ML100560441
| ML100560441 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 02/24/2010 |
| From: | Foyto L Univ of Missouri - Columbia |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML100560441 (34) | |
Text
Research Park Research Reactor Center Columbia, MO 65211 University of Missouri-Columbia PHONE (573) 882-4211 FAX (573) 882-6360 February 24, 2010 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 2009 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, 2009 through December 31, 2009.
This document is submitted to the U.S. Nuclear Regulatory Commission in accordance with the University of Missouri Research Reactor Technical Specification 6.1 .h(4).
If you have any questions regarding the contents of this report, please contact me at (573) 882-5276 or FoytoLnamissouri.edu.
Sincerely, Les P. Foyto Reactor Manager LPF/djr Enclosure xc: Mr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC AIQ2.O QlU?4 AN EQUAL OPPORTUN1TY/ADA 1NSTITUrFION
UNIVERSIfTY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2009 - December 31, 2009
UNIVERSITY OF MISSOURI .
RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2009 through December 31, 2009 Compiled by the Research Reactor Staff of MURR Submitted by:
Leslie P. FoytV Reactor Manager Reviewed and approved by:
Ralph A. Butler, PE Director
UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2009 through December 31, 2009 INTRODUCTION The University of Missouri Research Rtactor (MURR) is a multi-disciplinary research and education facility providing a broad range of analytical, materials science, and irradiation services to the research community and the commercial sector. Scientific programs include research in archaeometry, epidemiology, health physics, human and animal nutrition, nuclear medicine, radiation effects, radioisotope studies, radiotherapy, and nuclear engineering; and research techniques including neutron activation analysis, neutron and gamma-ray scattering, and neutron interferometry. The heart of this facility is a pressurized, reflected, open pool-type, light water moderated and cooled, heterogenous reactor designed.for operation at a maximum steady state power level of 10 Megawatts thermal - the highest powered University-owned research reactor in the United States.
The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2009. Included within this report are changes to MURR procedures, revisions to the Hazards Summary Report, facility modifications, new tests and experiments, reactor physics activities, and environmental and health physics data.
This Report is being- submitted to the U.S. Nuclear Regulatory Commission (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 mad&, 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 this calendar year included (1) establishing and characterizing an irradiation facility on Beamport 'E' in support of the Boron Neutron Capture Therapy project, (2) irradiating and processing a 5-gram low-enriched uranium (LEU) target to determine the feasibility of producing fission product molybdenum-99 from LEU, and (3) securing the next generation fresh and spent fuel shipping containers. Additionally, in August 2006 MURR submitted a request to the NRC to renew Amended Facility Operating License R-103. This year the NRC began the i
review process of our submittal. Significant efforts have already been placed in responding to the Requests for Additional Information (RAIs) and these efforts will continue in the upcoming year.
The facility is also actively collaborating 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 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.
ii
TABLE OF CONTENTS Section Title Pages I. Reactor Operations Sum m ary ............................................................... I-I through 6 II. M U RR Procedures .............................................................................. I1 -I 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 .......................................... Ill-I through 4 IV. Plant and System M odifications ..................................... :..................... IV-l through 2 V. New Tests and Experiments ............................................................ V-I VI. Special Nuclear Material and Reactor Physics Activities ..................... VI-I VII. Radioactive Effl uent ............................................................................. 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 75 Table 2 - Summary of Environmental Set 76 Table 3 - Environmental TLD Summary Table 4 - Number of Facility Radiation and Contamination Surveys IX. Summary of Radiation Exposures to Facility Staff, Experimenters, and V isitors ........................................................................................... IX -1
SECTION 1 REACTOR OPERATIONS
SUMMARY
January 1, 2009 through December 31, 2009 The following table and discussion summarizes reactor operations during the period from January 1, 2009 through December 31, 2009.
Full Power % of Full Power % of Month Full Power Hours Megawatt Days Total Time Scheduled(')
January 683.79 284.97 91.9 102.9 February 607.11 253.02 90.3 101.2 March 674.91 281.29 90.7 101.6 April 646.52 269.50 89.8 100.7 May 671.42 279.82 90.2 101.0 June 637.30 265.65 88.5 99.3 July 681.25 283.91 91.6 102.5 August 668.24 278.52 89.8 100.6 September 659.64 274.90 91.6 102.7 October 669.26 278.95 90.0 100.7 November 648.55 270.33 90.1 101.0 December 687.63 286.59 92.4 103.5 Total for 7935.62 3307.45 90.58 % 101.48 %
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 2009 The reactor operated continuously in January with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one scheduled shutdown for a physics measurement. There were no unscheduled/unplanned power reductions this month.
\
Major maintenance items for the month included: replacing the pump-end of primary coolant system circulation pump P-501B; adjusting the scram set point on reflector differential pressure transmitter PT-917; refurbishing and cleaning the gasket inflate and deflate solenoid assemblies and valve actuators on containment ventilation isolation Doors 504 and 505 three-way, dual solenoid-operated valves; 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);" refurbishing and cleaning the gasket inflate and deflate solenoid assemblies and valve actuators on containment personnel airlock Doors 276 and 277 three-way, dual solenoid-operated valves; replacing rod control power unavailable relay 1K30; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-I I(D);" draining and back-flushing Beamport 'E' with helium for flux measurements in support of the Boron Neutron Capture Therapy I-1
project; replacing the west pneumatic tube system blower and motor; replacing cooling tower fan CTF-3 gearbox; and completing Modification Record 96-1, Addendum 2, "Removal of the Nuclepore Experiment Equipment."
February 2009 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance. There were no unscheduled/unplanned power reductions this month.
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; refurbishing air control valve A-146; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-11(D);" replacing the Eberline stack monitor blower motor; refurbishing and cleaning the gasket inflate and deflate solenoid assemblies and valve actuator on containment truck entry Door 101 three-way, dual solenoid-.
operated valve; replacing containment exhaust ventilation isolation valve 16B; replacing the electrical supply breaker for the valve operating system air compressor; and performing flux measurements on Beamport 'E' in support of the Boron Neutron Capture Therapy project.
March 2009 The reactor operated continuously in March with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and two scheduled shutdowns for physics. measurements. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: replacing the pump casing gasket on primary demineralizer system pump P-513A; sealing the containment sump abandoned underground gravity drain lines; 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 three (3) sets of flux measurements on Beamport 'E' in support of the Boron Neutron Capture Therapy project; performing a zero and span procedure on primary coolant system flow transmitter FT-912E chart recorder; completing compliance procedure CP-29, "Calibration of the NMC RAK Radiation Stack Monitor;" replacing the springs in the gasket inflate and deflate solenoid assemblies and valve actuator on containment personnel entry Doors 276 and 277 three-way, dual solenoid-operated valves; replacing cooling tower fan CTF-3 gear box shaft oil seal; performing a reactivity worth measurement in accordance with reactor test procedure "RTP Experimental Measurement of the MURR Primary Temperature Coefficient of Reactivity;" replacing the springs in the gasket inflate and deflate solenoid assemblies and valve actuators on containment ventilation isolation Doors 504 and 505 three-way, dual solenoid-operated valves; and flooding Beamport 'E' with demineralized water.
April 2009 The reactor operated continuously in April with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one scheduled shutdown for a physics measurement, and two unscheduled/unplanned power reductions.
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On April 25, with the reactor operating at 10 MW in the automatic control mode, a "Power Level Interlock" reactor scram was automatically initiated. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. 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. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
On April 26, with the reactor operating at 10 MW in the automatic control mode, a "Power Level Interlock" reactor scram was automatically initiated. All immediate and subsequent actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Control room operators noted that the scram annunciation failed to "lock in" and had reset immediately. Once again, investigation of all relays, switches and wiring associated with the power level interlock circuit revealed no abnormalities. 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. The reactor was subsequently restarted to 10 MW operation.
