12 Calibration and Operation of Tennelec LB-5 100 Alpha/Beta Replaced with IC-HP-331 and OP-HP-227 HP/III-13 Calibration and Operation of Baird Polyspec Obsolete HP/III-14 Calibration and Operation of Eberline BC-4 Beta Counter or Replaced with IC-HP-333 Eberline SAC-4 Alpha Counter HP/II- 15 Portal Monitor Calibration/Optimization Replaced with IC-HP-335 HP/II- 16 Portal Monitor Figure of Merit Functional Test Replaced with IC-HP-337 HP/II-22 Quench Curve on the Packard 2300 TR Liquid Obsolete Scintillation Counter HP/lIl-24 Preparing Europium Sources Replaced with OP-HP-600 HP/III-25 Calibration of Sodium Iodide Detector For Counting Air Replaced with IC-HP-343 Sample Tanks Containing Ar-41 11-2

IV. HEALTH PHYSICS APPLICATIONS HP/IV-4 MURR Hot Cell Operation Replaced with AP-HP-129 HP/IV-5 Cobalt-60 Facility Safety Checks Obsolete HP/IV-6 Co-60 Facility Pool Water Analysis Obsolete HP/IV-7 Sealed Source Leak Test Procedure Replaced with SV-HP-105 HIP/IV-8 Cleaning Returned Shipping Containers Replaced with RP-HP-1 10 HP/IV-9 Can Melting Procedure Obsolete IP/IV-l0 Returning Lead Pigs to Service at MURR Replaced with RP-HP-1 15 V. ENVIRONMENTAL MONITORING HPN-1 Environmental Sampling Replaced with SV-HP-110 and OP-HP-221 HP/V-2 Analysis of Radioactivity in Environmental Samples Replaced with OP-HP-221 HP/V-3 Changing Stack Monitor Filters: Eberline Ping 1A, Serial Obsolete Number 257 HP/V-4 Changing Stack Monitor Filters: NMC Model RAK Replaced with OP-HP-351 HP/V-5 Analysis of Particulate and Charcoal Filters Replaced with OP-HP-352 HP/V-6 Tritium Monitoring of Stack Air Exhaust Replaced with SV-I-P-1 15 HP/V-7 Waste Tank Analysis Replaced with OP-BP-353 HP/V-8 Secondary and Sump Water Analysis Replaced with SV-HP-1 17 IIPIV-9 Survey of Items for Unrestricted Release Replaced with SV-1-IP-1 19 HP/V-10 Stack Ar-41 Grab Sample Procedure Replaced with SV-HP-121 VI. WVASTE MANAGEMENT HP/VI-1 Experimenters Waste Disposal Procedure Replaced with WM-HP-100 HP/VI-2 Direct Barrel Compaction Operation Replaced with WM-HP- 105 VII. REACTOR OPERATIONS SUPPORT HP/VII-1 Room 114 Unscheduled Entry Replaced with RP-HP-135 HP/VII-2 Handling Radioactive Material in MURR Pool Replaced with RP-HP-137 HP/VII-3 Health Physics Monitoring of Beam Ports for Reactor Start-up Replaced with RP-HP- 139 HP/VII-4 Pool and Primary Water Analysis Replaced with OP-RO-420 HP/VII-5 Spent Fuel Shipping Cask Analysis Replaced with OP-HP-224 VIII. HEALTH PHYSICS EMERGENCY PROCEDURES HP/VflI-1 Air Sampling During Reactor Emergency Replaced with SV-BP-130 HP/VIII-2 Evaluation of Exhaust Gas Stack Monitor Filters Replaced with OP-HP-505 in an Emergency HP/VIII-3 Remote Sampling of Containment Air Replaced with SV-HP-135 II-3

SECTION III REVISIONS TO THE HAZARDS SU-MMARY REPORT January 1, 2002 through December 31, 2002 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 and 1989-90 Reactor Operations Annual Reports).

Add The following to the end of the list:

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

Add- The following to Table 7.1 under Staff Stations:

"Room 210 Laboratory Building Outer Corridor Room 285 Containment Building Lobby" Original HSR, page 9-8, Section 9.2, Table 9.2 (as revised by the 1981-82, 1985-86, 1995, 2000, and 2001 Reactor Operations Annual Reports):

