ML110600700
| ML110600700 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 02/25/2011 |
| From: | Fruits J Univ of Missouri - Columbia |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML110600700 (32) | |
Text
UNIVERSITY of MISSOURI RESEARCH REACTOR CENTER February 25, 2011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
REFERENCE:
Docket 50-186 University of Missouri-Columbia Research Reactor Amended Facility License R-103
SUBJECT:
University of Missouri Research Reactor 2010 Reactor Operations Annual Report I have enclosed one copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2010 through December 3 1, 2010.
This document is submitted to the U.S. Nuclear Regulatory Commission in accordance with the University of Missouri Research Reactor Technical Specification 6.1 .h(4).
If you have any questions regarding the contents of this report, please contact me at (573) 882-5319 or FruitsJgmissouri.edu.
Sincerel Y, I I*
Roet Lr. MIanag Reactor Manager LPF/djr Enclosure xc: Mr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC A90 1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: www.murr.missouri.edu Fighting Cancer with Tomorrow's Technology
UNIVERSIITY OF MISSOURI UNiVERSiTY OF MESSOUM RESEARCH REACTOR REACTOR OPETAffHONS ANNUAL REP©RT Jaiimtiry 11 2D*10 - DeceAbeir 31, 201@0
I UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2010 through December 31, 2010 Compiled by the Research Reactor Staff of MURR Submitted by:
Jo ~n L. Fruits Reactor Manager Reviewed and approved by:
Ralph A. Butler, PE Director
UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2010 through December 31, 2010 INTRODUCTION The University of Missouri Research Reactor (MURR) is a multi-disciplinary research and education facility providing a broad range of analytical, materials science, and irradiation 'services to the research community and the commercial sector. Scientific programs include research in archaeometry, epidemiology, health physics, human and animal nutrition, nuclear medicine, radiation effects, radioisotope studies, radiotherapy, and nuclear engineering; and research techniques including neutron activation analysis, neutron and gamma-ray scattering, and neutron interferometry. The heart of this facility is a pressurized, reflected, open pool-type, light water moderated and cooled, heterogenous reactor designed for operation at a maximum steady-state power level of 10 Megawatts thermal - the highest powered University-operated research ieactor in the United States.
The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2010. Included within this report are changes to MURR reactor operations and health physics procedures, revisions to the Hazards Summary Report, facility modifications, new tests and experiments, reactor physics activities, and environmental and health physics data.
This Report is being submitted to the U.S. Nuclear Regulatory Commission (NRC) to meet the administrative requirements of MURR Technical Specification 6.1 .h (4).
ACKNOWLEDGMENTS The success of MURR and these scientific programs is due to the dedication and hard work of many individuals and organizations. Included within this group are: the University administration; the governing officials of the State of Missouri; the Missouri State Highway Patrol; the City of Columbia Police Department; the Missouri University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our Regulators; those who have provided funding including the Department of Energy (DOE) and the Department of Homeland Security (DHS); Argonne National Laboratory (ANL); Idaho National Laboratory (INL); Sandia National Laboratories (SNL); the Researchers; the Students; the Columbia Fire Department; the Campus Facilities organization; members of the National Organization of Test, Research, and Training Reactors (TRTR); and many others who have made, and will continue to make, key contributions to our overall success. To these individuals and organizations, the staff of MURR wishes to extend its fondest appreciation.
Some of the major facility projects that were supported by Reactor Operations during this calendar year included (1) responding to the Request for Additional Information (RAI) regarding a License Amendment that was submitted to increase the flexibility and capacity in the center test hole, (2) assembling the design specifications for a new Cooling Tower that will support a power uprate to 12 MW for fuel conversion, and (3) characterizing an irradiation facility on Beamport 'E' in support of the Boron Neutron Capture Therapy project. Additionally, in August 2006 MURR submitted a request to the NRC to renew Amended Facility i
Operating License R-103. Significant efforts have already been placed in responding to the Requests for Additional Information (RAI) and these efforts will continue in the upcoming year.
The facility continues to actively collaborate with the US-RERTR (Reduced Enrichment for Research and Test Reactors) Program and four other U.S. high-performance research reactor facilities that use highly-enriched uranium (HEU) fuel to find a suitable low-enriched uranium (LEU) fuel replacement. Although each one of the five high-performance research reactors is responsible for its own feasibility and safety studies, regulatory interactions, fuel procurement, and conversion, there are common interests and activities among all five reactors that will benefit from a coordinated, working-group effort.
Reactor Operations Management also wishes to commend the three individuals who received their Reactor Operator certifications and the individual who received his Senior Reactor Operator certification from the NRC. These individuals participated in a rigorous training program of classroom seminars, self-study, and on-the-job training. The results of this training are confident, well-versed, decisive individuals capable of performing the duties of licensed operators during normal and abnormal situations.
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TABLE OF CONTENTS Section Title Pages I. Reactor Operations Sum mary ............................................................... 1-1 through 6 II. M URR Procedures ................................................................................ I-1 through 6 A. Changes to Reactor Operations Procedures B. Changes to the MURR Site Emergency Procedures and Facility Emergency Procedures C. Changes to Health Physics Procedures, Byproduct Material Shipping Procedures, and Preparation of Byproduct Material for Shipping Procedures III. Revisions to the Hazards Summary Report-, ....................................... Il-1 through 3 IV . Plant and System M odifications ........................................................... IV-1 V. New Tests and Experiments ............................................................ V-1 VI. Special Nuclear Material and Reactor Physics Activities ................ VI-1 VII. Radioactive Effluent ............................................................................. VII- 1 through 2 Table 1 - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII. Environmental Monitoring and Health Physics Surveys. ..................... VIII-1 through 5 Table 1 - Summary of Environmental Set 77 Table 2 - Summary of Environmental Set 78 Table 3 - Environmental TLD Summary Table 4 - Number of Facility Radiation and Contamination Surveys IX. Summary of Radiation Exposures to Facility Staff, Experimenters, an d V isitors ........................................................................................... IX -I
SECTION I REACTOR OPERATIONS
SUMMARY
January 1, 2010 through December 31, 2010 The following table and discussion summarizes reactor operations during the period from January 1, 2010 through December 31, 2010.
Full Power % of Full Power % of Month Full Power Hours Megawatt Days Total Time Scheduled')
January 685.72 285.79 92.2 103.2 February 614.23 256.06 91.4 102.4 March 656.67 273.73 88.3 98.8 April 640.74 267.04 89.0 99.8 May 668.74 278.74 89.9 100.6 June 667.03 277.99 92.6 103.9 July 684.80 285.40 92.0 103.1 August 673.08 280.60 90.5 101.3 September 662.04 275.94 92.0 103.1 October 667.19 278.06 89.7 100.4 November 650.85 271.28 90.4 101.4 December 677.61 282.43 91.1 102.0 Total for 7948.70 3313.06 90.75 % 101.66 %
the Year Note 1: 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 2010 The reactor operated continuously in January with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: repairing the safety edge on inner airlock door 277.
February 2010 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month. One additional reactor startup was performed in support of U.S. Nuclear Regulatory Commission operator licensing examinations.
U.S. Nuclear Regulatory Commission examiner arrived at facility to conduct operator licensing examinations.
Received notification from the U.S. Nuclear Regulatory Commission that two new Reactor Operator licenses had been issued.
I-1
Major maintenance items for the month included: replacing the blade arm guard on the regulating blade offset mechanism; performing a zero and span procedure on reactor inlet temperature element TE-901A as part of the instrument calibration; replacing the motor on pool coolant demineralizer pump P-513B; and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-I 1(D)."
