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==REFERENCE:==
==REFERENCE:==
Docket 50-186 University of Missouri-Columbia Research Reactor Amended Facility License R-103
==SUBJECT:==
==SUBJECT:==
University of Missouri Research Reactor 2013 Reactor Operations Annual Report Enclosed is a copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2013 through December 31, 2013.
Docket 50-186 University of Missouri-Columbia Research Reactor Amended Facility License R-103 University of Missouri Research Reactor 2013 Reactor Operations Annual Report Enclosed is a copy of the Reactor Operations Annual Report for the University Reactor. The reporting period covers January 1, 2013 through December 31, 2013.
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).
This document is submitted to the U.S. Nuclear Regulatory Commission in University of Missouri Research Reactor Technical Specification 6.1.h(4).
If you have any questions regarding the contents of this report, please contact John Fruits at (573) 882-5319 or FruitsJ(d@missouri.edu.
of Missouri Research accordance with the If you have any questions regarding the contents of this report, please contact John Fruits at (573) 882-5319 or FruitsJ(d@missouri.edu.
ENDORSEMENT:
S i n c e r e l y,
Reviewed and Approved y,
John L. Fruits Reactor Manager ENDORSEMENT:
nSice r e l John L. Fruits                                       Ralph A. Butler, P.E.
Reviewed and Approved Ralph A. Butler, P.E.
Reactor Manager                                      Director JLF/jlb Enclosure xc:           Mr. Alexander Adams, U.S. NRC Mr. Johnny Eads, U.S. NRC 1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: http://web.missouri.edu/-murrwww Fighting Cancer with Tomorrow's Technology
Director JLF/jlb Enclosure xc:
Mr. Alexander Adams, U.S. NRC Mr. Johnny Eads, U.S. NRC 1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: http://web.missouri.edu/-murrwww Fighting Cancer with Tomorrow's Technology


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UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2013 through December 31, 2013 Compiled by the Research Reactor Staff of MURR Submitted by:
UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2013 through December 31, 2013 Compiled by the Research Reactor Staff of MURR Submitted by:
John L. Fruits Reactor Manager Reviewed and approved by:     a/46<
John L. Fruits Reactor Manager Reviewed and approved by:
a/46<
Ralph A. Butler, PE Director
Ralph A. Butler, PE Director


UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1,2013 through December 31, 2013 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, boron neutron capture therapy 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, heterogeneous reactor designed for operation at a maximum steady-state power level of 10 Megawatts thermal - the highest powered university-operated research reactor in the United States.
UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1,2013 through December 31, 2013 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.
The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2013. 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.
Scientific programs include research in archaeometry, epidemiology, health physics, human and animal nutrition, nuclear medicine, radiation effects, radioisotope studies, radiotherapy, boron neutron capture therapy 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, heterogeneous reactor designed for operation at a maximum steady-state power level of 10 Megawatts thermal - the highest powered university-operated research reactor in the United States.
The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2013.
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).
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 Missou'i University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our regulators; those who have provided funding including the Department of Energy (DOE), the National Nuclear Security Administration (NNSA) and the Department of Homeland Security (DHS);
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 Missou'i University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our regulators; those who have provided funding including the Department of Energy (DOE), the National Nuclear Security Administration (NNSA) 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.
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) implementing Amendment No. 36 to Amended Facility License No. R-103, which revised the Safety Limit Curves based on newer, more accurate power peaking factors developed using a 3-dimensional diffusion code, (2) replacement of the 30-degree graphite reflector elements 'GH' and IJ' with a single 60-degree graphite reflector element 'GHIJ,' and (3) irradiating and processing a 5-gram natural uranium target to determine the feasibility of producing molybdenum-99 using a selective gaseous extraction process. Additionally, in August 2006 MURR submitted a request to the NRC to renew i
Some of the major facility projects that were supported by Reactor Operations during this calendar year included (1) implementing Amendment No. 36 to Amended Facility License No. R-103, which revised the Safety Limit Curves based on newer, more accurate power peaking factors developed using a 3-dimensional diffusion code, (2) replacement of the 30-degree graphite reflector elements 'GH' and IJ' with a single 60-degree graphite reflector element 'GHIJ,' and (3) irradiating and processing a 5-gram natural uranium target to determine the feasibility of producing molybdenum-99 using a selective gaseous extraction process.
Additionally, in August 2006 MURR submitted a request to the NRC to renew i


Amended Facility License No. R-103. Significant efforts have already been placed in responding to the Requests for Additional Information and these efforts continued in this past year.
Amended Facility License No. R-103. Significant efforts have already been placed in responding to the Requests for Additional Information and these efforts continued in this past year.
The facility continues to actively collaborate with the Reduced Enrichment for Research and Test Reactors (RERTR) 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. This past year, resources were focused on completing Phase 1 accident analyses for the LEU conversion core.
The facility continues to actively collaborate with the Reduced Enrichment for Research and Test Reactors (RERTR) 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. This past year, resources were focused on completing Phase 1 accident analyses for the LEU conversion core.
MURR also hosted the 2013 Annual Test, Research and Training Reactors Conference. The TRTR organization represents research reactor facilities across the nation from government, major universities, national laboratories and industry. TRTR's primary mission is education, fundamental and applied research, application of technology in areas of national concern and improving U.S. technological competitiveness around the world. TRTR membership includes managers and directors of research reactors, educators, administrators, regulators and research scientists and engineers.
MURR also hosted the 2013 Annual Test, Research and Training Reactors Conference.
The TRTR organization represents research reactor facilities across the nation from government, major universities, national laboratories and industry.
TRTR's primary mission is education, fundamental and applied research, application of technology in areas of national concern and improving U.S. technological competitiveness around the world.
TRTR membership includes managers and directors of research reactors, educators, administrators, regulators and research scientists and engineers.
Reactor Operations Management also wishes to commend the five individuals who received their Reactor Operator certifications and the four individuals who received their Senior 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 a licensed operator during normal and abnormal situations.
Reactor Operations Management also wishes to commend the five individuals who received their Reactor Operator certifications and the four individuals who received their Senior 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 a licensed operator during normal and abnormal situations.
ii
ii


TABLE OF CONTENTS Section Title                                                                                                     Pages I.     Reactor Operations Sum mary ...............................................................               I-I through 9 f]. M U RR Procedures ................................................................................       Il-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 ..........................................                         Ill-I through 4 IV. Plant and System M odifications ...........................................................               IV- 1 through 3 V.     New Tests and Experiments ............................................................                     V-1 VI. Special Nuclear Material and Reactor Physics Activities ................ VI-1 VII. Radioactive Effluent .............................................................................         VII-I through 2 Table 1- Sanitary Sewer Effluent Table 2 - Stack Effluent VIII. Environmental Monitoring and Health Physics Surveys ...................... VIII-l through 6 Table I - Summary of Environmental Set 83 Table 2 - Summary of Environmental Set 84 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
TABLE OF CONTENTS Section Title Pages I.
Reactor Operations Sum m ary...............................................................
I-I through 9 f].
M U RR Procedures................................................................................
Il-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..........................................
Ill-I through 4 IV.
Plant and System M odifications...........................................................
IV-1 through 3 V.
New Tests and Experiments............................................................
V-1 VI.
Special Nuclear Material and Reactor Physics Activities................ VI-1 VII.
Radioactive Effluent.............................................................................
VII-I through 2 Table 1 - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII.
Environmental Monitoring and Health Physics Surveys...................... VIII-l through 6 Table I - Summary of Environmental Set 83 Table 2 - Summary of Environmental Set 84 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 I REACTOR OPERATIONS  
SECTION I REACTOR OPERATIONS  


==SUMMARY==
==SUMMARY==
January 1,2013 through December 31, 2013 The following table and discussion summarizes reactor operations during the period from January 1, 2013 through December 31, 2013.
January 1,2013 through December 31, 2013 The following table and discussion summarizes reactor operations during the period from January 1, 2013 through December 31, 2013.
Full Power % of Total   Full Power % of Month       Full Power Hours         Megawatt Days               Time               Scheduled"'1 January           679.75                 283.43                   91.4                 102.3 February           589.33                 245.87                   87.7                   98.2 March             664.72                 277.30                   89.3                 100.0 April             619.93                 258.61                   86.1                   96.6 May             649.35                 270.93                   87.3                 97.7 June             633.77                 264.35                   88.0                 98.7 July             653.10                 272.39                   87.8                 98.3 August             653.01                 272.41                   87.8                 98.3 September           631.41                 263.39                   87.7                 98.4 October             672.05                 280.20                   90.3                 101.1 November             656.37                 273.77                   91.2                 102.2 December             666.32                 277.85                   89.6                 100.3 Total for           7769.11                 3240.50                 88.68 %               99.34 %
Full Power % of Total Full Power % of Month Full Power Hours Megawatt Days Time Scheduled"'1 January 679.75 283.43 91.4 102.3 February 589.33 245.87 87.7 98.2 March 664.72 277.30 89.3 100.0 April 619.93 258.61 86.1 96.6 May 649.35 270.93 87.3 97.7 June 633.77 264.35 88.0 98.7 July 653.10 272.39 87.8 98.3 August 653.01 272.41 87.8 98.3 September 631.41 263.39 87.7 98.4 October 672.05 280.20 90.3 101.1 November 656.37 273.77 91.2 102.2 December 666.32 277.85 89.6 100.3 Total for 7769.11 3240.50 88.68 %
the Year Note 1: MURR is scheduled to average at least 150 hours of full power operation per week. Total time is the number of hours in the month listed or the year.
99.34 %
January 2013 The reactor operated continuously in January with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.
the Year Note 1: MURR is scheduled to average at least 150 hours number of hours in the month listed or the year.
Major maintenance items for the month included: replacing Reactor Pool Reflector Region Differential Pressure Transmitter PT-917; 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).'"
of full power operation per week. Total time is the January 2013 The reactor operated continuously in January with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.
February 2013 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and two unscheduled/unplanned power reductions.
Major maintenance items for the month included:
replacing Reactor Pool Reflector Region Differential Pressure Transmitter PT-917; 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).'"
February 2013 The reactor operated continuously in February with the following exceptions:
four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and two unscheduled/unplanned power reductions.
On February 23, 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 the reactor safety system yellow leg Trip Actuator Amplifier 1-1
On February 23, 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 the reactor safety system yellow leg Trip Actuator Amplifier 1-1


(TAA) de-energized, causing control blades 'A' and 'B' anvils to separate from their electromagnets and drop. A manual scram was then 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 reactor safety system revealed that a normally closed contact in the manual scram switch., 1SI 0, was intermittently making a poor connection. The contact blocks in the manual scram switch were burnished and the yellow leg TAA was replaced. The system was 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.
(TAA) de-energized, causing control blades 'A' and 'B' anvils to separate from their electromagnets and drop. A manual scram was then 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 reactor safety system revealed that a normally closed contact in the manual scram switch., 1SI 0, was intermittently making a poor connection.
On February 23, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was automatically initiated when an interruption in electrical 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 Lead Senior Reactor Operator after confirmation from the power plant that the cause of the interruption in electrical power was corrected. A "hot reactor startup" was performed to return the reactor to 10 MW operation.
The contact blocks in the manual scram switch were burnished and the yellow leg TAA was replaced. The system was 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.
On February 23, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was automatically initiated when an interruption in electrical 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 Lead Senior Reactor Operator after confirmation from the power plant that the cause of the interruption in electrical power was corrected. A "hot reactor startup" was performed to return the reactor to 10 MW operation.
Major maintenance items for the month included: replacing the 30-degree graphite reflector elements 'GH' and 'IJ' with a single 60-degree graphite reflector element 'GHIJ;' and replacing the pool coolant demineralizer system inlet filters.
Major maintenance items for the month included: replacing the 30-degree graphite reflector elements 'GH' and 'IJ' with a single 60-degree graphite reflector element 'GHIJ;' and replacing the pool coolant demineralizer system inlet filters.
March 2013 The reactor operated continuously in March with the following exceptions:             four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and four unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of the Radiation Protection Program and Shipping.
March 2013 The reactor operated continuously in March with the following exceptions:
four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and four unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of the Radiation Protection Program and Shipping.
On March 4, while reviewing a list of the completed maintenance items and compliance procedures performed that day, the Surveillance Programs System Specialist discovered that compliance procedure CP-27, "Power Level Interlock Static Scram," was not completed within the prescribed Technical Specification (TS) periodicity. Failure to perform the surveillance within the required time interval resulted in a deviation from TS 5.4. Licensee Event Report No. 13-01 was submitted to the U.S. Nuclear Regulatory Commission on April 2, 2013. The compliance procedure was performed on March 11, the next scheduled maintenance day after discovery of the error.
On March 4, while reviewing a list of the completed maintenance items and compliance procedures performed that day, the Surveillance Programs System Specialist discovered that compliance procedure CP-27, "Power Level Interlock Static Scram," was not completed within the prescribed Technical Specification (TS) periodicity. Failure to perform the surveillance within the required time interval resulted in a deviation from TS 5.4. Licensee Event Report No. 13-01 was submitted to the U.S. Nuclear Regulatory Commission on April 2, 2013. The compliance procedure was performed on March 11, the next scheduled maintenance day after discovery of the error.
On March 5, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction. After a brief investigation was unable to determine the cause of the rod run-in, the rod run-in was not manually reset and the reactor was shut down. Subsequent investigation of all power supplies, relays, switches and wiring connections associated with the rod run-in system revealed no abnormalities. Additional troubleshooting and investigation were unable to reproduce this system response.
On March 5, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction. After a brief investigation was unable to determine the cause of the rod run-in, the rod run-in was not manually reset and the reactor was shut down. Subsequent investigation of all power supplies, relays, switches and wiring connections associated with the rod run-in system revealed no abnormalities.
Additional troubleshooting and investigation were unable to reproduce this system response.
Operational checks of the rod run-in system were performed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
Operational checks of the rod run-in system were performed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
On March 5 (5 hours and 55 minutes after the previous power reduction), with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated.
On March 5 (5 hours and 55 minutes after the previous power reduction), with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated.
The control room operator immediately noted all four shim control blades moving in the inward direction. After a brief investigation was unable to determine the cause of the rod run-in, the reactor was manually scrammed. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed.                   Subsequent 1-2
The control room operator immediately noted all four shim control blades moving in the inward direction. After a brief investigation was unable to determine the cause of the rod run-in, the reactor was manually scrammed. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed.
Subsequent 1-2


investigation did not identify a failed component; however, the most likely cause was a failure of either the rod run-in system Trip Actuator Amplifier (TAA) or Non-Coincidence Logic Unit (NCLU). The rod run-in system TAA and NCLUs were replaced and operational checks of the rod run-in system were performed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
investigation did not identify a failed component; however, the most likely cause was a failure of either the rod run-in system Trip Actuator Amplifier (TAA) or Non-Coincidence Logic Unit (NCLU). The rod run-in system TAA and NCLUs were replaced and operational checks of the rod run-in system were performed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
On March 13, 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 electromagnet during a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.
On March 13, 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 electromagnet during a routine sample handling evolution.
On March 20, 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 'A' anvil separated from its electromagnet during a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.
The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.
Major maintenance items for the month included: completing Modification Record 13-03, "Replacement of GH and IJ Wedge with a Single 600 Wedge;" completing Modification Record 12-02, "Control Blade Fabrication Alternative Using Laser Welding;" completing Modification Record 01-02, Addendum 9, "Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299) Renovations;" 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 a reactivity worth measurement in accordance with reactor procedure RP-RO-203, "Measurement of the Primary Coolant/Moderator Temperature Coefficient of Reactivity, RTP-19," in support of a Nuclear Engineering Department practicum; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP- II(D)," in support of a Nuclear Engineering Department practicum; and loading new de-ionization bed
On March 20, 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 'A' anvil separated from its electromagnet during a routine sample handling evolution.
The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.
Major maintenance items for the month included: completing Modification Record 13-03, "Replacement of GH and IJ Wedge with a Single 600 Wedge;" completing Modification Record 12-02, "Control Blade Fabrication Alternative Using Laser Welding;" completing Modification Record 01-02, Addendum 9, "Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299) Renovations;" 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 a reactivity worth measurement in accordance with reactor procedure RP-RO-203, "Measurement of the Primary Coolant/Moderator Temperature Coefficient of Reactivity, RTP-19," in support of a Nuclear Engineering Department practicum; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-II(D)," in support of a Nuclear Engineering Department practicum; and loading new de-ionization bed
'F' and placing on pool coolant system service.
'F' and placing on pool coolant system service.
April 2013 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and one unscheduled/unplanned power reduction. One additional reactor startup and shutdown were performed in support of NRC operator license examinations. MURR received notification from the U.S. Nuclear Regulatory Commission that two new Reactor Operator and one new Senior Reactor Operator licenses had been issued.
April 2013 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and one unscheduled/unplanned power reduction. One additional reactor startup and shutdown were performed in support of NRC operator license examinations. MURR received notification from the U.S. Nuclear Regulatory Commission that two new Reactor Operator and one new Senior Reactor Operator licenses had been issued.
On April 30, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction. The reactor was then subsequently shut down. Subsequent investigation did not identify a failed component; however, two resistors in the Trip Actuating Amplifier (TAA) circuit were determined to have resistance values outside their specified tolerances. Both resistors were replaced.
On April 30, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction.
The reactor was then subsequently shut down. Subsequent investigation did not identify a failed component; however, two resistors in the Trip Actuating Amplifier (TAA) circuit were determined to have resistance values outside their specified tolerances. Both resistors were replaced.
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On May 7, with the reactor operating at 10 MW in the automatic control mode, a manual scram was initiated when an operator discovered the regulating blade would not move in the inward direction. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram" were performed. Subsequent investigation revealed the ball plunger for the overload clutch had loosened and slightly backed out preventing the movement of the servomotor from being transferred to the lead screw assembly, thus preventing the regulating blade from being able to drive in the outward and inward directions. The overload clutch was inspected and the ball plunger was replaced. Operational checks of the regulating blade were performed satisfactorily and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
On May 7, with the reactor operating at 10 MW in the automatic control mode, a manual scram was initiated when an operator discovered the regulating blade would not move in the inward direction. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram" were performed. Subsequent investigation revealed the ball plunger for the overload clutch had loosened and slightly backed out preventing the movement of the servomotor from being transferred to the lead screw assembly, thus preventing the regulating blade from being able to drive in the outward and inward directions. The overload clutch was inspected and the ball plunger was replaced. Operational checks of the regulating blade were performed satisfactorily and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
Failure of the regulating blade to be operable during reactor operation resulted in a deviation from Technical Specification 3.4.c. Licensee Event Report No. 13-02 was submitted to the U.S. Nuclear Regulatory Commission on June 4, 2013.
Failure of the regulating blade to be operable during reactor operation resulted in a deviation from Technical Specification 3.4.c. Licensee Event Report No. 13-02 was submitted to the U.S. Nuclear Regulatory Commission on June 4, 2013.
On May 8, 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 electromagnet during a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.
On May 8, 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 electromagnet during a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator.
The reactor was subsequently restarted to 10 MW operation.
On May 14, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) reactor scram was automatically initiated. Investigation revealed all monitored parameters were normal and none had trended toward an automatic scram set point or exhibited any abnormalities. Subsequent troubleshooting efforts led to the replacement of Power Level Interlock relay I1K26. Operational checks of the Power Level Interlock circuit were performed satisfactorily and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
On May 14, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) reactor scram was automatically initiated. Investigation revealed all monitored parameters were normal and none had trended toward an automatic scram set point or exhibited any abnormalities. Subsequent troubleshooting efforts led to the replacement of Power Level Interlock relay I1K26. Operational checks of the Power Level Interlock circuit were performed satisfactorily and 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: replacing Power Level Interlock relay IK26; replacing the diaphragm and inlet and outlet flange gaskets for pool coolant demineralizer pump P-513B Discharge Valve 515N; 1-4
Major maintenance items for the month included:
replacing Power Level Interlock relay IK26; replacing the diaphragm and inlet and outlet flange gaskets for pool coolant demineralizer pump P-513B Discharge Valve 515N; 1-4