Delete: "31 Square Root Converter (EP 919A) -Primary Flow "A" Loop" Replace with: "31 Square Root Transmitter (EP 919A) -Primary Flow "A" Loop" Delete: "33 Square Root Converter (EP 919F) - Pool Flow "B" Loop" Replace with- "33 Square Root Transmitter (EP 919F) - Pool Flow "B" Loop" Delete: "35 Summer (EP 954) - Primary Coolant Differential Temperature" Replace with- "35 Adder-Subtractor Module (EP 954) - Primary Coolant Differential Temperature" Delete: "38 Summer (EP 952) - Pool Coolant Differential Temperature" Replace with: "38 Adder-Subtractor Module (EP 952) - Pool Coolant Differential Temperature" Delete: "43 Square Root Converter (EP 919E) -Primary Flow "B" Loop" Replace with: "43 Square Root Transmitter (EP 919E) - Primary Flow "B" Loop" Delete: "45 Square Root Converter (EP 919B) - Pool Flow "A" Loop" Replace with: "45 Square Root Transmitter (EP 919B) -Pool Flow "A" Loop" III-1

Original HSR, page 10-7, Section 10.6, paragraph 3, sentence 1 (as revised by the 1994 Reactor Operations Annual Report):

Delete- "A source check of the radiation monitoring modules which are connected to the Safety System will be performed at least once per week to ensure proper operation" Replace with: "A source check of the radiation monitoring modules which are connected to the Safety System will be performed at least monthly to ensure proper operation."

Original HSR, page 10-8, Section 10.7, Item (1) (as revised by the 1994 Reactor Operations Annual Report):

Delete Entire item, which states:

"(1) A yellow tag will be placed on the switch or controller prior to maintenance activities on a particular piece of equipment in which damage to equipment may occur if the switch is activated. The tag will be numbered and contain information as to the date it was initiated, the piece of equipment involved, and the potential hazard that exists."

Original HSR, page 10-8, Section 10.7, Item (2) (as revised by the 1994 Reactor Operations Annual Report):

Delete: Entire item, which states.

"(2) A red tag will be placed on the switch or controller of a piece of equipment to signify that operation of the equipment presents a hazard to personal. The tag will be numbered and contain information as to the date it was imtiated, the piece of equipment involved, and the potential hazard that exists."

Replace with" "(1) A danger tag will be placed on a piece of equipment to signify that operation of the equipment presents a hazard to personnel and/or potential damage to the equipment The tag will be numbered and contain information as to the date it was imtiated, the piece of equipment involved, and the reason for the tag."

Original HSR, page 10-8, Section 10.7, Items (3), (4), and (5) (as revised by the 1994 Reactor Operations Annual Report):

Renumber: Items (3), (4), and (5) to (2), (3), and (4), respectively.

Original HSR, page 12-2, Section 12.1, last paragraph, sentence 1 (as revised by the 1981-82 Reactor Operations Annual Report)

Delete: "Associate Vice President Academic Affairs" Replace with- "Office of the Provost" HII-2

Original IISR, page 12-2, Section 12.1, last paragraph, sentence 2 (as revised by the 1981-82 Reactor Operations Annual Report):

Delete: "The Associate Vice President Academic Affairs reports to the President of the University."

Replace with: "The Office of the Provost reports to the Chancellor, UM-Columbia."

Original RSR, page 12-2, Section 12.2.1, paragraph 1, sentence 1 (as revised by the 19981-82 Reactor Operations Annual Report):

Delete- "Associate Vice President Academic Affairs" Replace with- "Office of the Provost" Original HSR, page 12-4, Section 12.2.3 (as revised by the 1996 Reactor Operations Annual Report):

Delete: Last two sentences, which state, "He will be assisted in the performance of these duties by the Associate Reactor Supervisor. He will be assisted in the performance of these duties by the Operations Engineer and Reactor Shift Supervisors."

Replace with: "He will be assisted in the performance of these duties by the Assistant Reactor Managers and the Lead Senior Reactor Operators."

Original IISR, Figure 5.1, Piping & Instrument Diagram (as revised by the 1972-73, 1973-1974, 1994, 1996, and 2001 Reactor Operations Annual Reports):

Replace with: Updated Figure 5.1, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet 1 of 1, dated 8/8/02)

Original I-ISR, Figure 9.4, Safety System 10 MW (as revised by the 1995 and 2001 Reactor Operations Annual Reports):

Replace with: Updated Figure 9.4, Safety System (MURR Dwg No. 139, Sheet 1 of 1, dated 10/10/02) 111-3

ADDENDUMI 1 - HAZARDS

SUMMARY

REPORT (FEBRUARY 1966)

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

Add: The following bolded words to the first sentence: ". .intercommunications system, nitrogen station, and the evacuation alarms" HSR, Addendum 1, page 25a, Figure 3.8.1, Electrical Distribution Block Diagram (as revised by the 1989-90 Reactor Operations Annual Report):

Replace with: Updated Figure 3 8 1, Electrical Distribution Block Diagram (MIURR Dwg No. 2272, Sheet 1 of 1, dated 12/20/02)

HSR, Addendum 1, page 103, Figure 3.22.1, Diagram of Laboratory and Containment Building Ventilation System (as revised by 1995 Reactor Operations Annual Report):

Replace wit: Updated Figure 3 22.1, Diagram of Laboratory and Containment Building Ventilation System (IvIURR Dwg No. 2420, Sheet 1 of 1, dated 12/19/02) 111-4

ADDENDUM 3 - HAZARDS

SUMMARY

REPORT (AUGUST 1972)

HSR, Addendum 3, page 32, Section 2.5.3.4, paragraph 1:

Delete: The word: "converter."