March 2010 The reactor operated continuously in March with the following exceptions: five shutdowns 'for scheduled maintenance and/or refueling, and two unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission regional inspector arrived at the facility for a routine inspection of the Radiation Protection Program and Shipping.
On March 4, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was automatically initiated when an interruption in electric supply power from the University Power Plant to the facility occurred. All immediate and subsequent actions of reactor emergency procedure REP-11, "Momentary Loss of Normal Electrical Power," were performed. Permission to restart the reactor was obtained from the Reactor Manager after confirmation from the power plant that the cause of the interruption in electrical power was corrected. The reactor was refueled and subsequently restarted to 10 MW operation.
On March 9, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5: & 6 High Power Scram" was automatically initiated when Nuclear Instrumentation Power Range Channel No. 6 power level indication increased above the scram set point to full scale. The duty operator noted all other power level indications were normal - between 100 and 105%. All immediate and subsequent actions of reactor emergency procedure REP-5, "Nuclear Instrument Failure," were performed. Historically, after various periods of service, the cabling between detectors and amplifier assemblies have caused upward spiking due to radiation induced insulation damage or breakdown. The uncompensated ion chamber detector and cabling were replaced. An instrument channel calibration and pre-operational checks were performed satisfactorily. The system was response checked with a neutron source and permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
Major maintenance items for the month included: installing NEER Grant cobalt irradiation facility; collecting primary coolant system hydraulic data in support of the fuel conversion project; loading new de-ionization bed 'T' and placing it on primary coolant system service; replacing Nuclear Instrumentation Power Range Channel No. 6 uncompensated ion chamber detector and cabling; performing reactor test procedure "RTP Experimental Measurement of the MURR Primary Temperature Coefficient of Reactivity" in support of a Nuclear Engineering Department practicum; replacing reactor core differential pressure sensor DPS-929 alarm unit; completing re-alignment of annunciator alarm response switches; and completing the mechanical portion of Modification Record 09-04, "Cooling Tower Temporary Cooling."
April 2010 The reactor operated continuously in April with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and two unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission inspectors arrived at the facility for an unannounced, non-routine inspection of Reactor Operations.
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On April 5, during a reactor startup with the control blades at approximately 13-inches withdrawn (subcritical), a "Power Level Interlock" reactor scram was automatically initiated. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The control room operators noted that the scram annunciation failed to "lock in" and had reset immediately. Investigation of all relays, switches and wiring associated with the power level interlock circuit revealed no abnormalities. It was postulated that the most likely cause was "Power Level Interlock" relay 1K26. Relay 1K26 was replaced and retested satisfactorily and permission to resume the reactor startup was obtained from the Reactor Manager.
On April 18, with the reactor operating at 10 MW in the automatic control mode, a "Rod Not In Contact With Magnet" rod run-in was automatically initiated. Using various indications, the duty operator verified that no actual separation between the control rod drive mechanism electromagnets and the control blade anvils had occurred. A manual scram was subsequently initiated and all immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Investigation of all relays and wiring associated with this portion of the rod run-in circuit revealed no abnormalities. It was postulated that "Rod Magnet Engaged and on Lower Limit" relays K49, K51, K53 and K55 were the most likely cause. The relays were replaced and retested satisfactorily and permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
Major maintenance items for the month included: replacing "Power Level Interlock" relay 1K26; adjusting the door closed/gasket inflate limit switch on containment building personnel entry Door 277; connecting an electrical outlet in the Shipping and Receiving Building to emergency power; replacing "Magnet Engaged and on Lower Limit" relays K49, K51, K53 and K55; completing the biennial change-out of Control Blade 'B' Offset Mechanism; completing the electrical portion of Modification Record 09-04, "Cooling Tower Temporary Cooling;" adjusting the door closed/gasket inflate limit switch on containment building personnel entry Door 277; performing the biannual cleaning of the cooling tower sump and basin; replacing the air seal gasket on containment building personnel entry Door 277; performing a back flush on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B; and performing a back flush on the secondary coolant side of pool. coolant system heat exchanger HX-52 1.
May 2010 The reactor operated continuously in May with the following exceptions: six shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP- I1(D);" performing a back flush on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B; burnishing Regulating Blade Automatic Control Circuit contacts on relays 1K8, 1K9, 1K10, 1K12, 2K20 and 2K21; completing compliance procedure CP-26, "Containment Building Compliance Test;" flooding Beamport 'C' with demineralized water; completing compliance procedure CP-29, "Calibration of the NMC RAK Radiation Stack Monitor;" and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B)."
1-3
June 2010 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled/unplanned power reduction.
On June 21, during a reactor startup with the control blades at approximately 6-inches withdrawn (subcritical), a "Rod Not in Contact with Magnet" rod run-in was automatically initiated when control blade 'B' anvil separated from its electro-magnet during a shimming evolution. The reactor was shutdown and the pull rod to housing alignment was checked and verified, and the anvil and magnet were cleaned. The control rod was satisfactorily withdrawn to the full out position as part of the retest using compliance procedure CP-10, "Rod Drop Times."
Permission to restart the reactor was obtained from the Reactor Manager.
Major maintenance items for the month included: repairing the combination keypad for containment building personnel entry Door 277; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" performing a zero and span procedure on primary coolant flow transmitter FT-912G as part of the instrument calibration; replacing the filter cartridges in pool coolant demineralizer system inlet filter housing F-200;- replacing the reinforced element on pool coolant system pump;P-508A pump/motor coupling; and installing sample rotator alarm system upgrade.
July 2010 The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-1 I(D);" completing compliance procedure CP-31, "Calibration of the Eberline Radiation Stack Monitor;" replacing the rotary micro-switch for the regulating blade < 10% withdrawn rod run-in function; replacing the drive chain shock absorber on containment building personnel entry Door 276; performing a back flush on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B; performing a back flush on the secondary coolant side of pool coolant system heat exchanger HX-521; and replacing the coolant filter housing on the emergency diesel generator.
August 2010 The reactor operated continuously in August with the following exceptions: five shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: repairing the air supply lines to primary coolant isolation valves 507A and 507B air actuators; installing instrumentation in order to acquire the operating times of the primary coolant isolation valves, the anti-siphon isolation valves and the in-pool heat exchanger automatic isolation valves to refine the MURR thermal-hydraulic RELAP model; loading new de-ionization bed 'F' and placing it on pool coolant system service; replacing the pressurizer surge line isolation valve 527C air actuator; replacing the wear ring on the six-tube center test hole canister; adjusting the door stop micro switch on containment building personnel entry Door 277; repairing control blade selector switch 1S3; performing a reactivity worth measurement in accordance with 1-4
reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP- 17(B);" and realigning the motor on primary coolant demineralizer pump P-513A.
September 2010 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one scheduled shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: replacing contact cabling in controller for facility ventilation exhaust fan EF-13; replacing process instrumentation power supply 2PS5; performing a back flush on the secondary coolant side of pool coolant system heat exchanger HX-521; performing a back flush on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B;,replacing\upgrading contact cabling in the controllers for facility ventilation exhaust fans ,EF-13 and EF-14; completing Modification Record 10-01, "Addition of Junction Box and Terminal Board for Control Rod Drive 'D' Drive Cable;" performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" and installing modified PLC control program for containment building personnel airlock entry doors.
October 2010 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled/unplanned power reduction.
On October 11, during a reactor startup with the control blades at approximately 13-inches withdrawn (subcritical),
a "Channel 2 & 3 Short Period" rod run-in was automatically initiated when Intermediate Range Channel No. 3 period indication increased above the rod run-in set point. The duty operator noted all other power level and period indications were normal. All immediate and subsequent actions of reactor emergency procedure REP-5, "Nuclear Instrument Failure," were performed. Troubleshooting efforts lead to the replacement of the linear amplifier for Nuclear Instrumentation Signal Processor No. 2. An instrument channel calibration and pre-operational checks were performed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager.
