ML040630124

University of Missouri Research Reactor Annual Report for Period January 1 - December 31, 2003

ML040630124
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/24/2004
From:	Rhonda Butler Univ of Missouri - Columbia
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML040630124 (30)

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Research Reactor Center Research Park Columbia, MO 65211 University of Mlissouri-Columbia PHoNE (573) 882-4211 FAX (573) 882-6360 February 24,2004 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, 2003 through December 31, 2003.

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, Reactor Manager at (573) 882-5276.

Sincerely, I $~F-A .14 Ralph A.

Director Enclosure cc: Mr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC A-02Z AN EQUAL oPporruwNm/ADA INsTrTlmoN

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UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2003 - December 31, 2003 Compiled by the Reactor Staff Submitted February 2004 by Leslie P. Foyto Reactor Manager Reviewed and Approved Ralph A. Butler, PE Director

UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2003 through December 31, 2003 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 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 2003. 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.

ACKNOWLEDGMENTS The success of MURR and these scientific programs is due to the dedication and hard work of many individuals and organizations. Included within this group are: the University administration; the governing officials of the State of Missouri; the Missouri State Police; the 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 wvho 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 and challenges within our unique facility. 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 neutron scientists and engineers.

Reactor Operations Management also wishes to commend the five 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.

TABLE OF CONTENTS Section Pane I. Reactor Operations Summary ......................................... I-I through 6 II. MURR Procedures ........................................... II-through 5 A. Changes to Reactor Operations Procedures B. Changes to the 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 ....................................... III-1 through 2 IV. Plant and System Modifications ....................................... IV-I through 2 V. New Tests and Experiments .........................................V-1 VI. Special Nuclear Material and Reactor Physics Activities ........................ VI-1 VII. Radioactive Element .V . ....................................... through VII 2 VIII. Environmental Monitoring and Health Physics Surveys .......................... VIII-l through 5 IX. Personnel Radiation Exposures .T....................................... IX-I

.:SECTION I REACTOR OPERATIONS

SUMMARY

January 1,2003 through December 31, 2003 The following table and discussion summarize reactor operations in the period January 1, 2003 through December 31, 2003. . . -

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

Jan 2003 687.02 286.35 92.34 103.42 Feb 2003 583.70 243.28 86.86 97.28 Mar2003 670.90 279.65 90.17 101.00 Apr2003 640.58 267.04 88.97 99.64.

May 2003 674.18 281.00 90.62 - 101.49.

Jun 2003 622.32 259.50 86.43 96.80 Jul2003 *673.92 280.89 . . 90.58 101.45 Aug 2003 669.66 279.21 90.00 100.81 Sep 2003 -.656.10 273.54 91.12 102.06 Oct2003 674.26 281.06 . 90.63 . .101.50 Nov 2003 656.04 273.43 91.12 102.05 Dec 2003 675.86 281.70 90.84 101.74 Total for 7884.54 3286.65 90.00 % 100.81 %

the Year

• MURR is scheduled to average at least 150I hours of full power operation per week; Total time is the .number of I . , 6.; , . .. .

hours in the month listed or the year.

January 2003 The reactor operated continuously in January ,ith 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: inspecting two (2) fuel elements that had reached their operational end-of-life in accordance with Technical Specification 5.5.

February 2003 The reactor operated continuously in February with the following exceptions: three shutdowns for scheduled maintenance and/or refueling, and one unscheduled shutdown.

On February 16, a reactor scram was automatically initiated when the electric motor for Primary Temperature Control Valve S-1 shorted resulting in an overload condition on Breaker No. 9 of UPS Panel No. 1. Breaker No. 9 supplies electrical power to the reactor process instrumentation.. The loss of power resulted in trip signals from all process I-1

input channels to the reactor safety system. The motor for valve S-1 was replaced and tested satisfactory. The safety system was verified operable as part of the pre-startup checks. The reactor was subsequently refueled and returned to 10 MW operation.

Major maintenance items for the month included: removing, inspecting, and reinstalling level controller LC965 (Anti-Siphon System Rod Run-In input); completing Modification Record 03-1, "Installation of Flow Gauges to the Pneumatic Tube System"; replacing Primary Coolant Temperature Control Valve S-1 motor; completing reactor console upgrade in accordance with Modification Record 01-2; replacing the containment building inner airlock door motor and gearbox; replacing coolant charging pump relief valve 557A; repairing a broken wire and replacing Nuclear Instrumentation Signal Processor Drawer No. I Intermediate Level Display Board (A4); and loading new pool coolant system de-ionization bed 'WV.'

March 2003 The reactor operated continuously in March with 'he following 'exceptions: five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled shutdowns' this month. One short duration reactor startup to I MWV was performed for NRCboperator licensing examinations.

Major maintenance items for the month included: replacing Pool Coolart Temperature Control Valve S-2 motor; installing motor overload switches on Primary and Pool Coolant Temperature Control Valves S-I and S-2; and replacing the containment building outer airlock door sealing gasket solenoid-operated air supply valve A-122.

April 2003 The reactor operated continuously in April with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and three unscheduled shutdowns. Received notification from the NRC that one new Senior Reactor Operator license had been issued.

On April 6, a reactor scram was automatically initiated when Nuclear Instrumentation Power Range Monitor Channel 6 detector cabling shorted due to insulation degradation. This degradation is typical of detectors that have been in service for greater than one year. Channel 6 detector and cabling were replaced and tested satisfactory. The reactor was subsequently refueled and returned to 10 MIBV operation.