completing compliance procedure CP-26, "Containment Building Compliance Test;" 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)."
completing compliance procedure CP-26, "Containment Building Compliance Test;" 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)."
June 2013 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and two unscheduled/unplanned power reductions.
June 2013 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and two unscheduled/unplanned power reductions.
On June 11, 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 'A' anvil separated from its electromagnet during a routine sample handling evolution. The reactor was manually scrammed and the immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Inspection of the offset mechanism pull rod and housing revealed a slight misalignment between the anvil and electromagnet. The lower drive limit switch was adjusted and the anvil and electromagnet were cleaned. The control rod was satisfactorily withdrawn to the full out position as part of the retest by performing compliance procedure CP-10, "Rod Drop Times." Permission to perform a "hot reactor startup" was obtained from the Reactor Manager. While conducting the "hot reactor startup," the Reactor Operator noted, immediately after stabilizing reactor power level at 5 MW, that the heights of shim control blades 'B' and 'D' were at 21.90 and 23.10 inches, respectively. This 1.20 inch difference in shim blade height created a deviation from Technical Specification (TS) 3.2.b, which states, "Above 100 kilowatts the reactor shall be operated so that the maximum distance between the highest and lowest shim blade shall not exceed one inch." Licensee Event Report No. 13-03 was submitted to the U.S. Nuclear Regulatory Commission on July 10, 2013.
On June 11, 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 'A' anvil separated from its electromagnet during a routine sample handling evolution. The reactor was manually scrammed and the immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed.
On June 14, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction. The reactor was then subsequently shut down. Subsequent investigation did not identify a failed component. Additional troubleshooting and investigation were unable to reproduce this system response. Operational checks of the rod run-in system were performed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
Inspection of the offset mechanism pull rod and housing revealed a slight misalignment between the anvil and electromagnet. The lower drive limit switch was adjusted and the anvil and electromagnet were cleaned. The control rod was satisfactorily withdrawn to the full out position as part of the retest by performing compliance procedure CP-10, "Rod Drop Times." Permission to perform a "hot reactor startup" was obtained from the Reactor Manager. While conducting the "hot reactor startup," the Reactor Operator noted, immediately after stabilizing reactor power level at 5 MW, that the heights of shim control blades 'B' and 'D' were at 21.90 and 23.10 inches, respectively. This 1.20 inch difference in shim blade height created a deviation from Technical Specification (TS) 3.2.b, which states, "Above 100 kilowatts the reactor shall be operated so that the maximum distance between the highest and lowest shim blade shall not exceed one inch." Licensee Event Report No. 13-03 was submitted to the U.S. Nuclear Regulatory Commission on July 10, 2013.
On June 14, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction. The reactor was then subsequently shut down. Subsequent investigation did not identify a failed component.
Additional troubleshooting and investigation were unable to reproduce this system response. Operational checks of the rod run-in system were performed satisfactorily.
The reactor was refueled and 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: performing extensive troubleshooting on the rod run-in system wiring connections; completing Modification Record 13-04, "Rod Run-In Monitoring System;" completing Modification Record 75-01, Addendum 3, "Rod Run-In Electronic Circuit Jumper Panel;" completing Modification Record 13-01, "Replacement of TE-980A and TE-980B Power Supply 2PS5;" 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 replacing the Loss of Voltage to Magnet A and B Scram relay 2K20 and the Loss of Voltage to Magnet C and D Scram relay 2K2 1.
Major maintenance items for the month included: performing extensive troubleshooting on the rod run-in system wiring connections; completing Modification Record 13-04, "Rod Run-In Monitoring System;" completing Modification Record 75-01, Addendum 3, "Rod Run-In Electronic Circuit Jumper Panel;" completing Modification Record 13-01, "Replacement of TE-980A and TE-980B Power Supply 2PS5;" 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 replacing the Loss of Voltage to Magnet A and B Scram relay 2K20 and the Loss of Voltage to Magnet C and D Scram relay 2K2 1.
July 2013 The reactor operated continuously in July with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of Security and Material Control and Accountability. The U.S. Nuclear Regulatory Commission issued Amendment No. 36 to Amended Facility License No. R-103.
July 2013 The reactor operated continuously in July with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of Security and Material Control and Accountability. The U.S. Nuclear Regulatory Commission issued Amendment No. 36 to Amended Facility License No. R-103.
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The reactor was shut down and the immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The mating surfaces between the control rod drive mechanism electromagnet and pull rod anvil were cleaned and proper alignment of the offset mechanism pull rod and housing were verified. The control rod was satisfactorily withdrawn to the full out position as part of the retest by performing compliance procedure CP-10, "Rod Drop Times." Permission to restart the reactor was obtained from the Reactor Manager.
The reactor was shut down and the immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The mating surfaces between the control rod drive mechanism electromagnet and pull rod anvil were cleaned and proper alignment of the offset mechanism pull rod and housing were verified. The control rod was satisfactorily withdrawn to the full out position as part of the retest by performing 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: 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);" 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 Vent Tank Discharge Check Valve 550A; replacing Pool Below Refuel Level relay 2K5; replacing the chassis edge connectors for the rod run-in system and the reactor safety system Trip Actuator Amplifiers and Non-Coincidence Logic Units; and replacing the air actuator and diaphragm on pressurizer Water Drain Valve 527A.
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-I I(D);" 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 Vent Tank Discharge Check Valve 550A; replacing Pool Below Refuel Level relay 2K5; replacing the chassis edge connectors for the rod run-in system and the reactor safety system Trip Actuator Amplifiers and Non-Coincidence Logic Units; and replacing the air actuator and diaphragm on pressurizer Water Drain Valve 527A.
August 2013 The reactor operated continuously in August with the following exceptions:               four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, one shutdown for training and four unscheduled/unplanned power reductions.
August 2013 The reactor operated continuously in August with the following exceptions:
On August 21, with the reactor operating at 10 MW in the automatic control mode, a "Reactor Loop Low Pressure" scram was automatically initiated. All immediate and subsequent actions of reactor emergency procedure REP-3, "Primary Coolant System Low Pressure or Flow Scram," were performed. No actual low pressure condition indication was present. Investigation determined the most likely cause to be reactor core outlet pressure channels 944A or 944B. Contacts on Reactor Pressure/Flow Interlock relays 2K32 and 2K33 were burnished, reactor core outlet pressure transmitters were vented and applicable sections of compliance procedure CP-22, "Pressure Transmitters PT-944A/B and PT-943," were completed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, one shutdown for training and four unscheduled/unplanned power reductions.
On August 23, with the reactor operating at 10 MW in the automatic control mode, a "Reactor Loop Low Pressure" scram was automatically initiated. All immediate and subsequent actions of reactor emergency procedure REP-3, "Primary Coolant System Low Pressure or Flow Scram," were performed. No actual low pressure condition indication was present. Investigation determined the cause to be an intermittent failure of reactor core outlet pressure 944B meter/relay unit. The meter/relay unit was replaced and applicable sections of compliance procedure CP-22 "Pressure Transmitters PT-944A/B and PT-943," were completed satisfactorily.             The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
On August 21, with the reactor operating at 10 MW in the automatic control mode, a "Reactor Loop Low Pressure" scram was automatically initiated. All immediate and subsequent actions of reactor emergency procedure REP-3, "Primary Coolant System Low Pressure or Flow Scram," were performed.
No actual low pressure condition indication was present. Investigation determined the most likely cause to be reactor core outlet pressure channels 944A or 944B. Contacts on Reactor Pressure/Flow Interlock relays 2K32 and 2K33 were burnished, reactor core outlet pressure transmitters were vented and applicable sections of compliance procedure CP-22, "Pressure Transmitters PT-944A/B and PT-943," were completed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.
The reactor was subsequently restarted to 10 MW operation.
On August 23, with the reactor operating at 10 MW in the automatic control mode, a "Reactor Loop Low Pressure" scram was automatically initiated. All immediate and subsequent actions of reactor emergency procedure REP-3, "Primary Coolant System Low Pressure or Flow Scram," were performed.
No actual low pressure condition indication was present. Investigation determined the cause to be an intermittent failure of reactor core outlet pressure 944B meter/relay unit. The meter/relay unit was replaced and applicable sections of compliance procedure CP-22 "Pressure Transmitters PT-944A/B and PT-943," were completed satisfactorily.
The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
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On August 25, 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 was separated from its electromagnet during a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
On August 25, 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 was separated from its electromagnet during a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
On August 26, during a reactor startup with the control blades at approximately 11 inches withdrawn (subcritical), a "Channel 2 & 3 Period" scram was automatically initiated when Nuclear Instrumentation (NI) Intermediate Range Channel No. 2 period indication increased above the scram set point. The duty operator noted all power level and period indications other than those from NI Signal Processor No. 1 were normal. All immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Troubleshooting efforts led to the replacement of NI Signal Processor No. I fission chamber and its associated cabling. An instrument channel calibration and pre-operational checks were performed satisfactorily, including a response check using the neutron source. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.
On August 26, during a reactor startup with the control blades at approximately 11 inches withdrawn (subcritical), a "Channel 2 & 3 Period" scram was automatically initiated when Nuclear Instrumentation (NI) Intermediate Range Channel No. 2 period indication increased above the scram set point. The duty operator noted all power level and period indications other than those from NI Signal Processor No. 1 were normal. All immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Troubleshooting efforts led to the replacement of NI Signal Processor No. I fission chamber and its associated cabling. An instrument channel calibration and pre-operational checks were performed satisfactorily, including a response check using the neutron source. The reactor was refueled and 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: completing Modification Record 04-05, Addendum 8, "Cooling Tower Electrical Arc Flash Danger Mitigation;" completing Modification Record 12-01, "Replace PT-944A/B with Rosemount Transmitters;" 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 chemical cleaning of the secondary coolant side of primary coolant heat exchanger HX-503A; loading new de-ionization bed 'D' and placing it on pool coolant system service; and replacing the fission chamber detector and associated cabling for NI Signal Processor No. 1.
Major maintenance items for the month included: completing Modification Record 04-05, Addendum 8, "Cooling Tower Electrical Arc Flash Danger Mitigation;" completing Modification Record 12-01, "Replace PT-944A/B with Rosemount Transmitters;" 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 chemical cleaning of the secondary coolant side of primary coolant heat exchanger HX-503A; loading new de-ionization bed 'D' and placing it on pool coolant system service; and replacing the fission chamber detector and associated cabling for NI Signal Processor No. 1.
September 2013 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, two shutdowns for training and two unscheduled/unplanned shutdowns.
September 2013 The reactor operated continuously in September with the following exceptions:
four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, two shutdowns for training and two unscheduled/unplanned shutdowns.
On September 16, with the reactor operating at 10 MW in the automatic control mode, a reactor shutdown was initiated after the duty operator observed a blown fuse indication on Annunciator Control Power Fuse 2F7, accompanied, shortly thereafter, by an Uninterruptible Power Supply (UPS) trouble alarm. All other indications for 10 MW operation were normal. Further investigation revealed that the Annunciator 115VAC Supply Breaker on UPS Panel No. 2 was in the tripped condition and the Annunciator inoperable. Troubleshooting efforts determined that the most likely cause of the blown fuse and tripped breaker was a faulty alarm module. The Annunciator alarm module for "Channel 4, 5, or 6 Downscale" function was replaced and an operational test of the Annunciator was completed satisfactorily. Permission to the restart the reactor was obtained from the Reactor Manager. The reactor was subsequently returned to 10 MW operation.
On September 16, with the reactor operating at 10 MW in the automatic control mode, a reactor shutdown was initiated after the duty operator observed a blown fuse indication on Annunciator Control Power Fuse 2F7, accompanied, shortly thereafter, by an Uninterruptible Power Supply (UPS) trouble alarm. All other indications for 10 MW operation were normal. Further investigation revealed that the Annunciator 115VAC Supply Breaker on UPS Panel No. 2 was in the tripped condition and the Annunciator inoperable. Troubleshooting efforts determined that the most likely cause of the blown fuse and tripped breaker was a faulty alarm module. The Annunciator alarm module for "Channel 4, 5, or 6 Downscale" function was replaced and an operational test of the Annunciator was completed satisfactorily. Permission to the restart the reactor was obtained from the Reactor Manager. The reactor was subsequently returned to 10 MW operation.
On September 23, with the reactor operating at 10 MW in the automatic control mode, a reactor shutdown was initiated after the duty operator observed a greater than normal lowering of pressurizer liquid level of approximately 2 inches per hour. This abnormal decrease in liquid level was observed shortly after a reactor startup. A reactor refueling had been performed earlier in the day. Subsequent investigation revealed that the source of leakage was from the pressure vessel head packing gland seal, which provides the seal between the pressure vessel head and inner reactor pressure vessel. Note: The pressure vessel head is removed and then subsequently replaced and tightened 1-7
On September 23, with the reactor operating at 10 MW in the automatic control mode, a reactor shutdown was initiated after the duty operator observed a greater than normal lowering of pressurizer liquid level of approximately 2 inches per hour. This abnormal decrease in liquid level was observed shortly after a reactor startup. A reactor refueling had been performed earlier in the day. Subsequent investigation revealed that the source of leakage was from the pressure vessel head packing gland seal, which provides the seal between the pressure vessel head and inner reactor pressure vessel. Note: The pressure vessel head is removed and then subsequently replaced and tightened 1-7


after refueling a core has been completed. The packing gland was tightened and permission to restart the reactor was obtained from the Reactor Manager. The reactor was returned to 10 MW operation. Operators were subsequently counseled on proper bolting techniques.
after refueling a core has been completed. The packing gland was tightened and permission to restart the reactor was obtained from the Reactor Manager. The reactor was returned to 10 MW operation. Operators were subsequently counseled on proper bolting techniques.
Major maintenance items for the month included: completing Modification Record 01-02, Addendum 10, "Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299), Room 243, Room 246 and Room 271 Renovations;" 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);" completing a change-out of Control Blade 'A' Offset Mechanism and associated retesting; and replacing the "Channel 4, 5 or 6 Downscale" annunciator alarm module.
Major maintenance items for the month included:
October 2013 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unplanned/unscheduled shutdowns this month.
completing Modification Record 01-02, Addendum 10, "Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299), Room 243, Room 246 and Room 271 Renovations;" 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);" completing a change-out of Control Blade 'A' Offset Mechanism and associated retesting; and replacing the "Channel 4, 5 or 6 Downscale" annunciator alarm module.
October 2013 The reactor operated continuously in October with the following exceptions:
four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unplanned/unscheduled shutdowns this month.
Major maintenance items for the month included: completing Modification Record 04-03, Addendum 1, "Liquid Radioactive Waste System in MURR Industrial Building;" completing Modification Record 13-06, "Modifications to MURR Industrial Building (Room 299) in Support of the NS-99 Project;" replacing Nuclear Instrumentation Power Range "Channel 4 Downscale (95%)" relay unit K58; flooding and draining Beamport 'D' and back filling with helium; performing the biennial change-out of Control Blade 'C' Offset Mechanism and associated retesting; 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)."
Major maintenance items for the month included: completing Modification Record 04-03, Addendum 1, "Liquid Radioactive Waste System in MURR Industrial Building;" completing Modification Record 13-06, "Modifications to MURR Industrial Building (Room 299) in Support of the NS-99 Project;" replacing Nuclear Instrumentation Power Range "Channel 4 Downscale (95%)" relay unit K58; flooding and draining Beamport 'D' and back filling with helium; performing the biennial change-out of Control Blade 'C' Offset Mechanism and associated retesting; 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)."
November 2013 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and one unscheduled/unplanned power reduction. Three additional reactor startups and shutdowns were performed in support of NRC operator license examinations. U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of Reactor Operations and Emergency Preparedness. MURR received notification from the U.S. Nuclear Regulatory Commission that three new Reactor Operator and three new Senior Reactor Operator licenses had been issued.
November 2013 The reactor operated continuously in November with the following exceptions:
On November 11, 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 electromagnet during a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment and operability tests were performed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.
four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and one unscheduled/unplanned power reduction. Three additional reactor startups and shutdowns were performed in support of NRC operator license examinations. U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of Reactor Operations and Emergency Preparedness. MURR received notification from the U.S. Nuclear Regulatory Commission that three new Reactor Operator and three new Senior Reactor Operator licenses had been issued.
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);" and performing pre-beryllium change-out center test hole flux profile measurements.
On November 11, 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 electromagnet during a routine sample handling evolution.
The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment and operability tests were performed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.
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);" and performing pre-beryllium change-out center test hole flux profile measurements.
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December 2013 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.
December 2013 The reactor operated continuously in December with the following exceptions:
five shutdowns for scheduled maintenance and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: completing Modification Record 13-05, "T-300 and T-301 Level Sensing System;" 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);" loading new de-ionizing bed 'R' and placing on pool coolant system service; and performing a chemical cleaning of the secondary coolant side of pool coolant system heat exchanger HX-52 1.
Major maintenance items for the month included: completing Modification Record 13-05, "T-300 and T-301 Level Sensing System;" 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);" loading new de-ionizing bed 'R' and placing on pool coolant system service; and performing a chemical cleaning of the secondary coolant side of pool coolant system heat exchanger HX-52 1.
1-9
1-9
Line 141: Line 192:
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.
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-two (62) revisions issued to the reactor operations procedures, forms and operator aids. 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:
There were sixty-two (62) revisions issued to the reactor operations procedures, forms and operator aids. 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:
      ~Ntinier~                           Name                           Rev Aevision Dte             Notes AP-RO-130     Crane Operation                                     16       3/29/2013       Cover Page AP-RR-003     10 CFR 50.59 Evaluations                               8     6/5/2013       Minor Editorial EX-RO-105     Reactor Irradiation Experiments                     119       5/22/2013     Minor Editorial Type B Shipment of spent Fuel Using the BEA             I FB-SH- I10       e Research  Reactor PackageI                                    4/16/2013     Minor Editorial FB-SH- 110   ~Type B Shipment of spent Fuel Using the BEA                     5/14/2013       Full Review Research Reactor Package FM- 1       Reactor Shutdown Checksheet                             6     12/20/2013       Cover Page FM-15       110 CFR 50.59 Qualified Reviewers List                   15     6/5/2013 . Minor Editorial FM-15       10 CFR 50.59 Qualified Reviewers List                   16   12/19/2013     Minor Editorial FM-21       ARMS Trip Setpoints                                     9     6/6/2013       Minor Editorial FM-33       Containment Building Restricted Materials               5     12/9/2013       Cover Page FM-43       Nuclear and Process Data                               17     3/29/2013       Cover Page FM-43       Nuclear and Process Data                               18     10/17/2013     Minor Editorial FM-55       jStartup Nuclear Data Sheet                             7     3/29/2013     Minor Editorial FM-56       lReactor Routine Patrol                                 16     3/29/2013     Minor Editorial FM-57       Long Form Startup Checksheet                           20     5/2/2013       Minor Editorial FM-57       Long Form Startup Checksheet                           21     10/31/2013     Minor Editorial FM-58 .     Short Form Startup Checksheet                 .        11     10/31/2013     Minor Editorial
~Ntinier~
    . FM-63 .       DI Water Makeup Log                                 19       1/31/2013       Cover Page.
Name Rev Aevision Dte Notes AP-RO-130 Crane Operation 16 3/29/2013 Cover Page AP-RR-003 10 CFR 50.59 Evaluations 8
FM-66        Customer Sample Pre-Encapsulation Evaluation               1 77W6/0/213eino 6/10/2013       Minor Editorial
6/5/2013 Minor Editorial EX-RO-105 Reactor Irradiation Experiments 119 5/22/2013 Minor Editorial Type B Shipment of spent Fuel Using the BEA I
__________  Worksheet FM-68       Target Material Control Checksheet                     12   J 6/10/2013       Minor Editorial FM-93 .Post       Maintenance Valve Line-up Checksheet               5     6/10/20 1.3     Cover Page IRR-PSO- 111 ICustomer Sample Pre-Encapsulation Evaluation           I     -  6/10/2013     M inor Editorial 11-1
FB-SH-I10 e
4/16/2013 Minor Editorial Research Reactor PackageI FB-SH-110 ~Type B Shipment of spent Fuel Using the BEA 5/14/2013 Full Review Research Reactor Package FM-1 Reactor Shutdown Checksheet 6
12/20/2013 Cover Page FM-15 110 CFR 50.59 Qualified Reviewers List 15 6/5/2013.
Minor Editorial FM-15 10 CFR 50.59 Qualified Reviewers List 16 12/19/2013 Minor Editorial FM-21 ARMS Trip Setpoints 9
6/6/2013 Minor Editorial FM-33 Containment Building Restricted Materials 5
12/9/2013 Cover Page FM-43 Nuclear and Process Data 17 3/29/2013 Cover Page FM-43 Nuclear and Process Data 18 10/17/2013 Minor Editorial FM-55 jStartup Nuclear Data Sheet 7
3/29/2013 Minor Editorial FM-56 lReactor Routine Patrol 16 3/29/2013 Minor Editorial FM-57 Long Form Startup Checksheet 20 5/2/2013 Minor Editorial FM-57 Long Form Startup Checksheet 21 10/31/2013 Minor Editorial FM-58.
Short Form Startup Checksheet 11 10/31/2013 Minor Editorial FM-63.
DI Water Makeup Log 19 1/31/2013 Cover Page.
Customer Sample Pre-Encapsulation Evaluation 7 1 6/10/2013 Minor FM-66 7W6/0/213eino Editorial Worksheet FM-68 Target Material Control Checksheet 12 J 6/10/2013 Minor Editorial FM-93.Post Maintenance Valve Line-up Checksheet 5
6/10/20 1.3 Cover Page IRR-PSO-111 ICustomer Sample Pre-Encapsulation Evaluation I
6/10/2013 Minor Editorial 11-1


j Nu~mber OP-RO-100 Main Air System OP-RO-101 Instrument Air System Na~me j.10 J
Nu~mber Na~me Rgy. Revision Dite j No9tes OP-RO-100 Main Air System j.10 3/29/2013 Minor Editorial OP-RO-101 Instrument Air System J 10 3/29/2013 Minor Editorial OP-RO-210 Reactor Startup-Normal 113 5/22/2013 3 Cover Page OP-RO-211 Reactor Startup-Hot 11 ] 6/25/2013 3 Minor Editorial OP-RO-211 lReactor Startup - Hot 1
Rgy. Revision Dite 10 3/29/2013 3/29/2013 No9tes Minor Editorial Minor Editorial OP-RO-210 Reactor Startup-Normal                               113       5/22/2013 3   Cover Page OP-RO-211 Reactor Startup-Hot                                     11 ] 6/25/2013   3 Minor Editorial OP-RO-211 lReactor Startup - Hot                                   112    8/22/2013 3 Minor Editorial Reactor Startup - Recovery from Temporary Power         1 1 OP-RO-212   Reduction                                                     12/9/2013     Cover Page OP-RO-220   Reactor Shutdown or Power Reduction                     81   6/25/2013   Minor Editorial OP-RO-230   Changing Reactor Power Level                           8     6/25/2013   Minor Editorial OP-RO-310
12 8/22/2013 3 Minor Editorial Reactor Startup - Recovery from Temporary Power 1
_Nuclear             Instrumentation - Signal Processor #1     310       5/22/2013     Cover Page OP-RO-311 TNuclear Instrumentation - Signal Processor #2         11     5/22/2013     Cover Page OPhannOe316 OP-RO-312   Nuclear Instrumentation Power Range Monitor -         13 13     52/03         Cover Page OP-RO-330   Nuclear Instrumentation- Wide Range Monitor           13 1      5/22/2013     Cover Page OP-RO-340   Nuclear Instrumentation Adjustment           .        103     5/22/2013     Cover Page Reactor Power Calculator Flow Potentiometer OP-RO-350   Adjustment                                                   9/24/2013     Cover Page OP-RO-410 ]Primary Coolant System                             .l.1i     5/2/2013     Minor Editorial OP-RO-420 3Primary and Pool Water Analysis                   161 9/24/2013         j   Cover Page OP-RO-460 3Pool Coolant System - Two Pump Operation           314..3 9/24/2013         Minor Editorial OP-RO-461 JPool Coolant System - One Pump Operation               14T 9/24/2013       Minor Editorial OP-RO-465 3Pool Level Control - Skimmer System               18         3/29/2013   Minor Editorial OP-RO-480 3Secondary   Coolant System                           17     9/24/2013     Minor Editorial OP-RO-480   3Secondary Coolant System                             18       12/9/2013   Minor Editorial OP-RO-510   Nitrogen System                                   37.         5/2/2013 3 Minor Editorial OP-RO-515   Emergency Air System                             J9         9/24/2013 f Minor Editorial OP-RO-516   Valve Operation Air System1                             9 1 8/22/2013 1   Cover Page OP-RO-525   Chill Water System                                 17         6/25/2013     Minor Editorial OP-RO-530   Demineralized Water Supply System                 IT13       8/22/2013     Cover Page OP-RO-531   Primary and Pool Sample Station                   I1         9/24/2013     Cover Page OP-RO-555   Fire Protection System                             .10       1/31/2013   Minor Editorial OP-RO-555   Fire Protection System                             311       11/19/2013   Minor Editorial OP-RO-710   Radiation Monitoring - Area Monitors               181       8/22/2013     Cover Page .
1 OP-RO-212 Reduction 12/9/2013 Cover Page OP-RO-220 Reactor Shutdown or Power Reduction 81 6/25/2013 Minor Editorial OP-RO-230 Changing Reactor Power Level 8
OP-RO_720 jRadiation Monitoring - Stack Monitor Operational     1       6       1 OPhROec20                                                         11     6/25/2013     Minor Editorial OP-RO-730   Facility Exhaust System                               14     3/29/2013     Minor Editorial OP-RO-741   Waste Tank System Operation                           13     5/2/2013     Minor Editorial OP-RO-741   Waste Tank System Operation                           14     12/19/2013   Minor Editorial POL-20   Special Nuclear Materials Manual                         13 3/3/8/2013     Minor Editorial REP-RO-100 IReactor Emergency Procedures                       3161 1/31/2013           Cover Page RM-RO-400   Waste Tank System Filter Replacement               373 3/29/2013           Minor Editorial Receipt, Inspection and Accounting of Unirradiated           5/1nEo
6/25/2013 Minor Editorial OP-RO-310
    -RO-00                                                               5/22/2013     Minor Editorial SM-RO-200   Manual Operation of Airlock doors 276 and 277         2       5/7/2013     Minor Editorial SM-RO-301 lControl Console And Instrument Panel -Securing         10     9/24/2013     Cover Page 3Power 11-2
_Nuclear Instrumentation - Signal Processor #1 310 5/22/2013 Cover Page OP-RO-311 TNuclear Instrumentation - Signal Processor #2 11 5/22/2013 Cover Page OP-RO-312 Nuclear Instrumentation Power Range Monitor -
13 OPhannOe316 13 52/03 Cover Page OP-RO-330 Nuclear Instrumentation-Wide Range Monitor 1
13 5/22/2013 Cover Page OP-RO-340 Nuclear Instrumentation Adjustment 103 5/22/2013 Cover Page Reactor Power Calculator Flow Potentiometer OP-RO-350 Adjustment 9/24/2013 Cover Page OP-RO-410 ]Primary Coolant System  
.l.1i 5/2/2013 Minor Editorial OP-RO-420 3Primary and Pool Water Analysis 161 9/24/2013 j Cover Page OP-RO-460 3Pool Coolant System - Two Pump Operation 314..3 9/24/2013 Minor Editorial OP-RO-461 JPool Coolant System - One Pump Operation 14T 9/24/2013 Minor Editorial OP-RO-465 3Pool Level Control - Skimmer System 18 3/29/2013 Minor Editorial OP-RO-480 3Secondary Coolant System 17 9/24/2013 Minor Editorial OP-RO-480 3Secondary Coolant System 18 12/9/2013 Minor Editorial OP-RO-510 Nitrogen System
: 37.
5/2/2013 3 Minor Editorial OP-RO-515 Emergency Air System J9 9/24/2013 f Minor Editorial OP-RO-516 Valve Operation Air System1 9 1 8/22/2013 1 Cover Page OP-RO-525 Chill Water System 17 6/25/2013 Minor Editorial OP-RO-530 Demineralized Water Supply System IT13 8/22/2013 Cover Page OP-RO-531 Primary and Pool Sample Station I1 9/24/2013 Cover Page OP-RO-555 Fire Protection System  
.10 1/31/2013 Minor Editorial OP-RO-555 Fire Protection System 311 11/19/2013 Minor Editorial OP-RO-710 Radiation Monitoring - Area Monitors 181 8/22/2013 Cover Page.
OP-RO_720 jRadiation Monitoring - Stack Monitor Operational 1
6 1
OPhROec20 11 6/25/2013 Minor Editorial OP-RO-730 Facility Exhaust System 14 3/29/2013 Minor Editorial OP-RO-741 Waste Tank System Operation 13 5/2/2013 Minor Editorial OP-RO-741 Waste Tank System Operation 14 12/19/2013 Minor Editorial POL-20 Special Nuclear Materials Manual 13 3/3/8/2013 Minor Editorial REP-RO-100 IReactor Emergency Procedures 3161 1/31/2013 Cover Page RM-RO-400 Waste Tank System Filter Replacement 373 3/29/2013 Minor Editorial Receipt, Inspection and Accounting of Unirradiated 5/1nEo
-RO-00 5/22/2013 Minor Editorial SM-RO-200 Manual Operation of Airlock doors 276 and 277 2
5/7/2013 Minor Editorial lControl Console And Instrument Panel -Securing SM-RO-301 3Power 11-2 10 9/24/2013 Cover Page