Major maintenance items for the month included: replacing the pneumatic actuator on in-pool heat exchanger automatic isolation valve 546B; performing a back flush on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B; performing a back flush on the secondary coolant side of pool coolant system heat exchanger HX-521; completing the biennial change out of Control Blade 'D' Offset Mechanism; and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-1 1(D)."
November 2010 The reactor operated continuously in November with the following exceptions: five shutdowns for scheduied maintenance and/or refueling, and two scheduled shutdowns for physics measurements. There were no unscheduled/unplanned power reductions this month. U.S. Nuclear Regulatory Commission regional inspector 1-5
arrived at the facility for a routine inspection of Reactor Operations and Emergency Preparedness. U.S. Nuclear Regulatory Commission examiner arrived at the facility to conduct operator licensing examinations.
Major maintenance items for the month included: performing a back flush on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B; performing a back flush on the secondary coolant side of pool coolant system heat exchanger HX-521; performing two reactivity worth measurements in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" realigning pool coolant demineralizer system pump P-513B; replacing pressurizer isolation valve V527C air actuator and valve diaphragm; rebuilding hot exhaust line ventilation valve 16B air control solenoid valves A-150, A-151, and A-153; completing Modification Record 01-09, Addendum 2, "Emergency Electrical System in North Office Addition;" and installing the monochromator on Beamport "C."
December 2010 The reactor operated continuously in December with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, three scheduled shutdowns for physics measurements, and two unscheduled/unplanned power reductions. Received notification from the U.S. Nuclear Regulatory Commission that one new Senior Reactor Operator license and one new Reactor Operator license had been issued.
On December 13, during a reactor startup with the shim blades at approximately 15-inches withdrawn (subcritical),
an unannounced (no audible or visual alarm occurred) rod run-in was initiated as the duty operator noted all four shim blades moving inward. Investigation of all relays, switches and wiring associated with the rod run-in system revealed no abnormalities. It was postulated that the most likely cause was either the rod rmn-in system Non-Coincidence Logic Unit or the Trip Actuator Amplifier. The Non-Coincidence Logic Unit and the Trip Actuator Amplifier were replaced and operational checks of the rod run-in system were performed satisfactorily. Temporary monitoring equipment was attached to the circuit to monitor'certain input signals to aid in any future troubleshooting efforts.
Permission to restart the reactor was obtained from the Reactor Manager.
On December .15, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5 & 6 High Power Scram" was automatically initiated when Nuclear Instrumentation Power Range Channel No. 6 power level indication increased above the scram set point to full scale. The duty operator noted all other powerlevel indications were normal - between 100 and 105%. All immediate and subsequent actions of reactor emergencyiprocedure REP-5, "Nuclear Instrument Failure," were performed. Troubleshooting efforts discovered a damaged pin connector on the low voltage regulator for Nuclear Instrumentation Power Range Channel No. 6. The voltage regulator was replaced and instrument channel calibration and pre-operational checks were performed satisfactorily. The reactor was refueled and subsequently restarted to 10 MW operation with permission from the Reactor Manager.
Major maintenance items for the month included: draining and back-flushing Beamport 'C' with helium; performing three reactivity worth measurements in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" realigning offset mechanism guide tube for shim control blade 'D;' performing special maintenance procedure SM-RO-625, "Measuring Control Blade Pull Weight and Blade Drop Time with the Test Magnet Assembly, RTP-21;" replacing the trip actuator amplifier and non-coincidence logic unit for the rod run-in system; replacing the low voltage regulator for Nuclear Instrumentation Power Range Channel No. 6; performing a back flush on the secondary coolant side of primary coolant system heat exchangers HX-503A and HX-503B; and performing a back flush on the secondary coolant side of pool coolant system heat exchanger HX-52 1.
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SECTION II MURR PROCEDURES January 1, 2010 through December 31, 2010 As required by administrative Technical Specification 6.1.h (4), this sectidn of the Annual Report includes a summary of procedure changes. These procedure changes 'were reviewed by the Reactor Manager or Reactor Health Physics Manager and others to assure compliance with the requirements of 10 CFR 50.59. These procedure changes
-were also reviewed by the Reactor Procedure Review Subcommittee of the Reactor Advisory Committee to meet the requirements of Technical Specification 6.1.c (1).
A. CHANGES TO REACTOR OPERATIONS PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Reactor Operations Procedures and found them to be adequate for the safe and reliable operation of the facility.
There were fifty-five (55) revisions issued to the reactor operations procedures, forms and operator aids.
Additionally, five (5) new procedures were issued. The majority of the revisions were strictly format or editorial in nature, such as cover page changes. The following is a list of the new and revised procedures, forms and operator aids:
N..u I bejr I ____ Nanc Rev. lRevisiozi Date l Notets AP-RO-115 iModification Records 6 7/1/10 { Minor Editorial
- 6. 12/7/10 Minor Editorial AP-RR-003 I10 CFR 50.59 Evaluations AP-RR-003 110 CFR 50.59 Evaluations . 1 . 4/26/10, Minor Editorial
[EX-RO-105 IReactor Irradiation Experiments -............. 14 12/1/10 j Cover Page EX-RO- 120 "A" Operation .Beamport 8 1 9/27/10 .. Minor Editorial EX-RO-121
. eamport"B" Operation 8 1 9/27/10 [ Minor Editorial FEX-RO-122 Beamport "C" Operation 8 9/27/10 [ Minor Editorial F-EX-RO-123 !Beamport "D" Operation 8. .9/27/10 Minor Editorial FEX-RO-124 IBeamport "E" Operation . 9 . 9/27/10 [ Minor Editorial FEX-RO-125 1Beamport "F" Operation ._____ 10 9/27/10 j Minor Editorial EX-RO-126 Thermal Column Door I..6 1'12/1/10 Cover Page .
F .Biennial Inspection and Preventive Maintenance 0view Fl FB-SH- 125 BMI- Shipping Cask T i. 3/1/10 Full Review
]BI- aT 1npin
-Test.and Calibration Procedure BMI- 1 Shipping 0 18/10 FB-SH-130 Cask 3/18/10 Full Review F.Sh td w s e tI_ 1 cto..... .....
__ _,hc_
I Reactor Shutdown Checksheet. 4 2/16/10 . Minor Editorial FM-56 ]Reactor Routine Patrol 13 3/17/10 J Minor Editorial F FM-57 -Long Form. Startup Checksheet 16 12/1/10 j Minor Editorial F FM-58.. rsartupChecksheet Evaluation 8 12/1/10 Minor Editorial FCustomer Sample Pre-Encapsulation Editorial FM-66 lWorksheet 5 7/7/10 Minor t F FM-68 .Target Material Control Checksheet 8 9/7/10 J Minor Editorial GS-RA-100 IMURR Equipment Tag Out 9 7/28/10 Minor Editorial Il-1
~Number J _'" 5 Name' 1 Rev. Revision D~ate[ 7 Notes~
[IRR-PSO-106 1Target Material Control Checks 7 T 2/19/10 . Minor Editorial IRR-PSO-111 Customer Sample Pre-Encapsulation Evaluation : 5 7/7/10 Minor Editorial OP-RO-210 iReactor Startup-Normal .. .. 3/17/10 Minor Editorial FOP-RO-210 iReactor Startup-Normal 10 1 7/15/10 Minor Editorial OP-RO-2 1i ,Reactor Startup Hot
- - 1 8 8/20/10 Minor Editorial OReactor 2 Startup - Recovery from Temporary Power 8 2/1/0 OP-RO-212 Reduction 8 12/1/10 Minor Editorial OP-RO-250 .In-Pool Fuel Handling ] 13 T 9/27/10 . Minor Editorial FOP-RO-310 INuclear Instrumentation - Signal Processor #1 7 T '7/1/10 1 Minor Editorial OP-RO-311 Nuclear Instrumentation - Signal Processor #2 8 7/1/10 Minor Editorial T
OP-RO-3 12 Nuclear Instrumentation Power Range Monitor -
IChanne6 j7/1/10 1
jMinor Editorial OP-RO-330 JNuclear Instrumentation - Wide Range Monitor , 7 } 7/1/10 Minor Editorial OP-RO-460 'Pool Coolant System - Two Pump Operation 12 8/20/10 _Minor Editorial O-P-Rp-461. ToolCoolant System - One Pump Operation ] 10 { 8/20/10 Minor Editorial.