On April 23, a Rod Not In Contact With Magnet Rod Run-In was automatically initiated when control blade 'D' anvil separated from its magnet. Control Rod "D" Drive Mechanism, connectors, wiring, seating surfaces, magnet and anvil were inspected. Investigation revealed a slight misalignment of the anvil within the upper housing and that the drive mechanism was not securely fastened to the housing. The upper housing was realigned and the drive mechanism securely fastened. Drive mechanism operability and alignment were verified as part of the pre-startup checks. The reactor was subsequently refueled and returned to 10 MW operation.

On April 29, a reactor scram was manually initiated when control room personnel observed on the facility security video camera system that both containment building airlock doors appeared to be open. The Master Control Switch

-was immediately placed in the "Off' position thereby placing the reactor in .a secured condition. Investigation revealed that the failure was not in the airlock docr circuitry but rather the video camera system. The video feed had frozen while the doors were cycling leading the operators to believe that both doors were open simultaneously.

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Reactor containment integrity was never lost. The reactor was subsequently refueled and returned to 10 MW operation.

Major maintenance items for the month included: replacing Nuclear Instrumentation Power Range Monitor Channel 6 detector and cabling; and replacing the Eberline Ping IA Stack Monitor Iodine Channel card cage.

May 2003 The reactor operated continuously in May with the following exceptions: three shutdowns for scheduled maintenance and/or refueling, and two unscheduled shutdowns.

On May 17, 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 and/or a slight misalignment between the motor and pumnp;, Thee.coupling flex element was replaced, alignment was verified to be within specifications, and P501A was tested satisfactorily.! The reactor was subsequently refueled and returned to.

10 MW operation. - --

On May 18, a reactor scram was manually initiated when the duty operator discovered that'Reactor Inlet Temperature Element 980A indication had failed downscale. -There are two channels of reactor inlet temrnperature 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. The RTD/Transmitter unit for 980A was replaced and Compliance Procedure 8B was performed to verify operability and calibration. The reactor was subsequently refueled and returned to 10 MW operation. Licensee Event Report -No. 03-01, providing a 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: installing a new drain tile sump pump with associated valves and piping; replacing P501A (primary coolant system pump) motor-to-pump coupling flex element; replacing reactor inlet temperature element 980A RTD/Transmitter unit; and completing Compliance Procedure 26, "Containment Building Compliance Test." : .'.: . .". -

.. . . . I . . . .

June 2003. -;i.,:

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

On June 9, a rod run-in was automatically initiated when Process Instrumentation Power Supply 2PS3 failed.

Investigation revealed that the power supply unit had reached its expected operational life expectancy. Power supply 2PS3 was replaced and process instrumentation was .tested satisfactorily on pre-startup checks. The reactor was subsequently refueled and returned to 10 MW operation.

On June 13, a reactor scram was manually initiated by the duty operator.when the containment building outer airlock door sealing'gasket did not inflate. The Master Control Switch was immediately placed in the "Off" position thereby placing the reactor in a secured condition. Investigationi revealed that while the outer airlock door sealing gasket did not inflate, the inner airlock door had remained shut and sealed; thereby maintaining containment integrity until the 1-3 `i

reactor was secured. Troubleshooting efforts revealed a broken wire to the solenoid that controls the outer airlock door brake assembly. This caused the brake to be engaged for the full travel of the door, which did not allow the door to fully shut. The wire was repaired and operation of the door wvas tested satisfactory. The reactor was subsequently refueled and returned to 10 MW operation.

On June 21, a reactor scram was manually initiated when an operator, who was exiting the containment building, reported to the control room that the inner airlock door had closed far enough to cause the inner door gasket to inflate, but not far enough to ensure a satisfactory seal with the door's surface. The Master Control Switch was immediately placed in the "Off' position thereby placing the reactor in a secured condition. Troubleshooting efforts revealed that the inner airlock door brake setting had changed thus preventing the door from fully closing. The brake tension was loosened and a locking nut was installed to help prevent any further problems. Operation of the door was tested satisfactorily and the'reactor was subsequently refueled and returned to 10.MW. operation. Licensee Event Report No. 03-02, providing a description of this event and the corrective actions taken, was submitted within the Technical Specification thirty-day time requirement.

On June 30, a Rod Not In Contact With Magnet Rod Run-In was automatically initiated when control blade 'A' anvil separated from its magnet. Control Rod "A" Drive Mechanism, connectors, wiring, seating surfaces, magnet and anvil were inspected. Investigation revealed a slight misalignment of the anvil within the upper housing. The upper housing was realigned and the drive mechanism was reinstalled. The drive mechanism operability and alignment was verified as part of the pre-startup checks. The reactor was subsequently refueled and returned to 10 MW operation.

Major maintenance items for the month included: replacing containment building recirculation fan RF-2 motor; performing the annu'aI facility-wide emergency drill; replacing process instrumentation power supplies 2PS3 and 2PS4; replacing the Regulating Blade Drive Mechanism Rod Position Indication encoder; repairing a broken wire on the containment building outer airlock door motor braking solenoid; replacing the reach rod for demineralizer system valve R-2; loading new pool coolant system de-ionization bed 'V'; replacing a broken pin on the clutch mechanism for Door 101; and completing the biennial change out of Control Blade "A" Offset Mechanism.

July 2003 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: repairing a cooling water leak on P501A (primary coolant system pump).

August 2003 The reactor operated continuously in August with the following exceptions: six shutdowns for scheduled' maintenance and/or refueling, and one unscheduled shutdown.