Major maintenance items for the month included: loading new de-ionization bed 'R' and placing it on pool coolant system service; replacing the drive chain attachment mounting plates on containment building personnel entry Doors 276 and 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)" in support of the natural metal molybdenum-99 project; irradiating a low-enriched uranium (LEU) foil annular target in the K-2 irradiation position in support of the fission product molybdenum-99 project; completing the biennial change-out of control blade 'A' offset mechanism; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential"Worth of a Shim Blade, RTP- I1(D);" replacing power level interlock relay 2K9; draining and back-flushing Beamport 'E' with helium for flux measurements in support of the Boron Neutron Capture Therapy project; and performing the biannual cleaning of the cooling tower sump and basin.
Note: Replacement of power level interlock relay 2K9 was performed as a troubleshooting action in response to the two unscheduled power reductions that occurred this month. In September, reactor core differential l6ressure alarm unit EP-929 was also replaced. After bench top testing of both components, the most likely cause of the power reductions was determined to be alarm unit EP-929: Although neither component had failed, the reset set point of alarm unit EP-929 was not always repeatable.
May 2009 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one scheduled shutdown for a physics measurement. There were no unscheduled/unplanned power reductions this month. Additionally, U.S. Nuclear Regulatory Comnmission regional inspectors conducted a routine inspection of the Radiation Protection Program and Shipping.
Major maintenance items for the month included: installing the NEER Grant cobalt irradiation facility; performing an "end-of-life" inspection on two spent fuel elements; completing portions of Modification Record 01-09, Addendum 2, "Emergency Electrical System in North Office Addition;" repairing the amphenol connection, on control rod 'D' drive mechanism; completing compliance procedure CP-26, "Containment Building Compliance Test;" replacing cooling tower fan CTF-2 gearbox; 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 2009 The reactor operated continuously in June with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and one unscheduled/unplanned power reduction. Additionally, three reactor startups and two shutdowns were performed in support of U.S. Nuclear Regulatory Commission operator licensing examinations. U.S.
Nuclear Regulatory Commission examiner conducted operator licensing examinations.
On June 15, 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 when control blade 'D' anvil separated from its electro-magnet during a routine sample handling evolution. The immediate actions of REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques. The reactor was refueled and remained shutdown for previously scheduled maintenance activities. After completion of maintenance activities, the reactor was restarted to 10 MW operation.
Major maintenance items for the month included: replacing Nuclear Instrumentation signal processor No. 2 power range monitor (PRM-5) isolator; replacing primary coolant isolation valve V507A/B position interlock relay 2KI 1; 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 the north shock absorber on containment building personnel entry Door 276; replacing Nuclear Instrumentation signal processor No. 2 intermediate range monitor (IRM-3) isolator; completing compliance procedure CP-31, "Calibration of the Eberline Radiation Stack Monitor;" collecting reflector differential pressure data in support of the fission product molybdenum-99 project; performing a zero and span procedure on primary coolant system flow transmitter FT-912G and square root converter EP-919G as part of the instrument calibration; performing a zero and span procedure on primary coolant system flow transmitter FT-912H as part of the instrument calibration; 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)."
July 2009 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: replacing the valve bonnet on containment truck entry Door 101 three-way, dual solenoid-operated valve; placing the Lab Impex stack monitor on line for testing; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP- I1(D);" replacing a latch finger on the flux trap hold down device; performing a zero and span procedure and adjusting the scram set points on reflector differential pressure transmitter PT-917 as part of the instrument calibration; replacing the motor and gearbox assembly on containment building personnel entry Door 276; and replacing the trip set point adjustment switch on containment building ventilation exhaust Air Plenum No. 2 radiation monitor.
August 2009 The reactor operated continuously in August with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and two scheduled shutdowns for physics measurements. There were no 1-4
unscheduled/unplanned power reductions this month. Received notification from the U.S. Nuclear Regulatory Commission that three (3) new Reactor Operator licenses had been issued.
Major maintenance items for the month included: 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);" performing troubleshooting maintenance on the Uninterruptible Power Supply' (UPS); replacing Nuclear Instrumentation wide range pico-ammeter with a refurbished unit; replacing Nuclear Instrumentation signal processor No. 1 fission chamber detector and cabling; and connecting normal electrical power to the shipping and receiving building as part of Modification Record 04-05, Addendum 7, "Extension of Normal Electrical Service from MCC-1 to the Shipping and Receiving Building."
September 2009 The reactor operated continuously, in September 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 zero and span procedure on primary coolant system flow transmitter FT-912A as part of the instrument calibration; completing Modification Record 06-03, Addendum 2, "Replace Flux Trap Holder Wear Ring;" removing the NEER grant cobalt irradiation facility; completing compliance procedure CP-29, "Calibration of the NMC RAK Radiation Stack Monitor;" replacing reactor core differential pressure alarm unit EP-929; and placing three "spent" graphite reflector wedges in the wedge storage cask.
October 2009 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and two unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission regional inspector conducted a routine inspection of Reactor Operations and Emergency Preparedness.
On October 7, 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 when control blade 'D' anvil separated from its electro-magnet during a routine sample handling evolution. The immediate actions of REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
On October 28, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was automatically initiated when an interruption in normal electric supply power from the University Power Plant to the facility occurred. All immediate and subsequent actions of reactor emergency procedure REP-10, "Sustained 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 had been corrected. The reactor was refueled and subsequently restarted to 10 MW operation.
Major maintenance items for the month included: adjusting the scram set point on reactor core outlet pressure transmitter PT-944A; replacing laboratory building ventilation exhaust plenum pressure controller; completing the I-5
biennial change-out of control blade 'C' offset mechanism; 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);" loading new de-ionization bed 'B' and placing it on pool coolant system service; installing the NEER grant cobalt irradiation facility; completing Modification Record 90-1, Addendum 2, "Evacuation System Changes in Support of the Shipping and Receiving Building;" completing Modification Record 01-2, Addendum 4, "Intercommunication and Paging System Changes in Support of the Shipping and Receiving Building;" and completing Modification Record 09-1, "Interfacing MURR Systems with the Shipping and Receiving Building."
November 2009 The reactor operated continuously in November with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, and, one scheduled shutdown for a physics measurement. 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-201, "Measurement of Reactivity Worth of Flux Trap Loadings or Individual Samples, RTP-17(B);" replacing a section of the make-up water supply line on the secondary coolant system; repairing primary coolant demineralizer outlet valve V527F air actuator; 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; installing a split screen monitor in the control room as part of Modification Record 09-02, "Airlock Door Control;" replacing the drive motor on containment building personnel entry Door 276; replacing the mechanical seal water supply line on primary coolant system circulation pump P-5011B; and installing a proxy card reader as part of Modification Record 09-02, "Airlock Door Control."
December 2009 The reactor operated continuously in December with the following exceptions:- four shutdowns for scheduled maintenance and/or refueling, one scheduled shutdown for a physics measurement, and one scheduled shutdown for training. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: completing Modification Record 09-02, "Airlock Door Control;"
completing Modification Record 01-09, Addendum 3, "Emergency Electrical System in the Shipping and Receiving Building;" 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-I7(B)."
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SECTION If MURR PROCEDURES January 1, 2009 through December 31, 2009 As required by administrative Technical Specification 6.1.h (4), this section of the Annual Report includes a summary of procedure changes. These procedure changes were reviewed by the Reactor Manager or Reactor Health Physics Manager and others to assure compliance with the requirements of 10 CFR 50.59. These procedure changes were also reviewed by the Reactor Procedure Review Subcommittee of the Reactor Advisory Committee to meet the requirements of Technical Specification 6.1 .c (1).
A. CHANGES TO REACTOR OPERATIONS PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Reactor Operations Procedures and found them'to be adequate for the safe and reliable operation of the facility.
There were sixty-six (66) revisions issued to the reactor operations procedures, forms and operator aids.