OP-RO-466 Pool Level Control - Pool Coolant System 9 7/1/10 Minor Editorial O.P-RO-480 iSecondary Coolant System 13 1/ ] 'Minor Editorial OP-RO-516 NValve Operation Air System 7 9/270 Minor Editorial OP-RO-525 ]Chill Water System 3 7/1/10 Minor Editorial OP-RO-530 bDemineralized Water Supply System ] 10 9/27/10 Minor Editorial OP-RO-532 jDrain Collection System 7 7/28/10 Minor Editorial IOP-RO-555 rFire Protection System 8.12/30/10...Minor Editorial OP-RO-730 lFacility Exhaust System 112 7/1/10 j Minor Editorial OP-RO-741 jWaste Tank System Operation . 10 4 7/1/10 Minor Editorial REP-RO-100 iReactor Emergency Procedures 11 . 1/15/10 1 Minor Editorial RM-RO-405 lReactor Demineralizer System 11 9/27/10 1 Minor Editorial RP-RO-300FuelReceipt, Inspection and Accounting of Unirradiated 1 4/13/10 Full Review ISM-RO-200 RM-RO-300 Ml1 Manual Operation of Airlock Doors 276 and 277 0 4/13/1 8/3/10 0 1Review______
Full____
J0 Review O- Control Console And Instrument Panel-Securing 8 1 0 1 SM-RO-3 P 8 9/3/10 Minor Editorial SMd~O625 Measuring Control Blade Pull Weight and Blade Drop Time with the Test Magnet Assembly, RTP-21 10 8/2/1 8/20/10 F
Full Review SM-RO-635 lRetracting and Reinserting Beamport 'A' Liner 3 1/9/10 Mior Editorial SM-RO-636 jRetracting and Reinserting Beamport 'B' Liner
... 3 Minor Editorial SM-RO-637 JRetracting and Reinserting Beamport 'C' Liner 131 3.. 11/9/10 Minor Editorial SM-RO-638 ]Retracting and Reinserting Beamport 'D' Liner {4 11/9/10 .._Minor Editorial I SM-RO-639 ,Retracting and Reinserting Beamport 'E' Liner 3 1 12/20/05 Minor Editorial SM-RO-650 3Cleaning the Acid Day Tank Sight Glass . FllReview u0l2/16/10 SM-RO-660 JReplacement of Inner and Outer Pressure Vessels 2 4/2/10 Mifnor Editorial 11-2
B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Emergency Plan Implementing Procedures and found them to be adequate for the safe and reliable operation of the facility.
There were eleven (11) revisions issued to the emergency procedures, forms and operator aids. The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures, forms and operator aids:
~Numiber7 7 7.Nm7 IRev. l~epi-s1 aU__________
F -EP-RO-003
]Emergency Preparedness Training i 3 5/3/10 . Minor Editorial EP-RO-004 Fire 4 5/3/10 Minor Editorial EP-RO-007 Severe Natural Phenomenon 3 5/3/10 [ Minor Editorial EP-RO-014 EPZ and Site Area Evacuations 6 5/3/10 Minor Editorial SEp-R 5-01Emergency Notifications . 5 5/3/10 . Minor Editorial EP-RO-0-17 Emergency Air Sampling 5 _51 5/3/10
/1.. [ Minor Editorial 1 FM-104 . EmergencyCall List 13 2/18/10 Minor Editorial FM- 104 Emergency Call List 14 6.. Minor Editorial FM-104 Emergency Call List 15 12/21/10 [ Minor Editorial OA-0 .JFire Extinguisher Locations and Types 5 5/3/10 Minor Editorial OA-20 Emergency Equipment 8 2/18/10 Minor Editorial C. CHANGES TO HEALTH PHYSICS PROCEDURES, BYPRODUCT MATERIAL SHIPPING PROCEDURES, and PREPARATION OF BYPRODUCT MATERIAL FOR SHIPPING PROCEDURES As required by the MURR Technical Specifications, the Reactor Health Physics Manager reviewed the procedures for radioactive materials handling, shipping, and preparation for shippingof byproduct materials.
There were seventy-seven (77) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. Additionally, one (1) new form and four (4) new procedures were issued, and two (2) procedures were obsoleted. The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures and forms:
7 7 Nam
- , ~I Rev.e s e Notes-7:
AP-HP-105 Radiation Work Permit 10_f 11/23/2010 Cover Page AP-HP-120 Beamport Area 5 11/23/2010 Cover Page AP-HP-121 isotope Closet 5 12/30/2010 Minor Editorial AP-HP-23 .......Visitor Dosimetry - Reception Desk 7 [ 2/4/2010 Cover Page AP-HP-125 Review of Unplanned Radiation Exposure 3 [ 11/23/2010 Cover Page BPB-SH-002 20WC-1 Packaging and Shipment of Type B Non-Waste RadiOactive Material 9 2/3/2010 I Cover Page BPB-SH-005 DOT 6M Packaging of Type B Non-Waste Radioactive Material I 8 9/30/2010 Cover Page
__ dintv Material______________________ ___I_____________________
BPB-SH- .008 1Type B(U) F-327 Series Packaging of Type B 7 9/30/2010 Obsolete
-Non-Waste Radioactive Material 11-3
Number.. I* Name I Rev. ision Datel Notes ....
BPackaging O and Shipment of Radioactive Material 1 1 using USA DOT 7 A Model H or I Package 1 Cover Page
.....BPB-SH-020 . ShHpng0naier Reciept Inspection of Type B Byproduct Material 1 9/9/201.0 ... Cover Page Shipping ContainersI__ . _______
BPB-SH-021 '120.......
20 WC-I All-Thread Rod Replacment 6/3/2010 T. Cover Page BPB-SH-022 Painting USA DOT 20 WC-1 Overpack j BPB-SH-023 Torque Wrench Calibration J1 1 6/3/2010 .
- 6/3/2010 Cover Page Cover Page BPB-SH-024 Type B(U) F-458 Series Packaging of Type B 9/9/2010 Full Review Non-Waste Radioactive Material . .
Type B(U) ZA/NNR1005 (Beatrice) Packaging ofI BPB-SH-025
- Wase....on-..
Radioactive .Te R M MaterMateral I0 j 9/9/2010 Full Review g
F-327 Packaging and Shipment of Type A Non- Mi BP-SH-007 Radioactive 7/14/2010 Cover Page F-327 Packaging and Shipment of Type A BP-SH-0 Radioactie Material Packages 29/9/2010 Minor Editorial BP-SH-01^ [Packaging and Shipment of Non-Waste T A 4 2 PRadioactive Materials i Excepted Packages Pki Shipment of and Non-WasteUSADOT7AType MarI sSHB70!2
..... .............-7
-OTPack g.. ert.. c ti. .......... ... ......