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.
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 thirteen (13) 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:
There were thirteen (13) 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                           R1ev. fRevision Datej               Not~es EP-RO-002     Emergency Responsibilities                                     4     5/7/2013             Minor Editorial EP-RO-006     Radiological Emergency                                         5     5/7/2013             Minor Editorial EP-RO-013     Facility Evacuation                                   .        5             15/7/23 Minor Editorial EP-1R-0 15     Emergency Notifications                                         9     4/4/2013             Minor Editorial.
Number~
EP-RO-0 15     Emergency Notifications                                       10     5/7/2013             Minor Editorial EP-RO-0 15     Emergency Notifications                                       I1    10/29/2013             Minor Editorial EP-RO-0 18     Emergency Radiation Exposure                                   5     5/7/2013             Minor Editorial FM-104     JEmergency Call List                                           22     4/4/2013             Minor Editorial FM-i 10     Fire Flowchart                                                 4     5/7/2013             Minor Editorial OA-09       Combined Emergency Flowcharts                                   5     7/8/2013       1 Minor Editorial OA-10     jFire Extinguisher Locations and Types                   '      9   12/12/2013             Minor Editorial OA-20     jEmergency Equipment                                       .15       7/8/2013             Minor Editorial OA-20     JEmergency Equipment                                           16   12/12/2013             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.
Name R1ev. fRevision Datej Not~es EP-RO-002 Emergency Responsibilities 4
5/7/2013 Minor Editorial EP-RO-006 Radiological Emergency 5
5/7/2013 Minor Editorial EP-RO-013 Facility Evacuation 5
15/7/23 Minor Editorial EP-1R-0 15 Emergency Notifications 9
4/4/2013 Minor Editorial.
EP-RO-0 15 Emergency Notifications 10 5/7/2013 Minor Editorial EP-RO-0 15 Emergency Notifications I 1 10/29/2013 Minor Editorial EP-RO-0 18 Emergency Radiation Exposure 5
5/7/2013 Minor Editorial FM-104 JEmergency Call List 22 4/4/2013 Minor Editorial FM-i 10 Fire Flowchart 4
5/7/2013 Minor Editorial OA-09 Combined Emergency Flowcharts 5
7/8/2013 1 Minor Editorial OA-10 jFire Extinguisher Locations and Types 9
12/12/2013 Minor Editorial OA-20 jEmergency Equipment  
.15 7/8/2013 Minor Editorial OA-20 JEmergency Equipment 16 12/12/2013 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 eighty-four (84) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. Additionally, three (3) new forms and four (4) new procedures were issued.
There were eighty-four (84) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. Additionally, three (3) new forms and four (4) new procedures were issued.
The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures and forms:
The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures and forms:
Naniber     JName                                                       Rev. ~Revision Date         ~     Notes tMURR Initial Radiation Worker Training AP-HP- 117     ]Mrral                                                       11   3/22/2013             Minor Editorial
Naniber JName Rev. ~Revision Date  
                    ~Program                                                         I_________________
~
AP-HP- 119     IHigh Radiation Area Access                                   5     1/3/2013             Minor Editorial AP-HP-123     IVisitor Dosimetry - Reception Desk   .....                19     4/29/2013             .r Minor   Editorial
Notes tMURR Initial Radiation Worker Training AP-HP-117  
* AP*-'HP- 123   .V~isitor Do..*?sim*etry 'rReception Desk ...
]Mrral 11 3/22/2013 Minor Editorial
                                            -                    . ........ ..!0...... 8/5/(2.013 .......... Mino&deg;r.E~ditori~al .
~Program I_________________
AP-HP-129       Hot Cell, HC-01 Control                                     9   ] 2/7/2013             Minor Editorial AP-SH-002     AIn-House Radioactive
AP-HP-119 IHigh Radiation Area Access 5
                    ]Isrcin           .2         Shipping Request Form                  6/18/2013             Minor Editorial AP-SH-002       In-House Radioactive Shipping Request Form                   3     9/17/2013             Minor Editorial Instructions 11-3
1/3/2013 Minor Editorial
.r AP-HP-123 IVisitor Dosimetry - Reception Desk 19 4/29/2013 Minor Editorial
* AP*-'HP-123  
.V~isitor Do..*?sim*etry  
-'rReception Desk...  
..........!0...... 8/5/(2.013.......... Mino&deg;r.E~ditori~al AP-HP-129 Hot Cell, HC-01 Control 9  
]
2/7/2013 Minor Editorial AIn-House Radioactive Shipping Request Form AP-SH-002  
]Isrcin  
.2 6/18/2013 Minor Editorial AP-SH-002 In-House Radioactive Shipping Request Form Instructions 11-3 3
9/17/2013 Minor Editorial


~'Number       jName                                             Rev. Rievision Date]                   Notes SAP-SH-002     jIn-House Radioactive Shipping Request Form           4       12/19/2013         Minor Editorial
~'Number jName Rev. Rievision Date]
_Instructions                                     ...................
Notes SAP-SH-002 jIn-House Radioactive Shipping Request Form 4
DOT 6M Packaging of Type B Non-Waste                 1     T     10/9/2013       Minor Editorial BPB-S-005_     ~Radioactive   Material Receiptlnspection Of Type B Byproduct Material       4           4/29/2013       Minor BPB-SH-020       Shipping Containers BPB-SH-023     jType B Equipment Calibration                   121             12/20/2013 .     Minor Editorial TypeB(U) F-458 Series Packaging of Type B BPB-SH-024       Non-Waste Radioactive Material                                                             Editorial BPB-SH-021 Type B(U) ZA/NNRI005 (Beatrice) Packaging of 2           10/9/20 13 I  Minor Editorial BP-SH-025_     gType B Non-Waste     Radioactive Material BPB-SH-026       Type B(U) F-327 Series Packaging of Type B                       1 Non-Waste Radioactive Material                                   1 h nC.BPB-SH-027 Survey   and Decontamination of Returned ShipingConainrs7                                       1         10/9/2013       Minor Editorial i BTYPE B(U) USA/0656/B(U)-96 (Ganuk)                   0 BPB-SH-029                       aiatv Packaging of Radioactive    aeilf Material                  0Pcaigo11/5/2013             New Procedure     j BP-SH-016   ~Packaging and Shipment of Radioactive Material           3           10/9/2013       Minor Editorial Using USA DOT 7 A Model H or I Package New Procedure BP-SH-017       Packaging and Shipment of Radioactive Material Using Tracerco LS-6 Reusable Type A Package 0
12/19/2013 Minor Editorial
I    7/18/2013 BP-SH-052       Radioactive Material Douetto               Shipment Package n aeig10                                       2/6/2013         Minor Editorial
_Instructions DOT 6M Packaging of Type B Non-Waste 1 T 10/9/2013 Minor Editorial BPB-S-005_ ~Radioactive Material Receiptlnspection Of Type B Byproduct Material 4
  *_      _    I~Documentation and Labeling_                                               ___
4/29/2013 Minor BPB-SH-020 Shipping Containers BPB-SH-023 jType B Equipment Calibration 121 12/20/2013.
BRadioactive Material Shipment Package BP-SH-052 IouettonadLbln                                             11           7/26/2013       Minor Editorial
Minor Editorial TypeB(U) F-458 Series Packaging of Type B BPB-SH-024 Non-Waste Radioactive Material Editorial Type B(U) ZA/NNRI005 (Beatrice) Packaging of I
  .I~~   ~Documentation and Labeling                                               _                        _
BPB-SH-021 2
Type B Shipment of spent Fuel Using the BEA           2         4/16/2013         Minor Editorial FB-SH- 110     ]Research Reactor Package                           ..........
10/9/20 13 Minor Editorial BP-SH-025_
                /Type B Shipment of spent Fuel Using the BEA FB-SH- 1I0     R a       Reactor Package                           3         5/13/2013           Full Review BP-SH-099     jPackaging of Radioactive Material Using MURR         3           1/4/2012       Minor Editorial Model 1500 FM-17       Radiation Work Permit                               i11         11/19/2013       Minor Editorial FM-27       In-House Radioactive Shipping Request Form           12         9/17/2013         Minor Editorial Control Checksheet for Documentation and             1i Labeling of Radioactive Material Shipment           11           __2/6/2013       MinorEditorial Control Checksheet for Documentation and       1121             7/26/2013         Minor FM-52__ Labeling of Radioactive Material Shipment           .....                                      Editorial FM-62       Radiation Instrument Certificate of Calibration 171             7/11/2013           Cover Page Control Checksheet for Reusable Type A FM-69       Radioactive Materials Shipment (5 to 30 Gallon       8         10/11/2013       Minor Editorial Drums)
gType B Non-Waste Radioactive Material BPB-SH-026 Type B(U) F-327 Series Packaging of Type B 1
FControl Checksheet for Tracerco LS-6 Reusable                   78       1   1         eF FM-70   _ IType A Package Radioactive Materials Shipment                   7/8/01               NewForm FM-74      FControl   Checksheet for Type Bnt14 RaiatvMaeilShp                  USA DOT 6M                   10i10/9/2013       Minor Editorial Radioactive Materials Shipment111_____                                           ________
Non-Waste Radioactive Material 1
FM-91     jDeclaration of Pregnancy                             51 ] 8/5/2013                   Cover Page FM-94     lExclusive Use Shipment Controls                     41           2/6/2013         Minor Editorial FM-94       Exclusive Use Shipment Controls                 j     5         4/29/2013     J   Minor Editorial FM-94     jExclusive Use Shipment Controls                       6         7/26/2013     1   Minor Editorial 11-4
h nC.BPB-SH-027 Survey and Decontamination of Returned 1
i ShipingConainrs7 1
10/9/2013 Minor Editorial BTYPE B(U) USA/0656/B(U)-96 (Ganuk) 0 BPB-SH-029 0Pcaigo aiatv aeilf 11/5/2013 New Procedure j Packaging of Radioactive Material BP-SH-016 ~Packaging and Shipment of Radioactive Material 3
10/9/2013 Minor Editorial Using USA DOT 7 A Model H or I Package BP-SH-017 Packaging and Shipment of Radioactive Material 0
7/18/2013 New Procedure Using Tracerco LS-6 Reusable Type A Package I
Radioactive Material Shipment Package BP-SH-052 Douetto n
aeig10 2/6/2013 Minor Editorial I~Documentation and Labeling_
BRadioactive Material Shipment Package BP-SH-052 IouettonadLbln 11 7/26/2013 Minor Editorial
.I~~  
~Documentation and Labeling Type B Shipment of spent Fuel Using the BEA 2
4/16/2013 Minor Editorial FB-SH-110  
]Research Reactor Package  
/Type B Shipment of spent Fuel Using the BEA FB-SH-1I0 R
a Reactor Package 3
5/13/2013 Full Review BP-SH-099 jPackaging of Radioactive Material Using MURR 3
1/4/2012 Minor Editorial Model 1500 FM-17 Radiation Work Permit i11 11/19/2013 Minor Editorial FM-27 In-House Radioactive Shipping Request Form 12 9/17/2013 Minor Editorial Control Checksheet for Documentation and 1i Labeling of Radioactive Material Shipment 11
__2/6/2013 MinorEditorial Control Checksheet for Documentation and 1121 7/26/2013 Minor FM-52__ Labeling of Radioactive Material Shipment Editorial FM-62 Radiation Instrument Certificate of Calibration 171 7/11/2013 Cover Page Control Checksheet for Reusable Type A FM-69 Radioactive Materials Shipment (5 to 30 Gallon 8
10/11/2013 Minor Editorial Drums)
FControl Checksheet for Tracerco LS-6 Reusable 78 1 1 eF FM-70
_ IType A Package Radioactive Materials Shipment 7/8/01 NewForm FControl Checksheet for Type B USA DOT 6M 10i FM-74 RaiatvMaeilShp nt14 10/9/2013 Minor Editorial Radioactive Materials Shipment111_____
FM-91 jDeclaration of Pregnancy 51 ]
8/5/2013 Cover Page FM-94 lExclusive Use Shipment Controls 41 2/6/2013 Minor Editorial FM-94 Exclusive Use Shipment Controls j 5 4/29/2013 J Minor Editorial FM-94 jExclusive Use Shipment Controls 11-4 6
7/26/2013 1 Minor Editorial


Number                                   Name                             JRev eis~ion'fDate       N FM-99         ModlControl checkshees for USA DOT 7A MURR                 7112/19/201!         MinorEditorial Model 1500 Series....
Number Name JRev eis~ion'fDate N
FM- 129       Control Checksheet for Receipt and Inspection of           3     4/16/2013     Minor Editorial Type B Byproduct Material Shipping Containers_
FM-99 ModlControl checkshees for USA DOT 7A MURR 7112/19/201!
FM-135  Control (Beatrice)  Checksheet forMaterials Radioactive  Type B(U)Shipment ZA/NNR 1005 I             /821         io   dtra FM-137       Type B Qualified Shipper List                               1     4/29/2013     Minor Editorial FM- 149
MinorEditorial Model 1500 Series....
____  151 Personnel Radiation Dose Estimate FControl Checksheet for USA DOT 7A Type A 55-Gallon Radioactive Material Package 0o      2/7/2013 812/19/2013 T  New Form Minor i
FM-129 Control Checksheet for Receipt and Inspection of 3
FM- 154       Control Checksheet for USA DOT 20WC-1                       3     4/29/201       Cover Page Overpack Rod Replacement                                                 013 FM-155       *QualityAssurance Control Checksheet Exterior4/                           013     CovePag Painting of USA DOT WC-I, Type B Overpack               ...
4/16/2013 Minor Editorial Type B Byproduct Material Shipping Containers_
Required Documentation for Non-MURR Owned '
Control Checksheet for Type B(U) ZA/NNR 1005 FM-135 (Beatrice) Radioactive Materials Shipment I  
FM-156         Type B Shipping Containers                                       7/26/2013     Minor Editorial RT ive Mate         Ship       ment6/18/201 Control Checksheet for Type B(U) F-458 Series               2                   M FM- 15.7                                                                 2. 6/18/2013     MinorEditorial Control Checksheet for Type B(U) F-327 Series FM- 160       Radioactive Materials Shipment..                            1     10/9/2013     Minor Editorial Control Checksheet for Type B(U)                      I FM- 163      USA/9337/B(U)-96 (LS) Packaging of                          1      3/22/2013    Minor Editorial Radioactive Material                                          ..
/821 io dtra FM-137 Type B Qualified Shipper List 1
4/29/2013 Minor Editorial FM-149 Personnel Radiation Dose Estimate 0o 2/7/2013 New Form FControl Checksheet for USA DOT 7A Type A 55-T i
____ 151 Gallon Radioactive Material Package 812/19/2013 Minor FM-154 Control Checksheet for USA DOT 20WC-1 3
4/29/201 Cover Page Overpack Rod Replacement 013 FM-155  
*Quality Assurance Control Checksheet Exterior4/
013 CovePag Painting of USA DOT WC-I, Type B Overpack Required Documentation for Non-MURR Owned FM-156 Type B Shipping Containers 7/26/2013 Minor Editorial RT ive Mate Ship ment6/18/201 Control Checksheet for Type B(U) F-458 Series 2
M FM-15.7
: 2.
6/18/2013 MinorEditorial Control Checksheet for Type B(U) F-327 Series FM-160 1
10/9/2013 Minor Editorial Radioactive Materials Shipment..
Control Checksheet for Type B(U)
Control Checksheet for Type B(U)
FM-167       USA/0656/B(U)-96 (Ganuk) Radioactive                       0     11/5/2013       New Form Materials Shipping                                     .....
I FM-163 USA/9337/B(U)-96 (LS) Packaging of 1
HC-PSO-002       Hot Cell Preparation of Radioactive Material for                   9/11/2013     Minor Editorial Shipment HC-PSO-005       Hot Cell Loading of Host Cans                           111.     9/11/2013   j Minor Editorial IC-HP-300       Calibration - Radiation Survey Instruments                 77     7/11/2013     Cover Page IC-HP-305       Calibration - Electrostatic Discharge Dosimeter           8         8/2/2013     Cover Page Calibration - Eberline Ping IA Stack Monitor-                     4/9/2013     M IC-HP-3 11     Iodine    Channel Ioin Channel013                                                                 Minor Editorial IC-H-347  Calibration Beta Swipe -Counter Protean Model WPC 9550 Alpha-                   7     0e
3/22/2013 Minor Editorial Radioactive Material Control Checksheet for Type B(U)
*IC-HIP-347       BeaSieCutr9                                                       7/11/2013     Cover Page Calibration - Canberra S5XLB-G & Tennelec Series 4 with Gamma, & Tennelec Series 3                                                 Page
FM-167 USA/0656/B(U)-96 (Ganuk) Radioactive 0
                                                                                                            ..
11/5/2013 New Form Materials Shipping HC-PSO-002 Hot Cell Preparation of Radioactive Material for 9/11/2013 Minor Editorial Shipment HC-PSO-005 Hot Cell Loading of Host Cans 111.
                                                                                                              ...
9/11/2013 j
ICalibration - Lab Impex Stack Monitor-Particulate IC-HP-349       I~anl.4 Channel                                                            7/11/20 13     Cover Page IC-HP-350
Minor Editorial IC-HP-300 Calibration - Radiation Survey Instruments 77 7/11/2013 Cover Page IC-HP-305 Calibration - Electrostatic Discharge Dosimeter 8
                  ]Calibration - Lab Impex Stack Monitor-Iodine
8/2/2013 Cover Page Calibration - Eberline Ping IA Stack Monitor-4/9/2013 M
[Channel I  2       8/2/2013     Minor Editorial
IC-HP-3 11 Ioin Channel013 Minor Editorial Iodine Channel Calibration - Protean Model WPC 9550 Alpha-7 0e
  *IC-HP-35 1     Calibration - Lab Impex Stack Monitor-Gas                 2       7/11/2013     Cover Page Channel IC-HP-352     ~Calibration - Lab Impex Stack Monitor-Flow IC-ibr-35o                                                           3       7/11/2013     Cover Page IRR-PSO-1 12       Preparing Shipping Paperwork                           17         8/13/2013     Minor Editorial OP-HP-200         Air Sampling- Containment Building Tritium                 6     1 8/2/2013   f Cover Page OP-HP-220         Tritium Bioassay                                           9       8/5/2013   j Minor Editorial Il-5
*IC-HIP-347 BeaSieCutr9 7/11/2013 Cover Page IC-H-347 Beta Swipe Counter Calibration - Canberra S5XLB-G & Tennelec Series 4 with Gamma, & Tennelec Series 3 Page ICalibration - Lab Impex Stack Monitor-Particulate IC-HP-349 I~anl.4 7/11/20 13 Cover Page Channel
]Calibration - Lab Impex Stack Monitor-Iodine I
IC-HP-350
[Channel 2
8/2/2013 Minor Editorial
* IC-HP-35 1 Calibration - Lab Impex Stack Monitor-Gas 2
7/11/2013 Cover Page Channel IC-HP-352 ~Calibration - Lab Impex Stack Monitor-Flow IC-ibr-35o 3
7/11/2013 Cover Page IRR-PSO-1 12 Preparing Shipping Paperwork 17 8/13/2013 Minor Editorial OP-HP-200 Air Sampling-Containment Building Tritium 6 1 8/2/2013 f
Cover Page OP-HP-220 Tritium Bioassay 9
8/5/2013 j
Minor Editorial Il-5


