ML17262A146
| ML17262A146 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 02/24/2017 |
| From: | Rhonda Butler, Meffert B Univ of Missouri - Columbia |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17262A146 (41) | |
Text
lEJj University of Missouri February 24, 2017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station Pl -3 7 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 2016 Reactor Operations Annual Report Research Reactor Center 1513 Research Park Drive Columbia, MO 65211 PHONE 573-882-4211 WEB murr.missouri.edu Enclosed is a copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2016 through December 31, 2016.
This document is submitted to the U.S. Nuclear Regulatory Commission in accordance with the University of Missouri Research Reactor Technical Specification 6.6.e.
If you have any questions regarding the contents of this report, please contact Bruce Meffert at MeffertB@missouri.edu or by calling (573) 882-5118.
Sincerely, =.Mr Reactor Manager BAM/jlm Enclosure xc:
Mr. Geoffrey Wertz, U.S. NRC Mr. Johnny Eads, U.S. NRC ENDORSEMENT:
Reviewed and Approved
<.i4.u~
Director
UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERA TIO NS ANNUAL REPORT January 1, 2016 - December 31, 2016
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UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2016 through December 31, 2016
- Compiled by the Research Reactor Staff of MURR Submitted by:
Reviewed and approved by:
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R~lph A. Butler, PE.
Reactor Facility Director
INTRODUCTION UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2016 through December 31, 2016 The University of Missouri Research Reactor (MURR) is a multi-disciplinary research and education facility providing a broad range of analytical, materials science, and irradiation services to the research community and the commercial sector. Scientific programs include research in archaeometry, epidemiology, health physics, human and animal nutrition, nuclear medicine, radiation effects, radioisotope studies, radiotherapy, boron neutron capture therapy, and nuclear engineering; and re.search techniques including neutron activation analysis, neutron and gamma-ray scattering, and neutron interferometry. The heart of this facility is a pressurized, reflected, ppen pool-type, light water moderated and cooled, heterogeneous reactor designed for operation at a maximum steady-state power level of I 0 Megawatts thermal - the highest powered university-operated research reactor in the United States.
On October 13, 2016, MURR celebrated 50 years of safe and reliable operation. Additionally, MURR received the American Nuclear Society (ANS) Nuclear Historic Landmark Award. The ANS Nuclear HiStoric Landmark Award was established in 1985 to identify and memorialize sites or facilities where outstanding physical accomplishments have taken place that have been instrumental in the advancement and implementation of nuclear technology and the peaceful uses of nuclear energy.
The Reactor Operations Annual Report presents a summary ofreactor operating experience for calendar year 2016.
Included within this report are changes to MURR reactor operations and health physics procedures, revisions to the Hazards Summary Report and its addenda, facility modifications, new tests and experiments, reactor physics activities, and environmental and health physics data.
This report is being submitted to the U.S. Nuclear Regulatory Commission (NRC) to meet the administrative requirements of MURR Technical Specification 6.6.e.
ACKNOWLEDGMENTS The success of MURR and these scientific programs is due to the dedication and hard work of many individuals and organizations. Included within this group are: the University administration; the governing officials of the State of Missouri; the Missouri State Highway Patrol; the City of Columbia Police Department; the Missouri University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our regulators; those who have provided funding including the Department of Energy (DOE) and the National Nuclear Security Administration (NNSA);
Argonne National Laboratory (ANL); Idaho National Laboratory (INL); Sandia National Laboratories (SNL); the researchers; the students; the Cofombia Fire Department (CFD); the Campus Facilities organization; members of the National Organization of Test, Research and Training Reactors (TRTR); and many others who have made, and will continue to make, key contributions to our overall success. To. these individuals and organizations, the staff of MURR wishes to extend its fondest appreciation.
Some of the major facility projects that were supported by Reactor Operations during this past calendar year included (1) removal of two unused nuclear instrumentation drywells, (2) replacement of trolleys on reactor containment building pedestrian entry door 277, (3) replacement of nuclear instrumentation power range channel no.
6 detector and cabling, (4) replacement of the reactor containment building truck entry door 101 inflatable seal, (5) replacement of three primary coolant pressure instrument channel meter-relay trip units, and (6) irradiating and processing multiple natural and low-enriched uranium (LEU) targets to determine the feasibility of producing molybdenum-99 using a variety of processing technologies. Additionally, in August 2006, MURR submitted a request to the NRC to renew Amended Facility Operating License No. R-103. Significant efforts to complete the process of renewing the Facility Operating License continued in 2016 by responding to the NRC's Requests for Additional Information.
The facility continues to actively collaborate with the Reduced Enrichment for Research and Test Reactors (RERTR) Program and four other U.S. high-performance research and test reactor facilities that use highly-enriched uranium (HEU) fuel to find a suitable LEU fuel replacement. Although each one of the five high-performance reactors is responsible for its own feasibility and safety studies, regulatory interactions, fuel procurement and conversion, there are common interests and activities among all five reactors that will benefit from a coordinated,.
working-group effort. This past year, Phase 2 of the accident analyses for the proposed LEU conversion core was completed. This included finalizing the Maximum Hypothetical, Fuel Handling, Loss of Coolant, Loss of Flow, and Reactivity Insertion Accidents. Additionally, one PhD studerit continued assisting MURR in the fuel conversion work by supporting research in determining the material property changes in the beryllium reflector, and hence its lifetime, as a result of a fuel conversion. Work also started in drafting a Fuel Conversion Safety Analysis Report that will be submi.tted to the NRC in calendar year 2017.
Reactor Operations management also wishes to commend the two individuals who received their Reactor Operator.
certifications from the NRC. These individuals participated in a rigorous training program of classroom seminars, self-study, and on-the-job training. The results of this training are confident, well-versed, decisive individuals capable of performing the duties of a licensed operator during normal and abnormal situations.
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TABLE OF CONTENTS Reactor Operations Summary......................................................................................... 1-1 through 5 MURR Procedures.......................................................................................................... 11-1 through 14 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 Revisions to the Hazards Summary Report..................................................................... III-1 through 3 Plant and System Modifications...................................................................................... IV-1 through 2 New Tests and Experiments............................................................................................ V-1
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Special Nuclear Material and Reactor Physics Activities..................,............................ VI-1 Radioactive Effluent............................................................................... _......... :............... VII-1 through 2 Table 1 - Sanitary Sewer Effluent Table 2 - Stack Effluent Environmental Monitoring and Health Physics Surveys................................................. VIII-1through6 Table 1 - Summary of Environmental Set 89 Table 2-Summary of Environmental Set 90 Table3-Environmental TLD Summary Table 4-Number of Facility Radiation and Contamination Surveys Summary of Radiation Exposure to Facility Staff, Experimenters,............................... IX-1 and Visitors iii J
SECTION I REACTOR OPERATIONS
SUMMARY
January 1, 2016 through December 31, 2016 The following table and discussion summarizes reactor operations during the period from January 1, 2016 through December 31, 2016.
Month FulHPower Hours Megawatt Dajrs Full Power % o[T:otal Full Power % of
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Sch.~duled{
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January 678.00 282.72 91.1 102.0 February 623.82 260.22 89.6 100.5 March 682.02 284.48 91.7 102.6 April 645.48 269.11 89.7 100.5 May 663.11 276.78 89.l 99.8 June 659.02 274.75.
91.5 102.7 July 679.80 283.42 91.4 102.3 August 661.85 276.01 89.0 99.6 September 660.58 275.42 91.7 102.9 October 661.20 275.63 88.9 99.5 November 656.94 273.83 91.2 102.3 December 676.59 281.97 90.9 101.8 Total for 7948.41 3314.34 90.49 %
101.38 %
the Year MURR is scheduled to average at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> of full power operation per week. Total time is the number of hours in the month listed or the year.
JANUARY 2016 The reactor operated continuously in January with the following exceptions:
four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, and one unscheduled/unplanned power reduction. An NRC inspector conducted a routine scheduled inspection of Reactor Operations and Emergency Preparedness.
On January 5, with thereactor operating at 10 MW in the automatic control mode, the Lead Senior Reactor Operator (LSRO) observed a noticeable internal snap of the three-position ("In-Normal-Out") Control Rod Operate Switch (1S4) while attempting to perform a routine control blade shimming evolution. Operation of the Control Rod Operate Switch failed to cause movement of control blade 'D' in either the inward or outward direction and the switch would also not automatically spring return to the "Normal" mid-position. A manual scram was immediately initiated by the LSRO due to the inability to manually operate the shim control blades. The LSRO completed all 1-1
Immediate and Subsequent Actions of reactor emergency procedure REP-2, "Reactor Scram," and verified all control blades were fully inserted. Subsequent investigation of the switch assembly verified the torsion spring had failed. The entire switch assembly was replaced, and operational checks were completed satisfactorily. Permission to restart the reactor was obtained from the Reactor Manager, and the reactor was subsequently returned to 10 MW operation.
