ML070640055
| ML070640055 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 02/28/2007 |
| From: | Foyto L Univ of Missouri - Columbia |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML070640055 (43) | |
Text
Research Reactor Center University of Missouri-Columbia 1513 Research Park Drive Columbia, MO 65211 PHoNE (573) 882-4211 FAX (573) 882-6360 WEBsITE http://web.missouri.edu/-murrwww February 28, 2007 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop 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 2006 Reactor Operations Annual Report I have enclosed one copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2006 through December 31, 2006.
This document is submitted to the U.S. Nuclear Regulatory Commission in accordance with the University of Missouri Research Reactor Technical Specification 6.1.h (4).
If you have any questions regarding the contents of this report, please contact me at (573) 882-5276.
Sincerely, Les Foyto Reactor Manager Enclosure xc: Mr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC A74QcO FIGHTING CANCER WITH ToMoRRow's TECHNOLOGY
,OF MNISSoUI UNIVERSITY OF MISSOURI R ElSEARCHUREACTOR REACTOR. OPERTIONS
ý.ANNUALUREPORT January 1, 2006 - December 31, 2006
UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2006 through December 31, 2006 Compiled by the Research Reactor Staff Submitted February 2007 by:
Leslie P. FoYto Reactor Manager Reviewed and-Approved by:
Ralph A. Butler, PE Director
UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2006 through December 31, 2006 INTRODUCTION The University of Missouri Research Reactor (MURR) is a multi-disciplinary research and education facility providing a broad range of analytical, materials science, and irradiation services to the research community and the commercial sector.
Scientific programs include research in archaeometry, epidemiology, health physics, human and animal nutrition, nuclear medicine, radiation effects, radioisotope studies, radiotherapy, and nuclear engineering; and research techniques including neutron activation analysis, neutron and gamma-ray scattering, and neutron interferometry.
The heart of this facility is a:
pressurized, reflected, open pool-type, light water moderated and cooled, heterogenous reactor designed for operation at a maximum steady state power level of 10 Megawatts thermal - the highest powered University-owned research reactor in the United States.
The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2006.
Included within this report are changes to MURR procedures, revisions to the Hazards Summary Report, facility modifications, new tests and experiments, reactor physics activities, and environmental and health physics data.
This Report is being submitted to the U.S. Nuclear Regulatory Commission to meet the administrative requirements of MURR Technical Specification 6.1.h (4).
ACKNOWLEDGMENTS The success of MURR and these scientific programs is due to the dedication and hard work of many individuals and organizations. Included within this group are: the University administration; the governing officials of the State of Missouri; the Missouri State Highway Patrol; the City of Columbia Police Department; the Missouri University Police Department; the Federal Bureau of Investigation (FBI); our Regulators; those who have provided funding including the Department of Energy (DOE); the Researchers; the Students; the Columbia Fire Department; the Campus Facilities organization; members of the National Organization of Test, Research, and Training Reactors; 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.
Three major facility projects were completed this calendar year and in each of these, Operations played a vital role. The first was the replacement of the beryllium reflector that surrounds the reactor core. This is a planned evolution that is performed approximately every eight years and takes about seven to nine days to complete, including low power physics testing. During this time the necessary piping and equipment are disassembled, the old beryllium is removed and the new one is inserted, and then all piping and equipment that was disassembled is once again reassembled. This outage also afforded us the opportunity to retract Beamports 'A', 'B', and 'C' in order to replace the graphite reflector elements in positions 1, 2, 3 and 4.
These reflector elements were approaching the end of their operational lifetime.
i
The second major project was the submittal of the facility's relicensing application to the U.S. Nuclear Regulatory Commission for authorization to operate the reactor for an additional 20 years. Included within this application was an updated Safety Analysis Report. The format and content of this document followed the guidance of NUREG-1537, "Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors."
Efforts were directed to assure that each chapter of the Safety Analysis Report contained the technical content and necessary information requested by NUREG-1537, including the updating of regional demographic, hydrological, seismological, and meteorological data, and performing accident analyses using newer, updated computer codes and methodologies.
The preparation of this document, and also the Environmental Report, represented the collective cooperation, support and efforts of many individuals, including members of the facility staff and external organizations.
The final major project that was completed in 2006 was the replacement of the primary and pool coolant system heat exchangers.
Two shell and tube-type and one plate-type heat exchanger, which were approaching the end of their operational lifetime, were replaced with three new plate-type heat exchangers.
Beamports 'D', 'E' and 'F' were also retracted during this outage in order to replace the graphite reflector elements in positions 7 and 8. Within the last two years, ten of the twelve graphite reflector elements have been replaced, thus ensuring continued reliable operation.
The facility is also actively collaborating with the US-RERTR (Reduced Enrichment for Research and Test Reactors) Program and four other U.S. high-performance research reactor facilities that use highly-enriched uranium (HEU) fuel to find a suitable low-enriched uranium (LEU) fuel replacement. Although each one of the five high-performance research reactors is responsible for its own feasibility and safety studies, regulatory interactions, fuel procurement, and conversion, there are common interests and activities among all five reactors that will benefit from a coordinated, working-group effort.
Reactor Operations Management also wishes to commend the four individuals who received their Senior Reactor Operator and Reactor Operator certifications from the U.S. Nuclear Regulatory Commission.
These individuals participated in a rigorous training program of classroom seminars, self-study, and on-the-job training.
The results of this training are confident, well-versed, decisive individuals capable of performing the duties of licensed operators during normal and abnormal situations.
ii
TABLE OF CONTENTS Section Title Pages I.
Reactor Operations Summary...............................................................
I-1 through 9 II.
M U RR Procedures................................................................................
11-1 through 7 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..........................................
ii1-1 through 7 IV.
Plant and System M odifications...........................................................
IV-1 through 4 V.
New Tests and Experiments.............................
V-1 VI.
Special Nuclear Material and Reactor Physics Activities................ VI-1 VII.
Radioactive Effluent.............................................................................
VII-l through 2 Table 1 - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII.
Environmental Monitoring and Health Physics Surveys...................... VIII-1 through 5 Table 1 - Summary of Environmental Set 69 Table 2 - Summary of Environmental Set 70 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, 2006 through December 31, 2006 The following table and discussion summarize reactor operations during the period from January 1, 2006 through December 31, 2006.
Full Power % of Full Power % of Month Full Power Hours Megawatt Days Total Time Scheduled~')
January 478.50 199.78 64.3 93.0(2)
February 624.74 260.49 93.0 104.1 March 677.61 282.45 91.1 102.0 April 638.47 266.11 88.7 99.5 May 665.57 277.42 89.5 100.2 June 655.92 273.47 91.1 102.2 July 657.22 273.95 88.3 98.9 August 662.73 276.32 89.1 99.7 September 668.04 278.41 92.8 104.1 October 657.91 274.24 88.4 99.0 November 645.84 269.20 89.7 100.6 December 546.49 227.95 73.5 106.2(3)
Total for 7579.04 3159.79 86.61%
100.78 %
the Year I
(')MURR is scheduled to average at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> of full power operation per week. Total time is the number of hours in the month listed or the year.
(2)The reactor was shutdown for one week in January for the scheduled replacement of the beryllium reflector. This week is not included in the "Full Power % of Scheduled" operating time.
(3)The reactor was shutdown for one week in December for the scheduled replacement of the primary and pool coolant system heat exchangers. This week is not included in the "Full Power % of Scheduled" operating time.
January 2006 The reactor operated continuously in January with the following exceptions:
six shutdowns for scheduled maintenance and/or refueling, and three unscheduled/unplanned power reductions. NRC regional inspector arrived at MURR to observe and perform a special inspection of the beryllium replacement outage.
On January 21, an "Evacuation or Isolation" reactor scram was automatically initiated when a momentary disruption of site electrical power occurred at the facility. The loss of power was confirmed with the University power plant.
The operability of all systems was verified; the reactor was refueled, and subsequently restarted to 10 MW operation.
On January 23 during a reactor startup, the reactor was manually shutdown when Nuclear Instrumentation Wide Range Monitor (WRM) indication indicated low in comparison to the other Nuclear Instruments. Upon investigation, it was determined that the WRM compensated ion chamber (CIC) detector was positioned approximately three feet 1-1
from the bottom of the drywell. Earlier that day, the WRM CIC detector was replaced due to degradation of the detector cabling insulation. Using a camera, it was ascertained that there was a weld seam where the dry well transitioned from a non-anodized to an anodized surface. After repeated attempts to insert the detector past this weld area were unsuccessful, the anodized sleeve, which insulates the detector, was removed and replaced with glass bead insulating tape. This provided sufficient clearance to insert the detector to the bottom of the drywell. Operability of the detector was verified with the neutron source and the reactor was subsequently restarted to 10 MW operation.
Note: The WRM provides no reactor safety functions nor is it required for reactor operations; therefore, no deviation from Technical Specification Limiting Conditions of Operation for high power rod run-in or reactor scram occurred.
On January 26, a "Channel 4, 5, & 6 Hi Power" rod run-in was automatically initiated when Nuclear Instrumentation (NI) Channel No. 5 exceeded its rod run-in set point of 114% while pulling the sample holder out of the N6 irradiation position in the graphite reflector region. The sample holder had become slightly bound, and after applying greater force, became free and was withdrawn at a rate which caused the rod run-in. The rod run-in was reset and the reactor was restored to 10 MW operation.
A new holder was placed in service and loaded with spacers until corrective actions could be determined. This graphite reflector element was subsequently replaced.
Major maintenance items for the month included: completing Modification Record 05-10, "Replace Pressure Vessel Tie-Rod Clevis Pins with Instrumented Load-Cell Clevis Pins;" completing Modification Record 04-5, "Cooling Tower Electrical Upgrade Project;" completing Modification Record 04-5, Addendum 5, "Phase 5 of the Cooling Tower Electrical Upgrade Project - Upgrade Secondary Pump Motors to 150 HP Motors;" replacing the filter cartridges in pool coolant demineralizer system inlet filter housing F-200; replacing reactor safety system relay 2K12; replacing the nuclear instrumentation wide range monitor compensated ion chamber detector; installing a harmonic filter on secondary coolant pump SP-2 adjustable speed drive; and back-flushing beamport 'A' with helium.
In addition to the items listed above, the reactor was shutdown for approximately nine days to replace the beryllium reflector that surrounds the reactor core. During this planned extended shutdown, which is performed approximately every eight years, the following tasks were accomplished in addition to replacing the beryllium reflector: rebuilding anti-siphon isolation valves V543A and V543B; rebuilding in-pool heat exchanger isolation valves V546A and V546B; replacing primary coolant system water addition check valves V550C and V550D; replacing graphite reflector elements 1, 2, 3, 4 and 5A; performing a reactivity worth measurement to characterize the new beryllium and graphite reflector elements; and performing a reactivity measurement in accordance with RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-11 (D)," in order to determine the new worth values of all four shim control blades and the regulating blade.
February 2006 The reactor operated continuously in February with the following exceptions:
seven shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: replacing the mechanical seal and bearings on primary coolant demineralizer pump P-513A; performing a flux profile measurement of the center test hole region; performing a reactivity worth measurement in accordance with RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-1 7(B);" and performing a reactivity measurement for a Nuclear Engineering practicum in accordance with RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-11 (D)."
1-2
March 2006 The reactor operated continuously in March with the following exceptions:
four shutdowns for scheduled maintenance and/or refueling, and two unscheduled/unplanned power reductions.
On March 8, a "Pool Loop Low Flow" reactor scram was automatically initiated with no corresponding indication of a low flow condition on the chart recorder or an associated low flow alarm on the annunciator panel. Power supply voltages and all wiring connections were checked with no abnormalities discovered. Compliance Procedure No. 7B (CP-7B) was performed to verify scram set point and transmitter calibration - both were within specification. A multi-meter was connected to the chart recorder test points to continuously monitor the instrumentation current loop.