On August 7, a reactor scram was manually initiated when a fault in the Rod Position Indication System resulted in fluctuating position indication for control rod 'D.' Troubleshooting efforts revealed a broken grouhd wire on the position indication amphenol connector. The broken wire was repaired and the integrity of the remaining position indication amphenols was verified satisfactory. The Rod Position Indication System was verified operable as part of I-4

the pre-startup checks. The reactor was subsequently refueled and returned to 10 MW operation.

Major maintenance items for the month included: relocating Room 202 facility evacuation switch; completing Modification Record 88-7, Addendum 2, "Removal of the Facility Ventilation System Fan Failure Alarm Panel Located in Room 202"; replacing reactor inlet temperature element 980B RTD/Transmitter unit; replacing the Regulating Blade Drive Mechanism Rod Position Indication encoder; and replacing the nitrogen system pressure regulators N-24 and N-25.

September 2003 The reactor operated continuously in September -with the following exceptions; five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled shutdowns this month. One reactor startup was performed for NRC operator licensing examinations.

Major maintenance items for the month included: replacing Nucleii Instrumentation Signal Processor Drawer No. 1 power range isolator.

October 2003 The reactor operated 'continuously in October with' the' following exceptions: - five shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns this month. Received notification from the NRC that one new Reactor Operator license and three new Seiior Reactor Operator licenses had been issued.

Major maintenance items for the month included: none.

November 2003 The reactor operated continuously in November 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: rebuilding 16A exhaust solenoid-operated air supply valve A-147; replacing Nuclear Instrumentation Wide Range Monitor picoarmmeter; loading new pool'coolant system de-ionization bed 'L'; and completing the biennial change out of Control Blade "C"' Offset Mechanism.

December 2003 The reactor operated continuously in December 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: completing Modification Record 03-2, "Replace the General Electric' Measurement and Control Type 553 Pool Coolant Demineralizer Flow Transmitter FT-912C with a Rosemount Model 1151"; rebuilding V507B (primary coolant system isolation valve) air actuator; replacing Nuclear I1-5 '<

Instrumentation Signal Processor Drawer No. I Driver Card (A2); and replacing PSOIA (primary coolant system pump) oil seal.

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SECTION II MURR PROCEDURES January 1, 2003 through December 31, 2003 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.Conimittee 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 the newly revamped Reactor Operations procedures have been refined throughout the year, there were 62 new and revised procedures issued. The majority of the revisions were strictly format or editorial in nature, with the following exceptions:

• _ _ _ __eev_ b AP-RO-110 Conduct of Operations '- 6/17/2003 AP-RO-110 Conduct of Operations - '2 10/10/2003 -_:

EX-RO-105 Reactor Irradiation Experiments. 131/26/2003 EX-RO-120 Beamport '!A" Operation' 1 11/18/2003 EX-RO-121 Beamport "B" Operation 1 11/1812003 EX-RO-122. Beamport "C" Operation . 1 11/18/2003 EX-RO-123' Beamport "D" Operation I 11/18/2003 EX-RO-124. Beamport "EF Operation 1 11/18/2003 EX-RO-125' Beamport "F" Operation 1 11/18/2003 EX-RO-126 Thermal Column Door 1 11/26/2003 OP-RO-210 Reactor Startup-Normal 3 9/10/2003 OP-RO-211 Reactor Startup - Hot, ..- . 2 9/10/2003 OP-RO-212 Reactor Startup - Recovery from Temporary 2 9/10/2003

, Power Reduction -_._________..

OP-RO-220 jReactor Shutdown or Power Reduction 2 9/10/2003 OP-RO-230 Changing Reactor Power Level 1 9/10/2003 _ _ _

OP-RO-250 In-Pool Fuel Handling. .

• 4 12/17/2003' OP-RO410: Primary Coolant System- -2 2/7/2003 -

OP-RO460 Pool Coolant System-Two Pump Operation -2 3/5/2003 .

OP-RO460 Pool Coolant System--Two Pump Operation 3 12/29/03

• OP-RO-461 Pool Coolant System--One Pump Operation I1 3/5/2003 OP-RO-461 Pool Coolant System-One Pump Operation 2 7/14/2003 OP-RO465 Pool Level Control - Skimmer System 2 5/2/2003 II-1

NW- in. B W Mm__ _______

OP-RO466 Pool Level Control-Pool Coolant System l_ 2 5/2/2003 OP-RO480 Secondary Coolant System 4 6/17/2003 OP-RO-510 Nitrogen System 2 4/15/2003 OP-RO-515 EmergencyAir System l2 10/10/2003 OP-RO-520 Emergency Diesel Generator 2 7/14/2003 OP-RO-520 Emergency Diesel Generator 11/18/2003 OP-RO-532 Drain Collection System 2 7/14/2003 OP-RO-533 Skimmer System I 3/5/2003 OP-RO-533 ISkimmer System 2_9 -.- --9/18/2003

/-18/---2003 -

OP-RO-710 JRadiation Monitoring-Area Monitors l1 10/10/2003 OP-RO-720 Radiation Monitoring-Stack Monitor 2 10/10/2003 Operational Check _.___

OP-RO-730 Building Exhaust System Fans 2 3/21/2003 OP-RO-730 Building Exhaust System Fans 3 4/15/2003 OP-RO-730 Building Exhaust System Fans _ _.4.6/5/2003 OP-RO-730 Building Exhaust System Fans 5 8/11/2003 OP-RO-741 Waste Tank System Operation 3 2/7/2003 l OP-RO-741 Waste Tank System Operation 4 7/16/2003 RM-RO-405 Reactor Demineralizer System 2 3/5/2003 RM-RO405 Reactor Demineralizer System 13 9/18/2003 RM-RO-470 [Sulfuric Acid System 2/7/2003 SM-RO-300 Control Console And Instrument Panel- 3 3/21/2003 Securing Power - __ _ __

SM-RO-620 Control Blade Bubble Leak Test l 0 9/29/2003 (New) 1-RTP-21 lProcedure for Control Rod Drop Tinier Using -- 1/2/03 RSpare Magnet' l l 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. Two revisions were issued; Revision No. 35, dated February 10, 2003, and Revision No. 36, dated March 5, 2003. Details are provided in the table on the following page.