Failure of the three-position Control Rod Operate Switch (1S4) while operating resulted in a deviation from Technical Specification 3.2.a, which states, "All control blades, including the regulating blade, shall be operable during reactor operation." Licensee Event Report No. 16-01 was submitted to the U.S. Nuclear Regulatory Commission on January 29, 2016.
Major maintenance items for the month included:
removing an unused nuclear instrumentation drywell; and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-17(B)."
FEBRUARY 2016 The reactor operated continuously in February with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, two shutdowns for training, one shutdown for physics measurements, and one unscheduled/unplan11ed power reduction.
On February 29, with the reactor operating at 10 MW in the automatic control mode and while attempting a routine control blade shimming evolution, the duty operator mistakenly operated the Regulating Rod Operate Switch (1S5);
thereby, placing the reactor in the manual control mode. While attempting to return the reactor to the automatic control mode, a "Channel 4, 5 & 6 High Power" rod run-in was automatically initiated when indicated reactor power reached 114% on Nuclear Instrumentation Power Range Channel No. 6. All other reactor power indications were
- less than 114%, and the primary power meter indicated a maximum power level of 9.80 MW.
All reactor
- temperature, pressure, and flow indications at the time of the rod run-in remained within prescribed operating bands.
The Lead Senior Reactor Operator verified that no Safety Limits had been exceeded. Permission to recover from the rod run-in was given by the Assistant Reactor Manager-Operations, and the reactor was returned to 10 MW operation.
Major maintenance items for the month included: replacing the air actuator for primary coolant. demineralizer inlet valve 527E; loading new de-ionizing bed 'S' and placing it on pool coolant system service; removing an unused nuclear instrumentation drywell; and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, Measurement of Differential Worth of a Shim Blade, RTP-1 l(D)."
MARCH2016 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one shutdown for training.
There were no unscheduled/unplanned power reductions this month. An NRC examiner administered reactor operator licensing exams. An NRC inspector conducted a routine inspection of the Radiation Protection and Shipping Programs. MURR received notification of the issuance of Amendment No. 37 to Amended Facility Operating License No. R-103.
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Major maintenance items for the month included: replacing the trolleys on reactor containment building pedestrian entry door 277.
APRIL2016 The reactor operated continuously in April with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: completing the biennial change out of Controi Blade 'B' Offset Mechanism and associated retesting; and performing a reactivity worth* measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth ofa Shim blade', RTP-1 l(D)."
MAY2016 The reactor operated continuously in May with the following exceptions: six shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, and one unscheduled/unplanned power reduction.
On May 3, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5 & 6 High Power" rod run-in was automatically initiated when Nuclear Instrumentation Power Range Channel No. 6 front panel indicated that a rod run-in signal had occurred. Investigation did not reveal any upward spikes or abnormal indication on Power Range Channel No. 6 strip chart recorder. All other power level indications were normal -
between 100 to 105%. After reactor power was allowed to reduce to 2 MW, the rod run-in was reset. Additional investigation did not reveal a specific failure or cause. Permission was granted from the Reactor Manager to return 10 MW operation. Note: Nuclear Instrumentation Power Range Channel No. 6 detector and cabling were replaced on the next scheduled maintenance day in response to this rod run-in.
Major maintenance items for the month included: replacing Nuclear Instrumentation Power Range Channel No. 6 detector and cabling; completing compliance procedure CP-26, "Containment Building Compliance Test;" and performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-l 7(B)."
JUNE 2016 The reactor operated continuously *in June with the following exceptions:
four shutdowns for scheduled maintenance and/or refueling, and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: loading new de-ionizing bed 'G' and placing it on pool coolant system service; performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-l 7(B);" conducting the annual emergency preparedness drill; completing Modification Record 01-09, Addendum 7, "MURR Industrial Building Expansion Emergency Power Fitout;" and competing Modification Record 16-01, "Trip Actuator Amplifier Biasing Resistors Replacement."
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JULY2016 The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, two shutdowns for physics measurements, and one shutdown for license examination. There were no unscheduled/unplanned power reductions this month. An NRC examiner administered reactor operator licensing examinations.
Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-R0-200, "Measurement of Differential Worth of a Shim blade, RTP-1 l(D);" performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-17(B);" and completing Modification Record 99-04, Addendum 1, "Replace Conductivity Indicators."
AUGUST2016 The reactor operated continuously in August with the following exceptions:
five shutdowns for scheduled maintenance and/or refueling, one shutdown for unscheduled maintenance and/or refueling and one shutdown for training. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: replacing reactor containment building truck entry door 101 inflatable seal; replacing control blade 'B' rod position indication encoder; and completing Modification Record 03-03, Addendum 7, "Fire Protection in NOA Shell Space Laboratory Fitout."
SEPTEMBER 2016
- The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no Uf!.scheduled/unplanned power reductions this month.
Major maintenance items for the month included: replacing the valve operating air compressor pop-off relief valve; and loading new de-ionizing bed 'W' and placing it on pool coolant system service.
OCTOBER 2016 The reactor operated continuously in October with the following exceptions:
five shutdowns for scheduled maintenance and/or refueling. There* were no unscheduled/unplanned power reductions this month.
An NRC inspector conducted a routine scheduled inspection of Reactor Operations and Emergency Preparedness.
Major maintenance items for the month included: performing.the biennial changecout of Control Blade 'D' Offset Mechanism :;ind associated retesting; performing a reactivity worth measurement in accordance *with reactor procedure RP-R0~200, "Measurement of Differential Worth of a Shim blade, RTP-1 l(D);" and completing Modification Record 86-03, Addendum 1, "P~Tube Lab Control S.tation PLC."
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I NOVEMBER 2016 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, and one unscheduled/unplanned power reduction.
On November 8, with the reactor operating at 10 MW in the automatic control mode, a "Power Level Interlock" reactor scram was automatically initiated by 1K26 relay contact loss of conductivity. The duty operator and Lead Senior Reactor Operator verified all lights on the "yellow leg" portion of the scram monitoring system were extinguished. Investigation revealed dirty contacts on 1K26 relay (contacts 3-4). The contacts were. burnished followed by a discussion with Operations management, and the reactor was returned to 10 MW operation with the permission of the Reactor Manager.
Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-R0-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-17(B)."
DECEMBER 2016 The reactor operated. continuously in December with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.
Major maintenance items for the month included: loading new de-ionizing bed 'O' and placing it on primary*
coolant system service; completing Modification Record 16-02, "Replacement of Primary Coolant Pressure Instrument Channel PT-943 Control Room Meter-Relay (BEEDE Model MR4) with Rosemount BG 241 Meter Readout and API 1000 G Dual Alarm Trip Unit;" and completing Modification Record 16-03, "Replacement of Primary Coolant Pressure Instrument Channels PT-944A and PT-944B Control Room Meter-Relays (BEEDE Model 3324) with Rosemount BG 241 Meter Readouts and API 1000 G Dual Alarm Trip Units."
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- SECTION II MURR PROCEDURES January 1, 2016 through December 31, 2016 As required by administrative Technical Specification 6.6.e(5), this section of the Annual Report includes a summary of procedure changes. These procedure changes were reviewed by the Reactor Manager or Reactor Health Physics Manager, as applicable, and others to assure compliance with the requirements of 10 CFR 50.59. These procedure changes were also reviewed by the Reactor Procedure Review Subcommittee of the Reactor Advisory Committee to meet the requirements of Technical Specification 6.2.a(2).
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 we_re one hundred and four (104) revisions issued to the reactor operations procedures, forms, and operator aids. Additionally, two (2) new procedures were issued while one (1) form and three (3) procedures were obsoleted.