Number::Name                                                                   Rev. R*ovision Date           Notes__:::___:__:_
Number ::Name Rev. R*ovision Date Notes__:::___:__:_
OP-HP-222               Air Sampling - Containment Building Ar-41                 6         2/7/2013       Minor Editorial OP-HP-348               Operation - Protean WPC-9550 Swipe Counter                 4     7/11/2013       Cover Page OP-HP-356 Operation - Lab Impex Stack Monitor Changepand Source4checks
OP-HP-222 Air Sampling - Containment Building Ar-41 6
                                                                    - Filter 8/5/2013 I     Cover Page QAB-SH-002               jProcurement of Type B Packages                               2"     2/6/2013       Cover Page QAB-SH-003               Material Control for Type B Shipping Program                 3     5/14/2013       Minor Editorial QAB-SH-004               Type B Program Vendor Qualification                         3   1 5/14/2013       Cover Page QAB-SH-005               Type B QA Personnel Training                                 3   . 2/6/2013       Minor Editorial QAB-SH-006 , Type.B Shipping Program ,Quality Audits                                   1       2/6/2013   ... Minor Editorial...
2/7/2013 Minor Editorial OP-HP-348 Operation - Protean WPC-9550 Swipe Counter 4
QAB-SH-009               jPre-Shipment leak Testing of the Ganuk Shipping Container                                                   0       11/5/2013     New Procedure Stack Monitor Preventive Maintenance - Lab RM-HP- 102               m Impex                                                              7/11/2013       Cover Page RP-HP-100               Contamination Monitoring - In Facility                 16.           4/3/2013       Minor Editorial RP-HP-105               Transfer of Radioactive Material - In Facility .             71     4/3/2013       Minor Editorial RP-HP-120             IPersonnel Radioactive Contamination                           7     4/29/20 13     Minor Editorial RP-HP-120               Personnel Radioactive Contamination                         8       8/5/2013       Minor Editorial RP-HP- 125               Radiation Monitoring - Performing and RP-HP....           .... Documenting.a.Survey                                         0       8/5/20.13     New Procedure RP-HP-135               Room 114 Entry     -. Self Monitored                       6       5/22/2013       Minor Editorial RP-HP-137               Handling Radioactive     Material in the Reactor   Pool I1           8/5/2013       Cover Page jPost-Irradiation Processing:   Exported FloodedMioEdtra SI-PSO-008                       Cans                                               6Silicon 6M12/11/201                   Edi SV-HP- I 10             Environmental Sampling                                       5     6/21/2013       Minor Editorial SV-HP- 121             IBuilding Exhaust Stack Effluent - Ar-41
7/11/2013 Cover Page Operation - Lab Impex Stack Monitor - Filter OP-HP-356 Changepand Source4checks 8/5/2013 I Cover Page QAB-SH-002 jProcurement of Type B Packages 2"
  ..................... M on itoring 5        8/2/2013
2/6/2013 Cover Page QAB-SH-003 Material Control for Type B Shipping Program 3
                                                                                                ......
5/14/2013 Minor Editorial QAB-SH-004 Type B Program Vendor Qualification 3
Minor Editorial TPZ-PSO-002 lrradiation of Gemstone Irradiation Containers                           6       12/11/2013     Minor Editorial TPZ-PSO-003 TSP-02                Loading Gemstone ITransportation        Irradiation Security  Plan Containers                 55      12/11/2013 12/19/2013     Minor Minor Editorial Editorial WM-SH-100               Radioactive Waste - Preparation and Storage                 7       7/26/2013       Cover Page WM-SH-105                 Radioactive Waste Processing                               8       2/6/2013 I   Minor Editorial WM-SH-105                 Radioactive Waste Processing ..                             9       7/26/2013       Cover Page Exclusive Use Shipment of LSA or SCO                       11lT 6/18/2013           Minor Editorial WRadioactive Waste                                     ..........                                  _
1 5/14/2013 Cover Page QAB-SH-005 Type B QA Personnel Training 3
WM-SH-300               lExclusive Use Shipment of LSA or SCO                       12       11/20/2013       Cover Page Radioactive Waste I1-6
2/6/2013 Minor Editorial QAB-SH-006, Type.B Shipping Program,Quality Audits 1
2/6/2013  
... Minor Editorial...
QAB-SH-009 jPre-Shipment leak Testing of the Ganuk Shipping Container 0
11/5/2013 New Procedure Stack Monitor Preventive Maintenance - Lab RM-HP-102 m
7/11/2013 Cover Page Impex RP-HP-100 Contamination Monitoring - In Facility
: 16.
4/3/2013 Minor Editorial RP-HP-105 Transfer of Radioactive Material - In Facility.
71 4/3/2013 Minor Editorial RP-HP-120 IPersonnel Radioactive Contamination 7
4/29/20 13 Minor Editorial RP-HP-120 Personnel Radioactive Contamination 8
8/5/2013 Minor Editorial RP-HP-125 Radiation Monitoring - Performing and RP-HP....  
.... Documenting.a.Survey 0
8/5/20.13 New Procedure RP-HP-135 Room 114 Entry -. Self Monitored 6
5/22/2013 Minor Editorial RP-HP-137 Handling Radioactive Material in the Reactor Pool I1 8/5/2013 Cover Page jPost-Irradiation Processing: Exported FloodedMioEdtra SI-PSO-008 6Silicon Cans 6M12/11/201 Edi SV-HP-I 10 Environmental Sampling 5
6/21/2013 Minor Editorial SV-HP-121 I Building Exhaust Stack Effluent - Ar-41 5
8/2/2013 Minor Editorial
..................... M on itoring TPZ-PSO-002 lrradiation of Gemstone Irradiation Containers 6
12/11/2013 Minor Editorial TPZ-PSO-003 Loading Gemstone Irradiation Containers 5
12/11/2013 Minor Editorial TSP-02 ITransportation Security Plan 5
12/19/2013 Minor Editorial WM-SH-100 Radioactive Waste - Preparation and Storage 7
7/26/2013 Cover Page WM-SH-105 Radioactive Waste Processing 8
2/6/2013 I Minor Editorial WM-SH-105 Radioactive Waste Processing..
9 7/26/2013 Cover Page Exclusive Use Shipment of LSA or SCO 11lT 6/18/2013 Minor Editorial WRadioactive Waste WM-SH-300 lExclusive Use Shipment of LSA or SCO Radioactive Waste 12 11/20/2013 Cover Page I1-6


SECTION III REVISIONS TO THE HAZARDS  
SECTION III REVISIONS TO THE HAZARDS  
Line 214: Line 371:
REPORT (ORIGINAL JULY 1, 1965)
REPORT (ORIGINAL JULY 1, 1965)
Original HSR, pages 3-11, Figure 3.2, Grade Level Plan (as revised by the 1972-1973, 1979-1980, 1990-1991, 1995, 1996 and 2012 Reactor Operations Annual Reports):
Original HSR, pages 3-11, Figure 3.2, Grade Level Plan (as revised by the 1972-1973, 1979-1980, 1990-1991, 1995, 1996 and 2012 Reactor Operations Annual Reports):
Replace with:   Updated Figure 3.2, Grade Level Plan (MURR Dwg No. 1145, Sheet 2 of 5)
Replace with:
Updated Figure 3.2, Grade Level Plan (MURR Dwg No. 1145, Sheet 2 of 5)
Original HSR, pages 7-19, Section 7.2.7 (as revised by the 1974-75, 1989-1990 and 1995 Reactor Operations Annual Reports):
Original HSR, pages 7-19, Section 7.2.7 (as revised by the 1974-75, 1989-1990 and 1995 Reactor Operations Annual Reports):
Delete:         "...beamport ventilation air, air which is drawn from the surface of the pool and exhaust from the film irradiator shield box."
Delete:  
Replace with:   "...beamport ventilation air and air which is drawn from the surface of the pool."
"...beamport ventilation air, air which is drawn from the surface of the pool and exhaust from the film irradiator shield box."
Replace with:  
"...beamport ventilation air and air which is drawn from the surface of the pool."
Original HSR, pages 7-20, Section 7.2.9, Table 7.1 (as revised by the 1974-75, 1995, 2001, 2002, 2007 and 2008 Reactor Operations Annual Reports):
Original HSR, pages 7-20, Section 7.2.9, Table 7.1 (as revised by the 1974-75, 1995, 2001, 2002, 2007 and 2008 Reactor Operations Annual Reports):
Delete:         The following from Table 7.1 under Staff Stations:
Delete:
                          "Room 288                   Health Physics Office" Add:             The following to Table 7.1 under Staff Stations:
The following from Table 7.1 under Staff Stations:
                          "Room 271B                 Health Physics Office" Original HSR, pages 7-21, Section 7.2.9, Table 7.2 (as revised by the 1995, 2001, 2007, 2009. 2011 and 2012 Reactor Operations Annual Reports):
"Room 288 Health Physics Office" Add:
Add:             The following after "Room 299":
The following to Table 7.1 under Staff Stations:
                          "Corridor C299D Room 299N Room 299P Room 299Q" Original HSR, pages 9-7 through 9-9, Table 9.2 (as revised by the 1981-82, 1985-86, 1995, 2000, 2001, 2002. 2006 and 2007 Reactor Operations Annual Reports):
"Room 271B Health Physics Office" Original HSR, pages 7-21, Section 7.2.9, Table 7.2 (as revised by the 1995, 2001, 2007, 2009. 2011 and 2012 Reactor Operations Annual Reports):
Add:             "137       Isolated Power Supply (EP 91 IC) - TE-980 A/B" III-I
Add:
The following after "Room 299":
"Corridor C299D Room 299N Room 299P Room 299Q" Original HSR, pages 9-7 through 9-9, Table 9.2 (as revised by the 1981-82, 1985-86, 1995, 2000, 2001, 2002. 2006 and 2007 Reactor Operations Annual Reports):
Add:  
"137 Isolated Power Supply (EP 91 IC) - TE-980 A/B" III-I


Add:             "138       Rod Run-In System Monitoring Circuit" Add:            "139       T-300 & T-301 Water Level Display" Original HSR, Figure 9.3, Instrument Panel Layout (as revised by 1995, 2001, 2004 and 2006 Reactor Operations Annual Reports):
Add:
Replace with:   Updated Figure 9.3, Instrument Cabinet (MURR Dwg No. 74, Sheet 12 of 12)
Add:
Original HSRI   Figure 9.5, Rod Run-In System (as revised by 1995 and 2001 Reactor Operations Annual Reports):
"138 Rod Run-In System Monitoring Circuit" "139 T-300 & T-301 Water Level Display" Original HSR, Figure 9.3, Instrument Panel Layout (as revised by 1995, 2001, 2004 and 2006 Reactor Operations Annual Reports):
Replace with:   Updated Figure 9.5, Rod Run-In System (MURR Dwg #140, Sheet 1 of 1, dated 9/10/13)
Replace with:
Updated Figure 9.3, Instrument Cabinet (MURR Dwg No. 74, Sheet 12 of 12)
Original HSRI Figure 9.5, Rod Run-In System (as revised by 1995 and 2001 Reactor Operations Annual Reports):
Replace with:
Updated Figure 9.5, Rod Run-In System (MURR Dwg #140, Sheet 1 of 1, dated 9/10/13)
ADDENDUM 3 - HAZARDS  
ADDENDUM 3 - HAZARDS  


Line 235: Line 403:
REPORT (AUGUST 1972)
REPORT (AUGUST 1972)
HSR, Addendum 3, page 15, Figure 2.2.b, Secondary Coolant System (as added by the 2012 Reactor Operations Annual Report):
HSR, Addendum 3, page 15, Figure 2.2.b, Secondary Coolant System (as added by the 2012 Reactor Operations Annual Report):
Replace with:   Updated Figure 2.2.b, Secondary Cooling System (MURR Dwg No. 502, Sheet 2 of 3, dated 4/24/13)
Replace with:
Updated Figure 2.2.b, Secondary Cooling System (MURR Dwg No. 502, Sheet 2 of 3, dated 4/24/13)
HSR, Addendum 3, page 18, Figure 2.3.a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):
HSR, Addendum 3, page 18, Figure 2.3.a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):
Replace with:     Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of 5, dated 8/20/13)
Replace with:
Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of 5, dated 8/20/13)
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, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):
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, 2007, 2009, 2010, 2011 and 2012 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 10/4/13)
Replace with:
Updated Figure 2.3.b, Electrical Distribution North Office Addition (MURR Dwg No. 522, Sheet 2 of 5, dated 10/4/13)
HSR, Addendum 3, page 23c, Figure 2.3.c, Electrical Distribution (as added by the 2004 and revised by the 2005, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):
HSR, Addendum 3, page 23c, Figure 2.3.c, Electrical Distribution (as added by the 2004 and revised by the 2005, 2007, 2009, 2010, 2011 and 2012 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 8/27/13)
Replace with:
Updated Figure 2.3.c, Electrical Distribution Reactor/Laboratory Panels (MURR Dwg No. 522, Sheet 3 of 5, dated 8/27/13)
HSR, Addendum 3, page 23d, Figure 2.3.d, Electrical Distribution (as added by the 2007 and revised by the 2008, 2009, 2010, 201 land 2012 Reactor Operations Annual Reports):
HSR, Addendum 3, page 23d, Figure 2.3.d, Electrical Distribution (as added by the 2007 and revised by the 2008, 2009, 2010, 201 land 2012 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, dated 8/27/13) 111-2
Replace with:
Updated Figure 2.3.d, Electrical Distribution Reactor/Laboratory Panels-2 (MURR Dwg No. 522, Sheet 4 of 5, dated 8/27/13) 111-2


HSR, Addendum 3, page 23e, Figure 2.3.e, Electrical Distribution (as added by the 2007 and revised by the 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):
HSR, Addendum 3, page 23e, Figure 2.3.e, Electrical Distribution (as added by the 2007 and revised by the 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):
Replace with:     Updated Figure 2.3.e, Electrical Distribution North Office Addition Panels (MURR Dwg No. 522, Sheet 5 of 5, dated 10/7/13)
Replace with:
Updated Figure 2.3.e, Electrical Distribution North Office Addition Panels (MURR Dwg No. 522, Sheet 5 of 5, dated 10/7/13)
ADDENDUM 4 - HAZARDS  
ADDENDUM 4 - HAZARDS  


Line 252: Line 426:
REPORT (OCTOBER 1973)
REPORT (OCTOBER 1973)
HSR, Addendum 4, page A-22, Figure A.4.a, Reactor Control System - 10 MW (as revised by 1995, 2001, 2004, 2006 and 2007 Reactor Operations Annual Reports):
HSR, Addendum 4, page A-22, Figure A.4.a, Reactor Control System - 10 MW (as revised by 1995, 2001, 2004, 2006 and 2007 Reactor Operations Annual Reports):
Replace with:     Updated Figure A.4.a, Reactor Control System (MURR Dwg No. 42, Sheet 1 of 2, dated 8/22/13)
Replace with:
Updated Figure A.4.a, Reactor Control System (MURR Dwg No. 42, Sheet 1 of 2, dated 8/22/13)
HSR, Addendum 4, page A-25, Figure A.6, 10 MW Process Instrumentation Control & Interlock (as revised by the 1995, 2001, 2002, 2003, 2005 and 2006 Reactor Operations Annual Reports):
HSR, Addendum 4, page A-25, Figure A.6, 10 MW Process Instrumentation Control & Interlock (as revised by the 1995, 2001, 2002, 2003, 2005 and 2006 Reactor Operations Annual Reports):
Replace with:     Updated Figure A.6, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 2 of 4, dated 8/22/13)
Replace with:
Updated Figure A.6, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 2 of 4, dated 8/22/13)
HSR, Addendum 4, page A-26, Figure A.7, Annunciator Control 10 MW (as revised by the 1995, 2001, 2002, 2005, 2006, 2007, 2008 and 2012 Reactor Operations Annual Reports):
HSR, Addendum 4, page A-26, Figure A.7, Annunciator Control 10 MW (as revised by the 1995, 2001, 2002, 2005, 2006, 2007, 2008 and 2012 Reactor Operations Annual Reports):
Replace with:     Updated Figure A.l, Annunciator Control 10 MW (MURR Dwg No. 138, dated 9/11/13)
Replace with:
HSR, Addendum 4, page A-29, Figure A.I1,           Schematic Diagram of Laboratory and Containment Building Ventilation Systems (as revised by the 1995, 2002, 2005, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):
Updated Figure A.l, Annunciator Control 10 MW (MURR Dwg No. 138, dated 9/11/13)
Replace with:     Updated Figure A. 11, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (MURR Dwg No. 1125, Sheet 1 of 4, dated 8/19/13)
HSR, Addendum 4, page A-29, Figure A.I1, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (as revised by the 1995, 2002, 2005, 2009, 2010, 2011 and 2012 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 8/19/13)
ADDENDUM 5 - HAZARDS  
ADDENDUM 5 - HAZARDS  


Line 264: Line 442:
REPORT (JANUARY 1974)
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, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):
HSR, Addendum 5, page 15, Figure 2.1, Electrical Distribution (as revised by the 1989-90, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):
Replace with:     Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet I of 5, dated 8/20/13) 111-3
Replace with:
Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet I of 5, dated 8/20/13) 111-3


As a result of the issuance of Amendment No. 36 to Amended Facility License No. R-103 on July 8, 2013, the following changes to the MURR Hazards Summary Report and its addenda were performed:
As a result of the issuance of Amendment No. 36 to Amended Facility License No. R-103 on July 8, 2013, the following changes to the MURR Hazards Summary Report and its addenda were performed:
Line 271: Line 450:
==SUMMARY==
==SUMMARY==
REPORT (AUGUST 1972)
REPORT (AUGUST 1972)
HSR, Addendum 3, Section 3.3, Evaluation of Peaking Factors in the MURR 6.2 Kg Core Delete:           Entire section.
HSR, Addendum 3, Section 3.3, Evaluation of Peaking Factors in the MURR 6.2 Kg Core Delete:
Replace with:     Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 11).
Entire section.
Replace with:
Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 11).
ADDENDUM 4 - HAZARDS  
ADDENDUM 4 - HAZARDS  


==SUMMARY==
==SUMMARY==
REPORT (OCTOBER 1973)
REPORT (OCTOBER 1973)
HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR Delete:           Entire section.
HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR Delete:
Replace with:     Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 11).
Entire section.
Replace with:
Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 11).
HSR, Addendum 4, Appendix H, Bases for Limiting Safety System Settings for Modes I and I!
HSR, Addendum 4, Appendix H, Bases for Limiting Safety System Settings for Modes I and I!
Operation Delete:           Entire section.
Operation Delete:
Replace with:     Revised HSR, Addendum 4, Appendix H, Bases for Limiting Safety System Settings for Modes I and II Operation, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 12).
Entire section.
Replace with:
Revised HSR, Addendum 4, Appendix H, Bases for Limiting Safety System Settings for Modes I and II Operation, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 12).
ADDENDUM 5 - HAZARDS  
ADDENDUM 5 - HAZARDS  


==SUMMARY==
==SUMMARY==
REPORT (JANUARY 1974)
REPORT (JANUARY 1974)
HSR, Addendum 5, Section 6, Addendum to the Safety Limit Analysis for the MURR Delete:           Entire section.
HSR, Addendum 5, Section 6, Addendum to the Safety Limit Analysis for the MURR Delete:
Replace with:     Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 1I).
Entire section.
Replace with:
Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 1I).
111-4
111-4


Line 294: Line 481:
Addition of Blow-Down Meter to the Data Acquisition Monitoring System This addendum to modification record 11-03, "Data Acquisition and Monitoring System for Secondary Coolant System" documents the installation of an additional component to the Data Acquisition and Monitoring System for the Secondary Coolant System. A secondary coolant blow-down transmitter and associated indication were installed to assist in monitoring the amount of secondary coolant that is required to be discharged to the sanitary sewer in order to maintain appropriate Secondary Coolant System chemistry control.
Addition of Blow-Down Meter to the Data Acquisition Monitoring System This addendum to modification record 11-03, "Data Acquisition and Monitoring System for Secondary Coolant System" documents the installation of an additional component to the Data Acquisition and Monitoring System for the Secondary Coolant System. A secondary coolant blow-down transmitter and associated indication were installed to assist in monitoring the amount of secondary coolant that is required to be discharged to the sanitary sewer in order to maintain appropriate Secondary Coolant System chemistry control.
Modification 12-01:
Modification 12-01:
Replace PT-944A/B with Rosemount Transmitters This modification record documents the replacement of two pressure transmitters, PT-944A and PT-944B, which sense reactor core outlet pressure in the Primary Coolant System. The previous pressure transmitters could not be directly replaced due to obsolescence of both the transmitters and repair parts. The replacement pressure transmitters meet or exceed the performance specifications of the previous transmitters.
Replace PT-944A/B with Rosemount Transmitters This modification record documents the replacement of two pressure transmitters, PT-944A and PT-944B, which sense reactor core outlet pressure in the Primary Coolant System. The previous pressure transmitters could not be directly replaced due to obsolescence of both the transmitters and repair parts.
The replacement pressure transmitters meet or exceed the performance specifications of the previous transmitters.
Modification 12-02:
Modification 12-02:
Control Blade Fabrication Alternative Using Laser Welding This modification record documents a fabrication alternative for construction of the control blades. An assembly method using laser welding on the edge channels required a change in the edge channel alloy. A more streamlined connection between the top mounting plate and the BORALC absorber plate was also documented.
Control Blade Fabrication Alternative Using Laser Welding This modification record documents a fabrication alternative for construction of the control blades. An assembly method using laser welding on the edge channels required a change in the edge channel alloy. A more streamlined connection between the top mounting plate and the BORALC absorber plate was also documented.
Line 306: Line 494:
Rod Run-In Electronic Circuit Jumper Panel This addendum to modification record 75-01, "Electronic Circuits Jumper Panel" documents the installation of a jumper panel dedicated to the rod run-in system. This jumper panel supports the use of the rod run-in system monitoring circuit installed under Modification Record 13-04.
Rod Run-In Electronic Circuit Jumper Panel This addendum to modification record 75-01, "Electronic Circuits Jumper Panel" documents the installation of a jumper panel dedicated to the rod run-in system. This jumper panel supports the use of the rod run-in system monitoring circuit installed under Modification Record 13-04.
Modification 13-04:
Modification 13-04:
Rod Run-In Monitoring System This modification record documents the implementation of a passive monitoring circuit on the rod run-in system to improve troubleshooting capabilities for rod run-in signals that are too short in duration to detect with the annunciator system. The monitoring circuit works in conjunction with a new jumper panel dedicated to the rod run-in system, and provides additional unused monitoring capacity for future troubleshooting expansion. The monitoring circuit was constructed in a manner similar to the reactor scram system monitoring circuit.
Rod Run-In Monitoring System This modification record documents the implementation of a passive monitoring circuit on the rod run-in system to improve troubleshooting capabilities for rod run-in signals that are too short in duration to detect with the annunciator system.
The monitoring circuit works in conjunction with a new jumper panel dedicated to the rod run-in system, and provides additional unused monitoring capacity for future troubleshooting expansion.
The monitoring circuit was constructed in a manner similar to the reactor scram system monitoring circuit.
Modification 13-02:
Modification 13-02:
Replacement of Secondary Chemistry Controllers This modification record documents the replacement of the Secondary Coolant System pH and conductivity controllers. The previous model controllers had become obsolete and repair parts were no longer available.
Replacement of Secondary Chemistry Controllers This modification record documents the replacement of the Secondary Coolant System pH and conductivity controllers. The previous model controllers had become obsolete and repair parts were no longer available.
Line 331: Line 521:
RUR 441: Natural Uranium Oxide Irradiation
RUR 441: Natural Uranium Oxide Irradiation


== Description:==
==
Description:==
This RUR authorizes the irradiation of up to 5.0 grams of natural Uranium Oxide in the reflector region of the reactor in support of research and development activities for medical applications.
This RUR authorizes the irradiation of up to 5.0 grams of natural Uranium Oxide in the reflector region of the reactor in support of research and development activities for medical applications.
RUR 271, as amended: Yttrium Microspheres:
RUR 271, as amended: Yttrium Microspheres:


== Description:==
==
This RUR was amended twice during calendar year 2013. The first amendment authorizes the use of quartz as a primary encapsulation and removed the requirement for the secondary encapsulation of aluminum for the microsphere targets. A second amendment to RUR 271 authorizes the use of discs, a different physical form of the same target material for irradiation.
Description:==
This RUR was amended twice during calendar year 2013. The first amendment authorizes the use of quartz as a primary encapsulation and removed the requirement for the secondary encapsulation of aluminum for the microsphere targets.
A second amendment to RUR 271 authorizes the use of discs, a different physical form of the same target material for irradiation.
RL-80: Selective Gaseous Extraction of Fission Products
RL-80: Selective Gaseous Extraction of Fission Products


== Description:==
==
Description:==
This RL authorizes the processing of up to 5.0 grams of natural Uranium Oxide to investigate Selective Gaseous Extraction as a novel separation process for producing radioisotopes from the fission of uranium.
This RL authorizes the processing of up to 5.0 grams of natural Uranium Oxide to investigate Selective Gaseous Extraction as a novel separation process for producing radioisotopes from the fission of uranium.
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.
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.
Line 358: Line 552:
VI-I
VI-I


SECTION VII RADIOACTIVE EFFLUENT January 1, 2013 through December 31, 2013 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2013 through December 31, 2013 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide                                     Activity (Ci)
SECTION VII RADIOACTIVE EFFLUENT January 1, 2013 through December 31, 2013 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2013 through December 31, 2013 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide H-3 S-35 Lu-177 Co-60 Ca-45 P-32 Mo-99 Zn-65 W-181 Cr-51 Ag-110m Sc-46 Tc-99m 1-131 As-76 Total H-3 Total Other Activity (Ci) 9.816E-02 7.312E-03 6.619E-03 2.256E-03 1.558E-03 1.384E-03 9.858E-04 6.517E-04 3.125E-04 5.560E-05 3.384E-05 3.075E-05 2.664E-05 1.592E-05 1.052E-05 9.816E-01 2.128E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."
H-3                                            9.816E-02 S-35                                          7.312E-03 Lu-177                                        6.619E-03 Co-60                                          2.256E-03 Ca-45                                          1.558E-03 P-32                                          1.384E-03 Mo-99                                          9.858E-04 Zn-65                                          6.517E-04 W-181                                          3.125E-04 Cr-51                                          5.560E-05 Ag-110m                                        3.384E-05 Sc-46                                          3.075E-05 Tc-99m                                        2.664E-05 1-131                                          1.592E-05 As-76                                          1.052E-05 Total H-3                                      9.816E-01 Total Other                                    2.128E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal By Release Into Sanitary Sewerage."
VII-1
VII-1


TABLE 2 STACK EFFLUENT January 1,2013 through December 31, 2013 Ordered by % Technical Specification (TS) Limit Isotope         Average Concentration             Total Release     TS Limit Multiplier       % TS (pCi/ml)                     (Ci)
TABLE 2 STACK EFFLUENT January 1,2013 through December 31, 2013 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration Total Release TS Limit Multiplier  
Ar-41                   2.73E-06                   1.22E+03               350               78.1054 H-3                   2.21E-08                   9.89E+00               350               0.0633 Kr-79                   6.72E-09                   3.OOE+00               350               0.0274 1-131                 3.38E-14                   1.51E-05                 1               0.0169 K-40                   6.02E-14                   2.69E-05                 1               0.0100 C-14                   2.48E-11                   1.13E-02                 1               0.0083 Co-60                   2.70E- 15                   1.21E-06                 1               0.0054 1-125                   1.12E-14                   4.99E-06                 1               0.0037 Sn- 113                 2.55E-15                   1.14E-06                 1               0.0003 Xe-135m                   1.94E- 11                 8.65E-03               350               0.0001 Os-191                   2.04E- 15                   9.12E-07                 1               0.0001 1-133                   1.96E- 13                 8.76E-05               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.
% TS (pCi/ml)
(Ci)
Ar-41 2.73E-06 1.22E+03 350 78.1054 H-3 2.21E-08 9.89E+00 350 0.0633 Kr-79 6.72E-09 3.OOE+00 350 0.0274 1-131 3.38E-14 1.51E-05 1
0.0169 K-40 6.02E-14 2.69E-05 1
0.0100 C-14 2.48E-11 1.13E-02 1
0.0083 Co-60 2.70E-15 1.21E-06 1
0.0054 1-125 1.12E-14 4.99E-06 1
0.0037 Sn-113 2.55E-15 1.14E-06 1
0.0003 Xe-135m 1.94E-11 8.65E-03 350 0.0001 Os-191 2.04E-15 9.12E-07 1
0.0001 1-133 1.96E-13 8.76E-05 350 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.
Isotopes observed at < 0.0001% Technical Specification limit are not listed.
Stack Flow Rate = -30,000 cfm Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, License R-103 Technical Specifications.
Stack Flow Rate = -30,000 cfm Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, License R-103 Technical Specifications.
Line 375: Line 577:
==SUMMARY==
==SUMMARY==
OF ENVIRONMENTAL SET 83 Spring 2013 Detection Limits]
OF ENVIRONMENTAL SET 83 Spring 2013 Detection Limits]
Matrix                 Alpha                 Beta                  Gamma                      Tritium Water                0.00 pCi/L           3.14 pCi/L          189.00 pCi/L          5.26 pCi/mL of sample Soil                0.58 pCi/g            3.47 pCi/g             0.61 pCi/g                   N/A Vegetation          0.00 pCi/g            8.94 pCi/g             1.53 pCi/g           6.33 pCi/mL of distillate Subsurface Soil      1.00 pCi/g            3.32 pCi/g            0.57 pCi/g                    N/A Activity Levels - Vegetation Sample           Aloha (oCi/g)           Beta (pCi/g)             Gamma (pCi/g)           H-3 (pCi/mL)
Matrix Water Soil Vegetation Subsurface Soil Alpha 0.00 pCi/L 0.58 pCi/g 0.00 pCi/g 1.00 pCi/g Beta 3.14 pCi/L 3.47 pCi/g 8.94 pCi/g 3.32 pCi/g Gamma 189.00 pCi/L 0.61 pCi/g 1.53 pCi/g 0.57 pCi/g Tritium 5.26 pCi/mL of sample N/A 6.33 pCi/mL of distillate N/A Activity Levels - Vegetation Sample I V83 2V83 3V83 4V83 5V83 6V83 7V83 10V83 Aloha (oCi/g) 0.35 0.35 0.00 0.35 0.00 0.70 1.38 0.70 Beta (pCi/g) 42.78 30.53 23.13 36.54 32.50 32.40 25.16 46.64 Gamma (pCi/g) 2.52 2.25
IV83                  0.35                  42.78                      2.52                 < 6.33 2V83                  0.35                  30.53                      2.25                 < 6.33 3V83                  0.00                  23.13                    < 1.53                 < 6.33 4V83                  0.35                  36.54                    < 1.53                 < 6.33 5V83                  0.00                  32.50                    < 1.53                < 6.33 6V83                  0.70                  32.40                      2.29                < 6.33 7V83                  1.38                  25.16                      < 1.53                < 6.33 10V83                  0.70                  46.64                        2.97                <6.33 VIII-I
< 1.53
< 1.53
< 1.53 2.29
< 1.53 2.97 H-3 (pCi/mL)
< 6.33
< 6.33
< 6.33
< 6.33
< 6.33
< 6.33
< 6.33
<6.33 VIII-I


TABLE 1 (Cont'd)
TABLE 1 (Cont'd)


==SUMMARY==
==SUMMARY==
OF ENVIRONMENTAL SET 83 Spring 2013 Activity Levels - Soil Sample           Alpha (pCi/g)             Beta (pCi/g)        Gamma (pCi/g)
OF ENVIRONMENTAL SET 83 Spring 2013 Activity Levels - Soil Sample IS83 2S83 3S83 4S83 5S83 6S83 7S83 10S83 Alpha (pCi/g) 1.47
IS83                1.47                   21.85                3.46 2S83                <0.58                     19.10                0.97 3S83                <0.58                     16.50                2.64 4S83                  1.15                   21.16                 1.72 5S83                2.03                    23.04                 1.09 6S83                  1.67                    14.98                2.21 7S83                  1.15                    27.91                  1.96 10S83              <0.58                    26.60                2.29 Activity Levels - Water Sample           Alpha (pCi/L)         Beta (pCi/L)           Gamma (pCi/L)         H-3 (pCi/mL) 4W83                1.06                    3.75              < 189.00                < 5.26 6W83                0.18                  4.12                < 189.00                < 5.26 10W83              0.35                  12.36                < 189.00                < 5.26 Activity Levels - Subsurface Soil Sample         Alpha (1Ci/2)             Beta (pCi/g)         Gamma (pCi/g)
<0.58
PSS83                1.50                    26.88                3.95 NESS83              1.50                    25.00                5.51 NSS83                1.50                    27.81                3.18 WSS83                1.50                    22.38                3.64 ESS83              < 1.00                    21.26                4.18 SSS83                1.32                    18.82                5.81 Note 1: Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
<0.58 1.15 2.03 1.67 1.15
<0.58 Beta (pCi/g) 21.85 19.10 16.50 21.16 23.04 14.98 27.91 26.60 Gamma (pCi/g) 3.46 0.97 2.64 1.72 1.09 2.21 1.96 2.29 Activity Levels - Water Sample 4W83 6W83 10W83 Alpha (pCi/L) 1.06 0.18 0.35 Beta (pCi/L) 3.75 4.12 12.36 Gamma (pCi/L)
< 189.00
< 189.00
< 189.00 H-3 (pCi/mL)
< 5.26
< 5.26
< 5.26 Activity Levels - Subsurface Soil Sample PSS83 NESS83 NSS83 WSS83 ESS83 SSS83 Alpha (1Ci/2) 1.50 1.50 1.50 1.50
< 1.00 1.32 Beta (pCi/g) 26.88 25.00 27.81 22.38 21.26 18.82 Gamma (pCi/g) 3.95 5.51 3.18 3.64 4.18 5.81 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.
HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity.
VIII-2
VIII-2
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==SUMMARY==
==SUMMARY==
OF ENVIRONMENTAL SET 84 Fall 2013 Detection Limits' Matrix             Alpha                 Beta                  Gamma                    Tritium Water            0.00 pCi/L             3.64 pCi/L            222.00 pCi/L      5.68 pCi/mL of sample Soil            0.73 pCi/g            3.98 pCi/g             0.55 pCi/g                 N/A Vegetation      2.53 pCi/g            7.98 pCi/g             1.56pCi/g       5.21 pCi/mL of distillate Subsurface      0.82 pCi/g             4.35 pCi/g              0.62 pCi/g                N/A Activity Levels - Vegetation Sample         Alpha (oCi/,)           Beta (pCi/g)            Gamma (pCi/g)      H-3 (pCi/mL) 1V84              < 2.53                   33.88                      2.51              < 5.21 2V84              < 2.53                   39.64                      1.86              < 5.21 3V84              < 2.53                   17.26                     2.81              < 5.21 4V84              <2.53                    21.19                      1.97               < 5.21 5V84              < 2.53                  27.72                    < 1.56               < 5.21 6V84              < 2.53                    12.91                  < 1.56              < 5.21 7V84              <2.53                    39.32                    < 1.56              < 5.21 10V84                2.84                  31.95                    < 1.56              < 5.21 Activity Levels - Soil Sample           Alpha (pCi/g)             Beta (pCi/g)            Gamma (pCi/g) 1S84                < 0.73                   20.18                  3.32 2S84                < 0.73                   10.35                  2.44 3S84                < 0.73                   17.93                  2.76 4S84                < 0.73                    10.71                  2.79 5S84                < 0.73                    21.52                   4.53 6S84                < 0.73                    13.11                  2.93 7S84                  1.77                    17.13                  4.57 10S84                  1.26                    21.68                  3.52 VIII-3
OF ENVIRONMENTAL SET 84 Fall 2013 Detection Limits' Matrix Water Soil Vegetation Subsurface Alpha 0.00 pCi/L 0.73 pCi/g 2.53 pCi/g 0.82 pCi/g Beta 3.64 pCi/L 3.98 pCi/g 7.98 pCi/g 4.35 pCi/g Gamma 222.00 pCi/L 0.55 pCi/g 1.56pCi/g 0.62 pCi/g Tritium 5.68 pCi/mL of sample N/A 5.21 pCi/mL of distillate N/A Activity Levels - Vegetation Sample 1 V84 2V84 3V84 4V84 5V84 6V84 7V84 10V84 Alpha (oCi/,)
< 2.53
< 2.53
< 2.53
<2.53
< 2.53
< 2.53
<2.53 2.84 Beta (pCi/g) 33.88 39.64 17.26 21.19 27.72 12.91 39.32 31.95 Gamma (pCi/g) 2.51 1.86 2.81 1.97
< 1.56
< 1.56
< 1.56
< 1.56 H-3 (pCi/mL)
< 5.21
< 5.21
< 5.21
< 5.21
< 5.21
< 5.21
< 5.21
< 5.21 Activity Levels - Soil Sample 1S84 2S84 3S84 4S84 5S84 6S84 7S84 10S84 Alpha (pCi/g)
< 0.73
< 0.73
< 0.73
< 0.73
< 0.73
< 0.73 1.77 1.26 Beta (pCi/g) 20.18 10.35 17.93 10.71 21.52 13.11 17.13 21.68 Gamma (pCi/g) 3.32 2.44 2.76 2.79 4.53 2.93 4.57 3.52 VIII-3


TABLE 2 (Cont'd)
TABLE 2 (Cont'd)


==SUMMARY==
==SUMMARY==
OF ENVIRONMENTAL SET 84 Fall 2013 Activity Levels - Water Sample           Alpha (pCi/L)           Beta (pCi/L)         Gamma (pCi/L)       H-3 (pCi/mL) 4W84                0.63                      6.52              < 222.00              <5.68 6W84                0.16                  < 3.64              < 222.00              < 5.68 10W84                0.00                    10.11              < 222.00              < 5.68 Activity Levels - Subsurface Soil Samole         Alpha (VCi/g)               Beta (pCi/g)       Gamma (pCi/g)
OF ENVIRONMENTAL SET 84 Fall 2013 Activity Levels - Water Sample 4W84 6W84 10W84 Alpha (pCi/L) 0.63 0.16 0.00 Beta (pCi/L) 6.52
PSS84                1.07                      22.51                6.23 NESS84              0.87                      22.62                4.24 NSS84                1.57                      26.15                4.47 WSS84                0.88                      21.16                3.16 ESS84                1.06                      21.91                4.76 SSS84                2.14                      23.46                5.48 Note 1: Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
< 3.64 10.11 Gamma (pCi/L)
< 222.00
< 222.00
< 222.00 H-3 (pCi/mL)
<5.68
< 5.68
< 5.68 Activity Levels - Subsurface Soil Samole PSS84 NESS84 NSS84 WSS84 ESS84 SSS84 Alpha (VCi/g) 1.07 0.87 1.57 0.88 1.06 2.14 Beta (pCi/g) 22.51 22.62 26.15 21.16 21.91 23.46 Gamma (pCi/g) 6.23 4.24 4.47 3.16 4.76 5.48 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.
HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity.
VIII-4
VIII-4
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==SUMMARY==
==SUMMARY==
 
January 1, 2013 through December 31, 2013 Badge Direction Map Distance from 1st Qtr.
January 1, 2013 through December 31, 2013 Badge       Direction     Map Distance from     1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total Number     From MURR         MURR Stack         2013    2013       2013   2013     2013 (meters)         Net mR   Net mR     Net mR   Net mR   Net mR Control 0                N/A            28.0      23.0      25.0    33.0    109.0 1   Control 1                16600          27.0      23.0      24.0    32.0    106.0 2   Control 2                16600          24.0      22.0      24.0    31.0    101.0 3   WSW                      N/A            0.0      0.0        0.0      0.0      0.0 4*
2nd Qtr.
3rd Qtr.
4th Qtr.
Number From MURR MURR Stack 2013 2013 2013 2013 (meters)
Net mR Net mR Net mR Net mR Total 2013 Net mR 1
2 3
4*
5*
5*
6   N                          34            0.0      1.0        5.0      9.0    15.0 7   NE                        57            4.0      2.0        5.0      1.0    12.0 8   SW                        27            6.0      4.0        3.0      2.0    15.0 9   S                          27            22.0      20.0      15.0    26.0    83.0 10   NE                        149            0.0      0.0        0.0      0.0    0.0 11   NW                        149            0.0      0.0        2.0      0.0    2.0 12   ENE                      301            0.0      2.0        3.0      2.0      7.0 13   NNE                      316            0.0      0.0        0.0      0.0    0.0 14   S                          156            0.0      3.0        0.0      0.0    3.0 15  S                          65            19.0    15.0      14.0    17.0    65.0 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            0.0      0.0        0.0      1.0      1.0 22   ESE                        168            0.0      0.0        0.0      0.0    0.0 23   NW                        110            0.0      0.0        0.0      3.0    3.0 24   SSW                      328            0.0      0.0        0.0      0.0    0.0 25   SSW                      480            0.0      0.0        3.0      0.0    3.0 26   SW                        301            0.0      0.0        0.0      0.0    0.0 27   WSW                      141            0.0      0.0        0.0      0.0    0.0 28   WNW                      210            0.0      0.0        3.0      1.0    4.0 29   NW                        255            2.0      0.0        4.0      0.0    6.0 30   NNW                      328            0.0      0.0        0.0      0.0    0.0 31   NNW                      671            0.0      0.0        0.0      0.0    0.0 32   NNW                      724            0.0      0.0          1.0    0.0      1.0 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            5.0      5.0        2.0      4.0    16.0 36   SE                        419            0.0      0.0        0.0      0.0    0.0 37   NE                        690            0.0      0.0        0.0      0.0    0.0 38   NW                        556            0.0      0.0          1.0    0.0      1.0 39   W                        491            0.0      0.0        0.0      0.0    0.0 40   N                        541            0.0      0.0        0.0      0.0    0.0 41   NNE                      137            0.0      0.0        0.0      0.0    0.0 42*
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42*
43*
43*
44   Spare                     N/A             0.0   missing   missing     0.0     0.0 45    S                          65             7.0     4.0         6.0     3.0   20.0 46    E                          70            0.0     0.0         0.0     0.0     0.0
44 45 46 Control 0 Control 1 Control 2 WSW N/A 16600 16600 N/A N
NE SW S
NE NW ENE NNE S
S SE E
NE NNE NE SE ESE NW SSW SSW SW WSW WNW NW NNW NNW NNW E
ENE SSE SE NE NW W
N NNE Spare S
E 34 57 27 27 149 149 301 316 156 65 107 293 476 606 907 236 168 110 328 480 301 141 210 255 328 671 724 671 587 499 419 690 556 491 541 137 N/A 65 70 28.0 27.0 24.0 0.0 0.0 4.0 6.0 22.0 0.0 0.0 0.0 0.0 0.0 19.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 2.0 0.0 0.0 0.0 0.0 0.0 5.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 7.0 0.0 23.0 23.0 22.0 0.0 1.0 2.0 4.0 20.0 0.0 0.0 2.0 0.0 3.0 15.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 5.0 0.0 0.0 0.0 0.0 0.0 0.0 missing 4.0 0.0 25.0 24.0 24.0 0.0 5.0 5.0 3.0 15.0 0.0 2.0 3.0 0.0 0.0 14.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3.0 0.0 0.0 3.0 4.0 0.0 0.0 1.0 0.0 0.0 2.0 0.0 0.0 1.0 0.0 0.0 0.0 missing 6.0 0.0 33.0 32.0 31.0 0.0 9.0 1.0 2.0 26.0 0.0 0.0 2.0 0.0 0.0 17.0 0.0 0.0 0.0 0.0 0.0 1.0 0.0 3.0 0.0 0.0 0.0 0.0 1.0 0.0 0.0 0.0 0.0 0.0 0.0 4.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3.0 0.0 109.0 106.0 101.0 0.0 15.0 12.0 15.0 83.0 0.0 2.0 7.0 0.0 3.0 65.0 0.0 0.0 0.0 0.0 0.0 1.0 0.0 3.0 0.0 3.0 0.0 0.0 4.0 6.0 0.0 0.0 1.0 0.0 0.0 16.0 0.0 0.0 1.0 0.0 0.0 0.0 0.0 20.0 0.0
*These badge numbers are no longer used.
*These badge numbers are no longer used.
VIII-5
VIII-5


TABLE 4 NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS January 1,2013 through December 31, 2013 Radiation         Surface Contamination*     Air Samples**     RWPs January                94                      94                    59            10 February              60                      60                    44              7 March                  97                      97                    45              9 April                  61                      61                    43              8 May                    87                      87                    36              8 June                  97                      97                    49              4 July                  94                      94                    62              7 August                97                      97                    63            10 September              80                      80                    62              8 October              101                      101                    66              6 November              85                      85                    45            10 December              74                      74                    11              9 TOTALS              1027                    1027                   585            96 In addition, general building contamination surveys are conducted each normal work day.
TABLE 4 NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS January 1,2013 through December 31, 2013 Radiation January February March April May June July August September October November December TOTALS 94 60 97 61 87 97 94 97 80 101 85 74 Surface Contamination*
** Air samples include exhaust stack Ar-41, containment building Ar-41, sump entries, and hot cell entries.
94 60 97 61 87 97 94 97 80 101 85 74 1027 Air Samples**
59 44 45 43 36 49 62 63 62 66 45 11 585 RWPs 10 7
9 8
8 4
7 10 8
6 10 9
96 1027 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 resigned as Assistant Health Physics Manager in August 2013.
Miscellaneous Notes Nathan Hogue resigned as Assistant Health Physics Manager in August 2013.
During calendar year 2013, MURR shipped 554 cubic feet of low-level radioactive waste containing 1.205 mCi of activity.
During calendar year 2013, MURR shipped 554 cubic feet of low-level radioactive waste containing 1.205 mCi of activity.
VIII-6
VIII-6