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 have been reviewed and approved, but not yet issued for use, pending the completion of an Emergency Plan revision.

The Reactor Emergency Procedures (REP) have also been modified in accordance with the MURR Procedure Writer's Guide, and were issued January 15, 2003.

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- Emergency Call List 35: 2/10/03 Updated phone numbers SEP-7 IPublic Information Procedure 36 3/5/03 Change emergency

.______._ .. -______ verification list REP-RO-100 iReactor Emergency Procedures 0 1/15/2003 New, replaces old REP

. ____;.____.. _.manual C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES As required by MURR Technical Specifications, the Reactor Health Physics Manager reviewed MURR procedures for radioactive materials handling, 'shipping, and preparation for shipping 'ofbyproduct materials.

!I As part of the ongoing process of revising and reformatting the procedures in accordance with the MURR Procedure Writer's Guide, 113 new and 'revised health physics; radioactive materials shipping; and preparation for 'shipping procedures were issued. The last of the old format procedures have been replaced by newly revised versions.. Many of the revisions were editorial or change in forrmat. Exceptions. are listed below

_ _ _ _ _ I i i ~ ~E _ _ _ eR eiy:1sDAI 3 t~ & tles AP-HP-119 High Radiation Area Access ' 0 217/2003. New (replaces HP/I-7)

AP-HP-120 . Beamport Area 0 3/17/2003 New AP-HP-121 Isotope Closet. '  : . 0 .3/17/2003' -,New AP-HP-125 Review Of Unplanned Radiation Exposure 0 2/7/2003 New (replaces HPIII-2)

BPB-SH-005 DOT 6M Packaging and Shipment of Type 0: ' 8/27/2003:' New B Non-Waste Radioactive Material '_',_.______'_ (replaces SAS-00010)

BPB-SH-006 2OWC-1 Packaging and Shipment of Type' '0 8/27/2003 New B Non-Waste Radioactive Material, . (replaces SAS-0014)

BR-RRD-205 Lutetium Chloride Batch Record 1 0 9/16/2003 New GMP-BR-102 BR: Holmium Nitrate Target Preparation .3 2/3/2003 GMP-BR-102 BR: Holmnium Nitrate Target Preparation 4 9/5/2003 _ ..

GMP-BR-105 BR: Holmium-166 Chloride Radiochemical 6 2/3/2003 Process ' . * . .

GMP-BR-105 BR: Holmium-166 Chloride Radiochemical 7.' '1219/2003 Process . 12/9/2003 GMP-MCE-003 Setup and Operation of Accurnet AR20 1l '5/11/2003 I

._____..____ pHlConductivityMeter .. . ' : :_ .... ' ' _.

GMP-MCE-008 Calibration of Germanium Detector '. 1 7/11/2003 -:

GMP-PRC-001 Submitting Targets for Irradiation (replace l.imu

.Hol-P001) ' '~ .. ..

GMP-PRC-1 12 Holmium Chloride Process Setup 'in HC-03 0

_1 11/13/2003

-'2/3/2003 New GMP-PRC-1 12 Holinium Chloride Process Setup'in HC-03 . 1 12/9/2003 ' __................

GMP-PRC-I 13 Holmium Chloride Production in HC-03' 1 12/9/2003 _ ' ' -

GMP-PRC-1 13 Holmium Chloride Production in HC-03' 0' 2/3/2003  :'. New GMP-PRC-115 Holmium Chloride Process Setup in' ' 0 12/9/2003 INew.

. HC-02a/b . - :- -' -. '._ . -- '

GMP-PRC-1 16 -Holmium Chloride Production in HC-02 a/b 0 12/9/2003 INew II-3

GMP-QU-110 Quantifying Holmium in Radiochemical 1 7/11/2003 Holmium Chloride GMP-QU-202 Lu-177 DOTA Labeling Test 0 5/9/2003 New GMP-QU-252 Determination of Radiochemical Purity of 0 5/9/2003 New

. _ __ _ _ ILu-177 ._ .

GMP-QU-253 Lu-177 Identification and Determination of 0 5/9/2003 New Radionuclidic Purity l Hol-PRO13 Geometry Calibration of Ho-166 Hotcell 0 1/22/2003 New Dose Calibrators Hol-Q011 lDose Calibrator Linearity-Check by Decay 1 2/18/2003 _

Hol-Q052 Determination of Radiochemical Purity 5 5/1/2003 _ _

Hol-Q053 Hol-166 Identification and Determination 5 1/3/2003 of Radionuclidic Purity IC-HP-341 Calibration -High Resolution Gamma 0 2/7/2003 New Spectroscopy Systems _ (replaces HP/III- 19, 20)

OP-HP-348 Operation - Protean WPC-9550 Swipe 0 2/7/2003 New Counter OP-HP-410 Decontamination ofVial Washing Station 0 9/18/03 Obsolete (replaced by OP-HP-420)

OP-HP-420 Decontamination of Enclosed Processing 0 10/10/2003 New Units _(replaces OP-HP4 10)