The majority of the revisions were strictly formator editorial in nature, such as cover page changes. The foiiowing is a list of the new and revised procedures, forms and operator' aids:
Number Name.*
Rev. Revision: Datei Notes AP-R0-110 Conduct of Operations 20 3/22/2016 Minor Editorial AP~R0-110 Conduct of Operations 21 9/20/2016 Minor Editorial AP-R0-110 Conduct of Operations Minor Editorial AP-R0-115 Modification Records Cover Page AP-R0-135 Reactor Utilization Requests AP-RR-003 10 CFR 50.59 Evaluations or Editorial EX-R0-105 Reactor Irradiation Experiments 22 EX-R0-105 Reactor Irradiation Experiments 23 10/11/2016 Minor Editorial EX-R0-110 Pneumatic Tube System 0
9/20/2016 New Procedure EX-R0-120 Beamport 'A' Operation 13 9/6/2016 Minor Editorial EXcR0-120 Beamport 'A' Operation 14 11/4/2016 Minor Editorial EX-R0-121. Beamport 'B' Operation
- 13 9/6/2016 Minor Editorial EX-R0-121 Beamport 'B' Operation 14 11/4/2016 Minor Editorial EX-R0-122 Beamport 'C' Operation 14 9/6/2016 EX-R0-122 Beamport 'C' Operation 15 11/4/2016 EX-R0-123 Beamport 'D'. Operation 13 9/6/2016 EX-R0-123 Beamport 'D' Operation EX-R0-124 Beamport 'E' Operation EX-R0-124 Beamport 'E' Operation EX-R0-125 Beiimp()rt 'F' Operation 11-1
Number EX-R0-125 EX-R0-126 FM-08 FM-11 FM-15 FM-15 FM-16 FM-18 FM-19 FM-33 FM-43 FM-43 FM-43 FM-56 FM-56 FM-57 FM-63 FM-64 FM-65 FM-66 FM-68 FM-127 FM-143 IRR-PS0-100 IRR-PS0-106 IRR-PS0-106 IRR-PS0-111 OA-3 OA-4 OA-5 OA-5 OA-23 OA-23 OP-R0-100 OP-R0-101 OP-R0-210 OP-R0-210 OP-R0-211 OP-R0-212 OP-R0-212 OP-R0-220 OP-R0-250 Name Beamport 'F' Operation Thermal Column Door Fuel Movement Sheet Reactor Shutdown Checksheet 10 CFR 50.59 Qualified Reviewers List 10 CFR 50.59 Qualified Reviewers List Primary - Pool Coolant Water Analysis Deviation From Procedure Report Unscheduled Power Reduction Report Containment Building Restricted Materials Nuclear and Process Data Sheet Nuclear and Process Data Sheet Nuclear and Process Data Sheet Reactor Routine Patrol Reactor Routine Patrol Long Form Startup Checksheet DI Water Makeup Log DI Resin Log Filter Status Log Customer Sample Pre-Encapsulation Evaluation Worksheet Target Material Control Checksheet MURR Irradiations Encapsulation Evaluation Worksheet l/M Graph Scheduling Flux Trap Tubes Target Material Control Checks Target Material Control Checks Customer Sample Pre-Encapsulation Evaluation Beamport and Pool Overflow Loop Seals Valve Operation Air Compressor Emergency Air Compressor Emergency Air Compressor North and South Condensate Pumps North and South Condensate Pumps Main Air System Instrument Air System Reactor Startup-Normal Reactor Startup-Normal Reactor Startup - Hot Reactor Startup - Recovery from Temporary Power Reduction Reactor Startup - Recovery from Temporary Power Reduction Reactor Shutdown or Power Reduction In-Pool Fuel Handlirig II-2 Rev.i Revision Date Notes 16 11/4/2016 I Minor Editorial 10 10/11/2016 Cover Page 9/20/2016 Cover Pag 7
12/5/2016 Minor Edi 20 7/18/2016 Minor Edi 21 12/6/2016 Minor Edi 10 2/23/2016 Minor Editorial 8
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6 12/5/2016 age 6
- 10/11 21 7/15/2016 Editorial 22 11/4/2016 io' Editorial 23 12/5/2016 or Editorial 19 2/23/2016 or Editorial 12/5/2016 Minor Editoria 2
2/3/2016 Minor Editoria 11 5/6/2016 Minor Editori 7
8/11/2016 Cover Page 7
8/11/2016 Cover Page
.8 5/6/2016 Minor Editori1 13 3/23/2016 Obsole 3
6/8/2016 Minor Editori 2
9/20/201_6 Cover Page 8
8/11/20 l~nor Editorial 11 21231201 Minor Editorial 12 12/6/2016 Minor Editorial 9
5/20/2016 Minor Editorial 10 12/5/2016 Cover Pag 9
11/4/2016 CoverPag 9
11/10/2016 Minor Edito 10 12/5/2016 Minor Edito 4
1/26/2016 c
5 11/4/2016 Cover Page
. 13 11/4/2016 Minor Editorial 12 2/23/2016 Cover Page
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10/11/2016 Minor Editorial 16 12/5/2016 Minor Editorial
~0/11/2016 Minor Editorial 9/6/2016 Cover Page 14 10/11/2016 Minor Editorial 10 61312016 l Minor Editorial 17 1114/2016 Minor Editorial
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Number *.
OP-R0-310 OP-R0-311 OP-R0-312 OP-R0-330 OP-R0-340 OP-R0-410 OP-R0-420 OP-R0-460 OP-R0-465 OP-R0-466 OP-R0-480 OP-R0-510 OP-R0-515 OP-R0-516 OP-R0-520 OP-R0-520 OP-R0-530 OP-R0-530 OP-R0-530 OP-R0-533 OP-R0-555 OP-R0-720 OP-R0-720 OP-R0-741 OP-R0-741 OP-R0-741 RM-R0-405 RP-R0-100 RP-R0-200 RP-R0-300 SM-R0-011 SM-R0-011 SM-R0-025 SM-R0-105 SM-R0-200 SM-R0-300 SM-R0-410 SM-R0-420
-SM-R0-500 SM-R0-620
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Name Nuclear Instrumentation - Signal Processor #1 Nuclear Instrumentation - Signal Processor #2 Nuclear Instrumentation Power Range Monitor - Channel 6 Nuclear Instrumentation - *Wide Range Monitor Nuclear Instrumentation Adjustment Primary Coolant System Primary and Pool Water Analysis Pool Coolant System - Two Pump Operation Pool Level Control - Skimmer System Pool Level Control - Pool Coolant System Secondary Coolant System Nitrogen System Emergency Air System Valve Operation Air System Emergency Power Generator Emergency Power Generator Demineralized Water Supply System Demineralized Water Supply System Demineralized Water Supply System Skimmer System Fire Protection System Radiation Monitoring - Stack Monitor Operational Check Radiation Monitoring - Stack Monitor Operational Check Waste Tank System Operation Waste Tank Systein Operation Waste Tank System Operation Reactor Demineralizer System
- Fuel Movement Measurement of Differential Worth ofa Shim Blade, RTPcl l (D)
Receipt, Inspection and Accounting ofUnirradiated Fuel Beryllium Reflector Replacement Beryllium Reflector Replacement Removal, Transfer or Installation of a Control Blade Offset Mechanism Replace.Primary and Pool Coolant System Heat Exchangers and Piping Manual Operation of Airlock Doors 276 and 277 Control Console And Instrument Panel-Securing Power Pool Hold-Up Tank (T-504) Epoxy Repair Pressurizer Operation - Maintenance & Test Replacement of Flux Trap Irradiations Reactivity Safety Trip Support Rig Control Blade Leak Test 11-3 Rev*: Revision Date*
Notes 1~016 Minor Editorial 1
016 Minor Editorial 14 3/22/2016 Cover Page 11 3/22/2016 ver Page 11 3/22/2016 ver Page 13 7/15/2016 or Editorial 8
1/26/201 over Pa 16 11/4/2016 Obsolete 10 1/26/2016 Cover Page 13
/2016 Cover Page 20 2/2016 Minor Editorial 8
8/11/2016 Minor Editorial 12 I
9/20/2016 Cover Pag 11 I
2/3/2016 over Pag 13 7/22/2016 inor Editorial 14 10/11/2016 Minor Editorial 1
/3/2016 Minor Editorial 17 9/20/2016 Minor Editorial 18 1114/2016 Minor Editorial 9
10/11/2016 Cover Page 13 2/3/2016 Minor Editor 13 3/22/2016
! Minor Editorial 14 7/22/2016 Minor Editorial 19 7/15/2016 Minor Editorial 20 8/11/2016
~or Editorial 21 1114/2016
- or Editorial 14 8/11/2016 over Page 12 2/23/2016 nor Editorial 6
10/14/2016
- Minor Editorial 5
8/24/2016 Minor Editorial 5
9/22/2016 Minor Editorial h
,, ' 0 /2016 Minor Editorial 0
7/19/2016 New Procedure 2
12/6/2016 Obsoleted 4
11/8/2016 Cover Page 12 9/22/2016 Cover Page 3
9/22/2016 Obsoleted 6
9/22/2016 Cover Page 2
10/14/2016 Cover Page 6
2/24/2016 Minor~
Number Name i
Rev.i Revision Date~
Notes i'
SM-R0-625 Measuring Control Blade Pull Weight and Blade Drop Time 3
9/22/2016 Minor Editorial with the Test Magnet Assembly, RTP-21 SM-R0-625 Measuring Control Blade Pull Weight and Blade Drop Time 4
12/6/2016 Minor Editorial with th~ Test Magnet Assembly, RTP-21 SM-R0-635 Retracting and Reinserting Beamport 'A' Liner 5
2/4/2016 Cover Page SM-R0-636 Retracting and Reinserting Beamport 'B' Liner 5
2/4/2016 Cover Page I SM-R0-637 Retracting and Reinserting Beamport 'C' Liner 5
2/4/2016 Cover Page SM-R0-638 Retracting and Reinserting Beamport 'D' Liner 6
2/4/2016 Cover Page SM-R0-639 Retracting and Reinserting Beamport 'E' Liner 5
2/4/2016
~over Pa SM-R0-661 Pool Coolant H<?!d:'CJP Tank We"lding Repair Insti:uctions 3
12/6/2016 nor Edito 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 th~m to be adequate for the safe and reliable operation of the facility.