Additionally, one (1) new form and one (1) new procedure 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:
Number [*, ' . Name I Rv Revision Date JK Notes J AP-RO-1 10 } Conduct of Operations 1141 2/13/2009 . Minor Editorial AP.. RO-.10I 10 Conduct of Operations 1 15 10/2709. Minor Editorial 11 J
AP-RO-l.15 [.Modification Records 15 10/27/2009 J Minor Editorial AP-RO-130 Crane Operation 1 41 3/17/2009 1 Minor Editorial EX-RO-105 Reactor Irradiation Experiments 13 : 12/29/2009 4 Cover Page EX-RO-120 Beamport."'" Operation 7 2/1/0 . Minor Editorial EX-RO-12 11.Beamp.r..Operation 7.. 2/13/2009 Minor Editoria EX-RO-122 Beamport "B" Operation j.7 2/13/2009 Minor Editorial EX-RO-125 1 Beamport "C" Operation P eT8i 7 12/3/2009 3/17/2009 1 Minor Editorial Minor Editorial EX-RO-T12 Beamport "d" Operation EX-RO-2 Termal Column Door 15 12/29/2009 Cover page FB-SH-130 JTest Cak0 and Calibration Procedure BMI-lI Shippin 9 j3/26/2009 Full Review
.M.?....
FM-Il ....
....Reactor a .t° .S. ........
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1-............
Checksheet .............. ]13..... i..22/13/2009
.................... ( 3209........i.................
........................... Io Cover ~ .P g .......
Page ........
FM-20 TanSample ,,Waste Report 1 8 1 8/18/2009 . Minor Editorial FM-43 ....... INuclear ..........
and Processs*
ar.n...cs ;Data
.. ...1.....................
- 12 ¢1 1/16/2009 7*?= ...[Minor .............. ri~
- ;....-.0................................................................................
Editorial FM-3 N~uclear and Process Data 13 2/00 M........Editorial FM-57 ] Long Form Startup Checksheet 15 3/17/2009 Minor Editorial TCustomer Sample Pre-Encapsulation EvaluationI FM-66 ....................................
- ;~ m l -.
.i
........ o Editorial to rial.......
Wokhe4 FM-66PPneumaticTube.Usere-Ecapr iov al u.2.
6/16/2009 8/18/2009....... . 1.Minor M E ia FM-127 MURR Irradiations Encapsulation Evaluation 0 4/1/2009 Full Review I1-1
-Number Name jRev. lRevisionfae Notes GS-RA-100 j MURR Equipment Tag Out 8 8/19/2009 Minor Editoriai JRR-PS07.1.00 . Scheduling Flux Trap Tubes .1 1.. 12/16/2009 Minor Editorial IRR-PSO-1061 Target Material Control Checks.... ........................................... ................ 6..... ..........
2/2/2009................ ...... Minor . .....Editorial IRR-PSO-IlIf Customer SamplePre-EncapsulationEvaluation J4 6/16/2009 Minor Editorial.......
O- 1 unn Exhaust Fans EF- 13 and EF- 14, EF--13129/095 Facility 12/29/2009 Cover CvrPg Page OA1 Running 4 __________
OA 2 Facility Exhaust Fans EF-13 and EF-14, EF-14 .15 112/29/2009 Cover Page
-_ Running OA-3 OA-7 JBeamport and Pool Overflow Loop Seals
] Receiving Bulk Chemicals ..
[53 J16/09 J 10/12/2009
[ Cover Page Minor!Edi.torial OP-RO-101 ] T.... *~Instrument j.......~ r*g aAir
........... pSystem 7* r~ ............
................. 17 ..........
5/22/2009 T...............
Minor Editorial q... ..............
[.oP-R*o725.........................................................8]
Reactor Startup - Normal11/720 10 /27/I(.6200.9........ Minor io Editorialdtra O-RO20 OP-RO-250_. In-Pool Fuel Handling 10 1/16/2009 [ inor Editorial FPR-5 .n-.o .....
/..op...o.5 t In-Pool FFuele Handling H a d i g. . ............ ....... ..... ...... { !1J2 . ..../13... 1309 fMinor 0 0 9..................... Editorial OP-RO-250 In-Pool Fuel Handling 12. 10/12/2009 Minor Editorial OP-RO-5101 Nuclear Instrumentation - Signal Processor.#1.6.. 6/17/2009 [.Minor Editorial OP-RO-311 I*T`2T`*..2.TN;;ciea*].*;;*m*;ati*.*i.*..*;**;;*.;*.*i.*;*". . . . .
[ OPRO-31 INuclear Nuclear Instrumentation -Poe SignalRangea Processor #2 Monitsor-. . . . . i[7 -*:Y2:Z [6/17/2009
-/7/09*Mnr [ Minor i*Z ..............
Editorial dtra op OP-R-312 R .............
- ..Channel
. .....6j9 .. W................
...... ........................................... ............................ 6/720
........... :........ MioEdtra OP-RO-330 1Nuclear Instrumentation - Wide Range Monitor f 6 _ýJ 6172009
[Minor Editorial .Mio OP-RO-410 Primary Coolant System [,5/22/2009 Minor Editorial OP-RO0.4 10 Primary Coolant System _________ 8 12/2r9/2009 VMinor Editorial OP-RO-420 Primary and Pool Water Analysis [ 4 9/3/2009 Minor Editorial IOP-RO-460 Pool Coolant System-*-Two Pump Operatin [*i 8 8/2009 [ Cover Page F.OP-RO-461 Pool Coolant System - One Pump Operation [.9 [ 8/18/2009 T Minor Editorial FOP-RO-465 Pool Level Control - Skimmer System [.6 1/16/20009 T Minor Editorial F.OP-RO-466 Pool Level Control - Pool Coolant System [....7I 3/4/2009 Minor Editorial OP-RO-466 Pool Level Control - Pool Coolant System [ 8 6/2009 . Minor Editorial. "
OP-RO-5201 Emergency Diesel Generator 7 3/17/2009 Minor Editorial O P-RO -520 Emergency 20 D iesel G enerator 8 0/12/2009......Editorial-
- IM I rr 9al999
.rd F OP-RO-525 Chill Water System 2 5/22/2009 T Minor Editorial FOP-RO-530 10P-R Oe-530~~~~~
Demineralizeda i e Water Supply System F [ 8.. . ...
8/18//2009 i Minor .. ......
.ei Editorial .
F OP-RO-530 Demineralized Water Supply System.F 9 [ 10/27/2009... Mi Editorial FOP-RO-531 JPrimary and Pool Sample Station F8 [8/18/2009 T Cover Page 0P-RO-532 O Drain Collection System . 6 8/!8/2009 Co Cover Page F0V...... ..
OP-RO-555 O.6 5ii33 System kiSkimmerrSy t Fire Protection System T. 6 [ 10/2/ /......2009 1/16/2009 f.Cover Page
. Cover...Pageag OP-RO-555 Fire Protection System l7 10/27/2009 Minor Editorial OP.-...RO-7..30 J,Facility Exhaust System ...1 [ 3/17/2009 Minor Editorial REP-RO- 100 JReactor Emergency Procedures 9 [ 3/4/2009 Minor Editorial REP-RO-100 [ Reactor Emergency Procedures T 10 r 11/10/2009 Minor Editorial I FRM-RO-400 JWaste Tank System Filter Replacement 5.3/17/200 Mior Editorial Measurement of Total Reactivity Worth of Flux I[
RP-RO-201
__________Trap Loadings, RTP-17(B) I~ 3 11/920 Minor Editorial io dtra 3 9/11/2009 Minor Editorial SM-RO-420 J Pressurizer Operation - Maintenance & Test 11-2
Number Rename N BI Rev.. 2 Revisiol2 0 .Im Notes, SM-RO-635 Retracting and Reinserting Beamport 'A' Liner 2 :2/27/2009 [ Minor Editorial SM-RO-636 Retracting and Reinserting Beamport 'B' Liner 2 1 2/27/2009 r Minor Editorial SM-RO-638 Retracting and Reinserting Beamport'D' Liner 3 2/27/2009 Minor Editorial SM-RO-639 Retracting and Reinserting Beamport 'E' Liner 3 2/27/2009 Minor Editorial. I 2/27/2009..
SM.. -. 6**0 ..... ac ti~ng and R.e.tr ein-s e rtiing Bea mp ort 'F' Lin er 4 Minor Editorial
)
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 we're ten (10) 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:
Number Name Rev.xileIvision DateL Notes
-EP-JRO-004 Fire.................................................................