PRC-RRD-212 Lutetiumr Chloride Process Setup 0 9/16/2003 New PRC-RRD-213 Lutetiumr Chloride Processing 0 9/16/2003 New PRC-RRD-214 Carrier-Free Lu-177 Process 0 9/16/2003 New PRC-RRD-316 Concentration of PM-149 0 9/16/2003 New RCP-PSO-002 lP-33 Sublimation with Glove Box Can 0 10/16/2003 lNew lOpening ,

RCP-PSO-004 P-33 Purification 0 11/6/2003 New RCP-PSO-005 P-33 Sublimation with Hot Cell Can 0 10/16/2003 New Opening RCP-PSO-006 P-33 Acid and Column Preparation 0 11/18/2003 New QA-HP-005 Shipment of Type B Radioactive Waste 1 8/27/03 Using Chem-Nuclear System 1-13G Cask RM-HP-101 Stack Monitor.Preventative Maintenance - 0 10/10/2003 New

_ _ Eberline PingA . . .

RP-QA-005 Operating Procedure for BMI-1 Shipping _ 8/28/03 Cask .

SP-SH-002 NeoRx 2OWC-1 Packaging and Shipment 0 8/17/2001 New (replaced by BPB- -

of Type B Non-Waste Radioactive Material . . SH-006)

SP-SH-002 NeoRx 2OWC-1 Packaging and Shipment 2 2/4/2002 Obsolete of Type B Non-Waste Radioactive Material _

SV-HP-131 Emergency Analysis of Environmental 0' 9/18/2003 New

_____ __ Samples For Callaway Nuclear Plant _

SV-HP-135 Containment Air - Emergency Remote 1 10/28/2003 Sampling . _ _.

WM-HP-200 Exclusive Use Shipment of LSA or SCO 0 2/7/2003 INew Radioactive Waste Utilizing a Broker _(replaces HP/VI-8)

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WM-SH-200 Exclusive Use Shipment of LSA or SCO 2 12/17/2003 New Radioactive Waste Utilizing a Broker (replaces WM-HP-200)

WM-SH-01l Shipment of Radioactive Material n.o.s., 0 12/1/2003 New

. Waste For Hot Cell Host Cans II WM-SH-300 IMURR Exclusive Use Shipment of LSA or 0 8/7/2003 New SCO Radioactive Waste _ ._-

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'SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT January 1, 2003 through December 31, 2003 I_ These changes were approved by the Reactor Manager and reviewed by licensed staff and members of the Reactor Safety Subcommittee and have been determined not to involve a change to the Technical Specifications. These changes have all been reviewed in accordance with 10 CFR 50.59.

HAZARDS

SUMMARY

REPORT (ORIGINAL JULY 1, 1965)

Original HSR,'Figure 5.1, Piping & Instrument Diagram (as revised by the' 1972-73, 1973-1974, 1994, 1996, 2001, and 2002 Reactor Operations Annual Reports):

Replace with: 'Updated Figure 5.1, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet I of 1, dated 3/21/03)

L Original HSR, Figure 9.4, Safety System 10 MW (as revised by the 1995, 2001, and 2002 Reactor Operations Annual Reports):

L Replace with: Updated Figure 9.4, Safety System (MURR Dwg No. 139, Sheet I of 1, dated 10/13/03) '.

ADDENDUM 3 - HAZARDS

SUMMARY

REPORT (AUGUST 1972) l -HSR, Addendum 3, Figure 2.2, Secondary Cooling System (as revised by the 1989-90, 1990-91, 1994, 1995, 2001, and 2002 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.2, Secondary Cooling System (MURR Dwg No. 502, Sheet I of 1, dated 713/03)

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

Replace with: Updated Figure 2.3.a, Electrical Distribution (MURR Dwg No. 522, Sheet 1 of 2, dated 11/4/03)

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

Replace with: ' Updated Figure 2.3.b, Electrical Distribution (MURR Dwg No. 522, Sheet 2 of 2, dated 11/3/03)

I- I

ADDENDUM 4 - HAZARDS SUMIMARY REPORT (OCTOBER 1973)

HSR, Addendum 4, Figure A.1, Safety System 10 AINV (as revised by the 1995, 2001, and 2002 Reactor Operations Annual Reports):

Replace with: Updated Figure A.1, Safety System (MURR Dwg No. 139, Sheet I of 1, dated 10/13/03)

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

RPC,,lice Willi: Updated Figure A.2, Piping &;Instnnmert Diagram (MURR D-xvg No 156, Sheet I of 1, dated 3/21/03)

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

Replace with: Updated Figure A.6, Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 2 of 4, dated 4/1/03)

ADDENDUM 5 - HAZARDS

SUMMARY

REPORT (JANUARY 1974)

IISR, Addendum 5, Figure 2.1, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, and 2002 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.1, Electiical Distribution (MURR Dwg No. 522, Sheet I of 2, dated 11/4/03)

III-2

SECTION IV PLANT AND SYSTEM MODIFICATION January 1, 2003 through December 31, 2003 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 88-7, Addendum 1:

MURR Industrial Buildinc Exhaust Ventilation System Connection to the Facility Ventilation System This addendum to modification record 88-7; "Exhaust-Ventilation Upgrade," documents connecting the exhaust ventilation system for the MURR Industrial Building (Room 299) to the Laboratory and Containment Building Exhaust Ventilation System. This will ensure that the facility Off-Gas Radiation Monitoring System continuously monitors the.Ijidpstrial Building air for radioactive gases and airborne contamination as it is discharged through the facility ventilation exhaust stack.