There were seventeen (17) revisions issued to the emergency procedures, forms and operator aids. The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures, forms and operator aids:
Number Name
- Rev. Revision Date Notes EP-R0-007 Severe Natural Phenomenon 6
7115/2016 Minor Editorial EP-R0-013 Facility Evacuation 8
7/15/2016 Minor Editori EP-R0-013 Facility Evacuation 9
12/19/2016 Minor Edit EP-R0-014 Emergency Planning Zone and Site Area Evacuations 8
7/15/2016 Minor Edito EP-R0-015 Emergency Notifications 13 1/29/2016 Minor Editoria EP-R0-015 Emergency Notifications 14 3/2/2016 Minor Editorial EP-R0-018 Emergency Radiation Exposure 6
8/23/2016 Minor Editorial EP-R0-019 Emergency Dosimeters 3
1114/2016 Minor Editorial FM-104 Emergency Call List 27 3/2/2016 Minor Editorial FM-104 Emergency Call List 28 7/15/2016 Minor Editorial FM-104 Emergency Call List 29 11/4/2016 Minor Editorial FM-104 Emergency Call List 30 12/19/2016 Minor Editorial OA-20 Emergency Equipment 20 7/15/2016 Minor Editorial OA-20 Emergency Equipment 21 8/23/2016 Minor Editorial REP-R0-100 Reactor Emergency Procedures 18 2/23/20l~uitorial REP-R0-100 Reactor Emergency Procedures 19 917/2016 nu1torial I REP-R0-100 Reactor Emergency Procedures 20 12/30/201 r J...
~ "torial I II-4
- * * * * * *
- I.
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 two hundred and forty-seven (247) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. Additionally, fifteen (15) new procedures, seven (7) new forms, and four (4) new operator aids were issued while eight (8) procedures and five (5) forms were obsoleted. The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures and forms:
Number 1
~'
Name.
- ~;
Rev. }!evisionDate! \\
Not~s.
ACG-NAA-217 Processing High Purity Materials 8
917/2016 Minor Editorial ACG-NAA-218 Cleaning Options for High Purity Materials 7
3/17/2016 Minor Editorial Processing ACG-NAA-221 High Purity Materials Analysis Flux Monitor 9
5/20/2016 Minor Editorial Measurement jACG-NAA-1725 jAnalyzing Platinum in Silicone 6
917/2016 Minor Editorial AP-HP-105 Radiation Work Permit 13 2/24/2016 Minor Editorial 1 AP-HP-105
!Radiation Work Permit I 14 I 5/6/2016 I Minor Editorial AP-HP-110 Controlled Special Exposures 6
1/11/2016 Minor Editorial AP-HP-115 Iodine 131 Bioassay 1
5/20/2016 Minor Editorial AP-HP-115 Iodine 131 Bioassay 2
9/27/2016 Minor Editorial AP-HP-117 MURR Initial Radiation Worker Training Program 12 9/26/2016 Minor Editorial AP-HP-119 High Radiation Area Access 8
3/22/2016 Minor Editorial AP-HP-122 Material License Projects Quarterly Review 10 12/22/2016 Minor Editorial AP~HP-122 Material License Projects Quarterly Review 9
2/10/2016 Minor Editorial AP-HP-123 Visitor Dosimetry - Reception Desk 11 1/11/2016 Cover Page AP-HP-127 Radioactive Material Licensing and Project 5
5/6/2016 Cover Page Designation Change Request AP"'.HP-129 Hot Cell, HC-01 Control 13 3/14/2016 Minor Editorial AP-HP-130 Reactor License Projects Annual Review 6
2/10/2016 Minor Editorial AP-HP-130 Reactor License Projects Annual Review 7
11/30/2016 Minor Editorial AP-HP-150 Source Calibration 6
7/19/2016 Cover Page AP-SH-001 Administrative Procedure - Radioactive Material 9
12/29/2016 Minor Editorial Shipping AP-SH-002 In-House Radioactive Shipping Request Form 6
12/29/2016 Minor Editorial Instructions BPB-SH-020 Receipt Inspection Of Type B Shipping Package 7
1117/2016 Minor Editorial BPB-SH-023 Type B Equipment Calibration 5
3/23/2016 Minor Editorial BPB-SH-024 Type B USN0697/B(U)-96 (F-458 Series) Packaging 6
5/19/2016 Minor Editorial of Type B Radioactive Material BPB-SH-024 Type B USN0697/B(U)-96 (F-458 Series) Packaging 7
9/21/2016 Minor Editorial lof Type B Radioactive Material 11-5 I
- Number...
}
Name BPB-SH-025 Packaging of Type B Radioactive Material Using USA/0562/B(U)-96 (BEATRICE)
BPB-SH-026 Type B(U) F-327 Series Packaging of Type B Non-Waste Radioactive Material BPB-SH-027 Survey and Decontamination of Returned Shipping Containers BPB-SH-027 Survey and Decontamination of Returned Shipping Containers BPB-SH-027 Survey and Decontamination of Returned Shipping Containers BPB-SH-027 Survey and Decontamination of Returned Shipping Containers Packaging of Type B Radioactive Material Using BPB-SH-028 USA/9337/B(U)-96 (SAFKEG-LS) and USA/9338/B(U)-96 (SAFKEG-HS)
Packaging ofType B Radioactive Material Using BPB-SH-028 USA/9337/B(U)-96 (SAFKEG-LS) and USA/9338/B(U)-96 (SAFKEG-HS)
. BPB-SH-029 Packaging of Type B Radioactive Material Using USA/0656/B(U)-96 (GANUK)
BPB-SH-030 Receipt Inspection of New SAFKEG LS/HS Type B Byproduct Material Shipping Packages
- BP-SH-005 Packaging of Type A Radioactive Material Using SAFKEG-LS and SAFKEG-HS BP-SH-010 Packaging Radioactive Material for a Limited Quantity Shipment BP-SH-011 Packaging of Type A Radioactive Material Using USA DOT 7A 55-Gallon BP-SH-012 DOT-7 A Package Certification BP-SH-012 DOT-7 A Package Certification BP-SH-013 Packaging of Type A Radioactive Material Using USA DOT 7 A 5-tb 30-Gallon Resuable Drum BP-SH-014 Packaging Type A Radioactive Material in an Overpack BP-SH-015 Packaging of Type A Radioactive Material Using USA DOT 7A Model E-Box 030-181 BP-SH-016 Packaging of Radioactive Material Using USA DOT 7 A Model H or I Package BP-SH-016 Packaging of Radioactive Material Using USA DOT 7 A Model H or I Package BP-SH-017 Packaging of Reusable Type A Radioacuv" 1rnuc11a1 Using Tracerco LS-6.