Another multi-meter was connected across the output signal of Dual Alarm Unit EP-920A/B. The multi-meters were selected to the MIN function, which would record the lowest current reading during a transient. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
On March 11, a "Pool Loop Low Flow" reactor scram was automatically initiated with no corresponding indication of a low flow condition on the chart recorder or an associated low flow alarm on the annunciator panel - same indications as the shutdown which occurred on March 8th. The multi-meter monitoring Dual Alarm Unit EP-920A/B output signal recorded a lower voltage reading than the operating voltage. The Dual Alarm Unit was replaced with one from spares and Compliance Procedures No. 7B (CP-7B) and No. 4A (CP-4A) were performed to verify scram set point and transmitter calibration - both were within specification. The multi-meters were left connected and permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
The removed Dual Alarm Unit was set up in the Electronics Technician Shop for bench top testing and its trip set point monitored. Over the course of 3 days, the trip set point had drifted from 40 to greater than 40.5 milliamps; sufficient enough to cause a scram if the unit was installed. Seven (7) transistors and four (4) capacitors were replaced and the unit was subsequently verified operational.
Major maintenance items for the month included: completing Modification Record 01-4, Addendum 8, "Replace General Electric Measurement and Control (GE/MAC) Type 570 Isolated Power Supply EP No. 91 IA with an API Model 9046 Power Supply;" completing Modification Record 06-1, "Removal of Pressurizer Low Liquid level Alarm Unit EP-932 and Signal Resistor Unit EP-93 1;" completing Compliance Procedure No. 29, "Calibration of the NMC RAK Radiation Stack Monitor;" replacing the coupling on secondary coolant system cooling tower fan CTF-3; replacing the reactor safety system dual alarm unit EP-920A/B; loading new pool coolant system de-ionization bed
'E;' replacing control blade 'B' full-in indication light relay 1K23; and re-taping the masonite cover in the thermal column.
April 2006 The reactor operated continuously in April with the following exceptions:
seven shutdowns for scheduled maintenance and/or refueling, and two unscheduled/unplanned power reductions.
On April 8, a "Reflector HI-LO Differential Pressure" reactor scram was automatically initiated when an operator placed his hand near the face of reflector differential pressure transmitter PT-917 meter. The discharge of static electricity from either the operator or the meter caused a deflection of the meter needle below the scram set point.
1-3
Standing Order 06-02 was issued, which states: "This Standing Order issues a caution regarding the potential of causing a reactor scram by the discharge of static electricity that may build up in electronic meters or in personnel.
Do not place your hand or any other item near an electronic meter, especially meters that not only provide indication but also scram functions, to prevent any inadvertent meter movement caused by static electricity." Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation. The Standing Order was later incorporated into AP-RO-110, "Conduct of Operations."
On April 29, a "Reactor Loop Low Flow" reactor scram was automatically initiated when the breaker for Primary Coolant Circulation Pump P-501B tripped. Upon investigation, it was discovered that the wiring insulation on one phase had rubbed against the inside cover of the motor junction box to a point that the wiring was exposed, thus creating a short that caused the breaker to trip on over current. The insulation was repaired, and the inside of the junction box was taped. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
Inspection of the other motor junction boxes in the mechanical equipment room was performed during the following maintenance day.
No abnormalities were discovered.
Major maintenance items for the month included:
completing Modification Record 86-1, Addendum 3, "Replacement of Graphite Reflector Element '51' - Reflector Tank Position 5A/Irradiation Position L6;" replacing the blade full-in/rod drop timer photocell collar unit for control blade 'B' as part of Modification Record 06-2, "Replacement of Rod Drop Timer and Blade Full-In Sensor Collars;" performing a back-flush on the secondary coolant side of pool coolant system heat exchanger HX521; completing the biannual cleaning of the cooling tower sump and basin; completing the biennial changeout of control blade 'B' offset mechanism; performing a reactivity measurement in accordance with RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-1 I(D);"
draining beamport 'B,' replacing beamport 'B' collimator liner, and then flooding beamport 'B' with demineralized water; refurbishing containment ventilation exhaust isolation valve 16A; replacing domestic cold water valve DCW-38; replacing the secondary coolant system pH probe; rebuilding two secondary coolant system pump suction strainers; replacing the secondary coolant system relief valve discharge header piping; and replacing the displacer wire for anti-siphon system level controller LC-965.
May 2006 The reactor operated continuously in May with the following exceptions: six shutdowns for scheduled maintenance and/or refueling, and one unscheduled/unplanned power reduction.
On May 26, a "Channel 2 & 3 Period" reactor scram was automatically initiated by Nuclear Instrumentation (NI)
Channel No. 2. No indication was received on the console meter or the chart recorder for that channel, nor any other NI channel. Following the shutdown, it was noted that the Source Range Monitor was reading less than 1 count per second. Signal Processor Drawer No. 1 provides the following three NI channels: Source Range Monitor (Channel No. 1), Intermediate Range Monitor (Channel No. 2), and Power Range Monitor (Channel No. 4). After adjusting the low count rate set point down and then back to its normal value, the condition cleared and could not be repeated. A calibration was performed on Signal Processor Drawer No. 1 with no problems noted. It was decided to replace the drawer and the Source Range Isolator with ones from spares.
The new drawer was calibrated satisfactorily.
Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation. A letter has been sent to the vendor asking for assistance in troubleshooting the cause of the trip.
1-4
Major maintenance items for the month included: replacing the filter cartridges in pool coolant demineralizer system inlet filter housing F-200; draining and back-flushing beamport 'B' with helium (twice); replacing the source range isolator in nuclear instrumentation signal processor No. 1 drawer; and performing a reactivity worth measurement in accordance with RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B)."
June 2006 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled/unplanned power reduction. NRC regional inspector arrived at MURR for routine inspection.
On June 30, with the reactor operating at 10 MW, a "Secondary Coolant Low Flow" alarm was received with a flow indication of 1 x 105 lb/hr (alarm set point - 17x 105 lb/hr); approximately half the normal operating value. The Reactor Manager was notified and a quick inspection of the cooling tower, cooling tower tunnel, and mechanical equipment room (Room 114) revealed no discrepancies. Room 114 can only be inspected from its entry way since it is inaccessible during reactor operation. The decision was made by the Reactor Manager to shut down the reactor to more thoroughly investigate the cause of the reduction in flow. Upon entering Room 114, it was discovered that Secondary Coolant System Valve S-210, which is the inlet isolation valve to Pool Coolant System Heat Exchanger HX52 1, was about two-thirds of the way closed. The valve handle had become slightly loosened, which caused it to move away from the valve body and disengage its locking device. The valve handle and valve were positioned correctly with the handle secured by additional mechanical means. All other Secondary Coolant System valves with similar locking devices were verified to be in their proper positions. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation. As part of the long-term corrective actions, redundant locking devices were installed on all similar valves.
Major maintenance items for the month included: completing Modification Record 01-4, Addendum 9, "Replace General Electric Measurement and Control (GE/MAC) Type 570 Isolated Power Supply EP No. 91 lB with an API Model 9046 Power Supply;" draining and back-flushing beamport 'B' with helium; installing a sapphire filter in beamport 'B;' completing the annual facility emergency preparedness drill; and rebuilding the air actuator for primary coolant demineralization isolation valve V527E.
July 2006 The reactor operated continuously in July with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, four shutdowns for reactivity measurements, and one unscheduled/unplanned power reduction.
On July 28, with the reactor operating at 10 MW, a reactor scram was automatically initiated when a momentary interruption in electrical supply power from the University power plant to the facility occurred. All immediate and subsequent actions of Reactor Emergency Procedure No. 11 (REP-11) were satisfactorily performed; including verification of the loss of electrical power with the University power plant. Permission to restart the reactor was obtained from the Reactor Manager after confirmation was received from the power plant that the cause of the interruption in electrical power was corrected.
The reactor was refueled and subsequently restarted to 10 MW operation.
I-5
Major maintenance items for the month included: completing Modification Record 01-4, Addendum 10, "Replace General Electric Measurement and Control (GE/MAC) Type 560 Alarm Unit EP No. 920C/D with an API Model 1000 G Alarm Trip Module;" replacing the blade full-in/rod drop timer photocell collar unit for control blade 'A' as part of Modification Record 06-2, "Replacement of Rod Drop Timer and Blade Full-In Sensor Collars;" completing Modification Record 86-1, Addendum 2, "Replacement of Graphite Reflector Element '5J' (N6);" replacing a portion of the pool coolant system piping as part of Modification Record 05-6, "Replace Pool Pump Piping;" performing a back-flush on the secondary coolant side of pool coolant system heat exchanger HX521 (twice); performing a reactivity worth measurement in accordance with RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B) (twice);" draining and back-flushing beamport 'B' with helium; installing a lead filter in beamport 'B;' loading new pool coolant system de-ionization bed 'U;' replacing in-pool heat exchanger HX505 resistance temperature detector (RTD); and installing a new isolation valve cluster in the fire protection loop external to the facility.
August 2006 The reactor operated continuously in August with the following exceptions:
four shutdowns for scheduled maintenance and/or refueling, one shutdown for a reactivity measurement, and two unscheduled/unplanned power reductions.
On August 1, with the reactor operating at 10 MW, a reactor scram was manually initiated when it was determined that annunciator indication, both audible and visible, was not working properly.
Upon investigation, it was discovered that Annunciator Fuse 2F7 had blown; thereby creating the loss of annunciator condition.
Further troubleshooting efforts discovered that relay 2K35, which de-energizes when reactor power is greater than 95%, was stuck in the energized position. This resulted in an overload condition which caused 2F7 to open. The fuse and relay were replaced and permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
On August 25, with the reactor operating at 10 MW, a reactor scram was manually initiated when a sustained fire main low pressure alarm condition occurred. The loss of pressure was confirmed by the University power plant, which in turn informed the facility that the loss of fire main pressure condition would be prolonged. A leak was discovered on the supply line between the facility and the campus fire main loop. The leaking section of piping was replaced. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
Major maintenance items for the month included: completing Modification Record 01-4, Addendum 11, "Replace General Electric Measurement and Control (GE/MAC) Type 560 Alarm Unit EP No. 903 with an API Model 1000 G Alarm Trip Module;" replacing annunciator "Channel 4, 5 or 6 Downscale" relay 2K35; replacing annunciator fuse 2F7; performing a back-flush on the secondary coolant side of pool coolant system heat exchanger HX521; replacing a section of piping in the fire protection loop external to the facility; draining and back-flushing beamport 'C' with helium; and performing a reactivity worth measurement in accordance with RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B)."
1-6
September 2006 The reactor operated continuously in September with the following exceptions:
three shutdowns for scheduled maintenance and/or refueling, one shutdown for a reactivity measurement, and one unscheduled/unplanned power reduction. NRC regional inspector arrived at MURR for routine inspection.
On September 11, a "Rod Not In Contact With Magnet" rod run-in was automatically initiated when control blade
'D' anvil separated from its magnet while the operator was shimming in the outward direction to 26.00-inches in preparation of performing Compliance Procedure No. 10 (CP-10, Rod Drop Times) prior to shutting down the reactor for weekly maintenance activities. The reactor was shutdown and the pull rod to housing alignment was checked and verified, and the anvil and magnet were cleaned. The control rod was satisfactorily withdrawn to the full out position as part of the retest using CP-10. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and normal maintenance day activities were resumed prior to reactor startup.
Major maintenance items for the month included: completing Modification Record 01-4, Addendum 12, "Replace General Electric Measurement and Control (GE/MAC) Type 560 Alarm Unit EP No. 920A/B with an API Model 1000 G Alarm Trip Module;" completing Compliance Procedure No. 29, "Calibration of the NMC RAK Radiation Stack Monitor;" performing a reactivity worth measurement in accordance with RP-RO-201, "Measurement of Total Reactivity Worth of Flux Trap Loadings, RTP-17(B);" performing an "end-of-life" inspection of a spent fuel element; installing a shielding filter in beamport 'C;' installing locking devices on various secondary coolant system isolation and throttle valves; and back-flushing beamport 'D' with helium.