Replace with: "transmitter" HSR, Addendum 3, page 33, Section 2.5.3.5, paragraphs I and 2:

Delete: The word: "converter."

Replace with: "transmitter" HSR, Addendum 3, page 34, Section 2.5.3.6, paragraph 3:

Delete: Entire paragraph, which states:

"Flow Integrators EP No's 919E and 919F Two flow integrators (square root converter), 10-50 MADC input, 10-50 MADC output, rack mounting, accuracy +/- 0.5% of full scale at 20% output, type 565 GE/MAC, Cat. No. 50-565100AAAC1, with GE Type 1952K40 cable and fuse."

Replace with: "Flow Integrators EP No.'s 919E and 919F Two flow integrators (square root transmitters), 10-50 MADC input, 10-50 MADC output, rack mounting, accuracy +/- 0.5% of full scale at 20%

output."

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

Replace with: Updated Figure 2.2, Secondary Cooling System (MURR Dwg No. 502, Sheet 1 of 1, dated 8/6/02)

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

Replace with: Updated Figure 2.3.a, Electrical Distribution (MTURR Dwg No. 522, Sheet 1 of 2, dated 6/13/02)

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

Replace with: Updated Figure 2.3.b, Electrical Distribution (MURR Dwg No. 522, Sheet 2 of 2, dated 11/22/02)

III-5

ADDENDUM 4 - HAZARDS

SUMMARY

REPORT (OCTOBER 1973)

HSR, Addendum 4, Figure A.1, Safety System (as revised by the 1995 and 2001 Reactor Operations Annual Reports):

Replace with: Updated Figure A.1, Safety System (MURR Dwg No 139, Sheet 1 of 1, dated 10/10/02)

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

Replace with: Updated Figure A.2, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet I of 1, dated 8/8/02)

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

Replace with: Updated Figure A.6, Process Instrumentation Control & Interlock (MIURR Dwg No. 41, Sheet 2 of 4, dated 10/10/02)

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

Replace with: Updated Figure A.7, Annunciator Control 10 MW (MURR Dwg No. 138, Sheet 1 of 2, dated 10/17/02)

HSR, Addendum 4, Figure A.11, Schematic Diagram of Laboratory and Containment Building Ventilation System (as revised by the 1995 Reactor Operations Annual Report):

Replace with Updated Figure A. 11, Schematic Diagram of Laboratory and Containment Building Ventilation System (MURR Dwg No 1125, Sheet I of 2, dated 12/19/02) 111-6

ADDENDUM 5 - HAZARDS

SUMMARY

REPORT (JANUARY 1974)

HSR, Addendum 5, page 12, Section 2.4.1 (as revised by the 1989-90 Reactor Operations Annual Report):

Add to end of list: "(14) Nitrogen Station The loss of electrical power to the solenoid-operated valves of the nitrogen station would prevent the nitrogen station from being able to supply nitrogen gas to the pressurizer. Since the reactor is shutdown due to the loss of electrical power and decay heat is being removed by the in-pool heat exchanger, the loss of the nitrogen station would have no effect on the status of the reactor."

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

Replace with" Updated Figure 2.1, Electrical Distribution (MURR Dwg No. 522, Sheet 1 of 2, dated 6/13/02) 111-7

SECTION IV PLANT AND SYSTEM MODIFICATION January 1, 2002 through December 31, 2002 For each modification described below, MURR has on file the safety evaluation as well as documentation of review in accordance with 10 CFR 50.59.

Modification 91-2, Addendum 1:

Place Nitrogen Station on Emergency Lighting This addendum to modification record 91-2, "Nitrogen Station Move to Inner Hallway," documents the transfer of electrical supply power for the nitrogen station control system from Lighting Panel No. 14 to Emergency Lighting Panel No. 2. Transferring supply power to a more reliable source provides the operators with additional time to trouble shoot a loss of the 120/280V Distribution Center before the reactor would need to be shutdown.