BP-SH-017 Packaging of Reusable Type A Radioactive Material Using Tracerco LS-6 BP-SH-018 Packaging of Type A Radioactive Material Using USA DOT 7A NorthStar Medical Radioisotopes Package BP-SH-018 Packaging of Type A Radioactive Material Using USA DOT 7 A NorthStar Medical Radioisotopes Package II-6 Rev. 1 R¢visioq:Date 4
8/12/2016 3
5/19/2016 4
5/19/2016 5
7/18/2016 6
8/30/2016 7
11/14/2016 4
8/25/2016 5
12/1/2016 1
1117/2016 2
10/13/2016 1
7/27/2016 7
11/7/2016 7
1/14/2016 6
5/11/2016 7
9/6/2016 9
. 8/12/2016 7
8/12/2016 5
5/19/2016 6
5/11/2016 7
9/21/2016 3
3/23/2016 4
1217/2016 2
9/21/2016 3
12/1/2016 Not~s Minor Editorial Obsoleted Minor Editorial Minor Editorial Cover Page Minor Editorial Minor Editorial Minor Editorial Obsoleted Minor Editorial Minor Editorial Minor Editorial Minor Editorial Minor Editorlfrj Minor Editori Minor Editorial Minor Editorial Minor Editorial Minor Editorial Minor Editorial Cover Page Minor Editorial Minor Editorial Minor Editorial
- * * *.i
- 1* * * * * * * * * * * * * * * * * *-* * * *
- Number BP-SH-031 BP-SH-031 BP-SH-052 BP-SH-052 BP-SH-099 BP-SH-145 BP-SH-145 BP-SH-302 BP-SH-302 BP-SH-302 FM-13 FM-27 FM-27 FM-28 FM-39 FM-51 FM-52 FM-52 FM-52 FM-54 FM-59 FM-60 FM-60 FM-62 FM-67 FM-69 Name Rev. Revision'Date, Packaging of Type A Radioactive Material Using DOT 2
5/26/2016 7A20WC-l Packaging of Type A Radioactive Material Using DOT 3
8/12/2016 7A20WC-l Radioactive Material Shipment Package 15 2/4/2016 Documentation and Labeling Radioactive Material Shipment Package 16 9/6/2016 Documentation and Labeling Packaging of Type A Radioactive Material Using USA 6
8/12/2016 DOT 7 A MURR Model 1500 Packaging of Type A Radioactive Material Using USA 0
6/13/2016 DOT7AF-458 Packaging of Type A Radioactive Material Using USA fi DOT7AF-458 I 9;2112016 Packaging of Type A Radioactive Material Using 7
4/18/2016 MURR Models 6 and 12 Packaging of Type A Radioactive Material Using USA 8
8/12/2016 DOT 7 A MURR Model 6 or 12 Packaging of Type A Radioactive Material Using USA 9
12/1/2016 DOT 7 A MURR Model 6 or 12 Receipt of Radioactive Material
- 8 1/11/2016 In-House Radioactive Shipping Request Form 16 2/4/2016 In-House Radioactive Shipping Request Form 17 5/11/2016 Controlled Special Exposure Authorization
- 5 1217/2016 Control Checksheet for Packaging of Radioactive 14 1117/2016 Material for a Limited Quantity Shipment Dispensing Radiation Protection Data Sheet C 4
12/29/2016 Control Checksheet for Documentation and Labeling 16 2/4/2016 of Radioactive Material Shipment Control Checksheet for Documentation and Labeling
~7 9/6/2016 of Radioactive Material Shipment Control Checksheet for Documentation and Labeling 18 1117/2016 of Radioactive Material Shipment Report of Personnel Contamination 9
2/10/2016 Control Checksheet for Spectratek Services Reusable 9
1117/2016 Packaging of Type A Radioactive Material Confrol Check Sheet for Packaging of Type A Radioactive Material Using USA DOT 7A Model E-5 5/19/2016 Box 030-181 Control Check Sheet for Packaging of Type A RadioaCtive Material Using USA DOT 7A Model E-6 10/13/2016 Box 030-181 Radiation Instrument Certificate of Calibration 1
o I
II LJ!L0l6 Receipt of Radioactive Gemstone Shipping Containers 9
1111/2016 Control Checksheet for Packaging of Type A Radioactive Material Using USA DOT 7 A 5-to 30-12 8/12/2016 Gallon Resuable Drum 11-7 Notes Minor Editorial Minor Editorial Minor Editorial Minor Editorial Minor Editorial New Procedure Minor Editorial Minor Editorial Minor Editorial Minor Editorial Cover Page Cover Page Minor Editorial Cover Page Minor Editorial Cover Page Minor Editorial Minor Editorial Minor Editorial Minor Editorial Minor Editorial Minor Editorial.
Minor Editorial Minor Edit Cover Page Minor Editorial
Numbei::,:~
'-~
Name Control Checksheet for Packaging of Type A FM-69 Radioactive Material Using USA DOT 7 A 5-to 30-Gallon Resuable Drum FM-70 Control Checksheet for Packaging of Type A Radioactive Material Using Tracerco LS-6 Reusable FM-70 Control Checksheet for Packaging of Type A Radioactive Material Using Tracerco LS-6 Reusable FM-76 Personnel Contamination Log FM-79 Lutetium Chloride Radiation Protection Data Sheet B FM-80.
Material License Project Review Report FM-80 Material License Project Review Report FM-89 Control Checksheet for Type A F-327 Series Radioactive Material Shipment FM-91 Declaration of Pregnancy FM-94 Exclusive Use Shipment Controls FM-96 Dysprosium Dissolution Data Sheet Control Checksheet for Packaging of Type A FM-98 Radioactive Material Using USA DOT 7A MURR Model 6 or 12 Control Checksheet for Packaging of Type A FM-98 Radioactive Material Using USA DOT 7 A MURR Model 6 or 12 FM-98 Control Checksheetfor Packaging of Type A Radioactive Material Using MURR Model 6 or 12 Control Checksheet for Packaging of Type A FM-99 Radioactive Material Using USA DOT 7 A MURR Model 1500 Control Checksheet for Packaging of Type A FM-99 Radioactive Material Using USA DOT 7A MURR Model 1500 FM-107.
Control Check Sheet for Packaging Type A Radioactive Material irt an Overpack FM-107 Control Checksheet for Packaging Type A Radioactive Material in an Overpack FM-109 Dy/Ho-166 Separation Data Sheet FM-125 Lutetium Chloride Process Notification FM-126 Documentation of Compliance for DOT-7 A Shipping Package FM-126 Documentation of Compliance for DOT-7 A Shipping Package Control Checksheet For Packaging of Type A FM-128 Radioactive Material Using USA DOT 7 A MURR Model H orl Control Checksheet For Packaging of Type A FM-128 Radioactive Material Using USA DOT 7 A MURR Model H orl FM-129 Control Checksheet for Receipt Inspection of Type B Byproduct M.aterial Shipping Package 11-8
. Rev. ~evision Date, 13 12/1/2016 3
3/23/2016 4
1217/2016 4
2/10/2016 10 9/8/2016 6
3/22/2016 7
9/23/2016 9
5/19/2016
~/2016
/2016 3
2/2/2016 10 8/12/2016 11 1117/2016 9
4/18/2016 10 1117/2016 9
8/12/2016 8
8/12/2016 9
1117/2016 2
12/29/2016 3
1/15/2016 4
5/11/2016 5
9/6/2016 5
5/11/2016 6
9/21/2016 5
317/2016 Notes Minor Editorial Cover Page Minor Editorial Minor Editorial Cover Page Minor Editorial Minor Editorial Obsoleted Minor Editor*
Cover Page Cover Page Minor Editorial Mirior Editorial Minor Editorial Minor Editorial Minor Editorial Minor Editorial Minor Editorial Cover Pag Cover Page Minor Editorial Minor Editorial Minor Editorial Minor Editorial Obsoleted
"""""'"'~
- I* * * * * * * * * * * * * * * * * * * * * * * *
- * * * * * * * *
- i. I.
1*
I Number_
FM-131 FM-132 FM-135 FM-137 FM-137 FM-137 FM-137 FM-137 FM-137 FM-138 FM-139 FM-141 FM-141 FM-144 FM-144 FM-145 FM-145 FM-147 FM-147 FM-150 FM-150 FM-150 FM-151 FM-151 FM-151 FM-156 FM-157 Name Dissolution of Gadolinium Data Sheet Neodymium Dissolution Data Sheet Control Checksheet for Packaging of Type B Radioactive Material Using USA/0562/B(U)-96 (BEATRICE)
Type B Qualified Shipper List Type B Qualified Shipper List Type B Qualified Shipper List Type B Qualified Shipper List Type B Qualified Shipper List Type B Qualified Shipper List Control Checksheet for Leak Testing the SAFKEG-LS or SAFKEG-HS Shipping Package Using the CALT Leakage Testing Device Lutetium Chloride Radiation Protection Data Sheet C Control Checksheet for Packaging of Type A Radioactive Material Using SAFKEG-LS and SAFKEG-HS Control Checksheet for Packaging of Type A Radioactive Material Using SAFKEG-LS and SAFKEG-HS Control Checksheet for Packaging of Type A Radioactive Material Using Tracerco LS-1 Control Checksheet for Packaging of Type A Radioactive Material Using Tracerco LS-1 Control Checksheet for Packaging of Type A Radioactive Material Using USA DOT 7A F-458 Control Checksheet for Packaging of Type A Radioactive Material Using USA DOT 7A F-4)8 Control Checksheet for Packaging of Type A Radioactive Material Using Tracerco LS-15 Control Checksheet for Packaging of Type A Radioactive Material Using Tracerco LS-15 Statement of Training and Experience Jstatement of Training and Experience l
- Statement of Training and Experience Control Checksheet for Packaging of Type A Radioactive Material Using USA DOT 7A 55-Gallon
. Control Checksheet for Packaging of Type A Radioactive Material Using USA DOT 7A 55-Gallon Control Checksheet for Packaging of Type A Radioactive Material Using USA DOT 7A 55~Gallon Required Documentation for Non-MURR Owned Type B Shipping Packages Control Checksheet for Type B USA/0697 /B(U)-96 (F-458 Series) Radioactive Material Shipment II-9 Rev. Revision Date, Notes i
1 12/29/2016 Cover Page 2
12/29/2016 Cover Page 5
8/12/2016 Minor Editorial 10 1114/2016 Minor Editorial 11 417/2016 Minor Editorial 12 4/18/2016 Minor Editorial 13
. 7/18/2016 Minor Editorial 14 10/5/2016 Minor Editorial 15 11116/2016 Minor Editorial 5
5/19/2016 Minor Editorial 4
5/20/2016 Minor Editorial 2
7/27/2016 Minor Editorial 3
12/112016 Minor Editorial 0
8/12/2016 New Form 1
1117/2016 Minor Editorial 0
6/13/2016 New Form 1
9/21/2016 Minor Editorial 0
8/12/2016
'T
~
n<Jvv L'Ullll 1
10/13/2016 Minor Editorial 5
5/20/2016 Minor Editorial I 6 I 12/29/2016 I Minor Editorial 6
12/29/2016 Minor Editorial 10 1114/2016 Minor Editorial 11 8/12/2016.*. Minor Editorial 12 12/i/2016 Minor Editorial 5
8/30/2016 Cover Page 7
5/19/2016 Minor Editorial
N:nmber :;;.