SECTION IX Summary of Radiation Exposure to Facility Staff, Experimenters and Visitors January I, 2013 through December 31, 2013 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP AC     BCS     DO     FOE HC/SH         HP     IRR     NA     NS       OPS     PRO     QA     RES     lIP     SIL   TEE   WC   Total January              12      2      10      4      419      128      7        6     52     1443     121   29       10     47       140     0     27   2457 February            18      3      0        6      346      90      6        9     62     1169     72     8     37       13     107     0   121   2067 March              39      7      0        17      534    121      3        11     34     1371     77   25     24       35       87     0     99   2484 April                14      0      0        0      450      207      13        11     22     1352     109     7       4       48     *86       5   254   2582 May                  15    10      0        0      414      109      3        2     21     1612     127   65       2       22       78     0     19   2499 June                3      0      0        7      434      219      0        4     84     1995     109   63     100     38       177     4     38   3275 July                0      6      0        0      340      89      9        12     1     1651     153   42       11     25       168     0     16   2523 August              15    13        1        3      335      122      7        15     54     2042     139   82       6       44     224     4     17   3123 September            0      2      0        5      310      II1      2      27     42     1598     129   47       4     246       137     8     39   2707 October              7    13      4        3      348    146      7      22     62     1666     130     85     9       65       94     2   101   2764 November            2      2      4        8      411      178      0      21     112     1865     117   21       2       28     411     0     37   3219 December            21      8        7        2      282      101      5      42     58     1725     171   32       7     30       114     2     23   2630 Total for Year     146     66       26       55     4623     1621     62     182     604     19489   1454   506   216     641     1823   25   791  32330 Monthly Avg          12      6        2        5      385      135      5      15     50     1624     121   42       18     53       152     2     66   2694 Highest WB         31     26       6       25     1565     425     57       64    212      1236    407    154    144    311      998      8    241 (annual)
SECTION IX Summary of Radiation Exposure to Facility Staff, Experimenters and Visitors January I, 2013 through December 31, 2013 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP January February March April May June July August September October November December AC 12 18 39 14 15 3
High EXT           479     58       NR     NR     3397     866     NR     2929    370      1556    5524    513    538    1832      1237    168  893 (annual)
0 15 0
AC - Analytical Chemistry BCS - Business & Central Services                   HP - Health Physics              OPS - Operations                        RP - Radiopharmaceutical DO - Director's Office                             IRR - Irradiations                PRO - Isotope Processing                SIL - Silicon FOE - Shops & Support                               NA - Nuclear Analysis            QA - Quality Assurance                  TEE - Trace Elemental Epidemiology HC/SH - Hot Cell/Shipping                           NS - Neutron Scattering           RES - Research                           WC - Work Control WB = Whole Body                   EXT = Extremities                 M = Minimal                 NR = None Reported Analysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA.
7 2
21 BCS 2
3 7
0 10 0
6 13 2
13 2
8 DO 10 0
0 0
0 0
0 1
0 4
4 7
FOE HC/SH HP IRR 4
419 128 7
6 346 90 6
17 534 121 3
0 450 207 13 0
414 109 3
7 434 219 0
0 340 89 9
3 335 122 7
5 310 II1 2
3 348 146 7
8 411 178 0
2 282 101 5
NA NS OPS PRO QA RES lIP SIL TEE WC Total 6
52 1443 121 29 10 47 140 0
27 2457 9
62 1169 72 8
37 13 107 0
121 2067 11 34 1371 77 25 24 35 87 0
99 2484 11 22 1352 109 7
4 48  
*86 5
254 2582 2
21 1612 127 65 2
22 78 0
19 2499 4
84 1995 109 63 100 38 177 4
38 3275 12 1
1651 153 42 11 25 168 0
16 2523 15 54 2042 139 82 6
44 224 4
17 3123 27 42 1598 129 47 4
246 137 8
39 2707 22 62 1666 130 85 9
65 94 2
101 2764 21 112 1865 117 21 2
28 411 0
37 3219 42 58 1725 171 32 7
30 114 2
23 2630 Total for Year 146 Monthly Avg 12 66 26 55 4623 1621 62 6
2 5
385 135 5
182 604 19489 1454 506 216 641 1823 25 15 50 1624 121 42 18 53 152 2
64 212 1236 407 154 144 311 998 8
2929 370 1556 5524 513 538 1832 1237 168 791 32330 66 2694 Highest WB 31 26 6
25 1565 425 57 (annual)
High EXT 479 58 NR NR 3397 866 NR (annual) 241 893 AC - Analytical Chemistry BCS - Business & Central Services DO - Director's Office FOE - Shops & Support HC/SH - Hot Cell/Shipping HP - Health Physics IRR - Irradiations NA - Nuclear Analysis NS - Neutron Scattering OPS - Operations PRO - Isotope Processing QA - Quality Assurance RES - Research RP - Radiopharmaceutical SIL - Silicon TEE - Trace Elemental Epidemiology WC - Work Control WB = Whole Body EXT = Extremities M = Minimal NR = None Reported 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.
Radiation workers who are not full time staff members have radiation exposures which are generally lower than full time radiation workers.
NOTES:
NOTES:
Dosimetry services are provided by Mirion Technologies (except self reading dosimetry).}}
Dosimetry services are provided by Mirion Technologies (except self reading dosimetry).}}

Latest revision as of 22:55, 10 January 2025

University of Missouri Research Reactor 2013 Reactor Operations Annual Report
ML14063A044
Person / Time
Site: University of Missouri-Columbia
Issue date: 02/27/2014
From: Rhonda Butler, Fruits J
Univ of Mississippi
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14063A044 (39)
v • d • e


Text

UNIVERSITY of MISSOURI RESEARCH REACTOR CENTER February 27, 2014 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

REFERENCE:

SUBJECT:

Docket 50-186 University of Missouri-Columbia Research Reactor Amended Facility License R-103 University of Missouri Research Reactor 2013 Reactor Operations Annual Report Enclosed is a copy of the Reactor Operations Annual Report for the University Reactor. The reporting period covers January 1, 2013 through December 31, 2013.

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

of Missouri Research accordance with the If you have any questions regarding the contents of this report, please contact John Fruits at (573) 882-5319 or FruitsJ(d@missouri.edu.

S i n c e r e l y,

John L. Fruits Reactor Manager ENDORSEMENT:

Reviewed and Approved Ralph A. Butler, P.E.

Director JLF/jlb Enclosure xc:

Mr. Alexander Adams, U.S. NRC Mr. Johnny Eads, U.S. NRC 1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: http://web.missouri.edu/-murrwww Fighting Cancer with Tomorrow's Technology

4 UNIVERSITY OF MISSOURI a.1 UNIVERSITY OFM*iSSoURI..'.'

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  • SEARCH REACTOR'.-:.

REACTOR OPERATIONS-,;q

.,..:...'ANNUAL".;REPORT.-

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UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2013 through December 31, 2013 Compiled by the Research Reactor Staff of MURR Submitted by:

John L. Fruits Reactor Manager Reviewed and approved by:

a/46<

Ralph A. Butler, PE Director

UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1,2013 through December 31, 2013 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, boron neutron capture therapy 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, heterogeneous reactor designed for operation at a maximum steady-state power level of 10 Megawatts thermal - the highest powered university-operated research reactor in the United States.

The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2013.

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 Missou'i University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our regulators; those who have provided funding including the Department of Energy (DOE), the National Nuclear Security Administration (NNSA) 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) implementing Amendment No. 36 to Amended Facility License No. R-103, which revised the Safety Limit Curves based on newer, more accurate power peaking factors developed using a 3-dimensional diffusion code, (2) replacement of the 30-degree graphite reflector elements 'GH' and IJ' with a single 60-degree graphite reflector element 'GHIJ,' and (3) irradiating and processing a 5-gram natural uranium target to determine the feasibility of producing molybdenum-99 using a selective gaseous extraction process.

Additionally, in August 2006 MURR submitted a request to the NRC to renew i

Amended Facility License No. R-103. Significant efforts have already been placed in responding to the Requests for Additional Information and these efforts continued in this past year.

The facility continues to actively collaborate with the Reduced Enrichment for Research and Test Reactors (RERTR) 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. This past year, resources were focused on completing Phase 1 accident analyses for the LEU conversion core.

MURR also hosted the 2013 Annual Test, Research and Training Reactors Conference.

The TRTR organization represents research reactor facilities across the nation from government, major universities, national laboratories and industry.

TRTR's primary mission is education, fundamental and applied research, application of technology in areas of national concern and improving U.S. technological competitiveness around the world.

TRTR membership includes managers and directors of research reactors, educators, administrators, regulators and research scientists and engineers.

Reactor Operations Management also wishes to commend the five individuals who received their Reactor Operator certifications and the four individuals who received their Senior 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 a licensed operator during normal and abnormal situations.

ii

TABLE OF CONTENTS Section Title Pages I.

Reactor Operations Sum m ary...............................................................

I-I through 9 f].

M U RR Procedures................................................................................

Il-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..........................................

Ill-I through 4 IV.

Plant and System M odifications...........................................................

IV-1 through 3 V.

New Tests and Experiments............................................................

V-1 VI.

Special Nuclear Material and Reactor Physics Activities................ VI-1 VII.

Radioactive Effluent.............................................................................

VII-I through 2 Table 1 - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII.

Environmental Monitoring and Health Physics Surveys...................... VIII-l through 6 Table I - Summary of Environmental Set 83 Table 2 - Summary of Environmental Set 84 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 I REACTOR OPERATIONS

SUMMARY

January 1,2013 through December 31, 2013 The following table and discussion summarizes reactor operations during the period from January 1, 2013 through December 31, 2013.

Full Power % of Total Full Power % of Month Full Power Hours Megawatt Days Time Scheduled"'1 January 679.75 283.43 91.4 102.3 February 589.33 245.87 87.7 98.2 March 664.72 277.30 89.3 100.0 April 619.93 258.61 86.1 96.6 May 649.35 270.93 87.3 97.7 June 633.77 264.35 88.0 98.7 July 653.10 272.39 87.8 98.3 August 653.01 272.41 87.8 98.3 September 631.41 263.39 87.7 98.4 October 672.05 280.20 90.3 101.1 November 656.37 273.77 91.2 102.2 December 666.32 277.85 89.6 100.3 Total for 7769.11 3240.50 88.68 %

99.34 %

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 /> number of hours in the month listed or the year.

of full power operation per week. Total time is the January 2013 The reactor operated continuously in January with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included:

replacing Reactor Pool Reflector Region Differential Pressure Transmitter PT-917; 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).'"

February 2013 The reactor operated continuously in February with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and two unscheduled/unplanned power reductions.

On February 23, 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 the reactor safety system yellow leg Trip Actuator Amplifier 1-1

(TAA) de-energized, causing control blades 'A' and 'B' anvils to separate from their electromagnets and drop. A manual scram was then 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 reactor safety system revealed that a normally closed contact in the manual scram switch., 1SI 0, was intermittently making a poor connection.

The contact blocks in the manual scram switch were burnished and the yellow leg TAA was replaced. The system was 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.

On February 23, with the reactor operating at 10 MW in the automatic control mode, a reactor scram was automatically initiated when an interruption in electrical 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 Lead Senior Reactor Operator after confirmation from the power plant that the cause of the interruption in electrical power was corrected. A "hot reactor startup" was performed to return the reactor to 10 MW operation.

Major maintenance items for the month included: replacing the 30-degree graphite reflector elements 'GH' and 'IJ' with a single 60-degree graphite reflector element 'GHIJ;' and replacing the pool coolant demineralizer system inlet filters.

March 2013 The reactor operated continuously in March with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and four unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of the Radiation Protection Program and Shipping.

On March 4, while reviewing a list of the completed maintenance items and compliance procedures performed that day, the Surveillance Programs System Specialist discovered that compliance procedure CP-27, "Power Level Interlock Static Scram," was not completed within the prescribed Technical Specification (TS) periodicity. Failure to perform the surveillance within the required time interval resulted in a deviation from TS 5.4. Licensee Event Report No. 13-01 was submitted to the U.S. Nuclear Regulatory Commission on April 2, 2013. The compliance procedure was performed on March 11, the next scheduled maintenance day after discovery of the error.

On March 5, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction. After a brief investigation was unable to determine the cause of the rod run-in, the rod run-in was not manually reset and the reactor was shut down. Subsequent investigation of all power supplies, relays, switches and wiring connections associated with the rod run-in system revealed no abnormalities.

Additional troubleshooting and investigation were unable to reproduce this system response.

Operational checks of the rod run-in system were performed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

On March 5 (5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 55 minutes after the previous power reduction), with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated.

The control room operator immediately noted all four shim control blades moving in the inward direction. After a brief investigation was unable to determine the cause of the rod run-in, the reactor was manually scrammed. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed.

Subsequent 1-2

investigation did not identify a failed component; however, the most likely cause was a failure of either the rod run-in system Trip Actuator Amplifier (TAA) or Non-Coincidence Logic Unit (NCLU). The rod run-in system TAA and NCLUs were replaced and operational checks of the rod run-in system were performed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

On March 13, 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 electromagnet during a routine sample handling evolution.

The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.

On March 20, 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 'A' anvil separated from its electromagnet during a routine sample handling evolution.

The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included: completing Modification Record 13-03, "Replacement of GH and IJ Wedge with a Single 600 Wedge;" completing Modification Record 12-02, "Control Blade Fabrication Alternative Using Laser Welding;" completing Modification Record 01-02, Addendum 9, "Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299) Renovations;" 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 a reactivity worth measurement in accordance with reactor procedure RP-RO-203, "Measurement of the Primary Coolant/Moderator Temperature Coefficient of Reactivity, RTP-19," in support of a Nuclear Engineering Department practicum; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-II(D)," in support of a Nuclear Engineering Department practicum; and loading new de-ionization bed

'F' and placing on pool coolant system service.

April 2013 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and one unscheduled/unplanned power reduction. One additional reactor startup and shutdown were performed in support of NRC operator license examinations. MURR received notification from the U.S. Nuclear Regulatory Commission that two new Reactor Operator and one new Senior Reactor Operator licenses had been issued.

On April 30, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction.

The reactor was then subsequently shut down. Subsequent investigation did not identify a failed component; however, two resistors in the Trip Actuating Amplifier (TAA) circuit were determined to have resistance values outside their specified tolerances. Both resistors were replaced.

1-3

Operational checks of the rod run-in system were performed satisfactorily and 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: performing extensive troubleshooting on the rod run-in system wiring; completing Modification Record 11-03, Addendum 1, "Addition of Blow-Down Meter to the Data Acquisition Monitoring System;" completing Modification Record 13-02, "Replacement of Secondary Chemistry Controllers;" replacing primary coolant circulation pump P-501A; 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-I 7(B);" 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);" replacing the actuator for manual scram switch, I SI0; and completing the biennial change-out of Control Blade 'A' Offset Mechanism and associated retesting.

May 2013 The reactor operated continuously in May with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and three unscheduled/unplanned power reductions.

On May 7, with the reactor operating at 10 MW in the automatic control mode, a manual scram was initiated when an operator discovered the regulating blade would not move in the inward direction. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram" were performed. Subsequent investigation revealed the ball plunger for the overload clutch had loosened and slightly backed out preventing the movement of the servomotor from being transferred to the lead screw assembly, thus preventing the regulating blade from being able to drive in the outward and inward directions. The overload clutch was inspected and the ball plunger was replaced. Operational checks of the regulating blade were performed satisfactorily and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

Failure of the regulating blade to be operable during reactor operation resulted in a deviation from Technical Specification 3.4.c. Licensee Event Report No. 13-02 was submitted to the U.S. Nuclear Regulatory Commission on June 4, 2013.

On May 8, 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 electromagnet during a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator.

The reactor was subsequently restarted to 10 MW operation.

On May 14, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) reactor scram was automatically initiated. Investigation revealed all monitored parameters were normal and none had trended toward an automatic scram set point or exhibited any abnormalities. Subsequent troubleshooting efforts led to the replacement of Power Level Interlock relay I1K26. Operational checks of the Power Level Interlock circuit were performed satisfactorily and 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:

replacing Power Level Interlock relay IK26; replacing the diaphragm and inlet and outlet flange gaskets for pool coolant demineralizer pump P-513B Discharge Valve 515N; 1-4

completing compliance procedure CP-26, "Containment Building Compliance Test;" 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)."

June 2013 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and two unscheduled/unplanned power reductions.

On June 11, 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 'A' anvil separated from its electromagnet during a routine sample handling evolution. The reactor was manually scrammed and the immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed.

Inspection of the offset mechanism pull rod and housing revealed a slight misalignment between the anvil and electromagnet. The lower drive limit switch was adjusted and the anvil and electromagnet were cleaned. The control rod was satisfactorily withdrawn to the full out position as part of the retest by performing compliance procedure CP-10, "Rod Drop Times." Permission to perform a "hot reactor startup" was obtained from the Reactor Manager. While conducting the "hot reactor startup," the Reactor Operator noted, immediately after stabilizing reactor power level at 5 MW, that the heights of shim control blades 'B' and 'D' were at 21.90 and 23.10 inches, respectively. This 1.20 inch difference in shim blade height created a deviation from Technical Specification (TS) 3.2.b, which states, "Above 100 kilowatts the reactor shall be operated so that the maximum distance between the highest and lowest shim blade shall not exceed one inch." Licensee Event Report No. 13-03 was submitted to the U.S. Nuclear Regulatory Commission on July 10, 2013.

On June 14, with the reactor operating at 10 MW in the automatic control mode, an unannounced (no audible or visual alarm occurred) rod run-in was automatically initiated. The control room operator immediately noted all four shim control blades moving in the inward direction. The reactor was then subsequently shut down. Subsequent investigation did not identify a failed component.

Additional troubleshooting and investigation were unable to reproduce this system response. Operational checks of the rod run-in system were performed satisfactorily.

The reactor was refueled and 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: performing extensive troubleshooting on the rod run-in system wiring connections; completing Modification Record 13-04, "Rod Run-In Monitoring System;" completing Modification Record 75-01, Addendum 3, "Rod Run-In Electronic Circuit Jumper Panel;" completing Modification Record 13-01, "Replacement of TE-980A and TE-980B Power Supply 2PS5;" 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 replacing the Loss of Voltage to Magnet A and B Scram relay 2K20 and the Loss of Voltage to Magnet C and D Scram relay 2K2 1.

July 2013 The reactor operated continuously in July with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and two unscheduled/unplanned power reductions. U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of Security and Material Control and Accountability. The U.S. Nuclear Regulatory Commission issued Amendment No. 36 to Amended Facility License No. R-103.

On July 3, with the reactor operating at 10 MW in the automatic control mode, a "Power Level Interlock or FIRST" scram was automatically initiated when the FIRST Support Rig was inadvertently bumped while performing a routine 1-5

sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The flux trap sample holder was verified to be positively latched to the inner reactor pressure vessel. The operators involved were counseled on the importance of proper handling techniques near the FIRST Support Rig.

The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

On July 15, during a reactor startup with the reactor subcritical, a "Rod Not in Contact with Magnet" rod run-in was automatically initiated when control blade 'B' anvil separated from its electromagnet during a shimming evolution.

The reactor was shut down and the immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The mating surfaces between the control rod drive mechanism electromagnet and pull rod anvil were cleaned and proper alignment of the offset mechanism pull rod and housing were verified. The control rod was satisfactorily withdrawn to the full out position as part of the retest by performing 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: 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);" 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 Vent Tank Discharge Check Valve 550A; replacing Pool Below Refuel Level relay 2K5; replacing the chassis edge connectors for the rod run-in system and the reactor safety system Trip Actuator Amplifiers and Non-Coincidence Logic Units; and replacing the air actuator and diaphragm on pressurizer Water Drain Valve 527A.

August 2013 The reactor operated continuously in August with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, one shutdown for training and four unscheduled/unplanned power reductions.

On August 21, with the reactor operating at 10 MW in the automatic control mode, a "Reactor Loop Low Pressure" scram was automatically initiated. All immediate and subsequent actions of reactor emergency procedure REP-3, "Primary Coolant System Low Pressure or Flow Scram," were performed.

No actual low pressure condition indication was present. Investigation determined the most likely cause to be reactor core outlet pressure channels 944A or 944B. Contacts on Reactor Pressure/Flow Interlock relays 2K32 and 2K33 were burnished, reactor core outlet pressure transmitters were vented and applicable sections of compliance procedure CP-22, "Pressure Transmitters PT-944A/B and PT-943," were completed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager.

The reactor was subsequently restarted to 10 MW operation.

On August 23, with the reactor operating at 10 MW in the automatic control mode, a "Reactor Loop Low Pressure" scram was automatically initiated. All immediate and subsequent actions of reactor emergency procedure REP-3, "Primary Coolant System Low Pressure or Flow Scram," were performed.

No actual low pressure condition indication was present. Investigation determined the cause to be an intermittent failure of reactor core outlet pressure 944B meter/relay unit. The meter/relay unit was replaced and applicable sections of compliance procedure CP-22 "Pressure Transmitters PT-944A/B and PT-943," were completed satisfactorily.

The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

1-6

On August 25, 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 was separated from its electromagnet during a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment was performed. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

On August 26, during a reactor startup with the control blades at approximately 11 inches withdrawn (subcritical), a "Channel 2 & 3 Period" scram was automatically initiated when Nuclear Instrumentation (NI) Intermediate Range Channel No. 2 period indication increased above the scram set point. The duty operator noted all power level and period indications other than those from NI Signal Processor No. 1 were normal. All immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Troubleshooting efforts led to the replacement of NI Signal Processor No. I fission chamber and its associated cabling. An instrument channel calibration and pre-operational checks were performed satisfactorily, including a response check using the neutron source. The reactor was refueled and 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: completing Modification Record 04-05, Addendum 8, "Cooling Tower Electrical Arc Flash Danger Mitigation;" completing Modification Record 12-01, "Replace PT-944A/B with Rosemount Transmitters;" 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 chemical cleaning of the secondary coolant side of primary coolant heat exchanger HX-503A; loading new de-ionization bed 'D' and placing it on pool coolant system service; and replacing the fission chamber detector and associated cabling for NI Signal Processor No. 1.

September 2013 The reactor operated continuously in September with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, two shutdowns for training and two unscheduled/unplanned shutdowns.

On September 16, with the reactor operating at 10 MW in the automatic control mode, a reactor shutdown was initiated after the duty operator observed a blown fuse indication on Annunciator Control Power Fuse 2F7, accompanied, shortly thereafter, by an Uninterruptible Power Supply (UPS) trouble alarm. All other indications for 10 MW operation were normal. Further investigation revealed that the Annunciator 115VAC Supply Breaker on UPS Panel No. 2 was in the tripped condition and the Annunciator inoperable. Troubleshooting efforts determined that the most likely cause of the blown fuse and tripped breaker was a faulty alarm module. The Annunciator alarm module for "Channel 4, 5, or 6 Downscale" function was replaced and an operational test of the Annunciator was completed satisfactorily. Permission to the restart the reactor was obtained from the Reactor Manager. The reactor was subsequently returned to 10 MW operation.

On September 23, with the reactor operating at 10 MW in the automatic control mode, a reactor shutdown was initiated after the duty operator observed a greater than normal lowering of pressurizer liquid level of approximately 2 inches per hour. This abnormal decrease in liquid level was observed shortly after a reactor startup. A reactor refueling had been performed earlier in the day. Subsequent investigation revealed that the source of leakage was from the pressure vessel head packing gland seal, which provides the seal between the pressure vessel head and inner reactor pressure vessel. Note: The pressure vessel head is removed and then subsequently replaced and tightened 1-7

after refueling a core has been completed. The packing gland was tightened and permission to restart the reactor was obtained from the Reactor Manager. The reactor was returned to 10 MW operation. Operators were subsequently counseled on proper bolting techniques.

Major maintenance items for the month included:

completing Modification Record 01-02, Addendum 10, "Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299), Room 243, Room 246 and Room 271 Renovations;" 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);" completing a change-out of Control Blade 'A' Offset Mechanism and associated retesting; and replacing the "Channel 4, 5 or 6 Downscale" annunciator alarm module.

October 2013 The reactor operated continuously in October with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unplanned/unscheduled shutdowns this month.