Modification 96-2:

Rod Position Indication Chance from Veeder-Root to Encoder Type This modification record documents the replacement of the mechanical Veeder-Root Control Rod Position Indication (RPI) system with an electronic, absolute encoder-based system Because of its age and the inability to purchase replacement parts, the Veeder-Root RPI system had become obsolete. Additionally, the mean time between failures (MTBF) for the new system is 3,100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />; on average, a failure every 3,100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of operation. The old system had a MTBF of only 672 hours0.00778 days <br />0.187 hours <br />0.00111 weeks <br />2.55696e-4 months <br />.

Modification 96-2, Addendum 1:

Replace Existing Rod Position Indication Indication (RPWD Encoder Sprocket with a Shafted Sprocket This addendum to modification record 96-2, "Rod Position Indication Change from Veeder-Root to Encoder Type," documents the changes performed to the control drive RPI encoder/chain assemblies. The original design was prone to periodic failure from the indicating chain coming off of the sprocket, wrapping around the encoder shaft, and bending it. The new design provides greater vertical alignment and support of the sprocket thereby minimizing the potential for failure.

Modification 01-2, Addendum 1:

Addition of Two (2) Staff Stations to the Reactor Facility Intercommunication and Paging System This addendum to modification record 01-2, "Installation of a New Reactor Facility Intercommunication and Paging System," documents the installation of two additional Staff Stations to the Intercommunication and Paging System. The new Staff Stations, installed at locations that have portal monitors, provide personnel the ability to contact the control room for assistance in case of personnel contamination without having to leave the area, thereby minimizing the potential of spreading the contamination. This modification was performed in response to Corrective Action Program (CAP) entry No. 02-0019.

Modification 01-3, Addendum 1:

Replacement of Temperature Element 980A/B Meter Relay Units This addendum to modification record 01-3, "Replacement of the 980A/B Temperature Transmitters, Meter Relay Units, and RTDs," documents the replacement of the Simpson Model 3324AXIXA Meter Relay IV-1

Units for temperature elements 980A and 980B with Beede Model MR4s. The Simpson Meter Relay Units were proven to be susceptible to Radio Frequency Interference (RFI), which caused severe meter deflections. The Beede Meter Relay Units are different in that the internal amplifier does not drive the meter indication, thus they are not vulnerable to RFI. This modification was performed m response to Corrective Action Program (CAP) entry No. 02-0021.

Modification 01-4:

Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation MV/I Transmitters, Differential Temperature Summers, Square Root Converters, and Dual Alarm Units This modification record was used as the initiating document for the replacement of GE/MAC process instrumentation with Moore Industries instrumentation. In order to simplify the replacement scheduling and post maintenance testing, the modification was implemented in seven (7) phases with each phase an addendum to this modification record. All phases are now complete.

Modification 01-4, Addendum 3:

Replace the Current General Electric Measurement and Control Type 563 Pool Coolant System Differential Temperature Summer with a New Moore Industries Adder-Subtractor Module This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation MV/I Transmitters, Differential Temperature Summers, Square Root Converters, and Dual Alarm Units," documents the replacement of the GE/MAC Type 563 differential temperature summer for the pool coolant system temperature elements 901C and 901D.

Because of age and the inability to purchase replacement parts, the GE/MAC differential temperature summers had become obsolete.

Modification 01-4, Addendum 5:

Replace the Current General Electric Measurement and Control Type 563 Pnmary Coolant System Differential Temperature Summer with a New Moore Industries Adder-Subtractor Module This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation MV/I Transmitters, Differential Temperature Summers, Square Root Converters, and Dual Alarm Units," documents the replacement of the GE/MAC Type 563 differential temperature summer for the primary coolant system temperature elements 901A and 901B.

Because of age and the inability to purchase replacement parts, the GE/MAC differential temperature summers had become obsolete.

Modification 01-4, Addendum 6:

Replace the General Electric Measurement and Control Type 565 Primary Coolant System Flow Square Root Converters with Moore Industries Square Root Transmitters This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation MV/I Transmitters, Differential Temperature Summers, Square Root Converters, and Dual Alarm Units," documents the replacement of the GE/MAC Type 565 square root converters for the primary coolant system flow transmitters 912A and 912E. Because of age and the inability to purchase replacement parts, the GE/MAC square root converters had become obsolete.

IV-2

Modification 01-4, Addendum 7:

Replace the General Electric Measurement and Control Type 565 Pool Coolant System Flow Square Root Converters with Moore Industries Square Root Transmitters This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation MV/I Transmitters, Differential Temperature Summers, Square Root Converters, and Dual Alarm Units," documents the replacement of the GE/MAC Type 565 square root converters for the pool coolant system flow transmitters 912D and 912F. Because of age and the inability to purchase replacement parts, the GE/MAC square root converters had become obsolete.