Nam~
j FM-157 Control Checksheet for Type B USA/0697/B(U)-96 (F-458 Series) Radioactive Material Package FM-159 Control Checksheet for Health Physics Review of Radioactive Material Shipment Documentation FM-159 Control Checksheet for Health Physics Review of Radioactive Material Shipment Documentation FM-159 Control Checksheet for Health Physics Review of Radioactive Material Shipment Documentation FM-160 Control Checksheet for Type B(U) F-327 Series Radioactive Materials Shipment FM-162 Mo-99 Process Health Physics Check Sheet Control Checksheet for Type B Radioactive Material FM-163 Using USA/9337/B(U)-96 (SAFKEG-LS) and USA/9338/B(U)-96 (SAFKEG-HS)
Control Checksheet for Type B Radioactive Material FM-163 Using USA/9337/B(U)-96 (SAFKEG-LS) and USA/9338/B(U)-96 (SAFKEG-HS)
FM-165 Mo-99 Radiation Protection Data Sheet A Control Checksheet for Packaging of Type B FM-167 Radioactive Material Using USA/0656/B(U)-96 (Ganuk)
Control Checksheet for Packaging of Type A FM-169 Radioactive Material Using USA DOT 7A 20WC-l FM-169 Control Checksheet for Packaging of Type A Radioactive Material Using USA DOT 7A 20WC-l FM-17 Radiation Work Permit Control Checksheet for Packaging of Type A FM-170 Radioactive Material Using USA DOT 7 A Northstar Medical Radioisotopes Package FM-172 Lutetium Chloride Radiation Protection Data Sheet D FM-174 Instrument Pre-Start-Up Check Sheet FM-175 Control Checksheet for Receipt Inspection of Customer Owned Type B Shipping Package Control Checksheetfor Packaging of Type A FM-176 Radioactive Material Using USA DOT 7A Northstar Medical Radioisotopes Package with 7.5 Ci ofMo-99 FM-177 Control Checksheet for Receipt Inspection of SAFKEG LS and HS Type B Shipping Package FM-178 Control Checksheet for Hot Cell HC-01 Entry and Exit FM-178 Control Checksheet for Hot Cell HC-01 Access GLP-MCE-003 Performance Checks of the High Purity Germanium Detectors GMP-BR-213 Lutetium Chloride Batch Record for HC-08 AIB GMP-BR-213 Lutetium Chloride Batch Record for HC-08 A/B GMP-BR-404 Mo-99 Process Cleaning and Line Clearance GMP-BR-404 Mo~99 Process ri,..,,nin~ and Line Clearance II-10 Rev. Revision.pate; 8
1117/2016 5
1111/2016 6
3/22/2016 7
1217/2016 3
5/19/2016 0
7/28/2016 6
8/30/2016 7
12/1/2016 1
12/6/2016 1
11/7/2016 2
5/26/2016 3
8112/2016 14 7/26/2016 2
9/21/2016 0
.12/29/2016 0
2/24/2016 1
1117/2016 0
1217/2016 1
1117/2016
_o 1/15/2016 1
3/29/2016 4
12/30/2016 3
2/22/2016 4
11/10/2016 2
2/22/2016 3
9/26/2016 Notes Minor Editorial Minor Editorial Minor Editorial Minor Editorial Obsoleted Obsoleted Minor Editorial.
Minor Editorial Minor Editorial Obsoleted Minor Editorial Minor Editorial Minor Editorial Minor Editorial New Form New Form Minor Editorial New Form Minor Editorial New Form Minor Editorial Cover Page Full Review Minor Editorial Full Review MinorE
- I
Number GMP-BR-502 GMP-BR-502 GMP-MCE-043 GMP-MCE-113 GMP~MCE~122 GMP-MCE-124 GMP-MCE-124 GMP-MCE-128 GMP-MCE-129 GMP-PRC-201 GMP-PRC-400 GMP-QC-008 GMP-QC-008 GMP-QC-008 GMP-QC-013 GMP-QC-021 GMP-QC-252 GMP-QC-253 GS-RA-014 GXP-APRT-014 GXP-MCE-127 GXP-QC-403 GXP-QC-404
. HC-PS0-002 HC-PS0-003
- HC-PS0-005 HC-PS0-005 IC-HP-300 IC-HP-305 Name Sodium Iodide I-131 Solution Batch Record Sodium Iodide I-131 Solution Batch Record Operation and Maintenance of the Ocean Optics ISS UV-Vis Spectrophotometer Cleaning, Maintenance and Operation of GB-18 Establishing Calibration Factors for Calicheck Dose Calibrator Linearity Test Kit Cleaning, Maintenance and Operation ofHC-08 A/B Cleaning, Maintenance and Operation ofHC-08 A/B Operation and Maintenance of the Millipore EZ-Stream Pump with EZ-Fit Manifold Operation and Maintenance for a Tuttnauer 3870 EA-B/L Electronic Tabletop Autoclave Transfer of cGMP Lu-177 Chloride Product to Shipping Transfer of cGMP Potassium Molybdate Final Intermediate Solution to Customer Microbial Bioburden Limits Testing Microbial Limits Testing Microbial Bioburden Limits Testing Sterility Test, Direct Inoculation pH Determination of Lu-177 Chloride Solution by Microcombination pH Probe Determination of Radiochemical Purity of Lu-177 Chloride Solution Lu-177 Identification and Determination of Radionuclidic Purity Use and Operation of the I-131 Production Facility Lifting Crane Protocol for the Animal Stability Evaluation ofLu-177 Chloride in 0.05 N Hydrochloric Acid Operation and Maintenance of Optima 2100 DV ICP-OES Radionuclidic Purity and Identity Confirmation Of Potassium Molybdate (Mo-99) Final Intermediate Radiochemical Solution Determination of Molybdenum and Iron Concentration and Activity Concentration in Potassium Mcilybdate (Mo-99) Final Intermediate Radiochemical Solution Hot Cell Preparation of Radioactive Material for Shipment Glove Box Preparation of Radioactive Material for Shipment Hot Cell Loading of Host Cans Hot Cell Loading of Host Cans Calibration - Radiation Survey Instruments Calibration - Electrostatic Discharge Dosimeter II-11 Rev. Revision bate Notes 1
8/2/2016 Minor Editorial 2
11/16/2016 Minor Editoria[
4 5/26/2016 Minor Editorial 3
2/18/2016 Obsoleted 2
11/9/2016 Minor Editorial LI
? 18/2016 Full Review 5
5/3/2016 Minor Editorial 1
7/20/2016 Cover Page 2
5/3/2016 Minor Editorial 9
8/16/2016 Minor Editorial 1
5/18/2016 Cover Page 10 12/2/2016 Minor Editorial 8
3/15/2016 Minor Editoria 9
11/9/2016 Minor Editoria 6
2/25/2016 Minor.Ediforial 4
2/18/2016 Full Review 13 9/29/2016 Minor Editorial 19 9/23/2016 Full~--*:-
0 3/22/2016
. New Procedure 2
10/19/2016 Minor Editorial 7
9/27/2016 Full Review 3
4/21/2016 Minor Editorial 4
1/6/2016 Minor Editorial 16 7/28/2016 Minor Editorial 11 11/14/2016 Minor Editorial 15
. 2/10/2016 Minor Editorial 16 12/6/2016 Minor Editorial 8
8/10/2016 Minor Editorial 10
. 2/5/2016 Minor Editorial
Number Name
, Rev. ll_evisioq Date:
Calibration - Portal Monitor Gamma SIN 1010 IC-HP-337 and 1011 7
' 4/21/2016 IC-HP-340 Calibration - Bladewerx Saber BPM Air Monitor 0
3/15/2016 IC-HP-341 Calibration -High Resolution Gamma Spectroscopy 7
5/6/2016 Systems IC-HP-343 Calibration - Sodium Iodide Detector 5
5/6/2016 IC-HP-346 Calibration - Lab Impex Smart MCA Continuous Air 1
3/7/2016 Monitor IC-HP-346 Calibration - Lab Impex Smart MCA Continuous Air 2
i 8/10/2016 Monitor IC-HP-353 Calibration - Lab Impex Monitor - DP2001 2
8/10/2016 IC-HP-357 Calibration - NOA Lab Impex Monitor - DP2001 1
7/15/2016 IC-HP-360 Calibration - Eberline AMS-3 Continuous Air Monitor 0
5/11/2016 Calibration - Eberline/Thermo Model AMS-4 IC-HP-362 Continuous Air Monitor, Radial Or In-Line Sampling 1
1/11/2016 Head Calibration - Eberline/Thermo Model AMS-4 IC-HP-362 Continuous Air Monitor: Radial Or In-Line Sampling 2
7/22/2016 Head IC-HP-363 Eberline BC-4 Beta Swipe Counter - Calibration 1
1119/2016 IC-HP-364 Calibration - Ludlum Model 3030 Swipe Counter 1
7/22/2016 IC-HP-365 Calibration -Thermo PM-12 Portal Monitor 0
7/29/2016 IC-HP-365 Calibration - Thermo PM-12 Portal Monitor 1
11/9/2016 IC-HP-366 Eberline Model PM-7 Portal Monitor Calibration 0
9/22/2016 IC-HP-367 Calibration - I-131 Bioassay Detection System 0
3/17/2016 IC-HP-367 Calibration 131 Bioassay Detection System 1
5/20/2016' IC-HP-368 Calibration - ALM0-6 Radiation Monitoring 0
12/7/2016 Instrument IRR-PS0-112 Preparing Shipping Paperwork 8_
10/11/2016 OA-25 Control Checksheet for Changing P-Tube Pre-Filters 0
5/11/2016 OA-25 Control Checksheet for Changing P-Tube Pre-Filters 1
8/10/2016 OA-60 Visual Aid for Packaging of Type A Radioactive 0
5/19/2016.