October 2006 The reactor operated continuously in October with the following exceptions:
five shutdowns for scheduled maintenance and/or refueling, and three unscheduled/unplanned power reductions. One reactor startup and shutdown was performed for NRC operator licensing examinations. Received notification from the NRC that 3 new Senior Reactor Operator licenses and 1 Reactor Operator license had been issued.
On October 16 during a normal reactor startup (reactor was subcritical at the time of the occurrence), a "Channel 2 and 3 Short Period" Rod Run-In (RRI) automatically initiated while attempting to clear "Control Blade 'D' Full In" indication light - light should have cleared since the control blade was above the reset height. Upon investigation it appeared that a section of the "Blade Full In" circuitry wiring had dropped near the reactor pool surface allowing pool water to enter a connector. Mechanical agitation of the connector caused a rapid cycling of the "Blade Full In" relay, which in turn created electrical noise that was sensed by the nuclear instrumentation and resulted in the RRI.
Permission to restart the reactor was obtained from the Reactor Manager.
On October 23 while performing RTP-1 1(D), "Measurement of Differential Worth of a Shim Blade," during a reactor startup, a "Rod Not in Contact With Magnet" RRJ automatically initiated when Control Blade 'B' anvil separated from its magnet during a shimming evolution. The reactor was shutdown and the pull rod to housing alignment was checked and found to be slightly misaligned. The alignment was corrected, and the control blade was satisfactorily withdrawn to the full out position as part of the retest using Compliance Procedure No. 10 (CP-10, Rod Drop Times).
Permission to restart the reactor was obtained from the Reactor Manager.
On October 27 with the reactor operating at 10 MW, the control room operator initiated a manual reactor scram when facility fire main pressure decreased and remained below the minimum pressure required for emergency pool fill 1-7
availability.
Upon investigation, the University water supply line immediately outside the facility grounds was leaking, causing a low-pressure condition. Campus Energy Management isolated the leaking section of piping and reconfigured the supply path which restored the fire main loop. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation. Note: Nearly all of the fire main loop that surrounds the facility and the campus supply header in Research Park has recently been replaced as part of an overall upgrade in services to the facility.
Major maintenance items for the month included: replacing the blade full-in/rod drop timer photocell collar unit for control blades 'C' and 'D' as part of Modification Record 06-2, "Replacement of Rod Drop Timer and Blade Full-In Sensor Collars;" completing Modification Record 06-2, "Replacement of Rod Drop Timer and Blade Full-In Sensor Collars;" completing the biannual cleaning of the cooling tower sump and basin; performing a back-flush on the secondary coolant side of pool coolant system heat exchanger HX52 1; completing the biennial changeout of control blade 'D' offset mechanism; and performing a reactivity measurement in accordance with RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-1 (D)."
November 2006 The reactor operated continuously in November with the following exceptions:
four shutdowns for scheduled maintenance and/or refueling, and three unscheduled/unplanned power reductions.
On November 11, a "Channel 4, 5, & 6 High Power" reactor scram was automatically initiated by the Nuclear Instrumentation (NI) system. Upon investigation, the chart recorders for both Intermediate Range Monitor No. 2 (IRM-2) and Power Range Monitor No. 4 (PRM-4) displayed an upward spike. In addition, the high power rod run-in and scram outputs from PRM-4 had tripped. All other NI channel indications were normal.
IRM-2 and PRM-4 are provided by Signal Processor No. 1 (SP-1). Troubleshooting efforts revealed a low resistance of the detector cabling for SP-1 fission chamber detector. The fission chamber detector and cabling were replaced (two replacements were required because the first spare detector failed the retest procedure after installation).
Furthermore, after the new spare detector was installed and tested satisfactorily, it was discovered that the High Voltage Power Supply for SP-1 amplifier assembly was faulty. The spare amplifier assembly was placed in service and tested satisfactorily. The entire system was response checked and permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
Additionally, on November 13, after maintenance day activities were complete, the reactor was shutdown twice after startup in order to adjust the signal gain on SP-1. Adjustment of the gain must be performed while the reactor is shutdown.
Major maintenance items for the month included: flooding beamports 'D' and 'E' with demineralized water in preparation for the December maintenance outage; replacing nuclear instrumentation signal processor No. 1 fission chamber detector (twice); performing a full power alignment on nuclear instrumentation intermediate range monitor No. 2; and replacing the filter cartridges in pool coolant demineralizer system inlet filter housing F-200.
1-8
December 2006 The reactor operated continuously in December with the following exceptions:
five shutdowns for scheduled maintenance and/or refueling, and one unscheduled/unplanned power reduction. NRC regional inspector arrived at MURR to observe and perform a special inspection of the primary and pool heat exchanger replacement outage.
On December 14, while removing a radioactive sample from the reactor pool during a routine sample handling evolution, an automatic Reactor Isolation was initiated when radiation levels from the sample increased above the Area Radiation Monitoring System (ARMS) reactor isolation system set point. A manual or automatic actuation of the Reactor Isolation system causes the following to occur: (1) a reactor scram, (2) closure of normally-open containment building penetrations, (3) an audible alarm throughout the containment building, and (4) actuation of a flashing light near the containment building airlock.
As required by operating procedure EX-RO-105, "Reactor Irradiation Experiments," the ARMS should be placed in the "Upscale" position prior to handling samples in the pool. This increases the reactor isolation set point to prevent an inadvertent isolation during a controlled sample handling evolution. In this case, the ARMS was not placed in the "Upscale" position prior to handling the sample.
After the reactor isolation occurred, the immediate actions of emergency procedure EP-RO-012, "Reactor Isolation,"
were performed. The sample was also immediately placed back in the reactor pool. Tasks required to return the reactor to 10 MW were commenced after entry back into containment. The operating crew was counseled on the importance of adhering to the procedure and permission to restart the reactor was obtained from the Reactor Manager. The reactor was refueled and subsequently restarted to 10 MW operation.
Major maintenance items for the month included: completing Modification Record 75-16, Addendum 3, "Reactor Safety System Monitoring Circuit ("White Rat") Panel - Revision to Panel Overlays in Support of Modification Record 05-8;" completing Modification Record 94-4, Addendum 1, "Replacement of Pool Coolant System Heat Exchanger HX521;" completing Modification Record 05-8, "Replacement of Primary Coolant System Heat Exchangers HX503A and HX503B;" completing Modification Record 05-8, Addendum 1, "Replacement of Primary Coolant System Heat Exchangers HX503A and HX503B - Instrumentation Portion;" completing Modification Record 05-8, Addendum 2, "Replacement of Primary Coolant System Heat Exchangers HX503A and HX503B -
Heat Exchanger and Piping Portion;" draining and flooding beamports 'D,' 'E,' and 'F' with demineralized water; performing a back-flush on the secondary coolant side of pool coolant system heat exchanger HX521; and switching primary coolant system de-ionization bed 'K' to pool coolant system service.
In addition to the items listed above, the reactor was shutdown for approximately 7 days to replace the primary and pool coolant system heat exchangers. During this planned extended shutdown, beamports 'D,' 'E,' and 'F' were retracted in order to replace graphite reflector elements 7 and 8. Once the reflector elements were replaced, the beamports were re-inserted and all piping associated with these beamports was replaced.
A reactivity worth measurement was also performed to characterize the new graphite reflector elements.
1-9
SECTION II MURR PROCEDURES January 1, 2006 through December 31, 2006 As required by administrative Technical Specification 6.1.h (4), this section of the Annual Report includes a summary of procedure changes. These procedure changes were reviewed by the Reactor Manager or Reactor Health Physics Manager and others to assure compliance with the requirements of 10 CFR 50.59. These procedure changes were also reviewed by the Reactor Procedure Review Subcommittee of the Reactor Advisory Committee to meet the requirements of Technical Specification 6.l.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-nine (69) 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 revised procedures, forms and operator aids:
Name.
Rev. R.evision Date[
Notes AP-RO-110 lConduct of Operations 6
5/2/2006 Minor Editorial AP-RO-lIl10 Conduct of Operations 7
8/7/2006 Full Review AP-RO-110 1Conduct of Operations 8
81/7/2006 i lnor Editvria AP-RO-I10 Conduct of Operations 9
12/18/2006 Minor Editorial EX-RO-105 Reactor Irradiation Experiments 8 T 11/7/2006 Minor Editorial EX-RO-120 Beamport "A" Operation 3J 2/13/2006 Minor Editorial EX-RO-120 Beamport "A" Operation 4j 9/5/2006 F Full Review EX-RO-12.1 ]Beamport "B" Operation 3
2/13/2006 Minor Editorial EX-RO-121 Beamport "B" Operation 4
9/5/2006 Full Review EX-RO-122
_BeamPort.
"C" Operation 3 1...
2/13/2006 Minor Editorial EX-RO-122 Beamport "C" Operation 14 9/5/2006 Full Review EX-RO-123 Beamport "D" Operation 13 9/5/2006 Full Review EX-RO-124 Beamport "E" Operation 13 2/13/2006 Minor Editorial EX-RO-125 Beamport "F" Operation 3
2/13/2006 Minor Editorial EX-RO-125 Beamport "F" Operation 4
9/5/2006 Full Review EX-RO-126 Thermal Column Door 3
10/18/2006 Minor Editorial FB-SH-005 IType B Shipment of Spent Fuel Using the BMI-1 1 8/16/2006 Minor Editorial Shipping Cask_
FM-16 Primary - Pool Coolant Water Analysis J4 3/13/2006 Cover Page FM-20 Waste Tank Sample Report 7
6/16/2006 Minor Editorial FM-43 Nuclear and Process Data 6
3/13/2006 Cover Page FM-43 Nuclear and Process Data 7
8/7/2006 Minor Editorial FM-43
.Nuclear and Process Data 8
12/18/2006.
Minor Editorial FM-56 Reactor Routine Patrol 10j [ 3/13/2006
,Minor Editorial II-1
Number Nai Revi.
Revision Dateri Notes<
FM-57 Long Form Startup Checksheet 7
9/5/2006 Full Review FM-57 Long Form Startup Checksheet 8
10/18/2006 Minor Editorial FM-57 Long Form Startup Checksheet 9
10/27/2006 Minor Editorial FM-66 Customer Sample Pre-Encapsulation Evaluation 2
5/12/2006 Cover Page Worksheet FM-68 Target Material Control Checksheet 4
5/12/2006 Full Review FM-68 Target Material Control Checksheet 5
7/12/2006 Minor Editorial FM-97 Operations and Facility Infrastructure Drawing 1
9/5/2006 Minor Editorial
. Revision Tracking Form.
IRR-PSO-100 Scheduling Flux Trap Tubes 3
11/17/2006 Minor Editorial IRR-PSO-11 Customer Sample Pre-Encapsulation Evaluation 2
5/12/2006 Cover Page OP-RO-100 Main Air System 6
3/13/2006 Cover Page OP-RO-101 Instrument Air System 5.
3/13/2006 Cover Page OP-RO-2!11 Reactor Startup - Hot 5 J 8/7/2006 Minor Editorial OP-RO-311 Nuclear Instrumentation - Signal Processor #2 5.