F ...................... .. ...............
..... .... ..I..... 13
.................... 17/23/2009 7...................E.d f Minor Editorial ...... a.!. .........
... ..................... ......... .and
............... Site Area
............................ Evacuations i ...........................
- ....[.. ..................
5 ' ............
...................................................................... 2/18/2009 Minor Editorial EP-RO-017 [Emergency Air Sampling 4 2/8/2009.f Minor Editorial EP-RO-020 FM-104 Emergency Equipment Maintenance Emergency Call List E.
[ 4
[ 1..[ 3/24/2009 f 2/18/2009 .
T Minor Editorial Minor Editorial FM-104 ..Emergency Call List 12 [ 10/29/2009 T Minor Editorial FM-l18 ] Evacuation Flowchart [ 2 [ 2/18/2009 Minor Editorial..
OA-09 Combined Emergency Flowcharts [ 2 2/18/2009 f Minor Editorial
.. 6
..OA-2
.................. . Em.......
ergency
............ Equipm E.. ent ... *........44..
.. ................... ..... ...... . .. . 3/24/2009 1*
I .....M. inor Editorial........'.....
OA-20 Emergency Equipment 5 7/23/2009 Minor Editorial C. CHANGES TO HEALTH PHYSICS PROCEDURES, BYPRODUCT MATERIAL SHIPPING PROCEDURES, and PREPARATION OF BYPRODUCT MATERIAL FOR SHIPPING PROCEDURES As required by the MURR Technical Specifications, the Reactor Health Physics Manager reviewed the procedures for radioactive materials handling, shipping, and preparation for shipping of byproduct materials.
There were sixty-eight (68) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. Additionally, six (6) new forms and fifteen (15) new procedures were issued, and five (5) 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:
$.Number 7 1< .Name RvRIin Datel 9 Notes AP-HP-105 Radiation Work Permit o9 9/23/2009 Minor Editorial
.A...... s 19H.... ................. 22 2 /1 3 20
/320 '**r..........
] ..... CvrPg ...
P.a.g..................................g
- iAP-HP-1 19 1 High Radiation Area Access AP-HP-120 Beamport Area I* 4*] 6/2/2009 -1 Cover Page 11-3
Numiber Name REV. l evision Date[ Notes AP-HP- 121 1 Isotope Closet f 4 6/2/2009 Cover Page AP-HP-123 SAP-HP-127 I............................................................................ .................T......
7 Visitor Dosimetry - Reception Desk Radioactive Material Licensing and Project DesignationChange Request 6
4
- 3 311/2009 2/13/2009 ....
. Minor Editorial Cover Page AP-HP-129 I Hot Cell Control f.6 xAP-HP-
- i15ý* 6...........
§SoreClbain]4
.our~c;.eCai b* ratio nii.ii 6/2/2009 8 13~~s 8/3/009.1.Cover Page
- 1 Minor Editorial
................ ** *l. . . .
Administrative Procedure, Radioactive Materials I .
AP-SH-00 1 Spn6 12/22/2009 j Minor Editorial
............ 7. .(). *. ............................... . ........ .... 6..J
-: .....* 2 2 . 9...... . ......... 0 !. *.se ............... ......
BPB-SH-001 2R1 Shipping Container Leak Check 16 13/2/2009 j __Obsolete 0 DOT 6M Packaging of Type B Non-Waste 7 4/8/2009 Minor Editorial BPB-SH-005 Radioactive Material .
i* T p BT
... .. . ..( Ue
.. o...s. 3IF... ......ia
.. ... .. S.c.eriesP.acikaging t liv...t
....
- P. .......e.a
..... a.........
... l. o To. TB.......................................................
N .r . ...
4/8/2009 I27S fMinor BPB-SH-08INnWseRdocieMtra 6 Editorial Receipt Inspection of Type B Byproduct Material0 BPB-SH-020 hpigCnanr aeil 0 3/26/2009 Full Review BPB-SH-021 20 WC-I All-Thread DOT RodW~~CReplacement
~ ~er~ac 20 10 ~.......... 0...........................
3/26/2009 Full Review .......
BPB-SH-022 ............
PC0 .........................
U I.............................. ;......................... 3/26/2009 Full Review 11....
BPB-SH-023 jTorque Wrench Calibration A0 3/26/009 FulfiReview F-327 Packaging and Shipment of Type BP-SH-007 NonWasteRadioactive aterial 12/22/2009 Minor Editorial BP-S-O H 12..rt ifi c a t on............................................................................................................................................
BP-SH-0.................
12 ....DT . - A.P.kg DOT-7A Packagee....3./2.9MCertification 13 {3/2/2009 JMinor in r.dit Editorial ri .. ..
Packaging and Shipment of Radioactive BP-SH-013 Materials Using MURR Reusable Type A 3 4/8/2009 Minor Editorial
. BPr-SH-u
. .s. Package .z . . . . . 3 4 .
,I/8/2009
. ___________ . Minor
. ..Ediltorial Packaging and Shipment of Radioactive Material .
BP-SH-014 UsinantiveMrpac 2 4/8/2009 Minor Editorial Packaging and Shipment of Radioactive Material I /320 B..........
........ Using D u mUSA n a iDOT-7A n a d L Model b l gH . orn Package
.. . . . .. 0 ] .Full.Revie . . ............... t Radioactive Material Shipment Package BP-SH-052 and Labeling 4Documentation 3/2/2009 Minor Editorial Radioactive Material Shipment Package1/520 MioEdtra
....... I ~~~~~Packaging and Shipment of Radioactive Material 2 3220 io dtra BP-SH-052 Using MURR Models 6 and 12 2...Minor
.. Editorial Biennial Inspection and Preventive g Maintenance Review
.. B.BMI- Shipping Cask .... 0. 3/2. F...u.l.......
FM-13 ........ ReceiPt Radioactive of Material . 4 7/14/2009 . Cover Page FM-13 FM-17 FY-52 ]* Receipt Radiation ~. of Radioactive
.. Work
...... Permit
..... Material T 58 T10/14/2009........ Minor Minor .Editorial!......:
lll o Editorial ldlora i FM-29 : nta Radiation Worker Training Packet T*6 8/19/2009 [ Cover Page FM13 FM-52 Control Checksheet for Documentation and Labeling of Radioactive Material Shipment
. 14/28/200 71/0 Minor Eioia FM-52 I Control Checksheet for Documentation and 11/i
__________Labeling FM-52. !Labeling of of Radioactive Radioactive . Material M aterial . Shimnf Shipment _ ____
. : . 6 .......i11/5/20(09iora ral Radioactive Material Licensing and Project FM-53 3 7/14/2009 Cover Page Designation Change Request FM-54 Report of Personnel Contamination 6 7/14/2009 Cover Page 11-4
N.......... ... N a me
!.< ...... !..... I..R ate.. Notes FM-62 j Radiation Instrument Certificate of Calibration j 5 J 3/18/2009 f Cover Page FM-67 JReceipt of Radioactive Gemstone Shipping oties___________1~
5 17/14/2009 j Cover Page IControl Checksheet for Type B(U) F-327 Series 10 FM-75 FM-75 Radioactive Raiatv Materials aeil Shipment hpetf
- .. i~ i r;i n o~
- a c ......................................................................
' . j12/22/2009
......................... jMinor ....... Editorial
............
- i* i* *.........!
FM-91 ]Declaration of Pregnancy 2 3/2/2009 I Cover Page Control Checksheet for USA DOT 7A MURR FM-99 SMMd odel 1500 1540 Series r ............ 3/26/2009 Minor Editorial FM-107 JControl Check Sheet for Overpack Shipment- 3 J 12/22/2009 Minor Editorial FM-i108 . 2RContainer Leak Check Data Sheet 1 J 3/26/2009 J Obsolete Certificate of Compliance for DOT-7A Shipping 0 FM-126 ' Container FM-126 Cotie0Sipn 3/2/2009 Full Review Control Check Sheet For MURR Shipment Using FM-128 USA DOT-7A MURR Model H or I ]8/329 FM-128 O AMR MlHUig 1 8/13/2009 Full Review FM-129 Control Checksheet for .. Receipt Inspection of I0 3/26/12009 1 Full Review
__ Type B Byproduct Material Shipping Containers _ _ ..... _... _ __....
- FM-15 FM
-154 Control Overpack Checksheet vrakRd Rod Replacement... elcmn for USA DOT 20 WC-1 0
0 3/26/2009 1 ..............