Material Using USA DOT 7A Model E-Box 030-181 OA-99 Visual Aid for Packaging of Type A Radioactive 0
8/12/2016 Material Using USA DOT 7A MURR Model 1500 OA-128 Packaging of Type A Radioactive Material Using USA 0
5/11/2016 DOT 7 A MURR Model H or I OP-HP-200 Air Sampling - Containment Building Tritium
- 7.
12/30/2016 OP-HP-220 Tritium Bioassay 10 3/14/2016 OP-HP-220 Tritium Bioassay 11 7/19/2016 OP-HP-221 Environmental Sample - Analysis 6
5/6/2016 OP-HP-223 Spent Fuel Shipping Cask Water Sample Analysis 4
9/7/2016 OP-HP-224 Spent Fuel Shipping Cask Air Sample Analysis 5
8/11/2016 OP-HP-228 Performing Iodine 131 Bioassay Measurements t+HTi¥2016 OP-HP-228 Performing Iodine 131 Bioassay Measurements
/2016 OP-HP-228 Performil1g I()di11e 131 Bioassay Measurements 3 I 512012016 II-12
. Notes Obsoleted i Ne Cover Page Cover Page Minor Editorial Minor Editorial Full Review Minor Editorial Obsoleted Minor Editorial Minor Editorial Minor Editorial Minor Editorial New Procedure Minor Editorial New Procedur New Procedur Minor Editor New Procedure Minor Editorial New Operator Aid Minor Editorial New Operator Aid New Operator Aid New Operator Aid Minor Edito
- Minor Editoria Minor Editorial Cover Page Obsoleted Minor Editorial MinorE
- Minu1 Minor Editor"
I Number:;
OP-HP-228 OP-HP-228 OP-HP-236 OP-HP-236 OP-HP-236 OP-HP-300 OP-HP-305 OP-HP-305 OP-HP-306 OP-HP-350 OP-HP-353 OP-HP-356 OP-HP-357 OP-HP-365 OP-HP-400 OP-HP-420 OP-HP-500 OP-HP-500 OP-HP-505 OP-HP-600 PRC-RRD-001 PRC-RRD-103 PRC-RRD-105 PRC-RRD-106 PRC-RRD-215 PRC-RRD-217 PRC-RRD-219 PRC-RRD-219 PRC-RRD-313 PRC-RRD-319 PRC-RRD-401 PRC-RRD-402 PRC-RRD-405 PRC-RRD-414 PRC-RRD-420 PRC-RRD-421 PRC-RRD-424 QAB-SH-002 QAB-SH-003 Name Performing Iodine 131 Bioassay Measurements Performing Iodine 131 Bioassay Measurements Respirator Selection, Issuance, and Wearing Respirator Selection, Issuance, and Wearing Respirator Selection, Issuance, and Wearing Receipt of Radioactive Material Ordering or Transfer of Radioactive Materials Ordering or Transfer of Radioactive Materials Health Physics Daily Facility Checks Eberline Model PING.IA-Filter Change Waste Tank Sample - Analysis Operation - Lab Impex Stack Monitor - Filter Change and Source Checks Operation - NOA Lab Impex Stack Monitor - Filter Change and Source Checks Operation - ALMO 6 Source Check
!Gemstone Shipping Barrel Analysis Decontamination of Enclosed Processing Units Operation of the Hot Cell (HC-09) Interim Storage Silo Operation of the Hot Cell (HC-09) Interim Storage Silo Emergency Stack Monitor Filter Analysis Europium Source Creation Preparing and Submitting a Radioactive Sample, for Packaging Remote Quartz Vial Washing Dysprosium Dissolution Separation of Dy/Ho 166 Supplemental Sample Dispensing Dissolving Lu-177 Lu-l 77m Processing Lu-l 77m Processing Au Dissolution Cd-l 15/In-l 15m Processing Preparing Sm-153 DOTMP from L Dissolving Sm-153 Quality Control Testing of 153Sm DOTMP Dissolution of Gadolinium Nitrate Rh-105 Processing Dissolving Re-186 Dissolving Platinum Powder Procurement of Type B Packages Material Control for Type B Shipping Program II-13 Rev. Revision Date' Notes 4
9/22/2016 Minor Editoriad 4
9/22/2016 Minor Editoria 0
3/17/2016 New Procedure 0
3/17/2016 New Procedure 1
7/15/2016 Minor Editorial 9
2/10/2016 Minor Editorial I
.5 3/28/2016 Minor Edit~
6 12/22/2016 r'~. " p~
8 10/13/2016 Cover Page 7
9/22/2016 Minor Editorial 8
5/6/2016 Cover Page 5
9/23/2016 Minor Editorial 4
7/15/2016 MinorEditorial 0
8/10/2016 New Procedure I 10 I 1/11/2016 I Cover Page 5
12/7/2016 Minor Editorial 0
8/4/2016.
New Procedure 0
8/4/2016 New Procedure 6
11/9/2016 Minor Editorial 4
9/7/2016 Minor Editorial 5
5/20/2016 Minor Editorial 4
2/24/2016 Minor Editorial 3
2/2/2016 Cover Page 2
5/20/2016 Minor Editorial 6
7/15/2016 Minor Editorial 2
. 12/29/2016 Cover Page 1
2/24/2016 Minor Editorial 2
7/15/2016 Minor Editori 5/20/2016 Minor Editorial
/20/2016 New Procedure 7/15/2016 Cover Page 7/15/2016 Minor Edi,v.;u; 1
7/15/2016 Cover Page 2/2/2016 Cover Page 016 Minor Editorial 4
2/24/2016 Minor Editorial 2
3/7/2016 Cover Page 4
3/7/2016 Minor Editorial 6
3/7/2016 Cover Page
Number,,
Name QAB-SH-004 Type B Program Vendor Qualification Leak Testing the SAFKEG-HS or SAFKEG-LS QAB-SH-007 Shipping Package Using the CALT Leakage Testing Device QAB-SH-008 Training for Type B Shipment Leak Test Performers QAB-SH-009 Pre-Shipment Leak Testing of the Type B USA/0656/B(U)-96 (Ganuk) Shipping Package Sodium Iodide Spectral Qualitative Analysis for QA-SH-002 Excepted, License-to-License, Type A, and Type B Radioactive Material Shipments QC-PS0-010 P-33 Radiochemical Purity QU-RRD-102 P-33 Radiochemical Purity RCP-PS0-001 P-33 Sublimation Set Up RCP-PS0-020 Selenium-75 Process RM-HP-101 Stack Monitor Preventive Maintenance - Eberline Ping IA RM-HP-102 Stack Monitor Preventative Maintenance - Lab Impex RP-HP-105 Transfer of Radioactive Material Within the Facility RP-HP-120 Personnel Radioactive Contamination RP-HP-120 Personnel Radioactive Contamination RP-HP-125 Radiation Monitoring - Performing and Documenting a Survey RP-HP-135 Room 114 Entry - Self Monitored RP-HP-137 Handling Radioactive Material in the Reactor Pool SI-PS0-008 Post-Irradiation Processing: Exported Silicon SI-PS0-009 Operation of the Can Press SV-HP-105 Sealed Calibration Source - Leak Check SV-HP-110 Environmental Sampling SV-HP-130 Emergency Air Sampling of Exhaust Plume TPZ-PS0-001 Receiving Gemstone Irradiation Shipping Drums TPZ-PS0-002 Irradiation of Gemstone Irradiation Containers TPZ-PS0-003 Loading Gemstone Shipping Drums WM-SH-100 Radioactive Waste - Preparation and Storage WM-SH-104 Solidification of Radioactive Liquid for Shipment WM-SH-105 Radioactive Waste Processing WM-SH-110 Radioactive Waste - Barrel Analysis for Shipment and Disposal WM-SH-300 Exclusive Use Shipment ofLSA or SCO Radioactive Waste WM-SH-300 Exclusive Use Shipment ofLSA or SCO Radioactive Waste II-14 Rev. Revision Date 6
317/2016 4
5/19/2016 2
3/23/2016 1
1117/2016 7
1117/2016 0
12/30/2016 4
12/30/2016 8
12/29/2016 0
9/26/2016 5
12/30/2016 2
12/7/2016 12 2/10/2016 11 2/10/2016 12 10/13/2016 4
10/13/2016 7
7/26/2016 15 5/11/2016 8
8/11/
2 4/18/2016 8
7/26/2016 7
317/2016 8
11/16/2016 7
2/23/2016 8
2/23/2016 6
3/30/2016 9 =
4/25/2016 1
7/27/2016 12 8/12/2016 2
-'111L016 15 3/23/2016 16 7/27/2016 Notes Cover Page Minor Editorial Minor Editorial Obsoleted Full Review New Procedure Obsoleted Minor Editorial New Procedure Cover Page Minor Editorial Minor Editorial Minor Editorial Minor Editorial Cover Page Minor Editorial MinmEdit~
Full Revie Minor Editor
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a Cover Page Cover Page Minor Editorial Cover Page Minor Editorial Cover Page Minor Editorial,
Minor Editorial Minor Editorial
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- SECTION III REVISIONS TO THE HAZARDS
SUMMARY
REPORT January 1, 2016 through December 31, 2016 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 beenreviewed in accordance with 10 CFR 50.59.