6/16/2006 Minor Editorial OP-RO-312 Nuclear Instrumentation Power Range Monitor -
6 6/16/2006 Minor Editorial Channel16 OP-RO-350 Reactor Power Calculator Flow Potentiometer 4
2/13/2006 Minor Editorial Adjustment OP-RO-4 10 Primary Coolant System 5
5/2/2006 Cover Page OP-RO-410 Primary Coolant System 6
12/18/2006 Minor Editorial OP-RO-460 IPool Coolant System - Two Pump Operation J 6 5/2/2006 Minor Editorial OP-RO-460 Pool Coolant System - Two Pump Operation 7 j 8/17/2006 Minor Editorial OP-RO-461 Pool Coolant System - One Pump Operation 5
5/2/2006 Minor Editorial OP-RO-461 Pool Coolant System - One Pump Operation 6
12/18/2006 Minor Editorial OP-RO-465 Pool Level Control - Skimmer System 4
3/13/2006 Cover Page OP-RO-466 Pool Level Control - Pool Coolant System 4
3/13/2006 Cover Page OP-RO-480 ISecondary Coolant System 8
6/16/2006 Minor Editorial OP-RO-480 lSecondary Coolant System 9
10/18/2006 Minor Editorial OP-RO-480 Secondary Coolant System 10 12/18/2006 Minor Editorial OP-RO-510 jNitrogen System 5
5/2/2006 Cover Page OP-RO-515 Emergency Air System 5
10/18/2006 Minor Editorial OP-RO-516 IValve Operation Air System 5
8/7/2006 Minor Editorial OP-RO-531 Primary and Pool Sample Station 151 6/16/2006 Minor Editorial OP-RO-555 Fire Protection System 2j 1/18/2006 Minor Editorial OP-RO-555 Fire Protection System 3
10/18/2006 Minor Editorial OP-RO-741 Waste Tank System Operation 8
3/13/2006 Minor Editorial RM-RO-400 Waste Tank System Filter Replacement 4
3/13/2006 Cover Page RM-RO-405 Reactor Dernineralizer System 8
8/7/2006 Minor Editorial RP-RO-100 Fuel Movement 5
5/2/2006 Minor Editorial RP-RO-100 Fuel Movement 6
9/14/2006 Minor Editorial RRTP-11D Measurement of Differential Worth of a i
RP-RO-200
- 2.
12/1120 Minor Editorial Shim Blade Draining and Filling the Primary System Side of 1
SM-RO-100 ar Hea E12x5/006 FuleReie 11-2
Number~
Rev.~( Reviio Date,
'Nte SM-RO-105 Replace Primary and Pool Coolant System Heat 0
12/12/2006 Full Review
............. Exchangers and Piping...
SM-RO-300 Control Console And Instrument Panel-Securing 6
8/18/2006 Minor Editorial Power SM-RO-638 Retracting and Reinserting Beamport 'D' Liner 1
12/15/2006 Full Review SM-RO-639 Retracting and Reinserting Beamport 'E' Liner 1
12/15/2006 Full Review SM-RO-640 Retracting and Reinserting Beamport 'F' Liner 2..
12/15/2006.
Full Review SM-RO-660 Removal of Pressure Vessel 0
1/6/2006 Full Review 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 seven (7) 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 Re.Rvso ae
'Notes EP-RO-006 IRadiological Emergency 2
9/26/2006 Minor Editorial EP-RO-015 JEmergency Notifications 3
9/26/2006 Minor Editorial FM-104 Emergency Call List 3
5/5/2006 Minor Editorial FM-104 Emergency Call List..
4 6/8/2006 Minor Editorial FM-104 Emergency Call List 5
9/26/2006 Minor Editorial OA-10 Fire Extinguisher Locations and Types 2
5/5/2006 Minor Editorial OA-20.
Emergency Equipment 2
5/5/2006 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 one hundred and twenty-nine (129) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping 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:
Number Name Rev. ReviskionDate
'%o Nes
- AP-HP-105 Radiation Work Permit 5
10/23/2006 Cover Page AP-HP-110 Controlled Special Exposures 5
10/23/2006 Minor Editorial AP-HP-117 MURR Initial Radiation Worker Training 7
13/06 CvrPg ProgramA7 1/30/2006 Cover Page AP-HP-119.High Radiation Area Access 1
3/24/2006 iMinorEditorial 11-3
Nuber J
N'ane Re% eisi*on Datel Notes AP-HP-. 19.High Radiation Area Access 1
3/24/2006 1 Minor Editorial AP-HP-120 Beamport Area 2
3/24/2006 Minor Editorial AP-HP-121 Isotope Closet 2
3/24/2006 Minor Editorial AP-HP-123 Visitor Dosimetry - Reception Desk 4
/3.02006 Cover Page IRadioactive Material Licensing and Project AP-HP-127 jeMat erial Licesi 3
1/30/2006 Cover Page
~~Designation Change Request_
AP-HP-129 Hot Cell Control 4
3/24/2006 Minor Editorial AP-HP-130 Reactor License Projects Annual Review 2
11/28/2006 Cover Page AP-HP-150 Source Calibration 3
5/3/2006 Cover Page AP-PSO-001 General Requirements for Preparation of 2
11/17/2006 Cover Page Radioactive M aterials for Shipping..............
AP-PSO-001 General Requirements for Preparation of 2
11/17/2006 Minor Editorial R ad io activ e M a terials fo r S h ip p in g......
AAdministrative Procedure, Radioactive Materials 4
1/11/2006 Minor Editorial AP-SH001 Shipping______
BPB-SH-001 2R Shipping Container Leak Check 5
3/7/2006 Minor Editorial BPB-SH-001.2R Shipping Container Leak Check T6 9/1/2006 Minor Editorial BPB-SH-002 20WC-1 Packaging and Shipment of Type B Non-:
6 1/11/2006 Minor Editorial Waste Radioactive Material 20WC-1 Packaging and Shipment of Type B Non-:
BPB-SH-002 Wat aiatv aeil7~
9/1/2006 Minor Editorial Waste Radioactive Material "BPB-SH-005 DOT 6M Packaging of Type B Non-Waste 9/20/2006 Minor Editorial Radioactive Material BPB-SH-008 Type B(U) F-327 Series Packaging of Type B 4
9/20/2006 Minor Editorial Non-Waste Radioactive Material F-327 Packaging and Shipment of Type A Non-6/16/2006 Minor Editorial Waste Radioactive Material BP-SH-010 Packaging and Shipment of Non-Waste 2
10/31/2006 Minor Editorial Radioactive Materials in Excepted Packages Shipment of Non-Waste USA DOT 7A Type A 2
55-Gallon Radioactive Material Package BP-SH-011 Shipment of Non-Waste USA DOT 7A Type A 3
4/1/2006 Minor Editorial BP-SH-011....... 55-Gallon Radioactive Material Package
- 3.
10/31/2006 Minor Editorial BP-SH-012 DOT-7A Package Certification 1
4/17/2006 Cover Page H
Packaging and Shipment of Radioactive Materials BP-SH-013 Usn URRual yeAPcae1 4/17/2006 Minor Editorial
________Using MURR Reusable Type A Package BP-SH-014 Packaging and Shipment of Radioactive Material 0
3/7/2006 Full Review
__________Using an OverpackI BP-H-014 Packaging and Shipment of Radioactive Material Using-anHOverpack 0
3/7/2006 Full Review B -
Radioactive Material Shipment Package 0
6 0R BP-SH-052 0~ouetto adLbln 6/16/2006 Full Review Documentation and Labeling Packaging and Shipment of Radioactive Material BP-SH-059 Using Spectratek Services Reusable DOT 7A 0
10/31/2006 Full Review Type A Package BP-SH-302 Packaging and Shipment of Radioactive Material 1
9/20/2006 Minor Editorial Using MURR Models 6 and 12 11-4
, Number.
mNam*vue.
Revision Date N otes:
+
FB-SH-005 Type B Shipment of Spent Fuel Using the BMI-1 1
8/16/2006 Minor Editorial 4~~Shipping Cask I_
FM-107 Control Check Sheet for Overpack Shipment 0
3/7/2006 Full Review FM-107
- Control Check Sheet for Overpack Shipment 1
1//2006 Minor Editorial FM-108 2R Container Leak Check Data Sheet 0
3/7/2006 Full Review FM-120
.Individual Type B QA Training Certification 0
10/31/2006 Full Review FM-13 Receipt of Radioactive Material 3
1/30/2006 Cover Page F Control Checksheet for Non-Waste USA DOT 7A FM-151 3Type A (Gemstone) Radioactive Material Package 1/11/2006 Minor Editorial FM-151 Control Checksheet for Non-Waste USA DOT 7A 4
9/1/2006 Minor Editorial Type A 55-Gallon Radioactive Material Package Control Checksheet for Non-Waste USA DOT 7A FM-151 Type A 55-Gallon Radioactive Material Package 5
10/31/2006 Cover Page FM-17 Radiation Work Permit 5
10/23/2006 Cover Page FM-17 Radiation Work Permit 6
11/29/2006 Minor Editorial FM-27 In-House Radioactive Shipping Request Form 1 5 4/17/2006 Minor Editorial FM-28 Controlled Special Exposure Authorization 14 11/7/2006 Cover Page FM-29 Initial Radiation Worker Training Packet 5
1/30/2006 Cover Page Control Checksheet for Type B USA DOT 20WC-1 FM-35 I1 Radioactive Materials Shipment 10 1/11/2006 Minor Editorial Control Checksheet for Type B USA DOT 20WC-11 9/1/2006 Minor Editorial I Radioactive Materials Shipment Control Checksheet for USA DOT 7A-MURR FM-36 7
1/11/2006 Minor Editorial iModel I1100 Series 6 Control Checksheet for USA DOT 7A-MURR FM-36 7
1/11/2006 Minor Editorial Model 1100 Series Control Checksheet for USA DOT 7A -MURR FM-37 Model 1220 Series 7
1/11/2006 Minor Editorial
___________Model 1220 Series Control Checksheet for USA DOT 7A -MURR FM-37 7
1/11/2006 Minor Editorial Model 1220 Series Control Checksheet for USA DOT 7A MURR FM-38 7
1/11/2006 Minor Editorial Model 1300 Series Control Checksheet for USA DOT 7A MURR FM-38 Mdl10Seis7 1/11/2006 Minor Editorial FM-39 iControl Checksheet for Excepted Package 7
6/16/2006 Minor Editorial
!Radioactive Materials Shipment Control Checksheet for Excepted Package 8
9/25/2006 Minor Editorial FRadioactive Materials Shipment FM-44 1Request for Radioisotope Shipment 6
6/16/2006 Cover Page Control Checksheet for Documentation and FM-44 Co0o o
n 6/16/2006 Full Review F ______Labeling of Radioactive Material Shipment 01 6/620 1 ullRevie Control Checksheet for Documentation and 9/1/2006 1 Minor Editorial FM-5 __Labeling of Radioactive Material Shipment Radioactive Material Licensing and Project 1/30/2006 C
FM-53 2
13/06 CoverPage Designation Change Request FM-54 Report ofPersonnel contamination 4
__3/24/2006
.ge 11-5
Numiber NaeRv eýso ae oe Control Checksheet for Spectratek Services FM-59 Reusable Type A Package Radioactive Materials 0
10/31/2006 Full Review Shipment FM-75 Control Checksheet for Type B(U) F-327 Series 7
9/20/2006 Minor Editorial Radioactive Materials Shipment FM-77 Control Checksheet for GB/0924BP/B(U) 5 1/11/2006 Minor Editorial Radioactive Materials Shipment FM-77 Control Checksheet for GB/0924BP/B(U) 5 1/11/2006 Minor Editorial Radioactive Materials ShipmenttS r...