...... 4 ., .!! , /20 ..C ve Pa e.....
Packaging and Shipment of Radioactive Material 1 Cover BP-SH-04 JSn an Ovrpck31/6/2010 Cove trPage BP-SH-012 BP-SH-013 SPackaging and Shipment of Radioactive Material Rdai aMUSA DOTabl Using u mentatn Doc.. . .
MtraSimnPcge andre7AyMoel Labeling1 Packaging and Shipment of Radioactive Materials 30 1p63/01.....oeag 6
/010 7/26/2010...............
Cover Page Pki oR ot iearlover sage IPackaging and Shipment of Radioactive Material I1 3 2/3/2010 Cover i Page BP-SH-01 using MURR Model 6 1 BP-SH-09 BP-SH-015 BPS-BP-SH-02 Moe Using 15011~
Fadiatin IPackaging no Wor perervice petatekS a e of Rand Shipment t Material11/23/2010..
RAMoeuale DOTMaterial p Radioactive R
7A 1 9Radioactive 8
/36/2010
//01]io 3//2010 r
[ C MioC, Cover dtra ioa Page FMP-2-59.......... Dosi2 Spetry R usingtrl AC ck sae Co di aestti e M equ f or e B etO a e ia U...U... 7 ...........
4/3/2010 r 10M Minor i o E Editorial i o r a.........
B ...... IlPackaging and Shipment of Radioactive Material ].I.....: ..
BP'-SH-059JU beli SnofdR L asin p:ctrate a ct iv e.........
adi ...........
oSerice t e....................
MaReusabl l S DO 7An ............
2" 2 /3S/2010 MinovrEdtriage TypAPackage Cve Pg BPS- 2 .M15 D.
........... Radioactive si..try MaterialsShipment
.......... Pakg
....... 6_
- 7. . 4/32 7/26/2011 CoverPage BP -SH -0..........................................e.i..........2/3/201t0 M inor E ditorial Coto hcsetfrDocumentation Lbln and 1Radioactive Materal Shipment of R t Material................. 82/01 oerPg BP-S-302 FMin3-R eksht 6oExcptd Pacag MontdlC 3 //00CvrPg
............. ........ adiactiv Ma9~~ hpmn .. 10 1/23/2010 .... Cover Page FM-352 o ouetto.ad ]/ /27/2010 8CnrlCekhe Cover Page
. .. ... .. R. dSc
................................ a elRad........ .. .......t ........ iM tm rp n...........t s h........................ .. . ...
h p.mne Radioactive Material Licensing and Project ýý FM-53 Designation Change Request 4 2/4/2010 Cover Page 11-4
_Number >4:.. f Name. m4j j;RevjRevision Date[
- q -Notes Control Checksheet for Spectratek Services FM-59 Reusable Type A Package Radioactive Materials 3 4/30/2010 Minor Editorial S...hipm .....ent .. ........ . .
Control Checksheet for Spectratek Services FM-59 Reusable Type A Package Radioactive Materials 4 11/16/2010 Minor Editorial Shipment .,_ _ ,
Control Check Sheet for MURR Shipment Using
U .1 6/3/2010 Cover Pag FM-69 ~ SControlChecksheet
~Radioactive MaterialsforShipment.............
MURR Reusable Type i FM-69 f~azieMtrasSimn yeAI6 6/3/2010 Minor Editorial
[Control Checksheet for Type B USA DOT 6M 1 Cover P M-4 Radioactive Materials Shipment 1 9/30/2010..
______Control Checksheet for Type B(U) F-327 Series FM-75 'RRadioactive Materials Shipment Materials S9/30/2010 i nObsolete FM-89FM-89 ]Control lRadioactive Checksheet MaterialforShipment Type A F-327 Series 8 7/14/2010 CvrPg Cover Page FM-91 Declaration of Pregnancy 3_j /32 0 Cover Page FM-94 Exclusive Use Shipment Controls 4/12/2010 Cover Page Control Checksheet for MURR Shipment Using I FM-98 USA DOT 7A MURR Model 6 or 12 5 8/27/2010 FM-99 - Control Checksheet for USA DOT 7A MURR 1 ] 1 Minor Editorial Model 1500 Series 5 1 FM-120 Individual Type B QA Training Certification 1ir21 2/3/2010 Mn Editorial FM126 ]Documentation of Compliance for DOT-7A 4/30/2010 Minor Editorial
. ........... Shipping Container] .............. . .
FControl Check Sheet For MURR Shipment Using I FM128 ]USA DOT 7A MURR Model H or I ] 8/27/2010 Cover Page MControl Checksheet for Receipt Inspection of FM-___ _ (BeaType B Byproduct Material Shipping ContainersF ve FM-135 Control Checksheet for Type B(U) ZA/NNR1005 I(Beatrice) Radioactive Materials Shipment To__1 u wz.9/9/2010 u ee FM- 150 [Statement of Training and Experience 2 [ 2/15/2010 MinorEditorial
........ Control OverpackCheksheet Rod Replacmentfor USA DOT 20 WC-1 I I FM-154 [~~c o elcet1 6/3/20 10 j Cover Page FM-155 Quality Assurance Control Checksheet Exterior Painting of USA DOT WC-1, Type B Overpack 1.?!lCvrPg .16/3/2010
[Control Checksheet for Type B(U) F-458 Series FRadioactive Materials Shipment 1/9200 ........Full Review HC-PSO_002 HC-p500 Hot Cell Preparation of Radioactive Material aeia 9~imn 3/31/2010....................... Minor Editorial 3/31/2010
_______ ShipmentI__I_ _ _ _ _ _ _ _
HC-PSO003 iGlove Box Preparation of Radioactive Material for MinorEditorial HC-PSO____ j00 pen 8 3/24/2010 MioEdtra HC-PSO-005 ]Hot Cell Loading of ..Host
................................................... Cans
............................. ............................ ]...............
7 : 340Mir or3/4/E1ditMnooEitrill ti IC-HP-305
.. ..[Calibration Electrostatic Discharge
..i-br.........................
a-t.