Full Review .
FM......... ju Panigof USA DOT WC-1, Type B Ovepck Assurance Control Checksheet Exterior Required Documentation for Non-MURR Owned
, . 0 ......... F.....u FM-156 R0 6/5/2009 Full Review
_______ Type B Sipping Containers HC-PSO-005
.. j Hot Cell ..........Loading*'*iqi;'i*,i~ition~
2566 of.........
Host l-urv~y Xiii~aignY Can nsti~ gn~s ................................ 6[- 2/9/2009 Minor g....... Editorial ...... -.......
IC-HP-300
. .. ... . ... ... ~ ~~.. .. .. .... ..... ...... ............................
Calibration ..-Radiation Survey .......
Instrumcnts . .. .. . .. -----------..
5 38209 .. . .. ...... . ........ .... ...... ......
Cover Page .... .. ....
IC-HP-305 Calibration - Electrostatic Discharge Dosimeter .5 2/13/2009 1 Cover Page IC-HP-3 31 Calibration- Tennelec LB-5 100 Alpha/Beta 6 6/2/2009 Cover Page IC-HP-333 Eberline BC-4 Beta Swipe Counter - Calibration 5 2/13/2009 Cover Page Calibration'- Portal Monitor Gamma S/N IC-HP-335 100 7 4 /9/2009 Cover Page Calibration - a Mon i orG am ma S ...11..............................
l tC'l-.*
- HP349"*0 ] Calibrand 10 0 a d 0- 1Lab m.p 1C . .........S*tk Mo nt- . ...............
0 12/3/2009 1* F...................
R .
IC-HP-337 Sre wt am 68/2/2009 Cover Page Calibration - Lab lmpex Stack Monitor- Gas...
IC-HP-38 .. . .... . . .Ch*a a. r ~ u a e t~ a l..... . . .. . .... ... . . ... . . t . 0.2/32009 .....
t.... . ..........
FoeUllrevew Calibration - Lab Impex Stack Monitor-Fow 0
.h n e IC-HP-351 Calibration 0 12/3/2009 Full Review
..R-.... 112 ~PCalibration - Lab impex Stack Monitor2 low , ...... inor Eioa IR-PO- 21- reaingShipping Paperwork . 3J 9/15/20o09 IMinr dtorial IO-HP-220 C h n e Bioassay 5 J 7/14/2009l /Tritium
............ ..9........ .........
CoverePage opHp-227 .... Tennelec LB-5100 Lab4 Alpha/Beta-Operation e [ 6/2/2009 .ntCover Page
.O-HP-230 Eberline BC-4 Beta Swipe CounterR- Operation [ 4 J 2/13/2009 Cov.erPage OP-HP-300 Receipt of Radioactive Material 6 2/13/2009 Cover Page 11-5
Number~ N e I1 Rev. jRevisioDae. 71 Notes §.7.
OP-HP-306 i Daily Facility Checks 2 10/14/2009 Minor Editorial
.i O P -HP-348 ...........................
Operation - Protean .. .. ..... ..... Swipe Counter WPC-9550 Cou te ........ ../ .............3 / 13/2009 Cover Page OP-HP-350 Eberline Model Ping IA - Filter Change 4 4/29/2009 j Cover Page OP-HP-351
,OP-HP-352 ............. ..... ......
f NMC Model RAK - Filter Change (particulate and Iod~ine Filter - Analysis .... ....... ....... ............ .....
4 ......... .. 1 .2/
2/13/2009 1 2/11111/2!3/20)09 3.......i .... ......]...........
Cover Page Cover Page .....
OP-H-35 Waste Tank Sample - Analysis 5.j_3/18/2009 Cover Page Preparing and Submitting a Radioactive Sample PRC-RRD-00 1 ffor Packaging P 0 j 12/30/2009 Full Review QAB-SH-002 Procurement of Type B Packages 0 J 3/2/2009 { Full Review QAB-SH-003 Material Control for Type B Shipping Program 0 3/2/2009 Full Review QAB-SH-004 Type B Program Vendor Qualification . 0 3/2/2009 Full Review QAB-SH-005 Type. B QA P ersonne Triin g .u. 0 3//20 6...... .............. Review...
QA-HP-005 Use of 13-G Shipping Cask .. 0.] 3/26/2009.. Obsolete Sodium Iodide Spectral Analysis for Excepted, QA-SH-2 Exempt, License-to-License, Type A, or Type B 3 3/2/2009 Minor Editorial Radioactive M aterials Shipments............. .... . . .... . . .... .... . .....
Sodium Iodide Spectral Analysis for Excepted, QA-SH-002 Exempt, License-to-License, Type A, or Type B 4 12/22/2009 Minor Editorial
.............. Radioactive M aterials Shipm ents .................. Editorial RP-HP-120 I Personnel Radioactive Contamination6 4/29/2009 Minor Editorial RP-HP-130 Receipt of New Fuel Elements f 5 4/29/2009 Cover Page RP-HP-135 Room 114 Entry - Self Monitored 1 J 4 4/29/2009 Cover Page SP-SH-00
,gi~i..ii....-.....g.ai./.*ii.r..n..... I Neo0 2 R2Shipping Co ;..... ia.i...Liner eak Check J i-T*................ 1 I 5i)ii 3/2/2009
_ _ _ O Obsolete S........................................
................ P . 1operty . Release [. [0
..3 CoverPage.
VHBuilding Exhaust Stack Effluent - Art-41 3 1 8/13/2009 -
SV P121 Monitoring 1 1 o SVH-... . i;56- .:~
...SV-HP-I19 Rlease7/14/2009. Proerty
....... .......... --.................. CvrPg Co . .i;.Page
. . ge..................
SV-HP___121 T ime..r~g*.n~c.y. Air..S.;m -pii-ing of..E. *x -h.a-u-s-ti.i;.~ .......... ! T4.............009 Emildigy ExairtStampinkoExhausnt Plm~.
~ 7/i 4i260 Cover .. . .
TPZ-PSO-001 I Receiving Gemstone Irradiation Shipping Drums [ -5 10/5/2009 Minor Editorial TPZ-PSO-002 Irradiation of Gemstone Irradiation Containers 4 6/16/2009 Minor Editorial TSP-02 ] Transportation Security Plan f 3 1 2/2/2009 f__Minor Editorial WMB-SH-005 Shipment of Type B Radioactive Waste Using Chem-Nuclear System 1-13G Cask I6 .
3/26/2009 Obsolete WM-SH- 10 Radioactive Waste - Preparation and Storage J.5. 6/520 Minor Editorial WM-SH-105 Radioactive Waste Processing .......................................... 5 6/5/2009 Minor Editorial WExclusive Use Shipment of LSA or SCO WM-SH-300 Radioactive Waste 5 9/24/2009 Minor Editorial 11-6
SECTION III REVISIONS TO THE HAZARDS
SUMMARY
REPORT January 1, 2009 through December 31, 2009 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, Section 3.2.1, paragraph 4, page 3-3 (as revised by 1967-68, 1973-74 and 1981-82 Reactor Operations Annual Reports):
Delete: "(12) 3/4" pvc Film irradiator helium supply" Replace with: "(12) 3/4" pvc (blanked)"
Original HSR, Figure 5.1, Piping & Instrument Diagram (as revised by the 1972-73, 1973-74, 1994, 1996, 2001, 2002, 2003, 2004, 2006 and 2007 Reactor Operations Annual Reports):
Replace with: Updated Figure 5.1, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet 1 of 1, dated 11/17/09)
Original HSR, Section 7.1.4, paragraph 3, page 7-4 (as revised by the 1972-73, 1,989-90, 2002 and 2004 Reactor Operations Annual Reports):
Add: "(16) Shipping and Receiving Building Fire Protection Panel" Original HSR, Section 7.2.9, Table 7.2, page 7-21 (as revised by the 1995, 2001 and 2007 Reactor Operations Annual Reports):
Add: "Shipping and Receiving Building Room 101 (2)"
Original HSR, Figure 8.4, MURR 3 Tube Flux Trap (as added by the 1972-73 and revised by the 2007 Reactor Operations Annual Reports):
Replace with: Updated Figure 8.4, Flux Trap: 3-Barrel Assembly View (MURR Dwg No.