Modification 01-6:

Replace the 529 Series Solenoid-Operated Poppet Valves with an Updated Model This modification record documents the replacement of the solenoid-operated poppet valves (also know as the 529 Series valves), which control supply air to the air-operated valves of the reactor plant, with functionally equivalent Schrader-Bellows Model 3/8-inch NC-N355-41-04853 valves. The 529 Series valves had become obsolete and their repair kits were no longer available.

Modification 01-9:

Installation of Emergency Lighting Panel No. 1 This modification record documents the addition of a lighting panel to the Emergency Electrical Distribution System. The addition of Emergency Lighting Panel (ELP) No. 1 allowed the transfer of critical, non-reactor related loads from the Uninterruptible Power Supply System to Emergency Power where ample load capacity exists. ELP-1 now supplies electrical power to the detectors of the radiation counting systems located in the laboratories in the north half of the Laboratory Building.

Modification 01-9, Addendum 1:

Relocation and Replacement of Emergency Lighting Panel No. 2 This addendum to modification record 01-9, "Installation of Emergency Lighting Panel No. 1," documents the relocation of Emergency Lighting Panel (ELP) No. 2 from the basement to the grade level of the Laboratory Building. ELP-2 was originally installed to support an experimental program that was once performed in Room 111. The programming needs of this room no longer require emergency electrical power. ELP-2 now supplies electrical power to a new network server, as well as other critical, non-reactor related loads located in the laboratories and offices in the south half of the Laboratory Building.

Modification 01-10:

Installation of Glove Boxes on the Reactor Containment Building Beamport Floor This modification record documents the relocation of eight (8) glove boxes from the Laboratory Building to the below grade level (Beamport Floor) of the Reactor Containment Building. This modification was performed to satisfy the current programming needs of the facility.

Modification 01-11:

Replace K Relays with an Improved Design This modification record documents the replacement of the relay sockets for nine (9) K-Relays; relays that are a part of the reactor safety and rod run-in systems and provide scram and rod run-in signals to the input strings of these systems as well as the Annunciator System. Due to excessive wear caused by repeated replacement, the relay sockets had become problematic, causing intermittent contact during and after Compliance Testing. The new relay sockets are very similar in design to the existing sockets; however, the pinholes are of an improved design providing better insertion guidance.

IV-3

Miodification 01-12:

Installation of a Security/Mail Trailer and Guard Gate for the MURR Facility This modification record documents the installation of a Security/Mail Trailer and guard gate at the south entrance to the MURR facility site.

Modification 01-14:

Installation of a 300 kVA Transformer This modification record documents the addition of a 300 kVA Transformer to the facility's Normal Electrical Power System. Installation of the transformer increased the facility's overall 120/208V load capacity while reducing the electrical load on the 120/208V Distribution Center The 120/208V Distribution Center is was operating near its load capacity Modification 02-1:

Replacement and Upgrade of Substation "B" 1000 kVA Transformer This modification record documents the replacement and upgrade of Substation "B" 1000 kVA transformer, which was located in the Laboratory Building, with a new 2000 kVA Transformer. The new transformer is situated on a concrete pad that is located at the southwest comer of the Laboratory Building.

In addition to supplying electrical power to Substation "B," the transformer supplies 480-volt power to a 200-amp distribution panel that supports the MURR Industrial Building.

IV-4

SECTION V NEW TESTS AND EXPERIMENTS January 1, 2002 through December 31, 2002 New experimental programs developed during this period are as follows:

RUR 402, Indium Metal

Description:

This RUR authorized irradiation of Indium Metal for use in research and development activities.

RUR 403, Ytterbium Nitrate

Description:

This RUR authorized irradiation of Ytterbium Nitrate for developing research radioisotopes.

RUR 404, Holmium Metal

Description:

The RUR Authorized irradiation of Holmium Metal for developing research radioisotopes.

RUR 405, Silicon Nitride

Description:

This RUR authorized irradiation of Silicon Nitride semi-conductor material for research activities RUR 305, Ruthenium Dioxide Description. This RUR was revised to authorize Ruthemum Dioxide as well as Ruthenium Metal for developing research radioisotopes.

RUR 219, Magnesium B oride

Description:

This RUR authorized irradiation of Magnesium Boride, a superconductor material, for research activities.

Each of these experiments has a written safety evaluation on file, which includes a 10 CRR 50.59 Screen to assure that the experiment is safe and within limits of the Technical Specifications.

V-1

SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2002 through December 31, 2002 Inspections: There was one NRC inspection reviewing SNM activities. All records and activities were found to be in compliance with NRC rules and regulations. No violations were noted.

Reactor Characteristic Measurements: Sixty-Seven refueling evolutions were completed in 2002.