FM-86.Reactor License Project Review Report 2
10/23/2006 Cover Page FControl Checksheet for Type A F-327 Series Radioactive Material Shipment FM-89 Control Checksheet for Type A F-327 Series 5
8/16/2006 Minor Editorial R adioactive M aterial Shipm ent FM-89 Control Checksheet for Type A F-327 Series 5
8/16/2006 Minor Editorial Radioactive M aterial Shipment FM-91 Declaration of Pregnancy 1
2/10/2006 Cover Page FM-94 Exclusive Use Shipment Controls 0
3/7/2006 Full Review FM-98..... Control Checksheet for MURR Shipment Using 1
1/11/2006 Minor Editorial USA DOT 7A MURR Model 6 or 12 FM-98 Control Checksheet for MURR Shipment Using 2
9/20/2006 Minor Editorial USA DOT 7A MURR Model 6 or 12 Control Checksheet for USA DOT 7A MURR FM-99 I
9/l/2006 Minor Editorial Model 1500 Series HC-PSO-002 Hot Cell Preparation of Radioactive Material for 5
12/8/2006 Full Review Shipment IC -HP-300 Calibration - Radiation Survey Instruments 4
3/24/2006 Cover Page IC-HP-305 Calibration - Electrostatic Discharge Dosimeter 3
2/10/2006 Cover Page IC-HP-3 10 Calibration - Eberline Ping 1 a Stack Monitor-4 2/10/2006 Cover Page Particulate Channel CoverPage LC-HP-3 11 Calibration - Eberline Ping 1 a Stack Monitor -
4 2/10/2006 Cover Page Iodine Channel IC-HP-312 Calibration - Eberline Ping la Stack Monitor - Gas 4
2/10/2006 Cover Page Channel NMC Model RAK Stack Monitor IC-HP-318 4
1/30/2006 Minor Editorial Offsets/Multipliers/High Voltages Determination Calibration - NMC Model RAK Monitor -
IC-HP-319 PriuaeCnel3 3/24/2006 Cover Page
~~Particulate Channel Calibration - NMC Model RAK Monitor - Iodine IC-HP-320 Canl3 3/24/2006 Cover Page Channel N
d M
r IC-HP-321 Caatien 3
3/24/2006 Minor Editorial Channel IC-HP-331 Calibration - Tennelec LB-5 100 Alpha/Beta
.4 3/24/2006 Cover Page IC-HIP-331 Calibration - Tennelec LB-5 100 Alpha/Beta 5
11/7/2006 Minor Editorial IC-HP-333 Eberline BC-4 Beta Swipe Counter - Calibration 4
1/30/2006 Cover Page Calibration - Portal Monitor Gamma S/N IC-HP-335 90646 3/24/2006 Cover Page 11-6
4~Numnber~
'Sni Rev.
j~
Rievision Date Noe Calibration - Portal Monitor Gamma S/N 5
5 IC-HP-337 5l5//206ndverPag IC-HP-~ 347 Calibration - Protean Model WPC 9550 Alpha-5 8/17/2006 Minor Editorial IC....347 Beta Swipe Counter......
IC-HP-347 iCalibration - Protean Model WPC 9550 Alpha-6 11/7/2006 Minor Editorial
_Beta Swipe Counter IC..
...8 Calibration - Canberra S5XLB-G & Tennelec 2.//06 Mno
.dtra IC-HP-3'.48 Sre wt am 2
5/3/2006 Minor Editorial
___________Series 4 with Gamma______
IRR-PSO-103 *Receipt of Radioactive Material for Irradiation 4
11/17/2006 Cover Page I OP-HP-200 Air Sampling-Containment Building Tritium j
2 11/7/2006 Cover Page OP-HP-221 Environmental Sample - Analysis j 4 3/24/2006 Cover Page OP-HP-227 ITennelec LB-5 100 Alpha/Beta - Operation 3
3/24/2006 Cover Page OP-HP-230 Eberline BC-4 Beta Swipe Counter - Operation 3
2/10/2006 Minor Editorial OP-HP-230 Eberline BC-4 Beta Swipe Counter - Operation 3
2/10/2006 Cover Page OP-HP-300 Receipt of Radioactive Material 5.
1/30/2006 Cover Page OP-HP-305 Ordering Radioactive Materials 2
10/23/2006 Cover Page OP-HP-306 Daily Facility Checks 0
8/7/2006 Full Review OP-HP-348 Operation - Protean WPC-9550 Swipe Counter 2
2/10/2006 Cover Page OP-HP-350 Eberline Model Ping 1A - Filter Change 3
3/24/2006 Cover Page OP-HP-351 NMC Model RAK - Filter Change 3
1/30/2006 Cover Page OP-HP-352 Particulate and Iodine Filter - Analysis 2
1/30/2006 Cover Page Sodium Iodide Spectral Analysis for Excepted, QA-SH-002 Exempt, License-to-License, Type A, or Type B 2
10/31/2006 Minor Editorial t
~
~~Radioactive Materials..Shipments......
RP-HP-1 15 Returning Lead Pigs to Service I 4 2/10/2006 Cover Page RP HP-120 Personnel Radioactive Contamination P
4 3/24/2006 Cover Page RP-HP-137 Handling Radioactive Material in the Reactor Pool 4
10/23/2006 Minor Editorial SV-HP-!10 Environmental Sampling 3
1/30/2006 Cover Page SV-HP-115 Building Exhaust Stack Effluent - Tritium 3
3/24/2006 CoverP SV-HP-115_
Monitoring Secondary Coolant and Sump Water - Sampling
. 3 3/24/2006 Minor Editorial and Analysis SV-HP-1 19 Property Release 2
3/24/2006 Cover Page SV-HP-121 Building Exhaust Stack Effluent - Ar-41 1 2 3/24/2006 SV-HP121 3/242006 Cover Page Monitoring SV-HP-135.Containment Air - Emergency Remote Sampling i 3 11/7/2006 Cover Page TPZ-PSO-001 Receiving Gemstone Irradiation Shipping Drums, 3 3/27/2006 Cover Page TPZ-PSO-002 Irradiation of Gemstone Irradiation Containers 3
3/27/2006 Cover Page TPZ-PSO-003 Loading Gemstone Shipping Drums 3
3/27/2006 Minor Editorial.
Shipment of Type B Radioactive Waste Using 4
9/1/2006 Minor Editorial WMB-S-005Chem-Nuclear System 1-13G Cask........
Shipment of Radioactive Material, Hot Cell Host 2
1/11/2006 Cover W M -SH-01 1 2an 1/11200 Page I~~ __Cans Waste Exclusive Use Shipment of LSA or SCO WM-SH-300 Radioactive Waste 3
8/18/2006 Minor Editorial 11-7
SECTION III REVISIONS TO THE HAZARDS
SUMMARY
REPORT January 1, 2006 through December 31, 2006 These changes were approved by the Reactor Manager and reviewed by licensed staff and members of the Reactor Safety Subcommittee and have been determined not to involve a change to the Technical Specifications. These changes have all been reviewed in accordance with 10 CFR 50.59.
HAZARDS
SUMMARY
REPORT (ORIGINAL JULY 1, 1965)
Original HSR, Figure 5.1, Piping & Instrument Diagram (as revised by the 1972-73, 1973-74, 1994, 1996, 2001, 2002, 2003, and 2004 Reactor Operations Annual Reports):
Replace with:
Updated Figure 5.1, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet 1 of 1, dated 8/7/06)
Original HSR, page 5-3, Section 5.2.3:
Delete:
Entire section, which states:
"The heat exchangers are water to water shell and tube type with removable tube bundles. The tubes, and all materials in contact with reactor coolant water, are stainless steel. The reactor coolant flows on the tube side of the exchanger with a velocity not in excess of 7 ft/sec. One heat exchanger is capable of removing 17 x 106 BTU/hr. of heat from 1800 gpm of coolant water and returning it at approximately 140 'F, using a maximum of 1600 gpm of secondary water flow at 87 'F.
Two such heat exchangers are installed for design power operation."
"The heat exchangers are plate-type with all surfaces in contact with the reactor coolant constructed of stainless steel. One heat exchanger is capable of removing 16.9 x 106 BTU/hr of heat from 1800 gpm of coolant and returning it at approximately 140 °F, using a maximum of 1600 gpm of secondary coolant flow at 87 'F. Two such heat exchangers are installed for design power operation."
Replace with:
Original HSR, page 5-8, Section 5.4.2 (as revised by the 1996 Reactor Operations Annual Report):
Delete:
Entire section, which states:
"The secondary water flows on the shell side of the reactor primary heat exchanger, and on the opposite plate side of the pool coolant in the pool heat exchanger."
Replace with:
"The secondary coolant flows on the opposite plate side of the primary coolant in the primary coolant heat exchangers and on the opposite plate side of the pool coolant in the pool coolant heat exchanger. In both the primary and pool coolant heat exchangers, the secondary water flows in a cross-flow configuration to the process water being cooled."
Original HSR, page 5-9, Section 5.4.4, 1s sentence (as revised by the 1994 Reactor Operations Annual Report):
Delete:
"A 125 horsepower centrifugal..."
Replace with:
"A 150 horsepower, variable speed, centrifugal..."
Original HSR, pages 9-7 through 9-9, Table 9.2 (as revised by the 1981-82, 1985-86, 1995, 2000, 2001, and 2002 Reactor Operations Annual Reports):
Delete:
Replace with:
Delete:
Replace with:
Delete:
Replace with:
Delete:
Replace with:
Delete:
Replace with:
Delete:
Replace with:
Delete:
Replace with:
Delete:
Replace with:
Delete:
Replace with:
Add:
Add:
"26 Primary Coolant HX503A Outlet Temperature Meter - TE 980A" "26 "27 "27 "43 "43 "46 "46 "89 "89 "90 "90 "91 "91 "100 "100 "101 "101 "133 "134 Primary & Pool Coolant Demineralizer Flow Recorder - 2 Pen" Primary Coolant HX503A Outlet Temperature Meter - TE 980B" Dual Alarm Unit (EP 920E/F) Primary Low Flow Scram" Square Root Transmitter (EP 919E) - Primary Flow "B" Loop" Square Root Transmitter (EP 919E) - Primary Flow "A" Loop" Alarm Unit - Pressurizer Water Level" Square Root Transmitter (EP 919G) - Primary Flow "B" Loop" Primary Coolant System Flow Recorder - 2 Pen" Primary Coolant System "A" Loop Flow Recorder - 2 Pen" Pool Coolant System Flow Recorder - 2 Pen" Primary Coolant System "B" Loop Flow Recorder - 2 Pen" Primary & Pool Coolant Demineralizer Flow Recorder - 2 Pen" Pool Coolant System Flow Recorder - 2 Pen" Primary Coolant HX503A Differential Pressure Meter - DPS 928A" Primary Coolant HX503A Outlet Temperature Meter - TE 980A" Primary Coolant HX503B Differential Pressure Meter - DPS 928B" Primary Coolant HX503B Outlet Temperature Meter - TE 980B" Dual Alarm Unit (EP 920G/H) Primary Low Flow Scram" Square Root Transmitter (EP 919H) - Primary Flow "B" Loop" 111-2
Original HSR, Figure 9.3, Instrument Panel Layout (as revised by 1995, 2001, and 2004 Reactor Operations Annual Reports):
Replace with:
Updated Figure 9.3, Instrument Cabinet (MURR Dwg No. 74, Sheet 12 of 12)
Original HSR, Figure 9.4, Safety System 10 MW (as revised by the 1995, 2001, 2002, and 2003 Reactor Operations Annual Reports):
Replace with:
Updated Figure 9.4, Safety System (MURR Dwg No. 139, Sheet 1 of 1, dated 12/26/06)
Original HSR, page 9-24, Section 9.8.2.1 (as revised by the 1982 and 1995 Reactor Operations Annual Reports):
Delete:
Entire section, which states:
"The reactor loop flow measurement system includes two orifice plates, one in each of the two heat exchanger legs.
Flow, as measured by the transmitters connected to these orifice plates, is recorded on a control room instrument panel mounted two pen recorder.
The orifice plate flow measuring channels will alarm at 90% of normal flow. At 85% of normal flow the core isolation valves, reactor convective loop valves, and the siphon break valves operate as the reactor scrams."
Replace with:
"The reactor loop flow measurement system includes two orifice plates, one in each of the two heat exchanger legs.
Flow, as measured by two transmitters connected to each orifice plate, is recorded on two, two-pen recorders mounted on the control room Instrument Panel. The orifice plate flow measuring channels will alarm at approximately 95% of normal flow.
At approximately 90% of normal flow the core isolation valves, reactor convective loop valves, and the siphon break valves operate as the reactor scrams."
ADDENDUM 3 - HAZARDS
SUMMARY
REPORT (AUGUST 1972)
HSR, Addendum 3, page 20, Figure 2.2, Secondary Cooling System (as revised by the 1989-90, 1990-91, 1994, 1995, 2001, 2002, 2003, 2004, and 2005 Reactor Operations Annual Reports):
Replace with:
Updated Figure 2.2, Secondary Cooling System (MURR Dwg No. 502, Sheet 1 of 1, dated 1/22/07)
HSR, Addendum 3, page 23a, Figure 2.3.a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, and 2005 Reactor Operations Annual Reports):
Replace with:
Updated Figure 2.3.a, Electrical Distribution (MURR Dwg No. 522, Sheet 1 of 3, dated 8/8/06)
HSR, Addendum 3, page 6, Section 2.1.2.2:
Add:
The following paragraph to the end of the section:
"In December 2006, shell and tube-type heat exchanger 503B was replaced with a Graham Model GPE-60 plate-type heat exchanger with 201 plates 111-3
and 1200 square feet of surface area. This heat exchanger is a duplicate of heat exchanger 503A, which was also replaced in December 2006."