Major maintenance items for the month included: completing Modification Record 04-03, Addendum 1, "Liquid Radioactive Waste System in MURR Industrial Building;" completing Modification Record 13-06, "Modifications to MURR Industrial Building (Room 299) in Support of the NS-99 Project;" replacing Nuclear Instrumentation Power Range "Channel 4 Downscale (95%)" relay unit K58; flooding and draining Beamport 'D' and back filling with helium; performing the biennial change-out of Control Blade 'C' Offset Mechanism and associated retesting; 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)."

November 2013 The reactor operated continuously in November with the following exceptions:

four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements and one unscheduled/unplanned power reduction. Three additional reactor startups and shutdowns were performed in support of NRC operator license examinations. U.S. Nuclear Regulatory Commission inspector arrived at the facility for a routine inspection of Reactor Operations and Emergency Preparedness. MURR received notification from the U.S. Nuclear Regulatory Commission that three new Reactor Operator and three new Senior Reactor Operator licenses had been issued.

On November 11, 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 electromagnet during a routine sample handling evolution.

The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The operators involved were counseled on the importance of proper sample handling techniques near the offset mechanisms. Visual verification of the pull rod to housing alignment and operability tests were performed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator. The reactor was subsequently restarted to 10 MW operation.

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);" and performing pre-beryllium change-out center test hole flux profile measurements.

1-8

December 2013 The reactor operated continuously in December with the following exceptions:

five shutdowns for scheduled maintenance and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: completing Modification Record 13-05, "T-300 and T-301 Level Sensing System;" 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);" loading new de-ionizing bed 'R' and placing on pool coolant system service; and performing a chemical cleaning of the secondary coolant side of pool coolant system heat exchanger HX-52 1.

1-9

SECTION I!

MURR PROCEDURES January 1, 2013 through December 31, 2013 As required by administrative Technical Specification 6.l.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, as applicable, 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-two (62) revisions issued to the reactor operations procedures, forms and operator aids. 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:

~Ntinier~

Name Rev Aevision Dte Notes AP-RO-130 Crane Operation 16 3/29/2013 Cover Page AP-RR-003 10 CFR 50.59 Evaluations 8

6/5/2013 Minor Editorial EX-RO-105 Reactor Irradiation Experiments 119 5/22/2013 Minor Editorial Type B Shipment of spent Fuel Using the BEA I

FB-SH-I10 e

4/16/2013 Minor Editorial Research Reactor PackageI FB-SH-110 ~Type B Shipment of spent Fuel Using the BEA 5/14/2013 Full Review Research Reactor Package FM-1 Reactor Shutdown Checksheet 6

12/20/2013 Cover Page FM-15 110 CFR 50.59 Qualified Reviewers List 15 6/5/2013.

Minor Editorial FM-15 10 CFR 50.59 Qualified Reviewers List 16 12/19/2013 Minor Editorial FM-21 ARMS Trip Setpoints 9

6/6/2013 Minor Editorial FM-33 Containment Building Restricted Materials 5

12/9/2013 Cover Page FM-43 Nuclear and Process Data 17 3/29/2013 Cover Page FM-43 Nuclear and Process Data 18 10/17/2013 Minor Editorial FM-55 jStartup Nuclear Data Sheet 7

3/29/2013 Minor Editorial FM-56 lReactor Routine Patrol 16 3/29/2013 Minor Editorial FM-57 Long Form Startup Checksheet 20 5/2/2013 Minor Editorial FM-57 Long Form Startup Checksheet 21 10/31/2013 Minor Editorial FM-58.

Short Form Startup Checksheet 11 10/31/2013 Minor Editorial FM-63.

DI Water Makeup Log 19 1/31/2013 Cover Page.

Customer Sample Pre-Encapsulation Evaluation 7 1 6/10/2013 Minor FM-66 7W6/0/213eino Editorial Worksheet FM-68 Target Material Control Checksheet 12 J 6/10/2013 Minor Editorial FM-93.Post Maintenance Valve Line-up Checksheet 5

6/10/20 1.3 Cover Page IRR-PSO-111 ICustomer Sample Pre-Encapsulation Evaluation I

6/10/2013 Minor Editorial 11-1

Nu~mber Na~me Rgy. Revision Dite j No9tes OP-RO-100 Main Air System j.10 3/29/2013 Minor Editorial OP-RO-101 Instrument Air System J 10 3/29/2013 Minor Editorial OP-RO-210 Reactor Startup-Normal 113 5/22/2013 3 Cover Page OP-RO-211 Reactor Startup-Hot 11 ] 6/25/2013 3 Minor Editorial OP-RO-211 lReactor Startup - Hot 1

12 8/22/2013 3 Minor Editorial Reactor Startup - Recovery from Temporary Power 1

1 OP-RO-212 Reduction 12/9/2013 Cover Page OP-RO-220 Reactor Shutdown or Power Reduction 81 6/25/2013 Minor Editorial OP-RO-230 Changing Reactor Power Level 8

6/25/2013 Minor Editorial OP-RO-310

_Nuclear Instrumentation - Signal Processor #1 310 5/22/2013 Cover Page OP-RO-311 TNuclear Instrumentation - Signal Processor #2 11 5/22/2013 Cover Page OP-RO-312 Nuclear Instrumentation Power Range Monitor -

13 OPhannOe316 13 52/03 Cover Page OP-RO-330 Nuclear Instrumentation-Wide Range Monitor 1

13 5/22/2013 Cover Page OP-RO-340 Nuclear Instrumentation Adjustment 103 5/22/2013 Cover Page Reactor Power Calculator Flow Potentiometer OP-RO-350 Adjustment 9/24/2013 Cover Page OP-RO-410 ]Primary Coolant System

.l.1i 5/2/2013 Minor Editorial OP-RO-420 3Primary and Pool Water Analysis 161 9/24/2013 j Cover Page OP-RO-460 3Pool Coolant System - Two Pump Operation 314..3 9/24/2013 Minor Editorial OP-RO-461 JPool Coolant System - One Pump Operation 14T 9/24/2013 Minor Editorial OP-RO-465 3Pool Level Control - Skimmer System 18 3/29/2013 Minor Editorial OP-RO-480 3Secondary Coolant System 17 9/24/2013 Minor Editorial OP-RO-480 3Secondary Coolant System 18 12/9/2013 Minor Editorial OP-RO-510 Nitrogen System

37.

5/2/2013 3 Minor Editorial OP-RO-515 Emergency Air System J9 9/24/2013 f Minor Editorial OP-RO-516 Valve Operation Air System1 9 1 8/22/2013 1 Cover Page OP-RO-525 Chill Water System 17 6/25/2013 Minor Editorial OP-RO-530 Demineralized Water Supply System IT13 8/22/2013 Cover Page OP-RO-531 Primary and Pool Sample Station I1 9/24/2013 Cover Page OP-RO-555 Fire Protection System

.10 1/31/2013 Minor Editorial OP-RO-555 Fire Protection System 311 11/19/2013 Minor Editorial OP-RO-710 Radiation Monitoring - Area Monitors 181 8/22/2013 Cover Page.

OP-RO_720 jRadiation Monitoring - Stack Monitor Operational 1

6 1

OPhROec20 11 6/25/2013 Minor Editorial OP-RO-730 Facility Exhaust System 14 3/29/2013 Minor Editorial OP-RO-741 Waste Tank System Operation 13 5/2/2013 Minor Editorial OP-RO-741 Waste Tank System Operation 14 12/19/2013 Minor Editorial POL-20 Special Nuclear Materials Manual 13 3/3/8/2013 Minor Editorial REP-RO-100 IReactor Emergency Procedures 3161 1/31/2013 Cover Page RM-RO-400 Waste Tank System Filter Replacement 373 3/29/2013 Minor Editorial Receipt, Inspection and Accounting of Unirradiated 5/1nEo

-RO-00 5/22/2013 Minor Editorial SM-RO-200 Manual Operation of Airlock doors 276 and 277 2

5/7/2013 Minor Editorial lControl Console And Instrument Panel -Securing SM-RO-301 3Power 11-2 10 9/24/2013 Cover Page

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 thirteen (13) 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 R1ev. fRevision Datej Not~es EP-RO-002 Emergency Responsibilities 4

5/7/2013 Minor Editorial EP-RO-006 Radiological Emergency 5

5/7/2013 Minor Editorial EP-RO-013 Facility Evacuation 5

15/7/23 Minor Editorial EP-1R-0 15 Emergency Notifications 9

4/4/2013 Minor Editorial.

EP-RO-0 15 Emergency Notifications 10 5/7/2013 Minor Editorial EP-RO-0 15 Emergency Notifications I 1 10/29/2013 Minor Editorial EP-RO-0 18 Emergency Radiation Exposure 5

5/7/2013 Minor Editorial FM-104 JEmergency Call List 22 4/4/2013 Minor Editorial FM-i 10 Fire Flowchart 4

5/7/2013 Minor Editorial OA-09 Combined Emergency Flowcharts 5

7/8/2013 1 Minor Editorial OA-10 jFire Extinguisher Locations and Types 9

12/12/2013 Minor Editorial OA-20 jEmergency Equipment

.15 7/8/2013 Minor Editorial OA-20 JEmergency Equipment 16 12/12/2013 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 eighty-four (84) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. Additionally, three (3) new forms and four (4) new procedures were issued.

The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures and forms:

Naniber JName Rev. ~Revision Date

~

Notes tMURR Initial Radiation Worker Training AP-HP-117

]Mrral 11 3/22/2013 Minor Editorial

~Program I_________________

AP-HP-119 IHigh Radiation Area Access 5

1/3/2013 Minor Editorial

.r AP-HP-123 IVisitor Dosimetry - Reception Desk 19 4/29/2013 Minor Editorial

  • AP*-'HP-123

.V~isitor Do..*?sim*etry

-'rReception Desk...

..........!0...... 8/5/(2.013.......... Mino°r.E~ditori~al AP-HP-129 Hot Cell, HC-01 Control 9

]

2/7/2013 Minor Editorial AIn-House Radioactive Shipping Request Form AP-SH-002

]Isrcin

.2 6/18/2013 Minor Editorial AP-SH-002 In-House Radioactive Shipping Request Form Instructions 11-3 3

9/17/2013 Minor Editorial

~'Number jName Rev. Rievision Date]

Notes SAP-SH-002 jIn-House Radioactive Shipping Request Form 4

12/19/2013 Minor Editorial

_Instructions DOT 6M Packaging of Type B Non-Waste 1 T 10/9/2013 Minor Editorial BPB-S-005_ ~Radioactive Material Receiptlnspection Of Type B Byproduct Material 4

4/29/2013 Minor BPB-SH-020 Shipping Containers BPB-SH-023 jType B Equipment Calibration 121 12/20/2013.

Minor Editorial TypeB(U) F-458 Series Packaging of Type B BPB-SH-024 Non-Waste Radioactive Material Editorial Type B(U) ZA/NNRI005 (Beatrice) Packaging of I

BPB-SH-021 2

10/9/20 13 Minor Editorial BP-SH-025_

gType B Non-Waste Radioactive Material BPB-SH-026 Type B(U) F-327 Series Packaging of Type B 1

Non-Waste Radioactive Material 1

h nC.BPB-SH-027 Survey and Decontamination of Returned 1

i ShipingConainrs7 1

10/9/2013 Minor Editorial BTYPE B(U) USA/0656/B(U)-96 (Ganuk) 0 BPB-SH-029 0Pcaigo aiatv aeilf 11/5/2013 New Procedure j Packaging of Radioactive Material BP-SH-016 ~Packaging and Shipment of Radioactive Material 3

10/9/2013 Minor Editorial Using USA DOT 7 A Model H or I Package BP-SH-017 Packaging and Shipment of Radioactive Material 0

7/18/2013 New Procedure Using Tracerco LS-6 Reusable Type A Package I

Radioactive Material Shipment Package BP-SH-052 Douetto n

aeig10 2/6/2013 Minor Editorial I~Documentation and Labeling_

BRadioactive Material Shipment Package BP-SH-052 IouettonadLbln 11 7/26/2013 Minor Editorial

.I~~

~Documentation and Labeling Type B Shipment of spent Fuel Using the BEA 2

4/16/2013 Minor Editorial FB-SH-110

]Research Reactor Package

/Type B Shipment of spent Fuel Using the BEA FB-SH-1I0 R

a Reactor Package 3

5/13/2013 Full Review BP-SH-099 jPackaging of Radioactive Material Using MURR 3

1/4/2012 Minor Editorial Model 1500 FM-17 Radiation Work Permit i11 11/19/2013 Minor Editorial FM-27 In-House Radioactive Shipping Request Form 12 9/17/2013 Minor Editorial Control Checksheet for Documentation and 1i Labeling of Radioactive Material Shipment 11

__2/6/2013 MinorEditorial Control Checksheet for Documentation and 1121 7/26/2013 Minor FM-52__ Labeling of Radioactive Material Shipment Editorial FM-62 Radiation Instrument Certificate of Calibration 171 7/11/2013 Cover Page Control Checksheet for Reusable Type A FM-69 Radioactive Materials Shipment (5 to 30 Gallon 8

10/11/2013 Minor Editorial Drums)

FControl Checksheet for Tracerco LS-6 Reusable 78 1 1 eF FM-70

_ IType A Package Radioactive Materials Shipment 7/8/01 NewForm FControl Checksheet for Type B USA DOT 6M 10i FM-74 RaiatvMaeilShp nt14 10/9/2013 Minor Editorial Radioactive Materials Shipment111_____

FM-91 jDeclaration of Pregnancy 51 ]

8/5/2013 Cover Page FM-94 lExclusive Use Shipment Controls 41 2/6/2013 Minor Editorial FM-94 Exclusive Use Shipment Controls j 5 4/29/2013 J Minor Editorial FM-94 jExclusive Use Shipment Controls 11-4 6

7/26/2013 1 Minor Editorial

Number Name JRev eis~ion'fDate N

FM-99 ModlControl checkshees for USA DOT 7A MURR 7112/19/201!

MinorEditorial Model 1500 Series....

FM-129 Control Checksheet for Receipt and Inspection of 3

4/16/2013 Minor Editorial Type B Byproduct Material Shipping Containers_

Control Checksheet for Type B(U) ZA/NNR 1005 FM-135 (Beatrice) Radioactive Materials Shipment I

/821 io dtra FM-137 Type B Qualified Shipper List 1

4/29/2013 Minor Editorial FM-149 Personnel Radiation Dose Estimate 0o 2/7/2013 New Form FControl Checksheet for USA DOT 7A Type A 55-T i

____ 151 Gallon Radioactive Material Package 812/19/2013 Minor FM-154 Control Checksheet for USA DOT 20WC-1 3

4/29/201 Cover Page Overpack Rod Replacement 013 FM-155

  • Quality Assurance Control Checksheet Exterior4/

013 CovePag Painting of USA DOT WC-I, Type B Overpack Required Documentation for Non-MURR Owned FM-156 Type B Shipping Containers 7/26/2013 Minor Editorial RT ive Mate Ship ment6/18/201 Control Checksheet for Type B(U) F-458 Series 2

M FM-15.7

2.

6/18/2013 MinorEditorial Control Checksheet for Type B(U) F-327 Series FM-160 1

10/9/2013 Minor Editorial Radioactive Materials Shipment..

Control Checksheet for Type B(U)

I FM-163 USA/9337/B(U)-96 (LS) Packaging of 1

3/22/2013 Minor Editorial Radioactive Material Control Checksheet for Type B(U)

FM-167 USA/0656/B(U)-96 (Ganuk) Radioactive 0

11/5/2013 New Form Materials Shipping HC-PSO-002 Hot Cell Preparation of Radioactive Material for 9/11/2013 Minor Editorial Shipment HC-PSO-005 Hot Cell Loading of Host Cans 111.

9/11/2013 j

Minor Editorial IC-HP-300 Calibration - Radiation Survey Instruments 77 7/11/2013 Cover Page IC-HP-305 Calibration - Electrostatic Discharge Dosimeter 8

8/2/2013 Cover Page Calibration - Eberline Ping IA Stack Monitor-4/9/2013 M

IC-HP-3 11 Ioin Channel013 Minor Editorial Iodine Channel Calibration - Protean Model WPC 9550 Alpha-7 0e

  • IC-HIP-347 BeaSieCutr9 7/11/2013 Cover Page IC-H-347 Beta Swipe Counter Calibration - Canberra S5XLB-G & Tennelec Series 4 with Gamma, & Tennelec Series 3 Page ICalibration - Lab Impex Stack Monitor-Particulate IC-HP-349 I~anl.4 7/11/20 13 Cover Page Channel

]Calibration - Lab Impex Stack Monitor-Iodine I

IC-HP-350

[Channel 2

8/2/2013 Minor Editorial

  • IC-HP-35 1 Calibration - Lab Impex Stack Monitor-Gas 2

7/11/2013 Cover Page Channel IC-HP-352 ~Calibration - Lab Impex Stack Monitor-Flow IC-ibr-35o 3

7/11/2013 Cover Page IRR-PSO-1 12 Preparing Shipping Paperwork 17 8/13/2013 Minor Editorial OP-HP-200 Air Sampling-Containment Building Tritium 6 1 8/2/2013 f

Cover Page OP-HP-220 Tritium Bioassay 9

8/5/2013 j

Minor Editorial Il-5

Number ::Name Rev. R*ovision Date Notes__:::___:__:_

OP-HP-222 Air Sampling - Containment Building Ar-41 6

2/7/2013 Minor Editorial OP-HP-348 Operation - Protean WPC-9550 Swipe Counter 4

7/11/2013 Cover Page Operation - Lab Impex Stack Monitor - Filter OP-HP-356 Changepand Source4checks 8/5/2013 I Cover Page QAB-SH-002 jProcurement of Type B Packages 2"

2/6/2013 Cover Page QAB-SH-003 Material Control for Type B Shipping Program 3

5/14/2013 Minor Editorial QAB-SH-004 Type B Program Vendor Qualification 3

1 5/14/2013 Cover Page QAB-SH-005 Type B QA Personnel Training 3

2/6/2013 Minor Editorial QAB-SH-006, Type.B Shipping Program,Quality Audits 1

2/6/2013

... Minor Editorial...

QAB-SH-009 jPre-Shipment leak Testing of the Ganuk Shipping Container 0

11/5/2013 New Procedure Stack Monitor Preventive Maintenance - Lab RM-HP-102 m

7/11/2013 Cover Page Impex RP-HP-100 Contamination Monitoring - In Facility

16.

4/3/2013 Minor Editorial RP-HP-105 Transfer of Radioactive Material - In Facility.

71 4/3/2013 Minor Editorial RP-HP-120 IPersonnel Radioactive Contamination 7

4/29/20 13 Minor Editorial RP-HP-120 Personnel Radioactive Contamination 8

8/5/2013 Minor Editorial RP-HP-125 Radiation Monitoring - Performing and RP-HP....

.... Documenting.a.Survey 0

8/5/20.13 New Procedure RP-HP-135 Room 114 Entry -. Self Monitored 6

5/22/2013 Minor Editorial RP-HP-137 Handling Radioactive Material in the Reactor Pool I1 8/5/2013 Cover Page jPost-Irradiation Processing: Exported FloodedMioEdtra SI-PSO-008 6Silicon Cans 6M12/11/201 Edi SV-HP-I 10 Environmental Sampling 5

6/21/2013 Minor Editorial SV-HP-121 I Building Exhaust Stack Effluent - Ar-41 5

8/2/2013 Minor Editorial

..................... M on itoring TPZ-PSO-002 lrradiation of Gemstone Irradiation Containers 6

12/11/2013 Minor Editorial TPZ-PSO-003 Loading Gemstone Irradiation Containers 5

12/11/2013 Minor Editorial TSP-02 ITransportation Security Plan 5

12/19/2013 Minor Editorial WM-SH-100 Radioactive Waste - Preparation and Storage 7

7/26/2013 Cover Page WM-SH-105 Radioactive Waste Processing 8

2/6/2013 I Minor Editorial WM-SH-105 Radioactive Waste Processing..

9 7/26/2013 Cover Page Exclusive Use Shipment of LSA or SCO 11lT 6/18/2013 Minor Editorial WRadioactive Waste WM-SH-300 lExclusive Use Shipment of LSA or SCO Radioactive Waste 12 11/20/2013 Cover Page I1-6

SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT January 1, 2013 through December 31, 2013 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, pages 3-11, Figure 3.2, Grade Level Plan (as revised by the 1972-1973, 1979-1980, 1990-1991, 1995, 1996 and 2012 Reactor Operations Annual Reports):

Replace with:

Updated Figure 3.2, Grade Level Plan (MURR Dwg No. 1145, Sheet 2 of 5)

Original HSR, pages 7-19, Section 7.2.7 (as revised by the 1974-75, 1989-1990 and 1995 Reactor Operations Annual Reports):

Delete:

"...beamport ventilation air, air which is drawn from the surface of the pool and exhaust from the film irradiator shield box."

Replace with:

"...beamport ventilation air and air which is drawn from the surface of the pool."