.2505, Sheet 1 of 3, dated 3/18/09)
Original HSR, Figure 8.5, Flux Trap: 6-Barrel Assembly View (as added by the 2000 and revised by the 2007 Reactor Operations Annual Reports):
Replace with: Updated Figure 8.5, Flux Trap: 6-Barrel Assembly View (MURR Dwg No.
2528, Sheet I of 3, dated 3/18/09) 111-1
Original HSR, Section 8.6, paragraph 2, page 8-13 (as revised by the 1969-70 and 1981-82 Reactor Operations Annual Reports):
Delete: "The graphite stack incorporates a bismuth filter, neutron radiographic variable aperture, and a slot for the irradiator case for the film irradiator experiment. The original thermal column door has been with a new door that incorporates a film irradiator experiment. Figure 8.3 is a cross sectional view, of the thermal column door, and the film irradiator experiment."
Replace with: "The graphite stack incorporates a bismuth filter, neutron radiographic variable aperture, and a slot that at one time was occupied by the irradiator case of a film irradiator experiment. Figure 8.3 is a cross sectional view of the thermal column door."
Original HSR, Section 9.2, Table 9.1, pages 9-5 through 9-7 (as revised by 1981-82, 1995, 2001, 2004 and 2008 Reactor Operations Annual Reports):
Delete: "54 Airlock Door Security "Closed-Ope'n" 2 Position" Replace with: "54 Airlock Door Security "Normal-Closed-Outer Open" 3 Position" Delete: "57 Airlock Door Open N/A Push Button" Replace with: "57 Airlock Door Open "Outer-Inner" 3 Pos. Spring Ret."
Original HSR, Figure 9.2, Control Console Layout (as revised by the 1995, 2001, 2004 and 2009 Reactor Operations Annual Reports):
Replace with: Updated Figure 9.2, Control Console Layout (dated 12/21/09)
Original HSR, Figure 9.4, Safety System 10 MW (as revised by the 1995, 2001, 2002, 2003, 2006 and 2007 Reactor Operations Annual Reports):
Replace with: Updated Figure 9.4, Safety System (MURR Dwg No. 139, Sheet 1 of 1, dated 8/10/09)
ADDENDUM 1 - HAZARDS
SUMMARY
REPORT (FEBRUARY 1966)
HSR, Addendum 1, Section 3.22, paragraph 8, page 102, (as revised by the 1989-90 and 1995 Reactor Operations Annual Reports):
Delete: The following words from the second sentence: "the Nuclepore film shield box,"
ADDENDUM 3 - HAZARDS
SUMMARY
REPORT (AUGUST 1972)
HSR, Addendum 3, page 23a, Figure 2.3.a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, 2005, 2006 and 2007 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of 5, dated 8/10/09) 111-2
HSR, Addendum 3, page 23b, Figure 2.3.b, Electrical Distribution (as added by the 1995 and revised by the 2001, 2002, 2003, 2004, 2005 and 2007 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 8/10/09)
HSR, Addendum 3, page 23c, Figure 2.3.c, Electrical Distribution (as added by the 2004 and revised by the 2005 and 2007 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 8/10/09)
HSR, Addendum 3, page 23d, Figure 2.3.d, Electrical Distribution (as added by the 2007 and revised by 2008 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, 8/10/09)
HSR, Addendum 3, page 23e, Figure 2.3.e, Electrical Distribution (as added by the 2007 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 8/10/09)
ADDENDUM 4 - HAZARDS
SUMMARY
REPORT (OCTOBER 1973)
HSR, Addendum 4, page A-28, Figure A.1, Safety System 10 MW (as revised by the 1995, 2001, 2002, 2003, 2006 and 2007 Reactor Operations Annual Reports): /
Replace with: Updated Figure A.1, Safety System (MURR Dwg No. 139, Sheet 1 of 1, dated 8/10/09)
HSR, Addendum 4, page A-29, Figure A.2, Piping & Instrument Diagram (as revised by the 1995, 2001, 2002, 2003, 2004, 2006 and 2007 Reactor Operations Annual Reports):
Replace with: Updated Figure A.2, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet I of 1, dated 11/17/09)
HSR, Addendum 4, page A-32, Figure A.5, 10 MW Process Instrumentation Control & Interlock (as revised by 1995, 2001, 2005, 2006 and 2008 Reactor Operations Annual Reports):
Replace with: Updated Figure A.5, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 1 of 4, dated 11/18/09)
HSR, Addendum 4, page A-38, Figure A.1I, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (as revised by the 1995, 2002 and 2005 Reactor Operations Annual Reports):
Replace with: Updated Figure A. 11, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (MURR Dwg No. 1125, Sheet I of 4, dated 12/16/09) 111-3
ADDENDUM 5 - HAZARDS
SUMMARY
REPORT (JANUARY 1974)
HSR, Addendum 5, page 15, Figure 2.1, Electrical Distribution (as revised by the 1989-90, 2001, 2002, 2003, 2004, '2005, 2006 and 2007 Reactor Operations Annual Reports):
Replace with: Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet I of 5, dated 8/10/09)
HSR, Addendum 5, Section 2.4.1, page 12 (as revised by the 1989-90, 2002 and 2004 Reactor Operations Annual Reports):
Add: "(16) Shipping and Receiving Building Normal supply power would be lost to Shipping and Receiving Building (SaRB). However, there are no electrical loads in the SaRB that are required to accomplish a safe shut down of the reactor or to maintain a safe shutdown condition."
111-4
SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2009 through December 31, 2009 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 90-1, Addendum 2:
Evacuation System Changes in Support of the Shipping and Receiving Building This addendum to modification record 90-1, "Evac Horn," documents changes to the facility evacuation system that were necessary in order to safely occupy the new shipping and receiving building (SaRB). To ensure a prompt and effective response from facility staff to an emergency or abnormal condition, the facility evacuation system was extended into the SaRB. One (1) horn was installed in the openspace of this building.
Modification 96-1, Addendum 2:
Removal of the Nuclepore Experiment Equipment This addendum to modification record 96-1, "Removal of Nuclepore Gas Lines, Isolation Valves, and Valve Control Wiring," documents the removal of the remaining utility connections and abandoned components associated with the nuclepore' facility not removed under modification record 96-1. and modification record 96-1, addendum 1. The nuclepore facility was installed in 1977 to provide a means of producing finely controlled porosity in an irradiated plastic film. To accommodate the r'equired equipment a redesigned thermal column door was installed. Within this door, a removable set of uranium-bearing
'fission plates' was exposed to thermal neutron flux in the thermal column facility. As the target film slid across these fission plates, the fission products released penetrated the film, thus producing finely distributed perforations, which were later acid-etched to produce the desired porosity. After the nuclepore facility was decommissioned and abandoned in place in 1993, modification record 96-1 documented the removal of gas lines, isolation valves and valve controls. The irradiator case (that part of the experiment that was moved into and out of the neutron flux) was removed using reactor test procedure RTP-16D.
Addendum 1 to modification record 96-1 documented the removal and disposal of the shield box ventilation exhaust filter housing and associated duct work.