... Dosimeter 6 3/23/2010
........ ir Editor
..............Minor Editorial IC HP.341 Calibration - High Resolution Gamma 3/23/2010 C P
,_______Spectroscopy Systems ...... ...... I CoverPage Calibration - Lab Impex Stack Monitor-Particulate IC-HP-349 ' I 7/8/2010 Minor Editorial Channel 11-5
Number ~L C~K~ 'Name~ j8e. lRevision DatelJ Notes~
IRR-PSO-1 12 Preparing Shipping Paperwork . 4 1 11/9/2010 1 Minor Editorial OP-HP-220 ITritium Bioassay 6 11/23/2010 1 Cover Page OP-HP-223 Spent Fuel Shipping Cask Water Sample Analysis 4 [12/30/2010 1 Cover Page OP-HP-300 Receipt of Radioactive Material 1 T 2/4/2010 1 Minor Editorial OP-HP-306 ]Daily Facility Checks T3 9/30/2010 Minor Editorial OP-HP-353ý iWaste Tank Sample - Analysis T6 T 11/24/2010 1 Cover Page OP HP..356 Operation - Lab Impex Stack Monitor - Filter 0 780 O Pta ge anou ceneS... .. ................................06...... 7/8/2010 Full R eview OP-HP-400 'Gemstone Shipping Barrel Analysis .7 ,1/14/2010 ] Minor Editorial OP-HP-420 Decontamination of Enclosed Processing Units 3 2/4/20 10 Minor Editorial OP-HP-505 Stack Monitor Filter Analysis SEm.ergency 4 6 0 Minor Editorial QAB-SH-005 .Type B QA Personnel Training I1. 6/3/20109 Mintor Editorial Stack Monitor Preventative Maintenance - Lab RM-HP-102 0 11/24/2010 Full Review RP-HP-130 Receipt of New Fuel Elements 6 7/8/2010 Minor Editorial RP-HP-135 Room 114 Entry - Self Monitored I 5 1 11/23/2010 T Cover Page RP-HP-137
!Handling Radioactive Material in the Reactor P 11.. 9 7/8/2010 1 Minor Editorial RP-HP-137 Handling Radioactive Material in the Reactor Pool 10 1/23/2010 T Cover Page RP-HP-139 13Beamport Radiation Level Monitoring During Reactor3Startup. 1.......3 I 11/23/2010 Cover Page SV-HP- 119 Property Release '1.4 j 6/9/20,10 f Cover Page r
- Bulding Exhaust Stack Effluent- Ar-41 SV-HP-121 ]M onitoring ........ ...... 4 ...... 4/21/2010 111111 Minor
...... Editorial SV-HP-130 Emergency Air Sampling of Exhaust Plume 11/24/2010 1 Cover Page
"..Tsp-02 .. .Transportation Security Plan 1 4 . 8/6/2010 . FullReview WM-SH-105 !:RadioactiveWaste Processing 6 1 11/16/20101 Cover Page Exclusive Use Shipment of LSA or SCO WM-SH-300 8 7/26/2010 Minor Editorial Radioactive Waste 11-6
SECTION III REVISIONS TO THE HAZARDS
SUMMARY
REPORT January 1, 2010 through December 31, 2010 These changes were approved by the Reactor Manager and reviewed by licensed staff and members of the Reactor Safety Subcommittee and have been determined not to involve a change to the Technical Specifications. These changes have all been reviewed in accordance with 10 CFR 50.59.
HAZARDS
SUMMARY
REPORT (ORIGINAL JULY 1, 1965)
Original HSR, Figure 5.1, Piping & Instrument Diagram (as revised by the 1972-73, 1973-74, 1994, 1996, 2001, 2002, 2003, 2004, 2006, 2007 and 2009Reactor Operations Annual Reports):
Replace with: Updated Figure 5.1, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet 1 of 1, dated 12/15/10)
Original HSR, Section, 7.1.4, paragraph 2, sentence 2, page 7-3 (as revised by the 1972-73, 1989-90, 2002, 2004 and 2009 Reactor Operations Annual Reports):
Delete: The word "50%"
Replace with: "40%"
Original HSR, Section 7.1.4, paragraph 3, page 7-4 (as revised by the 1972-73, 1989-90, 2002, 2004 and 2009 Reactor Operations Annual Reports):
Add: "(17) North Office Addition Stack Monitor"
"(18) North Office Addition Fire Protection Panel"
"(19) Cyclotron Control, Processing, and Pharmacy" ADDENDUM 1 - HAZARDS
SUMMARY
REPORT (FEBRUARY 1966)
HSR, Addendum 1, Section 3.8, paragraph 4, page 24, (as revised by the 1989-90, 2002 and 2004 Reactor Operations Annual Reports):
Add: "6) North Office Addition Emergency Lighting Panel (NOA ELP), which feeds through a transformer and 120/208 volt distribution panel, supplies NOA systems including facility access and security, fire protection, computer servers, NOA stack monitor, and Cyclotron control, processing and pharmacy."
HSR, Addendum 1, Figure 3.22.2, page 104, Ventilation Air Flow Diagram for the East Tower (as revised by 1995 and 2004 Reactor Operations Annual Reports):
Replace with: Updated Figure 3.22.2, MURR Supply Air Schematic (MURR Dwg No. 1125, Sheet 2 of 4, dated 12/16/09) 111-1
ADDENDUM 3 - HAZARDS
SUMMARY
REPORT (AUGUST 1972)
HSR, Addendum 3, Figure 2.3.a, page 23a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, 2005, 2006, 2007 and 2009 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of 5, dated 5/11/10)
HSR, Addendum 3, Figure 2.3.b, page 23b, Electrical Distribution (as added by the 1995 and revised by the 2001, 2002, 2003, 2004, 2005, 2007 and 2009 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.3.b, Electrical Distribution North Office Addition (MURR Dwg No. 522, Sheet 2 of 5, dated 3/25/10)
HSR, Addendum 3, Figure 2.3.c, page 23c, Electrical Distribution (as added by the 2004 and revised by the 2005, 2007 and 2009 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.3.c, Electrical Distribution Reactor/Laboratory Panels (MURR Dwg No. 522, Sheet 3 of 5, dated 5/11/10)
HSR, Addendum 3, Figure 2.3.d, page 23d, Electrical Distribution (as addedby the 2007 and revised by the 2008 and 2009 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.3.d, Electrical Distribution Reactor/Laboratory Panels-2 (MURR Dwg No. 522, Sheet 4 of 5, 3/25/10)
HSR, Addendum 3, Figure 2.3.e, page 23e, Electrical Distribution (as added by the 2007 and revised by the 2009 Reactor Operations Annual Report):
Replace with: Updated Figure 2.3.e, Electrical Distribution North Office Addition Panels (MURR Dwg No. 522, Sheet 5 of 5, dated 3/25/10)
ADDENDUM 4 - HAZARDS
SUMMARY
REPORT (OCTOBER 1973)
HSR, Addendum 4, Figure A.11, page A-38, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (as revised by the 1995, 2002, 2005 and 2009 'Reactor Operations Annual Reports):
Replace with: Updated Figure A. 11, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (MURR Dwg No. 1125, Sheet 1 of 4, dated 1/13/10)
ADDENDUM 5 - HAZARDS
SUMMARY
REPORT (JANUARY 1974)
HSR, Addendum 5, Section 2.2, paragraph 7, page 5 (as revised by the 1989-90 and 2004 Reactor Operations Annual Reports):
Add: "(5) One circuit services a distribution panel, which feeds through a transformer and 120/208 volt distribution panel, to supply North Office Addition systems including facility access and security, fire protection, computer servers, NOA stack monitor, and Cyclotron control, processing and pharmacy."
111-2
HSR, Addendum 5, Section 2.4.1, page 12 (as revised by the 1989-90, 2002, 2004 and 2009 Reactor Operations Annual Reports):
Add: "(17) North Office Addition Emergency Lighting Panel (NOA ELP)
Normal supply power would be lost to the affected NOA electrical loads.
However, there are no electrical loads in NOA that are required to accomplish a safe shut down of the reactor or to maintain a safe shutdown condition."
HSR, Addendum 5, Figure 2.1, page 15, Electrical Distribution (as revised by the 1989-90, 2001, 2002, 2003, 2004, 2005, 2006, 2007 and 2009 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of 5, dated 5/11/10) 111-3
SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2010 through December 31, 2010 For each facility modification described below, the MURR has on file the safety screen or evaluation, as well as the documentation of review, performed in accordance with 10 CFR 50.59.
Modification 01-9, Addendum 2:
Emergency Electrical System in North Office Addition This addendum to modification record01-9, "Installation of Emergency Lighting Panel No. 1," documents the extension of the Emergency Electrical Power System to the North Office Addition (NOA). This system extension provides 120/208 VAC electrical power to key NOA systems such as facility access and security, fire protection, computing servers, stack monitor, and Cyclotron processing and pharmacy.