Excess reactivity verification was performed for each refueling. The largest excess measured reactivity was 3.79%. MURR Technical Specification 3. l(f) requires that the excess reactivity be less than 9.8%.

Fourteen (14) reactivity measurements were made to measure the sample loading worth of all samples loaded in the flux trap region.

Twelve (12) measurements were made to determine the reactivity worth of several samples that are irradiated either in the flux trap region or in the graphite irradiation positions and that of the sample holders.

Five Differential blade-worth measurements, one Regulating blade-worth measurement and one Primary temperature coefficient measurement were also performed.

VI-1

SECTION VII RADIOACTIVE EFFLUENT January 1, 2002 through December 31, 2002 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2002 through December 31, 2002 Descending Order of Activity Released for Nuclide Totals > 1.000E-5 Ci Nuclide Activity (Ci)

H-3 1.763E-01 S-35 2.023E-03 Co-60 1.930E-03 Lu-177 7.620E-04 Cu-64 3.730E-04 Zn-65 2.5 1OE-04 Ca-45 2.080E-04 Mn-54 1.390E-04 P-32 8.800E-05 Lu-177m 8.300E-05 Ho-166 4.200E-05 Sm-153 3.700E-05 Gd-159 2.200E-05 Ga-72 2.100E-05 Ag-110m 1.700E-05 Cu-67 1.700E-05 Total H-3 1.763E-01 Total Other 5.973E-03 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage" VII-1

TABLE 2 STACK EFFLUENT January 1, 2002 through December 31, 2002 Ordered by % Techmcal Specification (TS) Limit Isotope Average Concentration liCi/ml Total Release Ci TS Limit Multiplier  % TS Ar-41 2.544E-06 1.18E+03 350 72.6874 Co-60 1.112E-13 5.14E-05 1 02224 Ho-166m 1.227E-14 5.67E-06 1 0.1363 1-131 1.648E-13 7.62E-05 1 0.0824 Ce-144 1.369E-14 6.33E-06 1 0.0685 Hg-203 4.218E-13 1.95E-04 1 0.0422 H-3 1.359E-08 6.28E+00 350 0.0388 1-125 3.829E-14 1.77E-05 1 0.0128 Cd-109 4.370E-15 2.02E-06 1 0.0062 W-188 1.021E-13 4.72E-05 1 0.0051 Cs-137 4.867E-15 2.25E-06 1 0.0024 Sc-46 6.685E-15 3.09E-06 1 0.0022 Hf-181 1.240E-14 5.73E-06 1 0.0021 Ce-141 1.443E-14 6.67E-06 1 0.0018 Zn-65 6.490E-15 3.OOE-06 1 0.0016 Fe-59 7.074E-15 3.27E-06 1 0.0014 Co-58 6.425E-15 2.97E-06 1 0.0006 Os-191 1.198E-14 5.54E-06 1 0.0006 1-133 1.573E-12 7.27E-04 350 0.0004 Zr-95 1.616E-15 7.47E-07 1 0.0004 Pa-233 2.856E-15 1.32E-06 1 0.0004 Br-82 5.062E-12 2.34E-03 350 0.0003 Eu-155 5.062E-16 2.34E-07 1 0.0003 Ir-192 7.528E-16 3.48E-07 1 0.0003 Sn-113 1.884E-15 8.71E-07 1 0.0002 As-77 5.214E-12 2.41E-03 350 0.0002 Sr-85 3.505E-15 1.62E-06 1 0.0002 Ce-139 1.196E-15 5.53E-07 1 0.0001 Se-75 8.048E-16 3.72E-07 1 0.0001 Mn-54 9.908E-16 4.58E-07 1 0.0001 Ru-103 6.641E-16 3.07E-07 1 0.0001 Isotopes observed at < 0.0001% TS limit are not listed Stack Flow Rate = 30,000 cfm Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, License R-103 Technical Specifications.

VII-2

SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2002 through December 31, 2002 Environmental samples are collected two times per year at eight locations and analyzed for radioactivity. Soil and vegetation samples are taken at each location. Water samples are taken at three of the eight locations. Analytical results are shown in Tables 1 and 2.

Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2002. All doses are about 50 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 transit. The environmental monitoring program confirms that no environmental impact exists from the operation of the MURR facility.