Modification 01-2, Addendum 4:
Intercommunication and Paging System Changes in Support of the Shipping and Receiving Building This addendum to modification record 01-2, "Installation of a New Reactor Facility Intercommunication and Paging System," documents changes to the facility intercommunication and paging system that were necessary in order to safely occupy the new Shipping and Receiving Building (SaRB). To ensure a prompt and effective response from facility staff to an emergency or abnormal condition, the intercommunication and paging system was extended into the SaRB. Two (2) paging speakers were installed in this building.
Modification 01-9, Addendum 3:
Emergency Electrical System in the Shipping and Receiving Building This addendum to modification record 01-9, "Installation of Emergency Lighting Panel No. 1," documents the addition of loads to the emergency electrical power system in the new shipping and receiving building IV-1
(SaRB). This addition provides two (2) 120 volt emergency power circuits to the SaRB for key systems such as fire protection and building access control.
Modification 06-3, Addendum 2:
Replace Flux Trap Holder Wear Ring This addendum to modification record 06-3, "Replace Flux Trap Holder Wear Ring," documents the replacement of the center test hole canister temporary wear ring with a different design. The new ring covers a larger circumference of the flux trap holder; thus ensuring rotation will not disengage the position sensing switches of the flux-trap irradiations reactivity safety trip (FIRST) instrument channel. This installation was done in support of preliminary long form modification record, "Flux-Trap Irradiations Reactivity Safety Trip (FIRST) Instrument Channel." The prototype FIRST rig was installed under modification record 08-5, and subsequent details of the FIRST device and its function are provided in this modification record.
Modification 09-1:
Interfacing MURR Systems with the Shipping and Receiving Building This modification record was used as' the initiating document to ensure all systems related to emergency response and routine operation have been identified and modified prior to safely occupying the facility's new shipping and receiving building. Actual modifications to these systems - facility evacuation, fire protection, intercommunication and paging, and normal and emergency electrical power - were performed under addendums to previously approved modification records.
Modification 09-2:
Airlock Door Control This modification record documents the replacement of the existing pedestrian "entry (airlock) door analog control system with a Programmable 'Logic Controller (PLC)-driven system. In addition, the control scheme was modified to maintain both airlock doors closed and sealed when in an idle condition. All existing interlocks and protective functions were preserved, with the addition of controls necessary to open and close both doors. This modification record is classified as "Safeguards Information" due to the inclusion of security-sensitive information.
IV-2
SECTION V NEW TESTS AND EXPERIMENTS January 1, 2009 through December 31, 2009 New tests or experiments developed during this period under a Reactor Utilization Request (RUR) or reactor Project are as follows:
RUR 118, asaamended: Molybdenum Metal
Description:
This RUR authorizes the irradiation of up to 375.0 grams of molybdenum metal, natural or enriched up to 100 % in the isotope Mo-98, for research and development activities.
RUR 219, as amended: Epithermal Neutron Irradiation Facility
Description:
This RUR authorizes the use of a cadmium-lined epithermal neutron irradiation container for research and development activities.
RUR 269, as amended: Platinum
Description:
This RUR authorizes the irradiation of up to 0.50 grams of platinum, natural or enriched up to 100% in the isotope Pt-192, Pt-194 or Pt-198, for research and development activities.
RUR 433: Lanthanum Nitrate
==
Description:==
This RUR authorizes the irradiation of up to 0.023 grams of lanthanum nitrate (La(N0 3)3) for research and development activities.
Project RL-70: Thermal Neutron Beam-Line for Neutron Capture Therapy on Beam Port E
Description:
This Project authorizes the use of a neutron irradiation facility in support of the development of neutron capture therapy (NCT) agents. The-NCT facility will enable experimenters to measure the efficacy of capture therapy agents in animal models and cell cultures.
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. In the case of RL-70, the Isotope Use Subcommittee also reviewed this project.
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SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2009 through December 31, 2009 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-five (55) refueling evolutions were completed in 2009. Excess reactivity verifications were performed for each refueling.' The largest measured excess reactivity value was 2.8.6%. MURR Technical Specification 3. 1(f) requires excess reactivity to be less than 9.8%.
Reactivity Measurements:
Differential blade-worth measurements of four (4) 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.
Three (3) reactivity measurements were performed to determine the reactivity worth of all samples, including the sample holder, loaded in the flux trap region.
Six (6) reactivity measurements were performed to determine the reactivity worth of various sample cans irradiated in the flux trap region.
One (1) reactivity measurement was performed to characterize the reactivity worth of a cadmium-lined epithermal neutron irradiation container in the graphite reflector 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.
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SECTION VII RADIOACTIVE EFFLUENT January 1, 2009 through December 31, 2009 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2009 through December 31, 2009 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide Activity (Ci)
H-3 5.123E-02 S-35 6.449E-03 Lu-177 4.726E-03 Co-60 3.261E-03 P-32 2.866E-03 Ca-45 2.5 1OE-03 Lu-177m 1.633E-03 Zn-65 1.004E-03 Cr-51 2.580E-04 Mn-54 1.994E-04 Sc-46 1.915E-04 Ru-105 1.295E-04 Ag- I00m 1.193E-04 Rh-105 6.020E-05 Gd-159 4.906E-05 Na-22 1.472E Cu-67 1.284E-05 Total H-3 5.123E-02 Total Otber 2.350E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."
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TABLE 2 STACK EFFLUENT January 1, 2009 through December 31, 2009 Ordered by % Technical Specification (TS) Limit IsotopeIsotope(ACi/ml)
Average Concentration Total(Ci)
Release T ii TS Limit utpirT Multiplier % TS Ar-41 1.92E-06 9.78E+02 350 70.3004 Os-191 8.35E-11 4.05E-02 1 4.1739 C-14 1.84E-11 8.34E-03 1 0.6130 1-131 1.21E-12 5.86E-04 1 0.6035 H-3 1.15E-08 5.58E+00 350 0.0328 1-125 2.20E- 14 1.07E-05 1 0.0073 Se-75 4.55E-14 2.21 E-05 1 0.0057 Hg-203 1.26E-14 6.13E-06 1 0.0013 1-133 1.21E-12 5.85E-04 350 0.0003 Ba-140 2.91E-15 1.41E-06 1 0.0001 C6-58 1.35E-15 6.57E-07 1 0.0001 Co-57 9.22E- 16 4.48E-07 1 0.0001 S-35 2.28E-15 1.11E-06 1 0.0001 Br-82 1.21E-12 5.88E-04 350 0.0001 Ce-139 6.22E- 16 3.02E-07 1 0.0001 Nb-95 1.33E-15 6.45E-07 1 0.0001 As-77 1.29E-12 6.27E-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% 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.
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SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2009 through December 31, 2009 Environmental samples are collected two times per year at eight (8) locations and analyzed for radioactivity. Soil and vegetation samples are taken at each location. Water samples are taken at three (3) of the eight (8) locations.
Analytical results are shown in Tables I and 2.
Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2009. All doses are approximately 16 mRem/year or less, except monitor numbers 9, 15 and 42. Monitors 9 and 15 are located near theloading 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. Monitor 42 is located in the Health Physics Office, which is in close proximity to the reactor. The environmental monitoring.
program confirms that no environmental impact exists from the operation of the MURR facility.
The number of radiation and contamination surveys performed each month is provided in Table 4.
TABLE I Summary of Environmental Set 75 Spring 2009 Detection LimitsI Matrix Al0pha Beta Gamma Tritium Water 0.73 pCi/L 3.26 pCi/L 200.41 pCi/L 3.76 pCi/mL of sample Soil 0.71 pCi/g 4.35 pCi/g 0.56 pCi/g N/A Vegetation 2.47 pCi/g 7.68 pCi/g 1.72 pCi/g 3.82 pCi/mL of distillate Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL)
IV75 < 2.47 20.57 < 1.72 < 3.82 2V75 < 2.47 9.14 < 1.72 < 3.82 3V75 < 2.47 13.15 < 1.72 < 3.82 4V75 < 2.47 16.62 < 1.72 < 3.82 5V75 < 2.47 18.90 < 1.72 < 3.82 6V75 < 2.47 19.75 < 1.72 < 3.82 7V75 < 2.47 19.76 < 1.72 < 3.82 10V75 < 2.47 15.90 < 1.72 < 3.82 VI1I-1
TABLE 1 (Cont'd)
Summary of Environmental Set 75 Spring 2009 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1S75 < 0.71 10.16 3.77 2S75 0.95 11.13 3.16 3S75 < 0.71 10.37 3.03 4S75 < 0.71 9.37 2.77 5S75 0.95 10.26 3.53 6S75 0.92 <4.35 2.17 7S75 <0.71 6.32 3.31 10S75 0.79 7.67 2.93 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W75 < 0.73 < 3.26 < 200.41 < 3.76 6W75 < 0.73 3.46 < 200.41 < 3.76 10W75 < 0.73 9.29 618.292 < 3.76 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.