Modification 88-7, Addendum 2:

Removal of the Facility Ventilation System Fan Failure -AlanrrPine1 Located in Room 202 (Front Lobby)

This addendum to modification record 88-7, "Exhaust Ventilation Upgrade," documents the removal of the Fan Failure Alarm Panel located in the Front Lobby. This panel is' no longer required since MURR's operating schedule requires the control room to be manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day/seven days a week.

Additionally, the Front Lobby Alarm Panel is not describedor discussed in Hazards Summary Report or its addenda. No credible accident scenario has been analyzed which requires a ventilation Alarm Panel to be located in the Front Lobby.

Modification 01-13:

Modification and Relocation of the l/4-Ton Sample Handling Jib Crane This Modification Record documents the modifications performed to, and the relocation of, the 'A-Ton Sample Handling Jib Crane. The Sample Handling Jib Crane was removed from the west side of the Biological Shield, and reinstalled just north of the Biological Shield on the beam and column support structure that forms the 3 rd, 4h, and 5"' floors of the reactor containment building. By relocating and modifying the Jib Crane, operations personnel will be able to better utilize the crane for sample handling evolutions.

Modification 03-1:

Installation of Flow Gauzes to the Pneumatic Tube System This Modification Record documents the installation of flow measurement equipment for the P-Tube System that will help assist the Facility Engineer in balancing system flow rates more accurately.

Modification 03-2:

Replacement of the General Electric Measurement and Control Tvpe 553 Pool Coolant Demineralizer Flow

-Transmitter FT-9 12C with a Rosemount Model 1151 This Modification Record documents the replacement the General Electric Measurement and Control (GE/MAC) Type 553 Differential Pressure Transmitter for FT-912C with a Rosemount Model 1151

. IV-1

Differential Pressure Transmitter. Because of its age and the inability to purchase replacement parts, the GE/MAC Type 553 Differential Pressure Transmitter has become obsolete.

IV-2,

SECTION V' NEW TESTS AND EXPERIMENTS January 1, 2003 through December 31, 2003 New experimental programs developed during this period are as follows:

RUR 406, Ytterbium Oxide

Description:

This RUR authorized irradiation of ytterbium oxide for use in research and development activities.

RUR 407, Silicon Carbide

Description:

This RUR authorized irradiation of silicon carbide for use in research and development activities.

RUR 409, Xenon Targets

Description:

This RUR authorized irradiation of xenon targets for use in research and development 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. The safety evaluations have been reviewed by the Reactor Manager, Reactor Health Physics Manager and the Reactor Safety Subcommittee.

V-1

SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2003 through December 31, 2003 Inspections:

There were two NRC inspections 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 (60) refueling evolutions were completed in 2003. Excess reactivity verification was performed for each refueling. The largest excess measured reactivity was 3.42%. MURR Technical Specification 3.1(f) requires that the excess reactivity be less than 9.8%.

Reactivity Measurements:

Nine (9) reactivity measurements were made to measure the sample loading worth of all samples loaded in the flux trap region.

Thirteen (13) 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.

Three differential blade-worth measurements and one primary temperature coefficient measurement were also performed.

VI-1

SECTION VII RADIOACTIVE EFFLUENT January 1, 2003 through December 31, 2003 TABLE I SANITARY SEWER EFFLUENT January 1, 2003 through December 31, 2003 Descending Order of Activity Released for Nuclide Totals > 1.OOOE-5 Ci Nuclide Activity (Ci)

H-3 8.156E-02 S-35 2.779E-03 Co-60 1.253E-03 As-77 5.781E-04 Lu-177 5.303E-04 Zn-65 8.644E-05 Lu-177m 6.965E-05 Ca-45 6.480E-05 Cr-51 6.356E-05 Ag- 10m 3.169E-05 Ru-97 3.112E-05 Mn-54 2.665E-05 Re-188 1.860E-05 Cu-67 1.737E-05 Cs-137 1.626E-05 As-76 1.128E-05 Gd-159 1.061E-05 Total H-3 8.156E-02 Total Other 5.588E-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, 2003 through December 31, 2003 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration liCi/ml Total Release Ci TS Limit Multiplier  % TS Ar-4l 2.69E-06 1.25E+03 350 76.9956 C-14 2.36E-11 1.07E-02 1 0.7870 Co-60 2.16E-13 9.99E-05 1 0.4323 Hg-203 1.61E-12 7.46E-04 1 0.1613 H-3 1.75E-08 8.08E+00 350 0.0500 I-125 6.81E-14 3.15E-05 1 0.0227 Cd-109 1.58E-14 7.31E-06 1 0.0226 1-131 3.91E-14 1.81E-05 1 0.0195 Cs-137 3.35E-15 1.55E-06 1 0.0017 Zn-65 5.21E-15 2.41E-06 1 0.0013 Eu-155 1.36E-15 6.29E-07 1 0.0007 Gd-153 1.46E-15 6.74E-07 1 0.0005 Ba-140 9.36E-15 4.33E-06 1 0.0005 Hf-181 2.73E-15 1.26E-06 1 0.0005 1-133 5.83E-13 2.69E-04 350 0.0002 Se-75 1.23E-15 5.69E-07 1 0.0002 Mn-54 1.51E-15 6.98E-07 1 0.0002 S-35 4.26E-15 1.97E-06 1 0.0001 Co-58 1.36E-15 6.30E-07 I 0.0001 Hf-175 1.28E-15 5.94E-07 1 0.0001 As-77 3.07E-12 1.42E-03 350 0.0001 Os-191 2.31E-15 1.07E-06 1 0.0001 Ce-139 8.21E-16 3.79E-07 1 0.0001 Br-82 1.50E-12 6.92E-04 350 0.0001 Note: C-14 activity is calculated based on the ratio of argon to nitrogen in the air and the (np) reaction cross sections for the activation of N-14 to C-14.