HSR, Addendum 3, page 7, Section 2.1.2.5:
Add:
The following paragraph to the end of the section:
"In December 2006, the flow orifice flanges for 913B were replaced with dual-tap flanges to allow for additional flow monitoring sensing points.
These flow orifice flanges are identical to those used for 913A, which were also replaced in December 2006."
HSR, Addendum 3, page 8, Section 2.1.2.12:
Add:
The following paragraph to the end of the section:
"As of December 2006, the valves numbered 595C, 595D, 595E, and 595F are the isolation valves for normally installed but isolated pressure gauges used for long-term trending of heat exchanger differential pressure."
HSR, Addendum 3, page 9, Section 2.1.2.14:
Add:
The following paragraph to the end of the section:
"As of December 2006, FE 913B is instrumented with valve manifolds 5681 and 568J."
HSR, Addendum 3, pages 9 through 10, Section 2.1.3.1 (as revised by the 1994 Reactor Operations Annual Report):
Add:
The following paragraph to the end of the section:
"In December 2006, DPS 928A and DPS 928B were removed as part of the primary coolant heat exchanger replacement project which consisted of replacing the shell and tube-type heat exchangers with plate-type heat exchangers. New dual tap flanges were installed for flow orifices 913A and 9133B, which allowed an additional flow transmitter to be connected to each heat exchanger leg, thus eliminating the need for DPS 928A and DPS 928B."
HSR, Addendum 3, page 18, Section 2.3.2.1:
Delete:
"... powered by 125 hp General Electric motors..."
Replace with:
"...powered by 150 HP Toshiba motors..."
HSR, Addendum 3, page 21, Section 2.4.2.1:
Delete:
"GE Model 5K405AK230B 1 125 hp - 1780 rpm FL 460 volts - 60 cycle - 3 wire - 3 phase FL Amps 151 Type K - Frame 405TS Nema Class Design B - Code G" Replace with:
"Toshiba Model B 1504ULF4USW 150 HP - 1780 rpm FL 460 volts - 60 cycle - 3 wire - 3 phase (variable speed rating) 111-4
FL Amps 170 Type TIKK - Frame 444T NEMA Class Design B - Code G" HSR, Addendum 3, page 21, Section 2.4.2.2:
Delete:
"General Electric controllers sized to fit 7700 line controller and provide operation for the associated motors."
Replace with:
"Pumps 501B and 508B have General Electric controllers sized to fit 7700 line controllers and provide operation for the associated motors. Pump SP-3 has a General Electric Evolution Series controller sized to provide operation for its motor."
HSR, Addendum 3, page 31, Section 2.5.3.2:
Add:
The following paragraph to the end of the section:
"In December 2006, DPS 928A and DPS 928B were removed as part of the primary coolant heat exchanger replacement project which consisted of replacing the shell and tube-type heat exchangers with plate-type heat exchangers. New dual tap flanges were installed for flow orifices 913A and 913B, which allowed an additional flow transmitter to be connected to each heat exchanger leg, thus eliminating the need for DPS 928A and DPS 928B."
HSR, Addendum 3, page 31, Section 2.5.3.3 (as revised by the 1995 Reactor Operations Annual Report):
Add:
The following paragraph to the end of the section:
"In December 2006, DPS 928A and DPS 928B were removed as part of the primary coolant heat exchanger replacement project which consisted of replacing the shell and tube-type heat exchangers with plate-type heat exchangers."
HSR, Addendum 3, page 33, Section 2.5.3.5 (as revised by the 1995 and 2002 Reactor Operations Annual Reports):
Add:
The following three paragraphs after the second paragraph:
"In December 2006, as part of the primary coolant heat exchanger replacement project, which consisted of replacing the shell and tube-type heat exchangers with plate-type heat exchangers, new dual tap flanges were installed for flow orifices 913A and 913B. This allowed an additional flow transmitter to be connected to each heat exchanger leg.
The following paragraphs describe how flow through the heat exchangers is now monitored.
Flow through heat exchanger 503A is monitored by flow element 913A, flow transmitters 912A and 912E, square root transmitters 919A and 919E, electronic alarm units 920A and 920C, and recorder 915A/B.
Flow through heat exchanger 503B is monitored by flow element 913B, flow transmitters 912G and 912H, square root transmitters 919G and 919H, electronic alarm units 920E and 920G, and recorder 915G/H."
111-5
Delete:
The third paragraph, which states:
"Output logic of the dual electronic alarm unit EP 920A and B determine the scram functions, alarms and control circuitry for 5 and 10 MW operation.
EP 920A output controls K9, K30 and K70.
EP 920B output controls K34, K38 and K71."
"Output logic of the dual electronic alarm units EP 920A, EP 920C, EP 920E, and EP 920G determine the scram functions, alarms and control circuitry for 5 and 10 MW operation."
Replace with:
HSR, Addendum 3, page 44, Section 2.5.5.1:
Add:
The following paragraph to the end of the section:
"In December 2006, DPS 928A and DPS 928B were removed as part of the primary coolant heat exchanger replacement project, which consisted of replacing the shell and tube-type heat exchangers with plate-type heat exchangers.
ADDENDUM 4 - HAZARDS
SUMMARY
REPORT (OCTOBER 1973)
HSR, Addendum 4, page A-9, Section A.3.3.5, second paragraph:
Delete:
"Reactor flow is the sum of flows through two heat exchangers for 10 MW operation.
Flow scram signals are developed by measuring the pressure drop across orifice plates and generating a trip from Alarm Units 920A or 920C (Figures A.2 and A.3). Auxiliary relays from these alarm units open inputs E4A and E3B to the noncoincidence logic units (Figure A.1).
An additional scram is generated by differential pressure switches 928A and B monitoring the pressure drop across each heat exchanger (Figures A.2 and A.3). A low differential pressure sensed by switches 928A and B actuates relays which open contacts in the E3B and E4A input to the noncoincidence logic units respectively."
Replace with:
"Reactor flow is the sum of flows through two heat exchangers for 10 MW operation.
Flow scram signals are developed by measuring the pressure drop across orifice plates with multiple taps and generating a trip from any one of the following Alarm Units: 920A, 920C, 920E or 920G. Auxiliary or internal relays from these alarm units open inputs E4A and E3B to the noncoincidence logic units (Figure A. 1)."
HSR, Addendum 4, page A-23, Section A.3.16:
Add:
The following paragraph to the end of the section:
"In December 2006, DPS 928A and DPS 928B were removed as part of the primary coolant heat exchanger replacement project; therefore, heat exchanger differential pressure is no longer used."
HSR, Addendum 4, page A-28, Figure A.1, Safety System 10 MW (as revised by the 1995, 2001, 2002, and 2003 Reactor Operations Annual Reports):
Replace with:
Updated Figure A.1, Safety System (MURR Dwg No. 139, Sheet 1 of 1, dated 12/26/06) 111-6
HSR, Addendum 4, page A-29, Figure A.2, Piping & Instrument Diagram (as revised by the 1972-73, 1973-1974, 1994, 1996, 2001, 2002, 2003, and 2004 Reactor Operations Annual Reports):
Replace with:
Updated Figure A.2, Piping & Instrument Diagram (MURR Dwg No. 156, Sheet I of 1, dated 8/7/06)
HSR, Addendum 4, page A-30, Figure A.3, 10 MW Process Instrumentation Control & Interlock (as revised by 1995, 1998, 2001, 2004, and 2005 Reactor Operations Annual Reports):
Replace with:
Updated Figure A.3, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 3 of 4, dated 12/26/06)
HSR, Addendum 4, page A-31a, Figure A.4.a, Reactor Control System - 10 MW (as revised by 1995, 2001, and 2004 Reactor Operations Annual Reports):
Replace with:
Updated Figure A.4.a, Reactor Control System (MURR Dwg No. 42, Sheet 1 of 2, dated 12/26/06)
HSR, Addendum 4, page A-32, Figure A.5, 10 MW Process Instrumentation Control & Interlock (as revised by 1995, 2001, and 2005 Reactor Operations Annual Reports):
Replace with:
Updated Figure A.5, 10 MW Process Instrumentation Control & Interlock (MURR Dwg No. 41, Sheet 1 of 4, dated 12/26/06)
HSR, Addendum 4, page A-33, Figure A.6, 10 MW Process Instrumentation Control & Interlock (as revised by the 1995, 2001, 2002, 2003, and 2005 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 12/26/06)
HSR, Addendum 4, page A-34, Figure A.7, Annunciator Control 10 MW (as revised by the 1995, 2001, 2002, and 2005 Reactor Operations Annual Reports):
Replace with:
Updated Figure A.7, Annunciator Control 10 MW (MURR Dwg No. 138, Sheet 1 of 1, dated 12/26/06)
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, and 2005 Reactor Operations Annual Reports):
Replace with:
Updated Figure 2.1, Electrical Distribution (MURR Dwg No. 522, Sheet 1 of 3, dated 8/8/06) 111-7
SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2006 through December 31, 2006 For each facility modification described below, MURR has on file the safety evaluation as well as the documentation of review in accordance with 10 CFR 50.59.
Modification 75-16, Addendum 3:
Reactor Safety System Monitoring Circuit ("White Rat") Panel - Revision to Panel Overlays in Support of Modification Record 05-8 This modification record documents a revision to the instrument panel overlays that were necessary to support the replacement of the primary coolant system heat exchangers HX503A and HX503B and associated instrumentation under the following modification records: 05-8; 05-8, Addendum 1; and 05-8, Addendum 2. Changes to the overlays were merely editorial in nature, and did not affect the electronics of the system.
Modification 86-1, Addendum 2:
Replacement of Graphite Reflector Element "5J" (N6)
This addendum to modification record 86-1, "Reflector Element 5A and 5B," documents the replacement of reflector element 5J; the graphite element that accommodates irradiation position N6. Replacement of the N6 reflector element was necessary because the element had reached the end of its operational lifetime.
Modification 86-1, Addendum 3:
Replacement of Graphite Reflector Element "51" - Reflector Tank Position 5A/Irradiation Position L6 This addendum to modification record 86-1, "Reflector Element 5A and 5B," documents the replacement of reflector element 5I; the graphite element that accommodates irradiation position L6.
During the beryllium change-out in January 2006, reflector element 51 was removed in order to perform a visual inspection of the element and adjacent reflector tank area. Due to swelling, most likely caused by the growth of the graphite, attempts to reinstall the element were unsuccessful. The graphite element, which had been previously installed in position 4, was temporarily installed until a time when a new element 5I could be constructed and installed.
Modification 94-4, Addendum 1:
Replacement of Pool Coolant System Heat Exchanger HX 521 This addendum to modification record 94-4, "The Replacement of the Pool Tube and Shell Heat Exchangers with a Plate Type," documents the replacement of the current plate-type pool coolant heat exchanger with the exact same model that was initially installed in 1995 (with 151 plates).
Since installation in 1995, the pressure drop across the heat exchanger had steadily increased, which resulted in a decrease in total pool coolant system flow rate. An evaluation of the pool coolant heat exchanger was performed in February 2005 by the Engineering Firm Black & Veatch (B&V), Kansas City, Missouri. In the evaluation B&V states that due to the tight clearances between the plates, the heat exchanger will act like a filter and collect impurities in the water. Additionally, the maker of the heat exchanger (Graham Corporation) had previously inspected plates that had what appeared to be a thin layer of surface contaminants.
Both of these are sufficient to cause an increase in the pressure drop across the heat IV-1
exchanger. Installation of the new heat exchanger returned total pool coolant system flow rate to design values.