Modification 10-1:
Addition of Junction Box and Terminal Board for Control Rod Drive 'D' Drive Cable This modification record documents the addition of a junction box and terminal board to the drive cable for control rod 'D' drive mechanism. The more frequent handling of control rod 'D' drive mechanism drive cable increases the likelihood of damage to the cable. Previous efforts at providing strain relief at significant flexure points have been less effective than desired. This modification record documents the addition of a junction box and terminal board near the drive mechanism. This addition reduces the magnitude of flexure and should extend the service life of the drive cable. The addition has the added advantage that when drive cable replacement is necessary; this work can be accomplished with a much shorter length of cable and can be performed entirely from the upper bridge.
IV-1
SECTION V NEW TESTS AND EXPERIMENTS January 1, 2010 through December 31, 2010 New tests or experiments developed during this period under a Reactor Utilization Request (RUR) or Reactor License (RL) Project are as follows:
RUR 118, as amended: Molybdenum
Description:
This RUR authorizes an increase in the allowable mass of molybdenum metal, natural or enriched, based on the encapsulation style and heat load restrictions; for research and development activities.
RUR 243, as amended: Graphite
Description:
This RUR authorizes the long term irradiation of natural graphite in support of research and development activities.
RUR 416, as amended: Iridium
Description:
This RUR authorizes an increase in the enrichment and mass of iridium, based on the encapsulation style and heat load restrictions, in support of research and development activities.
RUR 435: Molybdenum Trioxide (Molybdenum Oxide)
Description:
This RUR authorizes the irradiation of up to 270.0 grams of natural or enriched molybdenum trioxide in support of research and development activities.
RUR 436: Hydroxyapatite
Description:
This RUR authorizes the irradiation of up to 1.0 g of hydroxyapatite in support of research and development activities.
Thermal Neutron Beam-Line for Neutron Capture Therapy on Beam Port E
Description:
Test irradiations using the newly commissioned neutron irradiation facility designed for the development of neutron capture therapy (NCT) agents were conducted by the MU researchers during 2010. Neutron and gamma flux and dose measurements, as well as various other calibration and characterization measurements of the beam line, were completed earlier.
Each of these tests or experiments has a written safety evaluation on file, and a 10 CFR 50.59 Screen if applicable, to assure that the test or experiment is safe and within the limits of the Technical Specifications.
The safety evaluations have been reviewed by the Reactor Manager, Reactor Health Physics Manager, Assistant Reactor Manager-Physics, and the Reactor Safety Subcommittee, as applicable.
V-1
I SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2010 through December 31, 2010 Inspections:
There was one NRC inspection which reviewed Special Nuclear Material activities. All records and activities were found to be in compliance with NRC rules and regulations. No violations were noted.
Reactor Characteristic Measurements:
Fifty-six (56) refueling evolutions were completed in 2010. Excess reactivity verifications were performed for each refueling. The largest measured excess reactivity value was 3.63%. MURR Technical Specification 3.1 (f) requires excess reactivity to be less than 9.8%.
Reactivity Measurements:
Differential blade-worth measurements of three (3) shim control blades were performed following either a planned replacement of a control blade or characterization of the bum-in effect of a new control blade.
Six (6) reactivity measurements were performed to determine the reactivity worth of all samples, including the sample holder, loaded in the flux trap region.
Three (3) reactivity measurements were performed to determine the reactivity worth of various sample cans irradiated in the flux trap region.
In support of the Nuclear Engineering student labs, one (1) differential blade-worth measurement and one (1) primary coolant temperature coefficient measurement were also performed.
VI-1
SECTION VII RADIOACTIVE EFFLUENT January 1, 2010 through December 31, 2010 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2010 through December 31, 2010 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide Activity (Ci)
H-3 7.374E-02 S-35 4.648E-03 Lu-177 4.615E-03 Co-60 1.494E-03 Ca-45 1.128E-03 P-32 7.943E-04 Lu-177m 6.512E-04 Zn-65 4.672E-04 Sc-46 1.607E-04 Cr-51 5.115E-05 Rb-86 3.950E-05 Ag-110i n 3.202E-05 Mn-54 2.582E-05 Au-198 1.534E-05 Total H-3 7.374E-02 Total Other 1.412E-02 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, 2010 through December 31, 2010 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration Total Release TS Limit Multiplier % TS (pCi/ml) (Ci)
Ar-41 2.03E-06 1.03E+03 350 58.0857 C-14 1.74E- 11 8.79E-03 1 0.5800 1-131 8.29E-14 4.20E-05 1 0.0415 H-3 1.23E-08 6.25E+00 350 0.0353 Os-191 5.88E-13 2.97E-04 1 0.0294 Co-60 4.18E-15 2.12E-06 1 0.0084 S-35 1.65E-14 8.33E-06 1 0.0005 Cs-137 8.84E-16 4.48E-07 1 0.0004 Ba-140 3.38E-15 1.71E-06 1 0.0002 Co-58 1.10E-15 5.57E-07 1 0.0001 Hf-175 1.01E-15 5.12E-07 1 0.0001 Ru- 103 7.35E-16 3.72E-07 1 0.0001 1-133 2.74E-13 1.39E-04 350 0.0001 As-77 1.91E-12 9.68E-04 350 0.0001 Note: C-14 activity is, calculated based on the ratio of argon to nitrogen in the air and the (n,p) reaction cross sections for the activation of N-14 to C-14.
Isotopes observed at < 0.0001% Technical Specification limit are not listed.
Stack Flow Rate = -34,000 cfin Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, License R-103 Technical Specifications.
VII-2
SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2010 through December 31, 2010 Environmental samples are collected two times per year at eight (8) locations and analyzed for radioactivity. Soil and vegetation samples are taken at each location. Water samples are taken at three (3) of the eight (8) locations.
Analytical results are shown in Tables 1 and 2.
Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2010. All doses are approximately 17 mRemlyear or less, except monitor numbers 9, 15 and 46. These monitors are located near loading dock areas 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 77 Spring 2010 Detection Limits' Matrix Alpha Beta Gamma Tritium Water 0.00 pCi/L 3.21 pCi/L 204.97 pCi/L 4.95 pCi/mL of sample Soil 0.00 pCi/g 1.85 pCi/g 0.51 pCi/g N/A Vegetation 1.98 pCi/g 7.75 pCi/g 1.40 pCi/g 4.17 pCi/mL of distillate Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL) 1V77 < 1.98 17.75 < 1.40 <4.17 2V77 < 1.98 15.43 < 1.40 <4.17 3V77 < 1.98 8.73 < 1.40 <4.17 4V77 < 1.98 17.32 < 1.40 <4.17 5V77 < 1.98 15.31 <1.40 <4.17 6V77 < 1.98 17.83 < 1.40 <4.17 7V77 < 1.98 24.12 < 1.40 <4.17 10V77 < 1.98 21.17 1.44 <4.17 VIII-1
TABLE 1 (Cont'd)
Summary of Environmental Set 77 Spring 2010 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1S77 0.42 12.37 2.57 2S77 0.64 10.23 1.94 3S77 0.94 15.20 2.01 4S77 0.91 9.94 2.66 5S77 1.12 15.72 3.41 6S77 1.23 11.00 3.15 7S77 -0.54 10.05 3.06 10S77 1.11 13.58 2.82 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W77 0.16 <3.21 < 204.97 < 4.95 6W77 0.16 3.38 < 204.97 < 4.95 10W77 0.16 5.56 < 204.97 < 4.95 Note 1: Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity.