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

Stack Flow Rate = 30,500 cfm Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, License R-103 Technical Specifications.

VII-2

SECTION VIII ENVIRONMENTAL MIONITORING AND HEALTH PHYSICS SURVEYS January 1, 2003 through December 31, 2003 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 I and 2.

Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2003. All doses are about 50 mRem/year or less, except monitor numbers 9 and 15. These'monitors are located near the loading dock where packages containing radioactive material are loaded on transport vehicles. The doses recorded by these monitors are considered to be the result of exposure to packages in transit.- The environmental monitoring program confirms that no environmental impact exists from the operation of the MURR facility.

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

'TABLE 1 Summary of Environmental Set 63

'April 2003 Detection Limits*

Matrix 'Alpha Beta Gamma Tritium Water 0.97 pCi/L' 3.62 pCi/L' 220.36 pCi/L 4.02 pCi/mL of sample Soil 0.97'pCi/g 3.62 pCi/g 1.20 pCi/g , N/A '

Vegetation 1.93 pCi/g 7.25 pCi/g' 2.74 pCi/g' 4.02 pCCi/mL of distillate

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

Activity Levels ;-Vegetation Sample -Alpha (pCiJ) Beta (pCi/k) Gamma (pCi/k H-3 (pCi/mL) 1V63 < 1.93 28.63 < 2.74 < 4.02 2V63 < 1.93 10.76 '- <'2.74 .."< 4.02 '

3V63 < 1.93 23.16 <2.74 < 4.02 4V63 < 1.93, 23.16 , < 2.74 < 4.02

- 5V63 < 1.93 19.51 , <'2.74 < 4.02 6V63 < 1.93 30.46 3.72 < 4.02 7V63 < 1.93 23.89 <2.74 < 4.02 10V63 < 1.93 29.36 <2.74 < 4.02

. VIll-I-

TABLE 1 (Cont'd)

Summary of Environmental Set 63 April 2003 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1S63 1.42 20.24 9.20 2S63 < 0.97 13.86 < 1.20 3S63 < 0.97 16.05 5.33 4S63 < 0.97 8.94 4.09 5S63 < 0.97 18.42 6.72 6S63 < 0.97 6.02 2.96 7S63 < 0.97 15.32 5.08 10S63 1.58 17.51 4.88 Activity Levels - Water Sample Alpha (pCi/LM Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL 4W63 < 0.97 10.40 < 220.36 < 4.02 6W63 < 0.97 8.21 < 220.36 < 4.02 10W63* < 0.97 20.43 292.45 < 4.02

• Sample 1OW63 was found to have gamma activity above NMI)A. Sample was counted on HPGE 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 64 October 2003 Detection Limits**

Matrix Alpha Beta Gamma Tritium Water 0.53 pCi/L 2.81 pCi/L 308.29 pCi/L 4.09 pCi/mL of sample Soil 0.53 pCilg 2.81 pCi/g 1.03 pCi/g N/A Vegetation 1.07 pCi/g 5.62 p-Ci/g 2.20 pCi/g 4.09 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)

Summaiy of Environmental Set 64 October 2003, Activity Levels -'Vegetation Sample Alpha (pCi/g) Beta (pCi/) -Gamma (PCiE H-3 (pCi/mL) 1V64 < 1.07 15.49 <2.20 < 4.09 2V64 < 1.07 20.83 < 2.20 < 4.09 3V64 < 1.07 24.39 <2.20 < 4.09 4V64 < 1.07 31.87 < 2.20 < 4.09 SV64 < 1.07 23.32 < 2.20 < 4.09 6V64 < 1.07 25.46 , < 2.20 < 4.09 7V64 < 1.07 23.32 < 2.20 < 4.09 10V64 < 1.07 34.46 <2.20 < 4.09 Activity Levels - Soil I Sample Alpha (pCi/g) . Beta (pCikg) Ciamma (pCiIg)

IS64 0.65 . 19.32 15.68 2S64 0.65 , 15.40 3.80 3S64 <0 .53 20.03 7.19

• 4S64 0.97 15.22' 9.33 5S64 0 .65 17.54 12.18

'6S64 < 0 .53 6.32 1.64 7S64 < 0 .53 15.40: < 1.03 10S64 0.65 . 21.99- 2.13

'Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCiuL ' H-3'(pCi/mL) 4W64 < 0.53 26:26 < 308.29 < 4.09 6W64 < 0.53 4.272 < 308.29 < 4.09 10W64 <0.53 6.32 < 308.29 < 4.09 VM-3 ..