Modification 01-4, Addendum 8:
Replace General Electric Measurement and Control (GE/MAC) Type 570 Isolated Power Supply EP No.
91 IA with an API Model 9046 Power Supply This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation," is the continuation of the replacement of GE/MAC instrumentation and documents the upgrade of the existing GE/MAC Type 570- Isolated Power Supply, designated EP No. 911 A, with a new Absolute Process Instruments, Inc. (API) Model 9046-24 Regulated DC Power Supply. Additionally, this modification was necessary to support the instrumentation changes that were required for the primary coolant system heat exchanger replacement project. Modification record 01-4 is the blanket modification record that covers the systematic replacement of GE/MAC instrumentation.
Because of their age and the inability to purchase replacement parts, GE/MAC instrumentation had become obsolete.
Modification 01-4, Addendum 9:
Replace General Electric Measurement and Control (GE/MAC) Type 570 Isolated Power Supply EP No.
91 lB with an API Model 9046 Power Supply This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation," is the continuation of the replacement of GE/MAC instrumentation and documents the upgrade of the existing GE/MAC Type 570 Isolated Power Supply, designated EP No. 91 IB, with a new Absolute Process Instruments, Inc. (API) Model 9046-24 Regulated DC Power Supply. Additionally, this modification was necessary to support the instrumentation changes that were required for the primary coolant system heat exchanger replacement project. Modification record 01-4 is the blanket modification record that covers the systematic replacement of GE/MAC instrumentation.
Because of their age and the inability to purchase replacement parts, GE/MAC instrumentation had become obsolete.
Modification 01-4, Addendum 10:
Replace General Electric Measurement and Control (GE/MAC) Type 560 Alarm Unit EP No. 920C/D with an API Model 1000 G Alarm Trip Module This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation," is the continuation of the replacement and upgrade of GE/MAC instrumentation and documents the replacement of an existing GE/MAC Type 560 Alarm Unit, designated EP No. 920C/D, with a new Absolute Process Instruments, Inc. (API) Model 1000 G Alarm Trip Module.
Modification record 01-4 is the blanket modification record that covers the systematic replacement of GE/MAC instrumentation. Because of their age and the inability to purchase replacement parts, GE/MAC instrumentation had become obsolete.
Modification 01-4, Addendum 11:
Replace General Electric Measurement and Control (GE/MAC) Type 560 Alarm Unit EP No. 953 with an API Model 1000 G Alarm Trip Module This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation," is the continuation of the replacement and upgrade of GE/MAC instrumentation and documents the replacement of an existing GE/MAC Type 560 Alarm Unit, designated EP No. 953, with a new Absolute Process Instruments, Inc. (API) Model 1000 G Alarm Trip IV-2
Module.
Modification record 01-4 is the blanket modification record that covers the systematic replacement of GE/MAC instrumentation. Because of their age and the inability to purchase replacement parts, GE/MAC instrumentation had become obsolete.
Modification 01-4, Addendum 12:
Replace General Electric Measurement and Control (GE/MAC) Type 560 Alarm Unit EP No. 920A/B with an API Model 1000 G Alarm Trip Module This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation," is the continuation of the replacement and upgrade of GE/MAC instrumentation and documents the replacement of an existing GE/MAC Type 560 Alarm Unit, designated EP No. 920A/B, with a new Absolute Process Instruments, Inc. (API) Model 1000 G Alarm Trip Module. Modification record 01-4 is the blanket modification record that covers the systematic replacement of GE/MAC instrumentation. Because of their age and the inability to purchase replacement parts, GE/MAC instrumentation had become obsolete.
Modification 04-5:
Cooling Tower Electrical Upgrade Project This modification record documents the third step in an overall upgrade of the MURR Normal Electrical Power Distribution System. Modification record 01-14 documented the installation of a new 300-kVA transformer to help increase the facility's overall 120/208V load capacity while reducing load on the 120/208V Distribution Center.
Modification record 02-1 documented the replacement and upgrade of Substation "B" 1,000-kVA transformer with a 2,000-kVA transformer. This modification record was used as the initiating document with each phase of the cooling tower electrical upgrade project implemented as an addendum to this record.
Modification 04-5, Addendum 5:
Phase 5 of the Cooling Tower Electrical Upgrade Project - Upgrade Secondary Pump Motors to 150 HP Motors This addendum to modification record 04-5, "Cooling Tower Electrical Upgrade Project," implements the fifth phase of the cooling tower electrical upgrade project and documents the replacement of motors and motor controllers for secondary coolant circulation pumps, SP-1, SP-2, and SP-3.
This modification powers each motor from new motor controllers in the new Motor Control Center MCC-1, adds adjustable speed drives (ASD) with upstream harmonic filters, adds an electrical disconnect near the motor, replaces the secondary coolant circulation pump motors, and adds a control room display and control panel.
Modification 05-8:
Replacement of Primary Coolant System Heat Exchangers HX 503A and HX 503B This modification record was used as the initiating document in a coordinated set of addendums whose purpose was to replace the existing primary coolant system heat exchangers, modify and upgrade existing flow detectors and associated instrumentation, replace affected primary coolant system piping, and replace and replumb affected secondary coolant system piping.
Each major system modification (i.e. -
instrumentation, primary and secondary coolant system hydraulics) was documented as a separate addendum to this modification record.
IV-3
Modification 05-8, Addendum 1:
Replacement of Primary Coolant System Heat Exchangers HX 503A and HX 503B - Instrumentation Portion This addendum to modification record 05-8, "Replacement of Primary Coolant System Heat Exchangers HX 503A and HX 503B," documents the instrumentation changes that were necessary to support the replacement of the old shell and tube-type primary coolant heat exchangers with new plate-type heat exchangers.
Modification 05-8, Addendum 2:
Replacement of Primary Coolant System Heat Exchangers HX 503A and HX 503B - Heat Exchanger and Piping Portion This addendum to modification record 05-8, "Replacement of Primary Coolant System Heat Exchangers HX 503A and HX 503B," documents the primary and secondary coolant system changes that were necessary to support the replacement of the old shell and tube-type primary coolant heat exchangers with.
new plate-type heat exchangers. This addendum primarily documents the hydraulic modifications.
Modification 05-10:
Replace Pressure Vessel Tie-Rod Clevis Pins with Instrumented Load-Cell Clevis Pins This modification record documents the replacement of the reactor pressure vessel tie-rod clevis pins with instrumented load-cell clevis pins. The clevis pins are constructed with an internal strain gauge, as well as the full bridge circuit necessary to correlate strain to tension, thus allowing a more accurate method of determining the load applied to the tie-rods.
Modification 06-1:
Removal of Pressurizer Low Liquid Level Alarm Unit EP-932 and Signal Resistor Unit EP-931 This modification record documents the removal of alarm unit EP-932 and its associated signal resistor unit EP-93 1. EP-932 is a Bailey Type 745 Single Alarm Unit, whereas EP-931 is a Bailey Type 766 Signal Resistor Unit. Elimination of these components allowed for the removal of the Bailey Type 761 Instrument Rack, which was located below the other process instrumentation racks, allowing for the installation of a 4th General Electric Measurement and Control (GE/MAC) rack to support the additional instrumentation that was necessary for the primary coolant system heat exchanger project.
IV-4
SECTION V NEW TESTS AND EXPERIMENTS January 1, 2006 through December 31, 2006 New tests or experiments developed during this period under a Reactor Utilization Request (RUR) are as follows:
RUR 415: Neodymium Oxide
==
Description:==
This RUR authorizes the irradiation of up to 1.0 gram of enriched neodymium oxide (Nd 20 3) for use in research and development activities.
RUR 416: Iridium
==
Description:==
This RUR authorizes the irradiation of up to 3.6 grams of enriched iridium (Ir) for use in therapeutic applications.
RUR 417: Neodymium Nitrate
==
Description:==
This RUR authorizes the irradiation of up to 10.0 milligrams of enriched neodymium in the form of neodymium nitrate (Nd(N0 3)3) for use in research and development activities.
RUR 419 & 423: Iridium Oxide
==
Description:==
These RURs authorize the irradiation of up to 130 and 1700 grams of two different densities of iridium oxide (Ir20 3) doped ceramic beads for commercial applications.
RUR 420 & 422: Antimony Oxide
==
Description:==
These RURs authorize the irradiation of up to 130 and 375 grams of two different densities of antimony oxide (Sb 20 3) doped ceramic beads for commercial applications.
RUR 421 & 424: Scandium Oxide
==
Description:==
These RURs authorize the irradiation of up to 130 and 375 grams of two different densities of scandium oxide (Sc 20 3) doped ceramic beads for commercial applications.
RUR 425: Gadolinium Nitrate
==
Description:==
This RUR authorizes the irradiation of up to 10.0 milligrams of enriched gadolinium in the form of gadolinium nitrate (Gd(N0 3)3
- xH20) for use in research and development activities.
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.
V-1
SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2006 through December 31, 2006 Inspections:
There was one NRC inspection which reviewed Special Nuclear Material activities.
All records and activities were found to be in compliance with NRC rules and regulations. No violations were noted.
Reactor Characteristic Measurements:
Sixty-eight (68) refueling evolutions were completed in 2006.
Excess reactivity verifications were performed for each refueling. The largest measured excess reactivity value was 3.72%. MURR Technical Specification 3.1(f) requires excess reactivity to be less than 9.8%.
Reactivity Measurements:
In January 2006, the beryllium reflector, which surrounds the reactor core, was replaced. As part of this major maintenance activity, the change in reactivity due to the reflector replacement was quantified.
Additionally, the thermal and epithermal neutron flux profiles in the flux trap and graphite reflector regions were measured using flux wires before and after the replacement.
Differential blade-worth measurement of all four (4) shim control blades and the regulating blade was performed following the beryllium reflector replacement. Also, differential blade-worth measurement of two (2) shim control blades was performed following planned maintenance of the control blades.
Four (4) reactivity measurements were made to determine the reactivity worth of all samples loaded in the flux trap region experimental sample holder.
Three (3) reactivity measurements were made to determine the reactivity worth of several different types of sample or spacer materials irradiated in the flux trap region.
Five (5) reactivity measurements were made to characterize the reactivity worth of eight (8) new graphite reflector elements installed in the number 1, 2, 3, 4, 5A, 5B, 7, and 8 positions. Reactivity measurement of positions 1, 2 and 3 were made in conjunction with the beryllium reflector replacement measurement.
In support of the Nuclear Engineering labs, one (1) differential blade-worth measurement and one (1) primary coolant temperature coefficient measurement were also performed.
VI-l
SECTION VII RADIOACTIVE EFFLUENT January 1, 2006 through December 31, 2006 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2006 through December 31, 2006 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide Activity (Ci)
H-3 1.170E-01 Lu-177 3.952E-03 S-35 3.373E-03 Co-60 1.152E-03 Lu-177m 6.439E-04 Zn-65 6.244E-04 Ca-45 4.061E-04 P-32 2.776E-04 Cr-51 8.828E-05 Ag-110m 7.530E-05 Rh-105 5.764E-05 Sc-46 5.255E-05 Fe-59 3.148E-05 Re-188 3.090E-05 Ru-105 2.959E-05 K-42 2.237E-05 Rb-86 2.139E-05 Sb-124 2.070E-05 Np-239 1.165E-05 Mn-54 1.004E-05 Total H-3 1.170E-01 Total Other 1.088E-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, 2006 through December 31, 2006 Ordered by % Technical Specification (TS) Limit Isotope Average Concentration pCi/ml Total Release Ci TS Limit Multiplier
% TS Ar-41 2.55E-06 1.18E+03 350 72.8113 C-14 2.22E-11 1.01E-02 1
0.7400 Co-60 3.96E-14 1.83E-05 1
0.0792 H-3 1.82E-08 8.42E+00 350 0.0521 1-131 8.70E-14 4.02E-05 1
0.0435 Cd-109 7.83E-15 3.62E-06 1
0.0112 1-125 1.24E-14 5.71E-06 1
0.0041 Os-191 3.65E-14 1.69E-05 1
0.0018 Cs-137 2.57E-15 1.19E-06 1
0.0013 Hg-203 1.03E-14 4.77E-06 1
0.0010 Zn-65 4.05E-15 1.87E-06 1
0.0010 Au-196 1.08E-15 4.99E-07 350 0.0003 Ba-140 5.54E-15 2.56E-06 1
0.0003 As-77 4.24E-12 1.96E-03 350 0.0002 Pa-233 1.27E-15 5.86E-07 1
0.0002 Hf-181 6.59E-16 3.04E-07 1
0.0001 1-133 3.46E-13 1.60E-04 350 0.0001 S-35 2.05E-15 9.47E-07 1
0.0001 Note: C-14 activity is calculated based sections for the activation of N-14 to C-14.
on the ratio of argon to nitrogen in the air and the (n,p) reaction cross Isotopes observed at < 0.0001% TS limit are not listed.