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

TABLE 1 Summary of Environmental Set 61 May 2002 Detection Limits*

Matrix Al pha Beta Gamma Tritium Water 0.98 pCi/L 3.94 pCifL 216.68 pCi/L 1.13 pCiimL of sample Soil 0.98 pCi/g 3.94 pCilg 1.63 pCilg N/A Vegetation 1.97 pCi/g 7.88 pCi/g 3.67 pCi/g 1.13 pCi/mL of distillate

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

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

10V61 < 1.97 24.95 < 3.67 < 1.13 1V61 < 1.97 1633 < 3.67 < 1.13 2V61 < 1.97 9.51 <3 67 < 1.13 3V61 < 1.97 < 7.88 < 3.67 1.38 4V61 < 1.97 19.20 < 3.67 < 1.13 5V61 < 1.97 17.77 < 3.67 2.98 6V61 < 1.97 30.33 < 3.67 1.56 7V61 < 1.97 <7.88 < 3.67 < 1.13 VIII-1

TABLE 1 (Cont'd)

Summary of Environmental Set 61 May 2002 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 10S61 <0.98 12.92 6 16 1S61 <0.98 14.72 7 63 2S61 <098 12.02 6.86 3S61 <098 14.54 6.96 4S61 <098 9.51 6.29 5S61 < 0.98 8 26 8.19 6S61 < 0.98 12.38 7.66 7S61 <098 1131 5.19 Activity Levels - Water Sam*ple Alpha (pCi/L) Beta (pCi/L) Gamma (pCiIL) H-3 (pCi/mL) 10W61 <0 98 < 3.94 < 216.68 3.00 4W61 <0 98 5.83 < 216.68 < 1.13 6W61 <098 < 3.94 < 216.68 3 20 TABLE 2 Summary of Environmental Set 62 November 2002 Detection Limits*

Matrx Alpha Beta Gamma Tntium Water 0.81 pCifL 3 89 pCI/L 210.27 pCI.L 1.41 pCi/mL of sample Soil 0.81 pCi/g 3.89 pCl/g 1.26 pCi/g N/A Vegetation 1.62 pCi/g 7 78 pCi/g 3 53 pCi/g 1.41 pCi/mL of distillate

• Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights VIII-2

TABLE 2 (Cont'd)

Summary of Environmental Set 62 November 2002 Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL) 10V62 < 1.62 14.60 <3.53 < 1.41 1V62 < 1.62 12.08 < 3.53 < 1.41 2V62 < 1.62 8.83 < 3.53 < 1.41 3V62 < 1.62 22.17 < 3.53 < 1.41 4V62 < 1.62 22.89 < 3.53 < 1.41 5V62 < 1.62 10.27 < 3.53 < 1.41 6V62 < 1.62 23.61 < 3.53 < 1.41 7V62 < 1.62 18.93 < 3.53 < 1.41 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCiLg) Gamma (pCilg) 10S62 <0.81 9.91 4.68 1S62 <0.81 1063 4.62 2S62 <0.81 1676 4.98 3S62 <0.81 13.16 6.00 4S62 1.08 <3.89 5.45 5S62 <0.81 9.73 3.56 6S62 <0.81 7.39 4.38 7S62 <0.81 13.34 3.34 Activity Levels - Water Sample Alpha (pCIQL) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 10W62 <0.81 5.23 < 210.27 < 1.41 4W62 1.33 4.87 <210.27 < 1.41 6W62 2.98 6 13 < 210.27 1.41 VIII-3

TABLE 3 Environmental TLD Summary January 1, 2002 through December 31, 2002 Badge Direction Map Distance from 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr Total Number From MURR MURK Stack 2002 2002 2002 2002 (meters) Net mR Net mR Net mR Net mR Net mR 1 Control NIA 04 -02 -26 -22 -46 2 Control NIA -08 12 -28 -57 -81 3 WSW NIA -1.4 -28 -43 -31 -116 4 Spare NIA 9.3 98 -14 -32 145 5 Spare N/A 38 150 -45 -34 109 6 N 34 -3.6 -25 04 -15 -72 7 NE 57 4.3 absent -06 -19 18 8 SW 27 39 37 -3 3 -42 01 9 S 27 204 133 251 211 799 10 NE 149 -32 -57 -41 -49 -179 11 NW 149 -05 -16 -44 -48 -113 12 ENE 301 05 19 absent 03 27 13 NNE 316 13 -07 -31 -18 -43 14 S 156 12 42 17 -15 56 15 S 65 161 253 169 225 808 16 SE 107 -35 -57 -48 -86 -226 17 E 293 -3 3 absent -60 -89 -182 18 NE 476 -01 -30 -59 -86 -17.6 19 NNE 606 -48 -9 9 -94 -129 -37.0 20 NE 907 -5 2 -9 9 -9.8 -11.5 -36.4 21 SE 236 -2 0 -41 -2.8 -5.2 -14.1 22 ESE 168 -3 1 -8 2 -6 2 absent -17.5 23 NW 110 -06 -07 -26 -2.8 -6.7 24 SSW 328 -06 -52 -50 -8.3 -19.1 25 SSW 480 -08 -12 -3 1 -5.0 -101 26 SW 301 -26 -41 45 -5.7 -16.9 27 WSW 141 -48 -85 -90 -100 -32.3 28 WNW 210 00 -01 -40 -2.8 -6.9 29 NW 255 16 17 -2.0 0.7 2.0 30 NNW 328 -18 -24 -14 -04 -6.0 31 NNW 671 15 05 -0.9 -20 -0.9 32 NNW 724 00 -02 -1.7 -30 -4.9 33 E 671 -6 5 absent -5.7 -11 8 -24.0 34 ENE 587 43 -6 8 -73 -100 -284 35 SSE 499 43 -5 5 -68 -87 -253 36 SE 419 -28 43 -37 -79 -187 37 NE 690 -15 -50 absent -9 5 -160 38 NW 556 absent -06 -1 8 -42 -66 39 W 491 -01 09 -31 -17 -40 40 N 514 -03 -31 absent -39 -73 41 NNE 137 -37 45 -78 -81 -241 42 InBuilding N/A 51 165 -27 -0 8 181 43 In Buildmg N/A 39 38 03 44 124 44 Spare N/A 87 110 -27 03 173 45 S 65 -14 -10 -01 -3 5 -60 VIII-4