TABLE 3 Environmental TLD Summary January 1, 2003 through December 31, 2003 Badge Direction Map Distance from I st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total Number From MURR MIURR Stack 2002 2002 2002 2002 (meters) Net mR Net mR Net mR Net mR Net mR I Control N/A -1.8 -1.0 2.5 -1.4 -1.7 2 Control N/A -2.0 -3.5 -1.3 -5.1 -11.9 3 WSW N/A -1.1 -0.8 -2.4 -0.3 4.6 4 Spare N/A 0.7 -1.7 4.7 12.1 6.4 5 Spare NY'A 0.5 0.S -0.5 2.5 3.3 6 N 34 -3.9 4.0 -2.3 -2.4 -12.6 7 NE 57 6.0 -7.5 7.4- 0.4 6.3 8 . SW 27 -1.8 4.1 4.9 -3.5 -14.3 9 S 27 17.7 26.2 22.2 25.9 92.0 10 NE 149 -3.7 -6.0 -5.8 -3.5 -19.0 11 NW 149 -5.6 -1.5 4.6 -3.1 -14.8 12 ENE 301 5.5 0.3 1.2 -0.5 6.5 13 NNE 316 0.0 -1.9 -1.1 4.1 1.1 14 S 156 3.4 -5.3 0.3 -1.0 -2.6 15 S 65 18.1 23.2 21.5 17.4 80.2 16 SE 107 absent -3.7 -6.1 -3.0 -12.8 17 E 293 -4.1 -5.0 -21.2 -1.5 -31.8 18 NE 476 0.0 -5.4 4.2 -5.8 -15.4 19 NNE 606 -5.3 -8.4 -7.8 -8.5 -30.0 20 NE 907 -5.8 -9.1 -10.3 -7.9 -33.1 21 SE 236 -1.7 -5.5 -2.0 -2.7 -11.9 22 ESE 168 -3.4 -1.1 4.9 -5.8 -15.2 23 NW 110 0.9 -1.5 -0.5 absent -1.1 24 SSW 328 -6.7 -8.1 -2.3 -2.1 -19.2 25 SSW 480 -2.3 -2.0 absent -1.7 -6.0 26 SW 301 -5.5 -5.7 -0.3 4.1 -15.6 27 WSW 141 -6.8 -7.2 -6.9 -6.0 -26.9 28 WNW 210 -1.5 -0.3 2.1 -0.4 -0.1 29 NW 255 -1.9 3.9 0.1 1.3 3.4 30 NNW 328 absent -5.5 0.4 -0.9 -6.0 31 NNW 671 -8.7 -6.1 1.6 -1.8 -15.0 32 NNW 724 -0.5 -1.3 -1.9 -1.2 -4.9 33 E 671 -5'5 -6.7 4.3 -6.7 -23.2 34 ENE 587 -7.2 -5.3 4.0 absent -16.5 35 SSE 499 10.2 10.2 4.6 -5.8 10.0 36 SE 419 -2.2 -3.4 -3.4 -3.2 -12.2 37 NE 690 -5.6 -5.4 4.1 1.9 -13.2 38 NW 556 5.0 0.5 -1.0 0.5 5.0 39 W 491 -3.2 -3.7 5.5 -2.8 -4.2 40 N 514 -5.5 -2.0 -5.8 4.8 -18.1 41 NNE 137 -6.8 -6.4 4.9 4.3 -22.4 42 In Building N/A -2.1 -0.5 0.1 3.8 1.3 43 In Building N/A 2.2 1.5 absent 7.7 11.4 44 Spare N/A -0.6 0.1 -5.5 2.5 -3.5

-45 S 65 -1.9 -2.4 -1.3 0.5 -5.1

• TLD No. 35 left at site 1st and 2nd quarters of 2003 - total dose is divided between the two quarters.

VIII-4

Ij TABLE 4 Number of Facility Radiation and Contamination Surveys January 1, 2003 through December 31, 2003 Radiation Surface Contamination* Air Samples** RNVP's January 46 46 64 10 February 57 57 53 ' 10 March 55 52 '47 2 April 42 42 56 10 May 58 58 70 8 June 56 55 68 6 July 45  ; 45 62 4 August 54 43 63 0 September 48 48 59 4 October 68 67 63 4 November 36 - 36 55 5 December 48 48 63 7 TOTALS 613 597 723 70

• 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 Jessie Quichocho resigned as a Health Physics Technician in August 2003.

Scott Keithley resigned as a Health Physicist in August 2003.

Dan Nickolaus transferred from the Shipping group to the Health Physics group in September 2003.

During 2003, M1URR shipped 503.53 cubic feet of low level radioactive waste.

VIII-5

SECTION IX

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS January 1, 2003 through December 31, 2003 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP Month AC DO FSO IIC RAG IRR NA NS OPS PRO RP S11 SIL Total January 28 14 161 140 162 26 30 80 1218 317 124 65 37 2360 February 17 7 111 172 189 19 29 100 1212 246 64 58 26 2226 March 71 12 78 238 168 69 0 103 1207 179 75 83 39 2239 April 28 19 178 125 199 27 27 98 1387 148 117 61 30 2397 May 23 26 114 148 196 36 17 84 1268 121 108 71 41 2204 June 21 57 119 139 159 37 39 55 1460 129 54 53 38 2282 July 57 2 199 163 126 35 28 47 1373 184 39 44 52 2290 August 44 3 242 193 175 36 19 60 1013 182 72 70 29 2091 September 43 32 146 164 112 27 7 29 1281 86 47 63 42 2004 October 14 14 182 111 127 26 44 26 1375 105 76 39 42 2153 November 51 5 115 146 197 12 23 41 1397 109 18 58 43 2159 December 86 14 114 168 112 9 56 30 1076 126 35 33 30 1789 Total to Date 483 205 1759 1907 1922 359 319 753 15267 1932 829 698 449 26882 Monthly Ave 40 17 147 159 160 30 27 63 1272 161 69 58 37 2240 Highest NVB 24 57 43 97 71 31 19 57 183 123 86 42 50 Highest EXT 390 210 1060 660 310 80 500 180 970 1530 660 90 180 iL AC-Analytical Chemistry RAG-Health Physics NS-Neutron Scattering RP-Radiophariceutical DO-Director's Office IRR-Irradiations OPS-Operations SH-Shipping FSO-Shops NA-Nuclear Analysis PRO-Isotope Production SIL-Silicon i HC-Hot Cell NWB=Whole Body EXT=Extremities NOTE: Dosimetry services are provided by RS. 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