Stack Flow Rate = 30,500 cfm Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, License R-103 Technical Specifications.
VII-2
SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2006 through December 31, 2006 Environmental samples are collected two times per year at eight (8) locations and analyzed for radioactivity. Soil and vegetation samples are taken at each location. Water samples are taken at three (3) of the eight (8) locations.
Analytical results are shown in Tables 1 and 2.
Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2006. All doses are approximately 20 mRem/year or less, except monitor numbers 9 and 15. These monitors are located near the loading dock where packages containing radioactive material are loaded on transport vehicles.
The doses recorded by these monitors are considered to be the result of exposure to packages in transit. The environmental monitoring program confirms that no environmental impact exists from the operation of the MURR facility.
The number of radiation and contamination surveys performed each month is provided in Table 4.
TABLE 1 Summary of Environmental Set 69 April 2006 Detection Limits*
Matrix Water Soil Vegetation Alpha 1.09 pCi/L
< 0.69 pCi/g 1.69 pCi/g Beta 3.04 pCi/L 4.49 pCi/g 3.87 pCi/g Gamma 199 pCi/L 0.79 pCi/g 1.51 pCi/g Tritium 3.66 pCi/mL of sample N/A 3.66 pCi/mL of distillate
- Gamma and tritium analyses are based on wet weights while alpha and beta analyses are based on dry weights.
Activity Levels - Vegetation Sample 1V69 2V69 3V69 4V69 5V69 6V69 7V69 10V69 Alpha (pCi/g)
< 1.69
< 1.69
.< 1.69
< 1.69
< 1.69
< 1.69
< 1.69
< 1.69 Beta (pCi/g) 33.73 32.34 43.43 24.72 20.79 26.80 18.94 18.94 Gamma (pCi/g)
< 1.51
< 1.51
< 1.51
< 1.51
< 1.51
< 1.51
< 1.51
< 1.51 H-3 (pCi/mL)
< 3.66
< 3.66
< 3.66
< 3.66
< 3.66
< 3.66
< 3.66
< 3.66 VIII-1
TABLE 1 (Cont'd)
Summary of Environmental Set 69 April 2006 Activity Levels - Soil Sample 1S69 2S69 3S69 4S69 5S69 6S69 7S69 10S69 Alpha (pCi/g)
< 0.69 1.19 1.19 1.33
< 0.69
< 0.69 1.04 1.04 Beta (pCi/g) 13.86 9.59 11.20 14.44
< 4.49 10.51 14.55 11.09 Gamma (pCi/g) 4.36 5.12 4.65 2.26 5.05 5.18 4.73 5.65 Activity Levels - Water Sample 4W69 6W69 10W69 Alpha (pCi/L)
< 1.09
< 1.09
< 1.09 Beta (pCi/L) 8.09 5.31 15.02 Gamma (pCi/L)
< 199
< 199
< 199 H-3 (pCi/mL)
< 3.66
< 3.66
< 3.66 TABLE 2 Summary of Environmental Set 70 October 2006 Detection Limits**
Matrix Water Soil Vegetation Alpha 0.67 pCi/L 0.67 pCi/g 0.95 pCi/g Beta 1.92 pCi/L 1.86 pCi/g 4.57 pCi/g Gamma 200 pCi/L 0.94 pCi/g 2.12 pCi/g Tritium 3.66 pCi/mL of sample N/A 3.82 pCi/mL of distillate
- Gamma and tritium analyses are based on wet weights while alpha and beta analyses are based on dry weights.
VIII-2
TABLE 2 (Cont'd)
Summary of Environmental Set 70 October 2006 Activity Levels - Vegetation Sample 1V70 2V70 3V70 4V70 5V70 6V70 7V70 10V70 Alpha (pCi/g)
< 0.95
< 0.95
< 0.95 1.01
< 0.95
< 0.95 1.58 1.01 Beta (pCi/g) 10.56 14.03 24.19 15.64 20.18 32.75 28.74 31.14 Gamma (pCi/g)
<2.12
<2.12
<2.12
<2.12
<2.12
<2.12
< 2.12
<2.12 H-3 (pCi/mL)
< 3.82
< 3.82
< 3.82
< 3.82
< 3.82
< 3.82
< 3.82
< 3.82 Activity Levels - Soil Samrnle 1S70 2S70 3S70 4S70 5S70 6S70 7S70 10S70 Alpha (pCi/g) 0.72 1.15 1.30
< 0.67 1.44 2.01 1.15 1.15 Beta (pCi/g) 18.71 18.85 20.18 7.49 18.31 10.83 15.37 19.38 Gamma (pCi/g) 4.63 2.30 1.29
< 0.94 2.88 1.13 1.67
< 0.94 Activity Levels - Water Sample 4W70 6W70 10W70 Alpha (pCi/L)
< 0.67
< 0.67
<0.67 Beta (pCi/L) 9.42 5.81 12.50 Gamma (pCi/L)
< 200
< 200
< 200 H-3 (pCi/mL)
< 3.66
< 3.66
< 3.66 VIII-3
TABLE 3 Environmental TLD Summary January 1, 2006 through December 31, 2006 Badge Direction Map Distance from 1 st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Total Number From MURR MLURR Stack 2006 2006 2006 2006 2006 (meters)
Net mR Net mR Net mR Net mR 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 Control Control WSW Not used Not used 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
N NNE In Building In Building Spare S
N/A N/A N/A N/A N/A 34 57 27 27 149 149 301 316 156 65 107 293 476 606 907 236 168 110 328 480 301 141 210 255 328 671 724 671 587 499 419 690 556 491 514 137 N/A N/A N/A 65 4.6 11.8 5.9 11.0 10.3 11.5 26.7 6.6 11.5 16.5 11.7 8.6 28.4 6.0 5.8 4.6 absent 0.2 10.9 7.1 3.9 5.1 9.7 10.1 3.9 10.1 16.2 8.4 9.4 9.9 5.9 5.7 2.1 8.0 0.0 0.0 4.7 6.5 4.6 18.3 20.3 8.4 4.3 2.9 0.0 0.0 1.3 0.0 1.8 24.6 0.0 0.0 4.4 5.5 4.2 21.5 0.0 0.2 0.0 0.0 0.0 2.4 0.0 0.0 0.0 1.1 0.0 0.0 3.5 0.0 6.2 2.4 3.3 0.0 0.0 0.0 0.8 0.0 absent absent 0.0 0.0 4.9 8.2 1.2 0.1 3.9 0.0 0.0 2.5 0.0 0.0 18.0 0.0 3.3 4.4 0.5 0.0 20.0 0.0 0.0 absent 0.0 0.0 0.0 0.0 0.0 absent 0.8 0.0 0.0 0.0 2.9 6.2 2.2 0.0 0.0 0.0 0.0 0.0 absent 0.0 absent 0.0 0.0 2.5 3.9 0.0 1.7 0.0 1.2 0.0 0.1 3.9 3.2 31.2 0.0 2.6 6.0 1.5 1.4 18.1 0.0 0.0 absent 0.0 0.0 0.0 absent 2.0 0.2 0.0 0.4 0.0 0.2 2.8 0.0 2.6 0.6 0.0 0.0 0.0 0.5 absent 5.2 0.0 0.0 0.0 4.4 11.4 0.4 0.0 11.4 13.0 5.9 14.9 14.2 16.5 100.5 6.6 17.4 31.3 19.2 14.2 88.0 6.0 6.0 4.6 0.0 0.2 13.3 7.1 5.9 5.3 11.6 10.5 3.9 13.8 21.9 20.8 16.6 13.8 5.9 5.7 2.1 9.3 0.0 5.2 4.7 6.5 4.6 30.1 43.8 10.0 6.1
- TLD No. 4 moved from spare to fence outside shipping area.
- TLD No. 5 moved from spare to outside wall of shipping area.
VIII-4
TABLE 4 Number of Facility Radiation and Contamination Surveys January 1, 2006 through December 31, 2006 January February March April May June July August September October November December TOTALS Radiation 73 60 69 51 38 70 52 63 41 69 43 40 669 Surface Contamination*
73 60 69 51 38 70 52 63 41 69 43 40 669 Air Samples**
RWP's 30 10 40 7
51 7
46 9
40 9
46 4
36 11 48 8
39 6
32 5
26 11 21 10 455 97
- In addition, general building contamination surveys are conducted each normal work day.
- Air samples include stack Ar-41, containment Ar-41, sump entries, and hot cell entries.
Miscellaneous Notes Manual Diaz was promoted to Health Physicist in May 2006.
Robert Taylor resigned as Health Physicist in August 2006.
During calendar 2006, MURR shipped 700 cubic feet of low-level radioactive waste.
VIII-5
SECTION IX
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS January 1, 2006 through December 31, 2006 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP Month January (1)
February March (2)
April May June July August September October November December (4)
Total to Date Monthly Ave AC DO FSO HC RAG IRR NA 58 26 63 28 16 17 32 36 22 5
31 20 228 7
4 52 0
0 1
0 0
0 10 220 259 266 401 55 80 214 139 27 102 124 141 39 336 115 185 34 22 82 141 26 52 23 128 20 124 96 213 16 59 (3) 329 28 25 0
136 12 142 0
184 20 318 0
207 16 1137 0
464 48 57 10 10 16 37 15 21 37 15 14 13 21 NS OPS PRO RP SH SIL TCI 5
5376 41 239 140 136 0
36 1156 33 70 107 172 2
23 932 32 40 174 116 1
30 1255 39 37 171 136 0
16 1173 51 45 257 179 10 20 942 34 63 273 123 0
30 1522 76 79 268 131 0
71 1101 36 103 592 113 0
37 1017 49 28 266 105 0
32 1311 60 224 417 125 0
124 1503 107 37 351 113 0
2 1683 89 60 445 101 0
Total 7261 2079 1801 2434 2055 1710 2609 2505 1712 2534 2830 4290 354 522 2656 920 2668 341 30 44 221 77 222 28 Highest WB 11 102 200 123 143 39 266 426 18971 647 1025 3461 1550 22 36 1581 54 85 288 129 43 60 402 60 146 269 93 330 40 660 1690 150 800 290 OPS - Operations SIL - Silicon PRO - Isotope Production TCI - Special Project RP - Radiophariceutical SH - Shipping 13 33820 1
2818 10 70 Highest EXT 250 200 700 860 200 110 AC - Analytical Chemistry RAG - Health Physics DO - Director's Office IRR - Irradiations FSO - Shops NA - Nuclear Analysis HC - Hot Cell NS - Neutron Scattering WB = Whole Body EXT = Extremities Dosimetry services are provided by R.S. Landauer Jr. & Company (except self-reading dosimetry).
Analysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA. Radiation workers who are not full time staff members have radiation exposures which are generally lower than full time radiation workers.
Note (1): January numbers are higher than normal due to replacement of the beryllium reflector.
Note (2): Dosimetry based on estimates as postal service lost monthly shipment.
Note (3): Hot cell (HC) combined with shipping (SH) beginning in August 2006.
Note (4): Pool and primary coolant system heat exchangers and north side graphite element replacement project.
IX-1