Note 2: HPGE spectral analysis indicates high gamma activity as a result of a known medical isotope (Tc-99m) not produced at MURR.
TABLE 2 Summary of Environmental Set 76 Fall 2009 Detection Limits' Matrix Alpha Beta Gamma Tritium Water 0.00 pCi/L 2.65,pCi/L 198.75 pCi/L 3.62 pCi/mL of sample Soil 0.00 pCi/g 2.23 pCi/g 1.48 pCi/g N/A Vegetation 1.90 pCi/g 6.78 pCi/g 1.45 pCi/g 4.17 pCi/mL of distillate VIII-2
TABLE 2 (Cont'd)
Summary of Environmental Set 76 Fall 2009 Activity Levels - Vegetation Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/mL) 1V76 < 1.90 9.74 < 1.45 <4.17 2V76 < 1.90 11.37 < 1.45 <4.17 3V76 < 1.90 7.94 < 1.45 <4.17 4V76 < 1.90 12.14 < 1.45 <4.17 5V76 < 190 <6.78 < 1.45 <4.17 6V76 < 1.90 8.02 < 1.45 <4.17 7V76 < 1.90 10.13 < 1.45 <4.17 10V76 < 1.90 18.33 < 1.45 <4.17 Activity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1S76 0.71 12.48 .9.47 2S76 0.56 6.50 9.50 3S76 0.94 8.63 5.85 4S76 0.89 8.80 10.36 5S76 0.44 13.34 8.54 6S76 0.75 10.99 11.69 7S76 0.63 12.04 10.93 10S76 0.63 12.44 11.63 Activity Levels - Water Sample Alpha (pCi/L) Beta (pCi/L) Gamma (pCi/L) H-3 (pCi/mL) 4W76 0.62 < 2.65 < 198.75 < 3.62 6W76j 0.00 3.58 < 198.75 < 3.62 10W76 0.00 4.07 < 198.75 < 3.62 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.
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TABLE 3 Environmental TLD Summary January 1, 2009 through December 31, 2009 Badge Direction Map Distance from 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total Number From MURR MURR Stack 2009 2009 2009 2009 2009 (meters) Net mR Net mR Net mR Net mR Net mR 1 Control N/A 0.0 2.2 0.0 0.0 2.2 2 Control N/A 5.1 1.5 0.0 0.0 6.6 3 WSW N/A 2.6 1.5 0.0 0.1 4.2 4*
5*
6 N 34 3.9 3.2 3.9 1.3 12.3 7 NE 57 3.6 6.4 0.1 5.9 16.0 8 SW 27 0.8 4.3 0.0 1.0 6.1 9 S 27 23.9 20.5 28.7 35.5 108.6 10 NE 149 0.8 0.0 0.0 0.0 0.8 11 NW 149 3.1 1.7 0.5 0.0 5.3 12 ENE 301 2.7 5.8 1.7 2.0 12.2 13, NNE 316 4.2 3.8 0.1 0.0 8.1 14 S 156 0.1 3.1 0.0 0.0 3.2 15 S 65 19.3 22.1 13.9 16.4 71.7 16 SE 107 0.0 0.0 0.0 0.0 0.0 17 E 293 0.0 0.0 0.0 0.0 0.0 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 0.9 0.0 0.0 0.0 0.9 22 ESE 168 0.8 0.0 0.0 0.0 0.8 23 NW 110 0.3 1.1 0.7 1.4 3.5 24 SSW 328 1.9 0.0 0.0 0.0 0.0 25 SSW 480 3.7 0.7 0.0 0.0 4.4 26 SW 301 2.9 0.0 0.0 0.0 2.9 27 WSW 141 0.0 0.0 0.0 0.0 0.0 28 WNW 210 1.9 0.0 0.0 0.0 1.9 29 NW 255 3.2 0.9 0.0 0.0 4.1 30 NNW 328 0.0 0.0 0.0 0.0 0.0 31 NNW 671 2.9 0.8 0.0 0.0 3.7 32 NNW 724 no report 0.0 0.0 0.0 0.0 33 E 671 0.0 0.0 0.0 0.0 0.0 34 ENE 587 0.0 0.0 0.0 0.0 0.0 35 SSE 499 0.4 0.0 0.0 0.0 0.4 36 SE 419 1.7 0.0 0.0 0.0 1.7 37 NE 690 0.0 0.0 0.0 0.0 0.0 38 NW 556 2.1 1.1 0.0 0.0 3.2 39 W 491 0.0 0.0 0.0 0.0 0.0 40 N 514 0.0 0.0 0.0 0.0 0.0 41 NNE 137 0.6 0.0 0.0 0.0 0.6 42 In Building N/A 8.0 8.7 8.9 8.6 34.2 43 In Building N/A 3.2 1.0 0.0 0.0 4.2 44 Spare N/A 2.4 1.2 0.1 0.6 4.3 45 S 65 3.6 0.0 0.0 0.0 3.6
- These badge numbers are no longer used.
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0 TABLE 4 Number of Facility Radiation and Contamination Surveys January 1, 2009 through December 31, 2009 Radiation Surface Contamination* Air Samples** RWP's January 66 66 64 12 February 62 62 55 5 March 69 69 59 9 April 73 73 73 16 May 63 63 62 4 June 91 91 58 0 July 72 72 71 6 August 53 53 57 2 September 78 78 61 5 October 73 73 57 10 November 52 52 62 14 December 78 78 60 4 TOTALS 830 830 739 87
- 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 Nathan Hogue was hired as a Health Physics Technician in May 2009.
Lee Juengermann was promoted from his position as a Health Physics Technician to -the MURR Shipping Manager in November 2009.
During calendar year 2009, MURR shipped 785 cubic feet of low-level radioactive waste containing 5,692.1 mCi of activity.
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SECTION IX
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS January 1, 2009 through December 31, 2009 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP Month AC DO FSO HC/SH RAG IRR NA NS ýOPS PRO RES RP SIL Total January 68. 12 146 322 251 2 9 29 1412 81 0 58 77 2467 February 91 11 80 354 145 12 12 25 962 83 0 81 67 1923 March 26 25 54 404 251 5 34 14 1333 117 34 88 45 2430 April 37 47 305 305 143 3 24 44 1070 55 9 123 19 2184 May 28 29 76 287 119 7 28 65 953 52 43 60 33 1780 June 32 28 185 215 154 0 34 78 1347 114 39 101 79 2406 July 32 8 116 289 228 9 47 44 1449 88 47 136 56 2549 August 69 37 76 351 173 14 68 31 1519 90 9 145 89 2671 September 68 12 43 303 216 12 6 92 1327 111 20 96 110 2416 October 71 6 182 343 410 11 16 49 1398 150 3 176 92 2907 November 22 28 64 320 157 14 71 24 1071 112 53 128 77 2141 December 8 13 37 349 164 10 15 12 1087 88 25 .102 95 2005 Total to Date 552 256 1364 3842 2411 99 364 507 14928 1141 282 1294 839 27879 Monthly Ave 46 21 114 320 201 8 30 42 1244 95 28 108 70 2323 Highest WB 173 42 339 887 772 68 89 128 870 379 45 210 413 Highest EXT 2720 M 820 3290 810 M 1670 220 2930 5080 1280 1460 1450 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.
Note: Analytical Chemistry group was split into the Analytical Chemistry and Research groups.
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