TABLE 2 Summary of Environmental Set 78 Fall 2010 Detection Limits' Matrix Alpha Beta Gamma Tritium i'
Water 1.06 pCi/L 4.30 pCi/L 203.25 pCi/L 7.39 pCi/mL of sample Soil 0.00 pCi/g 3.83 pCi/g 0.60 pCi/g N/A Vegetation 0.00 pCi/g 5.54 pCi/g 1.40 pCi/g 6.15 pCi/mL of distillate VIII-2
TABLE 2 (Cont'd)
Summary of Environmental Set 78 Fall 2010 Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL) 1V78 0.00 12.74 < 1.40 <6.15 2V78 0.30 12.22 < 1.40 <6.15 3V78 0.61 10.08 2.25 <6.15 4V78 0.31 18.94 < 1.40 <6.15 5V78 0.00 25.47 4.68 <6.15 6V78 0.32 15.61 < 1.40 28.09 7V78 0.00 23.17 < 1.40 <6.15 10V78 0.93 23.37 < 1.40 < 6.15 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1S78 0.61 17.26 1.63 2S78 0.78 7.73 2.53 3S78 0.64 8.30 2.91 4S78 2.26 8.22 3.16 5S78 1.39 13.40 3.25 6S78 0.30 13.87 2.54 7S78 1.70 7.55 2.92
'10S78 0.60 13.97 2.26 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W78 < 1.06 <4.30 < 203.25 <7.39 6W78 < 1.06 <4.30 < 203.25 <7.39 10W78 < 1.06 6.49 < 203.25 <7.39 Note 1: Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity.
VIII-3
TABLE 3 Environmental TLD Summary January 1, 2010 through December 31, 2010 Badge Direction Map Distance from 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total Number From MURR MURR Stack 2010 2010 2010 2010 2010 (meters) Net mR Net mR Net mR Net mR Net mR 1 Control N/A 2.5 0.0 0.8 4.9 8.2 2 Control N/A 0.5 0.6 0.0 4.8 5.9 3 WSW N/A 0.0 0.0 0.0 1.6 1.6 4*
5*
6 N 34 0.0 4.5 2.4 8.5 15.4 7 NE 57 5.5 2.5 0.1 4.5 12.6 8 SW 27 0.0 5.7 1.2 7.4 14.3 9 S 27 21.8 24.3 29.2 34.2 109.5 10 NE 149 0.0 0.0 0.0 2.0 2.0 II NW 149 0.0 3.1 2.6 5.0 10.7 12 ENE 301 4.6 4.8 1.4 6.8 17.6 13 NNE 316 0.0 0.0 4.3 3.7 8.0 14 S 156 0.8 0.0 0.0 6.6 7.4 15 S 65 15.9 21.8 16.0 21.5 75.2 16 SE 107 0.0 0.0 0.0 4.2 4.2 17 E 293 0.0 0.0 0.0 1.1 1.1 18 NE 476 0.0 0.0 0.0 0.0 0.0 19 NNE 606 0.0 0.0 0.0 0.0 0.0 20 NE 907 0.0 0.0 0.0 0.0 0.0 21 SE 236 1.2 0.0 0.0 3.4 4.6 22 ESE 168 0.0 0.0 0.0 0.0 0.0 23 NW 110 3.4 0.0 2.8 4.3 10.5 24 SSW 328 0.0 0.0 0.0 10.2 0.0 25 SSW 480 0.5 0.4 1.1 2.8 4.8 26 SW 301 0.0 0.7 0.0 2.1 2.8 27 WSW 141 0.0 0.0 0.0 0.0 0.0 28 WNW 210 0.0 2.0 0.0 3.6 5.6 29 NW 255 0.0 0.3 0.0 3.7 4.0 30 NNW 328 0.0 absent 0.0 2.0 2.0 31 NNW 671 0.0 2.5 0.4 4.8 7.7 32 NNW 724 0.0 0.0 1.3 3.2 4.5 33 E 671 0.0 0.0 0.0 0.0 .0.0 34 ENE 587 0.0 absent 0.0 0.0 0.0 35 SSE 499 0.0 0.0 0.0 0.7 0.7 36 SE 419 0.0 0.0 0.0 0.0 0.0 37 NE 690 0.0 0.2 0.0 2.0 2.2 38 NW 556 0.2 2.0 0.0 4.4 6.6 39 W 491 0.0 0.0 0.0 1.8 1.8 40 N 514 0.0 0.0 0.0 0.0 0.0 41 NNE 137 0.0 0.0 0.0 0.0 0.0 42*
43*
44 Spare N/A 1.7 0.9 0.3 6.2 9.1 45 S 65 .0.0 0.0 0.0 4.2 '4.2 46 E 70 New New 10 10.2. 20.2
- These badge numbers are no longer used.
VIII-4
TABLE 4 Number of Facility Radiation and Contamination Surveys January 1, 2010 through December 31, 2010 Radiation Surface Contamination* Air Samples** RWP's January 66 66 44 5 February 47 47 19 5 March 98 98 49 10 April 54 54 39 8 May 63 63 42 6 June 91 91 33 4 July 58 58 35 4 August 72 72 21 5 September 64 64 34 3 October 86 86 54 5 November 59 59 50 10, December 57 57 52 7 TOTALS 815 815 472 72
- In addition, general building contamination surveys are conducted each normal work day.
- Air samples include exhaust stack Ar-41, containment building Ar-41, sump entries, and hot cell entries.
Miscellaneous Notes Ed Werner transferred from the Shipping/Hot Cell Group to the Health Physics Group in September 2010 to serve as a Health Physics Technician.
During calendar year 2010, MURR shipped 670 cubic feet of low-level radioactive waste containing 1, 156 mCi of activity.
VIII-5
SECTION IX
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS January 1, 2010 through December 31, 2010 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP Month AC DO FSO HC/SH RAG IRR NA NS OPS PRO RES RP SIL Total January 25 11 48 303 136 12 6 18 1146 115 9 47 69 1945 February 12 7 80 268 191 5 14 21 870 114 7 78 53 1720 March 5 18 38 250 160 14 29 16 1329 203 22 58 97 2239 April 43 33 167 395 184 4 40 9 1271 105 14 107 56 2428 May 26 32 97 347 126 12 29 34 1080 113 36 98 89 2119 June 29 42 70 478 218 15 39 75 1519 182 83 55 103 2908 July 59 87 134 256 171 28 56 73 1194 164 101 124 133 2580 August 57 62 165 325 296 32 71 62 1223 110 111 138 96 2748 September 36 38 135 291 183 14 66 51 954 166 116 175 96 2321 October 26 76 150 300 179 13 36 63 1279 116 88 134 123 2583 November 27 59 100 318 194 11 39 55 1171 155 99 116 104 2448 December 11, 7 37 366 302 8 41 32 1487 147 30 120 118 2706 Total to Date 356 472 1221 3897 2340 168 466 509 14523 1690 716 1250 1137 28745 Monthly Ave 30 39 102 325 195 14 39 42 1210 141 60 104 95 2395 Highest WB 101 32 312 1373 973 67 68 104 794 476 115 268 492 Highest EXT 2440 30 1650 4300 1270 M 2400 140 1110 4890 320 2260 1360 AC - Analytical Chemistry IRR - Irradiations RES - Research DO - Director's Office NA - Nuclear Analysis RP - Radiopharmaceutical FSO - Facility Support Organization NS - Neutron Scattering SIL - Silicon HC/SH - Hot Cell/Shipping OPS - Operations RAG - Regulatory Assurance Group PRO - Isotope Production WB = Whole Body EXT = Extremities M = Minimal Dosimetry services are provided by R.S. Landauer Jr. & Company (except self-reading dosimetry).
Analysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA. Radiation workers who are not full time staff members have radiation exposures which are generally lower than full time radiation workers.
IX-1