Original HSR, pages 7-20, Section 7.2.9, Table 7.1 (as revised by the 1974-75, 1995, 2001, 2002, 2007 and 2008 Reactor Operations Annual Reports):

Delete:

The following from Table 7.1 under Staff Stations:

"Room 288 Health Physics Office" Add:

The following to Table 7.1 under Staff Stations:

"Room 271B Health Physics Office" Original HSR, pages 7-21, Section 7.2.9, Table 7.2 (as revised by the 1995, 2001, 2007, 2009. 2011 and 2012 Reactor Operations Annual Reports):

Add:

The following after "Room 299":

"Corridor C299D Room 299N Room 299P Room 299Q" Original HSR, pages 9-7 through 9-9, Table 9.2 (as revised by the 1981-82, 1985-86, 1995, 2000, 2001, 2002. 2006 and 2007 Reactor Operations Annual Reports):

Add:

"137 Isolated Power Supply (EP 91 IC) - TE-980 A/B" III-I

Add:

Add:

"138 Rod Run-In System Monitoring Circuit" "139 T-300 & T-301 Water Level Display" Original HSR, Figure 9.3, Instrument Panel Layout (as revised by 1995, 2001, 2004 and 2006 Reactor Operations Annual Reports):

Replace with:

Updated Figure 9.3, Instrument Cabinet (MURR Dwg No. 74, Sheet 12 of 12)

Original HSRI Figure 9.5, Rod Run-In System (as revised by 1995 and 2001 Reactor Operations Annual Reports):

Replace with:

Updated Figure 9.5, Rod Run-In System (MURR Dwg #140, Sheet 1 of 1, dated 9/10/13)

ADDENDUM 3 - HAZARDS

SUMMARY

REPORT (AUGUST 1972)

HSR, Addendum 3, page 15, Figure 2.2.b, Secondary Coolant System (as added by the 2012 Reactor Operations Annual Report):

Replace with:

Updated Figure 2.2.b, Secondary Cooling System (MURR Dwg No. 502, Sheet 2 of 3, dated 4/24/13)

HSR, Addendum 3, page 18, Figure 2.3.a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):

Replace with:

Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of 5, dated 8/20/13)

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, 2007, 2009, 2010, 2011 and 2012 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 10/4/13)

HSR, Addendum 3, page 23c, Figure 2.3.c, Electrical Distribution (as added by the 2004 and revised by the 2005, 2007, 2009, 2010, 2011 and 2012 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 8/27/13)

HSR, Addendum 3, page 23d, Figure 2.3.d, Electrical Distribution (as added by the 2007 and revised by the 2008, 2009, 2010, 201 land 2012 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, dated 8/27/13) 111-2

HSR, Addendum 3, page 23e, Figure 2.3.e, Electrical Distribution (as added by the 2007 and revised by the 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):

Replace with:

Updated Figure 2.3.e, Electrical Distribution North Office Addition Panels (MURR Dwg No. 522, Sheet 5 of 5, dated 10/7/13)

ADDENDUM 4 - HAZARDS

SUMMARY

REPORT (OCTOBER 1973)

HSR, Addendum 4, page A-22, Figure A.4.a, Reactor Control System - 10 MW (as revised by 1995, 2001, 2004, 2006 and 2007 Reactor Operations Annual Reports):

Replace with:

Updated Figure A.4.a, Reactor Control System (MURR Dwg No. 42, Sheet 1 of 2, dated 8/22/13)

HSR, Addendum 4, page A-25, Figure A.6, 10 MW Process Instrumentation Control & Interlock (as revised by the 1995, 2001, 2002, 2003, 2005 and 2006 Reactor Operations Annual Reports):

Replace with:

Updated Figure A.6, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 2 of 4, dated 8/22/13)

HSR, Addendum 4, page A-26, Figure A.7, Annunciator Control 10 MW (as revised by the 1995, 2001, 2002, 2005, 2006, 2007, 2008 and 2012 Reactor Operations Annual Reports):

Replace with:

Updated Figure A.l, Annunciator Control 10 MW (MURR Dwg No. 138, dated 9/11/13)

HSR, Addendum 4, page A-29, Figure A.I1, Schematic Diagram of Laboratory and Containment Building Ventilation Systems (as revised by the 1995, 2002, 2005, 2009, 2010, 2011 and 2012 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 8/19/13)

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, 2007, 2009, 2010, 2011 and 2012 Reactor Operations Annual Reports):

Replace with:

Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet I of 5, dated 8/20/13) 111-3

As a result of the issuance of Amendment No. 36 to Amended Facility License No. R-103 on July 8, 2013, the following changes to the MURR Hazards Summary Report and its addenda were performed:

ADDENDUM 3 - HAZARDS

SUMMARY

REPORT (AUGUST 1972)

HSR, Addendum 3, Section 3.3, Evaluation of Peaking Factors in the MURR 6.2 Kg Core Delete:

Entire section.

Replace with:

Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 11).

ADDENDUM 4 - HAZARDS

SUMMARY

REPORT (OCTOBER 1973)

HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR Delete:

Entire section.

Replace with:

Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 11).

HSR, Addendum 4, Appendix H, Bases for Limiting Safety System Settings for Modes I and I!

Operation Delete:

Entire section.

Replace with:

Revised HSR, Addendum 4, Appendix H, Bases for Limiting Safety System Settings for Modes I and II Operation, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 12).

ADDENDUM 5 - HAZARDS

SUMMARY

REPORT (JANUARY 1974)

HSR, Addendum 5, Section 6, Addendum to the Safety Limit Analysis for the MURR Delete:

Entire section.

Replace with:

Revised HSR, Addendum 4, Appendix F, Safety Limit Analysis for the MURR, as submitted with the application to amend Amended Facility License No. R-103, dated August 19, 2011 (Attachment 1I).

111-4

SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2013 through December 31, 2013 For each facility modification described below, 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 11-03, Addendum 1:

Addition of Blow-Down Meter to the Data Acquisition Monitoring System This addendum to modification record 11-03, "Data Acquisition and Monitoring System for Secondary Coolant System" documents the installation of an additional component to the Data Acquisition and Monitoring System for the Secondary Coolant System. A secondary coolant blow-down transmitter and associated indication were installed to assist in monitoring the amount of secondary coolant that is required to be discharged to the sanitary sewer in order to maintain appropriate Secondary Coolant System chemistry control.

Modification 12-01:

Replace PT-944A/B with Rosemount Transmitters This modification record documents the replacement of two pressure transmitters, PT-944A and PT-944B, which sense reactor core outlet pressure in the Primary Coolant System. The previous pressure transmitters could not be directly replaced due to obsolescence of both the transmitters and repair parts.

The replacement pressure transmitters meet or exceed the performance specifications of the previous transmitters.

Modification 12-02:

Control Blade Fabrication Alternative Using Laser Welding This modification record documents a fabrication alternative for construction of the control blades. An assembly method using laser welding on the edge channels required a change in the edge channel alloy. A more streamlined connection between the top mounting plate and the BORALC absorber plate was also documented.

Modification 13-01:

Replacement of TE-980A and TE-980B Power Supply 2PS5 This modification record documents replacement of the power supplies for the temperature instrument channels on Primary Heat Exchanger outlet temperatures, TE-980A and TE-980B. The previous power supply, 2PS5, was obsolete and unavailable for purchase. The replacement power supply EP-91 IC meets or exceeds the performance specifications of the previous power supplies, and was relocated from behind the Instrument Cabinet to the former General Electric Measurement and Control (GE/MAC) rack on the Instrument Cabinet face.

IV-I

Modification 04-03, Addendum 1:

Liquid Radioactive Waste System In MURR Industrial Building This addendum to modification record 04-03, "Liquid Radioactive Waste Modification" documents the changes required to incorporate the MURR Industrial Building (MIB) Liquid Radioactive Waste (LRW) system into the existing facility LRW system.

Modification 75-01, Addendum 3:

Rod Run-In Electronic Circuit Jumper Panel This addendum to modification record 75-01, "Electronic Circuits Jumper Panel" documents the installation of a jumper panel dedicated to the rod run-in system. This jumper panel supports the use of the rod run-in system monitoring circuit installed under Modification Record 13-04.

Modification 13-04:

Rod Run-In Monitoring System This modification record documents the implementation of a passive monitoring circuit on the rod run-in system to improve troubleshooting capabilities for rod run-in signals that are too short in duration to detect with the annunciator system.

The monitoring circuit works in conjunction with a new jumper panel dedicated to the rod run-in system, and provides additional unused monitoring capacity for future troubleshooting expansion.

The monitoring circuit was constructed in a manner similar to the reactor scram system monitoring circuit.

Modification 13-02:

Replacement of Secondary Chemistry Controllers This modification record documents the replacement of the Secondary Coolant System pH and conductivity controllers. The previous model controllers had become obsolete and repair parts were no longer available.

The replacement controllers meet or exceed the performance specifications of the existing controllers.

Modification 13-03:

Replacement of the GH and IJ Wedge with a Single 60-Degree Wedge This modification record documents the redesign and replacement of the 30-degree "GH" and "IJ" graphite reflector elements with a single 60-degree graphite reflector element (GHIJ). The new reflector element accommodates a 6-inch irradiation position as well as a 3-inch, two 2-inch and two 1-inch irradiation positions designated G-6, B-3, B-2 and R-2, G-I and H-I, respectively. The 6-inch irradiation position is designed such that a sleeve insert with nickels bands may be installed to allow for manipulation of the flux profile. This insert is bolted securely to the element cover plate, and is inserted and/or removed only when the reactor is shutdown. The reflector element is constructed of aluminum 6061-T6 with graphite in the void area.

Modification 04-05, Addendum 8:

Cooling Tower Electrical Arc Flash Danger Mitigation This addendum to modification record 04-05, "Cooling Tower Electrical Upgrade Project" documents the changes to Motor Control Center 1 in order to provide for improved arc flash protection and subsequent classification reduction of the cooling tower motor control center.

IV-2

Modification 01-02, Addendum 9:

Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299)

Renovations This addendum to modification record 01-02, "Installation of a New Reactor Facility Intercommunication and Paging System" documents changes to the facility Intercommunication and Paging System that will enhance communications in Rooms 299M, N and 0.

Modification 01-02, Addendum 10:

Intercommunication and Paging System Changes in Support of MURR Industrial Building (Room 299),

Room 243, Room 246 and Room 271 Renovations This addendum to modification record 01-02, "Installation of a New Reactor Facility Intercommunication and Paging System" documents changes to the facility Intercommunication and Paging System that will enhance communications in MURR Industrial Building (Room 299), Room 243, Room 246 and Room 271B. It also documents the relocation of the Health Physics Office staff station from Room 288 to Room 271B.

Modification 13-05:

T-300 & T-301 Level Sensing System This modification to the Reactor Plant Make-Up Water Storage Tank System documents the replacement of the previous level sensing and annunciating instrument channels with current loop transmitters that also display the tank levels in the Control Room.

Modification 13-06:

Modifications to MURR Industrial Building (Room 299) in Support of the NS-99 Proiect This modification record documents the remodeling of portions of the MURR Industrial Building (Room 299) to provide the necessary space needs and services required to support the dispensing system for the NS-99 Project.

IV-3

SECTION V NEW TESTS AND EXPERIMENTS January 1, 2013 through December 31, 2013 New tests and experiments approved during this period under a Reactor Utilization Request (RUR) or Reactor License (RL) Project are as follows:

RUR 441: Natural Uranium Oxide Irradiation

==

Description:==

This RUR authorizes the irradiation of up to 5.0 grams of natural Uranium Oxide in the reflector region of the reactor in support of research and development activities for medical applications.

RUR 271, as amended: Yttrium Microspheres:

==

Description:==

This RUR was amended twice during calendar year 2013. The first amendment authorizes the use of quartz as a primary encapsulation and removed the requirement for the secondary encapsulation of aluminum for the microsphere targets.

A second amendment to RUR 271 authorizes the use of discs, a different physical form of the same target material for irradiation.

RL-80: Selective Gaseous Extraction of Fission Products

==

Description:==

This RL authorizes the processing of up to 5.0 grams of natural Uranium Oxide to investigate Selective Gaseous Extraction as a novel separation process for producing radioisotopes from the fission of uranium.

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

SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2013 through December 31, 2013 Inspections:

There was one NRC inspection reviewing Special Nuclear Material (SNM) activities. All records and activities were found to be in compliance with NRC rules and regulations. No violations were noted.

Reactor Characteristic Measurements:

Sixty-six (66) refueling evolutions were completed in 2013. Excess reactivity verification was performed for each refueling. The largest measured excess reactivity was 3.32%. MURR Technical Specification

3. 1(f) requires the 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.

Four (4) reactivity measurements were performed to determine the reactivity worth of various sample cans irradiated in the flux trap region, including the worth of an empty sample holder.

Two (2) measurements were performed to determine the reactivity worth of the newly constructed GHIJ 60-degree graphite reflector element and the target irradiation positions associated with the new reflector element.

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-I

SECTION VII RADIOACTIVE EFFLUENT January 1, 2013 through December 31, 2013 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2013 through December 31, 2013 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide H-3 S-35 Lu-177 Co-60 Ca-45 P-32 Mo-99 Zn-65 W-181 Cr-51 Ag-110m Sc-46 Tc-99m 1-131 As-76 Total H-3 Total Other Activity (Ci) 9.816E-02 7.312E-03 6.619E-03 2.256E-03 1.558E-03 1.384E-03 9.858E-04 6.517E-04 3.125E-04 5.560E-05 3.384E-05 3.075E-05 2.664E-05 1.592E-05 1.052E-05 9.816E-01 2.128E-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 1,2013 through December 31, 2013 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration Total Release TS Limit Multiplier

% TS (pCi/ml)

(Ci)

Ar-41 2.73E-06 1.22E+03 350 78.1054 H-3 2.21E-08 9.89E+00 350 0.0633 Kr-79 6.72E-09 3.OOE+00 350 0.0274 1-131 3.38E-14 1.51E-05 1

0.0169 K-40 6.02E-14 2.69E-05 1

0.0100 C-14 2.48E-11 1.13E-02 1

0.0083 Co-60 2.70E-15 1.21E-06 1

0.0054 1-125 1.12E-14 4.99E-06 1

0.0037 Sn-113 2.55E-15 1.14E-06 1

0.0003 Xe-135m 1.94E-11 8.65E-03 350 0.0001 Os-191 2.04E-15 9.12E-07 1

0.0001 1-133 1.96E-13 8.76E-05 350 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 = -30,000 cfm Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, License R-103 Technical Specifications.

VII-2

SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2013 through December 31, 2013 Environmental samples are collected two times per year at eight (8) locations and analyzed for radioactivity. Soil and vegetation samples are also taken at each location. Water samples are taken at three (3) of the eight (8) locations. Subsurface soil monitoring commenced in 2013 with six (6) samples taken each period. Analytical results are shown in Tables 1 and 2.

Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2013. All doses are approximately 20 mRem/year or less, except monitor numbers 9 and 15. 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. Additionally, during 2013, six (6) monitoring sites around the reactor facility were chosen for subsurface soil monitoring. The subsurface results are presented along with the traditional monitoring locations and results. The environmental monitoring program confirms that minimal 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 83 Spring 2013 Detection Limits]

Matrix Water Soil Vegetation Subsurface Soil Alpha 0.00 pCi/L 0.58 pCi/g 0.00 pCi/g 1.00 pCi/g Beta 3.14 pCi/L 3.47 pCi/g 8.94 pCi/g 3.32 pCi/g Gamma 189.00 pCi/L 0.61 pCi/g 1.53 pCi/g 0.57 pCi/g Tritium 5.26 pCi/mL of sample N/A 6.33 pCi/mL of distillate N/A Activity Levels - Vegetation Sample I V83 2V83 3V83 4V83 5V83 6V83 7V83 10V83 Aloha (oCi/g) 0.35 0.35 0.00 0.35 0.00 0.70 1.38 0.70 Beta (pCi/g) 42.78 30.53 23.13 36.54 32.50 32.40 25.16 46.64 Gamma (pCi/g) 2.52 2.25

< 1.53

< 1.53

< 1.53 2.29

< 1.53 2.97 H-3 (pCi/mL)

< 6.33

< 6.33

< 6.33

< 6.33

< 6.33

< 6.33

< 6.33

<6.33 VIII-I

TABLE 1 (Cont'd)

SUMMARY

OF ENVIRONMENTAL SET 83 Spring 2013 Activity Levels - Soil Sample IS83 2S83 3S83 4S83 5S83 6S83 7S83 10S83 Alpha (pCi/g) 1.47

<0.58

<0.58 1.15 2.03 1.67 1.15

<0.58 Beta (pCi/g) 21.85 19.10 16.50 21.16 23.04 14.98 27.91 26.60 Gamma (pCi/g) 3.46 0.97 2.64 1.72 1.09 2.21 1.96 2.29 Activity Levels - Water Sample 4W83 6W83 10W83 Alpha (pCi/L) 1.06 0.18 0.35 Beta (pCi/L) 3.75 4.12 12.36 Gamma (pCi/L)

< 189.00

< 189.00

< 189.00 H-3 (pCi/mL)

< 5.26

< 5.26

< 5.26 Activity Levels - Subsurface Soil Sample PSS83 NESS83 NSS83 WSS83 ESS83 SSS83 Alpha (1Ci/2) 1.50 1.50 1.50 1.50

< 1.00 1.32 Beta (pCi/g) 26.88 25.00 27.81 22.38 21.26 18.82 Gamma (pCi/g) 3.95 5.51 3.18 3.64 4.18 5.81 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-2

TABLE 2

SUMMARY

OF ENVIRONMENTAL SET 84 Fall 2013 Detection Limits' Matrix Water Soil Vegetation Subsurface Alpha 0.00 pCi/L 0.73 pCi/g 2.53 pCi/g 0.82 pCi/g Beta 3.64 pCi/L 3.98 pCi/g 7.98 pCi/g 4.35 pCi/g Gamma 222.00 pCi/L 0.55 pCi/g 1.56pCi/g 0.62 pCi/g Tritium 5.68 pCi/mL of sample N/A 5.21 pCi/mL of distillate N/A Activity Levels - Vegetation Sample 1 V84 2V84 3V84 4V84 5V84 6V84 7V84 10V84 Alpha (oCi/,)

< 2.53

< 2.53

< 2.53

<2.53

< 2.53

< 2.53

<2.53 2.84 Beta (pCi/g) 33.88 39.64 17.26 21.19 27.72 12.91 39.32 31.95 Gamma (pCi/g) 2.51 1.86 2.81 1.97

< 1.56

< 1.56

< 1.56

< 1.56 H-3 (pCi/mL)

< 5.21

< 5.21

< 5.21

< 5.21

< 5.21

< 5.21

< 5.21

< 5.21 Activity Levels - Soil Sample 1S84 2S84 3S84 4S84 5S84 6S84 7S84 10S84 Alpha (pCi/g)

< 0.73

< 0.73

< 0.73

< 0.73

< 0.73

< 0.73 1.77 1.26 Beta (pCi/g) 20.18 10.35 17.93 10.71 21.52 13.11 17.13 21.68 Gamma (pCi/g) 3.32 2.44 2.76 2.79 4.53 2.93 4.57 3.52 VIII-3

TABLE 2 (Cont'd)

SUMMARY

OF ENVIRONMENTAL SET 84 Fall 2013 Activity Levels - Water Sample 4W84 6W84 10W84 Alpha (pCi/L) 0.63 0.16 0.00 Beta (pCi/L) 6.52

< 3.64 10.11 Gamma (pCi/L)

< 222.00

< 222.00

< 222.00 H-3 (pCi/mL)

<5.68

< 5.68

< 5.68 Activity Levels - Subsurface Soil Samole PSS84 NESS84 NSS84 WSS84 ESS84 SSS84 Alpha (VCi/g) 1.07 0.87 1.57 0.88 1.06 2.14 Beta (pCi/g) 22.51 22.62 26.15 21.16 21.91 23.46 Gamma (pCi/g) 6.23 4.24 4.47 3.16 4.76 5.48 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-4

TABLE 3 ENVIRONMENTAL TLD

SUMMARY

January 1, 2013 through December 31, 2013 Badge Direction Map Distance from 1st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Number From MURR MURR Stack 2013 2013 2013 2013 (meters)

Net mR Net mR Net mR Net mR Total 2013 Net mR 1

2 3

4*

5*

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42*

43*

44 45 46 Control 0 Control 1 Control 2 WSW N/A 16600 16600 N/A N

NE SW S

NE NW ENE NNE S

S SE E

NE NNE NE SE ESE NW SSW SSW SW WSW WNW NW NNW NNW NNW E

ENE SSE SE NE NW W

N NNE Spare S

E 34 57 27 27 149 149 301 316 156 65 107 293 476 606 907 236 168 110 328 480 301 141 210 255 328 671 724 671 587 499 419 690 556 491 541 137 N/A 65 70 28.0 27.0 24.0 0.0 0.0 4.0 6.0 22.0 0.0 0.0 0.0 0.0 0.0 19.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 2.0 0.0 0.0 0.0 0.0 0.0 5.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 7.0 0.0 23.0 23.0 22.0 0.0 1.0 2.0 4.0 20.0 0.0 0.0 2.0 0.0 3.0 15.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 5.0 0.0 0.0 0.0 0.0 0.0 0.0 missing 4.0 0.0 25.0 24.0 24.0 0.0 5.0 5.0 3.0 15.0 0.0 2.0 3.0 0.0 0.0 14.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3.0 0.0 0.0 3.0 4.0 0.0 0.0 1.0 0.0 0.0 2.0 0.0 0.0 1.0 0.0 0.0 0.0 missing 6.0 0.0 33.0 32.0 31.0 0.0 9.0 1.0 2.0 26.0 0.0 0.0 2.0 0.0 0.0 17.0 0.0 0.0 0.0 0.0 0.0 1.0 0.0 3.0 0.0 0.0 0.0 0.0 1.0 0.0 0.0 0.0 0.0 0.0 0.0 4.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3.0 0.0 109.0 106.0 101.0 0.0 15.0 12.0 15.0 83.0 0.0 2.0 7.0 0.0 3.0 65.0 0.0 0.0 0.0 0.0 0.0 1.0 0.0 3.0 0.0 3.0 0.0 0.0 4.0 6.0 0.0 0.0 1.0 0.0 0.0 16.0 0.0 0.0 1.0 0.0 0.0 0.0 0.0 20.0 0.0

  • These badge numbers are no longer used.

VIII-5

TABLE 4 NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS January 1,2013 through December 31, 2013 Radiation January February March April May June July August September October November December TOTALS 94 60 97 61 87 97 94 97 80 101 85 74 Surface Contamination*

94 60 97 61 87 97 94 97 80 101 85 74 1027 Air Samples**

59 44 45 43 36 49 62 63 62 66 45 11 585 RWPs 10 7

9 8

8 4

7 10 8

6 10 9

96 1027 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 resigned as Assistant Health Physics Manager in August 2013.

During calendar year 2013, MURR shipped 554 cubic feet of low-level radioactive waste containing 1.205 mCi of activity.

VIII-6

SECTION IX Summary of Radiation Exposure to Facility Staff, Experimenters and Visitors January I, 2013 through December 31, 2013 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP January February March April May June July August September October November December AC 12 18 39 14 15 3

0 15 0

7 2

21 BCS 2

3 7

0 10 0

6 13 2

13 2

8 DO 10 0

0 0

0 0

0 1

0 4

4 7

FOE HC/SH HP IRR 4

419 128 7

6 346 90 6

17 534 121 3

0 450 207 13 0

414 109 3

7 434 219 0

0 340 89 9

3 335 122 7

5 310 II1 2

3 348 146 7

8 411 178 0

2 282 101 5

NA NS OPS PRO QA RES lIP SIL TEE WC Total 6

52 1443 121 29 10 47 140 0

27 2457 9

62 1169 72 8

37 13 107 0

121 2067 11 34 1371 77 25 24 35 87 0

99 2484 11 22 1352 109 7

4 48

  • 86 5

254 2582 2

21 1612 127 65 2

22 78 0

19 2499 4

84 1995 109 63 100 38 177 4

38 3275 12 1

1651 153 42 11 25 168 0

16 2523 15 54 2042 139 82 6

44 224 4

17 3123 27 42 1598 129 47 4

246 137 8

39 2707 22 62 1666 130 85 9

65 94 2

101 2764 21 112 1865 117 21 2

28 411 0

37 3219 42 58 1725 171 32 7

30 114 2

23 2630 Total for Year 146 Monthly Avg 12 66 26 55 4623 1621 62 6

2 5

385 135 5

182 604 19489 1454 506 216 641 1823 25 15 50 1624 121 42 18 53 152 2

64 212 1236 407 154 144 311 998 8

2929 370 1556 5524 513 538 1832 1237 168 791 32330 66 2694 Highest WB 31 26 6

25 1565 425 57 (annual)

High EXT 479 58 NR NR 3397 866 NR (annual) 241 893 AC - Analytical Chemistry BCS - Business & Central Services DO - Director's Office FOE - Shops & Support HC/SH - Hot Cell/Shipping HP - Health Physics IRR - Irradiations NA - Nuclear Analysis NS - Neutron Scattering OPS - Operations PRO - Isotope Processing QA - Quality Assurance RES - Research RP - Radiopharmaceutical SIL - Silicon TEE - Trace Elemental Epidemiology WC - Work Control WB = Whole Body EXT = Extremities M = Minimal NR = None Reported 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.

NOTES:

Dosimetry services are provided by Mirion Technologies (except self reading dosimetry).

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