TABLE 4 Number of Facility Radiation and Contamination Surveys January 1, 2002 through December 31, 2002 Radiation Surface Contamination* Air Samples RWP's January 65 65 31 15 February 58 55 32 5 March 58 58 34 5 April 45 43 32 6 May 60 59 45 11 June 57 57 32 3 July 49 47 34 7 August 70 68 37 6 September 36 37 32 5 October 54 54 38 6 November 60 60 30 8 December 67 67 32 13 TOTALS 679 670 409 90

• 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 Shaun Kelley was hired as a Health Physics Technician in October 2002.

Andrea Shipp resigned as a Health Physicist in August 2002.

Ron Dobey, CHP, was promoted to Health Physics Manager in October 2002 During 2002, MURR shipped 594 cubic feet of low level radioactive waste VIII-5

SECTION IX

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS January 1, 2002 through December 31, 2002

1. Largest single exposure and average exposure are expressed in millirem 2 Minimal exposure for Ring Badges Badges is defined to be gamma <10 mrem; beta < 40 mrem, neutron < 20 mrem.

3. Minimal exposure for Whole Body Badges is defined to be gamma <1 torem; beta <10 rnrem; neutron <20 mRemL

3. ME = Number of monthly units reported with minimal exposure.

4. AME = Number of monthly units reported with exposure above minimal

5. AE = Average mrem reported for all units above minimal.

6. HE = Highest mrem reported for a single unit for the month

7. Dosimetry services except for "Self Reading Dosimeters" are provided by R. S. Landauer, Jr. & Co.,

Dosimeter Types "T" - X, Gamma, Beta, Fast Neutron (Neutrak 144), Thermal Neutron; "P" - X Gamma, Beta, "U" - TLD (1 Chip Ring).

PERMANENT ISSUE BADGES Type "T" and "P" Whole Body Badges (Deep Dose):

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 114 142 131 132 153 101 79 64 84 70 78 84 "AM E 90 65 72 66 49 97 110 122 102 106 107 96 "AE 47.4 40.3 38.8 38 8 57.6 28 5 29.2 27.7 27.1 22.0 23.1 246 HE 1 222 3121 141 129 219 162 167 214 172 146 1371 127 Type "U" TLD Finger Rings:

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 122 154 139 148 160 168 153 152 149 126 139 150 AME 86 59 70 66 65 61 72 71 76 76 77 58 AE 135.9 114.1 139.1 109.4 168.0 87.7 99.4 109.3 97.2 90.4 96.7 87.6 HE 4101 380 790 330 910 210j 290 5901 410 510 370 400 IX-1

SPARE ISSUE BADGES Type "T" and "P" Whole Body Badges (Deep Dose):

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 55 81 50 54 45 47 42 31 28 21 24 49 AME 3 10 2 2 4 9 16 5 9 9 9 6 AE 17.7 10.2 2.0 26.0 15.3 10.0 20.0 2.0 4.1 8.7 5.1 5.8 HE 494 26 3, 27 221 66 1421 4 9 41 16 25 Type "U" TLD Finger Rings:

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 15 13 14 10 9 4 10 3 4 11 10 5 AME 4 0 4 3 3 5 4 2 4 5 6 5 AE 50.0 0.0 65.0 110.0 166.7 122.0 82.5 185.0 54.5 48.0 156.7 58.0 HE 70 0 80 210 430 220, 100 190 60 60 2901 290 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 staff radiation workers.

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