HAZARDS
SUMMARY
REPORT (ORIGINAL JULY 1, 1965)
Original HSR, Page 9-8, Table 9.2, Instrument Cubicle Devices (as revised by the 1982, 1986, 1995, 2000, 2001, 2002, 2006, 2007, and 2013 Reactor Operations Annual Reports)
Delete 27 Dual Alarm Unit (EP-920 E/F) Primary Low Flow Scram Replace with 27 Dual Alarm Unit (EP-920 E/F) Primary Low Flow Scram & Low Pressure Scram (PT-944A)
Original HSR, Page 9-10, Table 9.2, Instrument Cubicle Devices (as revised by the 1982, 1986, 1995, 2000, 2001, 2002, 2006, 2007, and 2013 Reactor Operations Annual Reports)
Add after Item No. 139 140
. Dual Alarm Unit (EP-920 J/K) Primary Low Pressure Scram (PT-943)
ADDENDUM 3 - HAZARDS
SUMMARY
REPORT (AUGUST 1972)
HSR, Addendum 3; Page 18. Figure 2.3.a, Electrical Distribution (as revised by the 1989-90, 1990-91, 1995, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011, 2012, 2013, 2014, and 2015 Reactor Operations Annual Reports)
Replace with Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of7; dated 08/01/16)
HSR, Addendum 3, Page 19A. Figure 2.3.c. Electrical Distribution (as added by the 2004 and revised by the 2005, 2007, 2009, 2010, 2011, 2012, 2013, 2014, and 2015 Reactor Operations Annual Reports)
Replace with Updated Figure 2.3.c, Electrical Distribution Reactor/Laboratory Panels-2 (MURR Dwg No. 522, Sheet 3 of7, dated 08/01/16)
III-1
HSR, Addendum 3, Page 19B, Figure 2.3.d, Electrical Distribution (as added by the 2007 and revised by the 2008, 2009, 2010, 2011, 2012, 2013, 2014, and 2015 Reactor Operations Annual Reports)
Replace with.
Updated Figure 2.3.d, Electrical Distribution Emergency Electrical Power System (MURR Dwg No. 522, Sheet 4 of 7, dated 05/02/16)
HSR, Addendum 3, Page 19C, Figure 2.3.e, Electrical Distribution (as added by the 2007 and revised by the 2009, 2010, 2011, 2012, 2013, and 2015 Reactor Operations Annual Reports)
Replace with Updated Figure 2.3.e, Electrical Distribution Emergency & UPS Panels (MURR Dwg No. 522, Sheet 5 of 7, dated 05/02/16)
HSR, Addendum 3, Page 35, Figure 2.11. Annunciator Control-10 MW Replace with Updated Figure 2.11, Annunciator Control-10 MW (MURR Dwg No. 138, Sheet 1 of 1, dated 07112116)
HSR, Addendum 3, Page 40, Figure 2.14, Safety System - 10 MW Replace with Updated Figure 2.14, Safety System (MURR Dwg No. 139, Sheet 1 of 1, dated 06/01/16)
ADDENDUM 4 - HAZARDS
SUMMARY
REPORT (OCTOBER 1973)
HSR, Addendum 4, Page A-7, Section A.3.3.7, Paragraph 2 Delete "Pressure transmitter 943, on sensing the low pressure, actuates the scram via alarm unit 942 (Figure A.3) to interrilpt input E3B of the logic units."
Repiace with "Pressure transmitter 943, on sensing the low pressure, actuates the scram via alarm unit EP920(J) (Figure A.3) to interrupt input E3B of the logic units."
HSR, Addendum 4, Page A-19, Figure A. l, Safety System - 10 MW (as revised by the 1995, 2001, 2002, 2003, 2006, 2007, 2009, and 2012 Reactor Operations Annual Reports)
Replace with Updated Figure A. l, Safety System (MURR Dwg No.139, Sheet 1 of 1, dated 06/01/16)
III-2
HSR, Addendum 4, Page A-26, Figure A.7, Annunciator Control-10 MW (as revised by the 1995, 2001, 2002, 2005, 2006, 2007, 2008, 2012, and 2013 Reactor Operations Annual Reports)
Replace with Updated Figure A-7, Annunciator Control - 10 MW (MURR Dwg No. 138, Sheet 1 of 1, dated 07 /12/16)
ADDENDUM 5 - HAZARDS
SUMMARY
REPORT (JANUARY 1974)
HSR, Addendum 5, Page 4, Figure 2.1, Electrical Distribution (as revised by the 1989-90, 2001, 2002, 2003, 2004, 2005, 2006, 2007, 2009, 2010, 2011, 2012, 2013, 2014, and 2015 Reactor Operations Annual Reports)
Replace with Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of 7, dated 08/11/16)
III-3
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- SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2016 through December 31, 2016
. For each facility modification described below, MURR has on file the safety screen or evaluation, as well as the documentation ofreview,performed in accordance with 10 CFR 50.59.
MODIFICATION RECORD 86-03, AD~ENDUM 1 P-Tube Lab Control Station PLC This addendum to Modification Record 86-03, "P-Tube Control Circuit," documents the replacement of the Pneumatic Tube (P-Tube) control boxes in Laboratories 216 and 218 with Programmable Logic Controller (PLC) control boxes. These new boxes make use of digital timers to automatically alternate between dispatch and return, as well as improve timing and monitoring of parameters. They also have the capability to better control the speed of the sample carriers, or "rabbits," as they return to the laboratory fume hoods, which will prevent rabbits from bouncing back and getting hung up in the tlibing.
MODIFICATION RECORD 99-04, ADDENDUM 1 Replace Conductivity Indicators This addendum to Modification Record 99-04, "Replace Conductivity Cells, Amplifiers & Indicators," documents the replacement of the Pfimary and Pool Coolarit System conductivity indicators with direct replacements from the same manufacturer. This modification upgraded the control room indication and imbedded alarm relay.*
MODIFICATION RECORD 01-09, ADDENDUM 7 MURR Industrial Building Expansion Emergency Power Fitout This addendum to Modification Record 01-09, "Installation of Emergency Lighting Panel No. l," documents the.
. addition of electrical loads to the MURR Industrial Building (MIB) portion of the Emergency Electrical Power System. Additions included in this modification consist of Hot Cell 11 Main Power, various radiation monitors, and a manual transfer switch.for Hot Cell 11 Exhaust Fan No. 1, which are normally tied to the Normal Electrical Power Distribution System.
MODIF.ICATION RECORD 03-03, ADDENDUM 7 Fire Protection in NOA Shell Space Laboratory Fitout This* addendum to Modification Record 03-03, "Installation of a Facility Fire Detection/Suppression System,"
documents the addition of fire protection system equipment to the North Office Addition (NOA) laboratory space in Rooms 2041, 2041A, 2041B; 2041C, and 2041D, as well as relocating existing sprinklers in Room 2010. This change was necessary to accommodate the new configuration of the NOA laboratories being fitted out in the shell IV-1
space. The expansion of the NOA Wet Fire Main Fire Protection System will better aid the functionality of the system for warning personnel and protecting equipment within the newly configured NOA laboratory spaces.
MODIFICATION RECORD 16-01 Trip Actuator Amplifier Biasing Resistors Replacement This Modification Record documents the replacement of the reactor safety system Trip Actuator Amplifier (TAA) biasing resistors with higher watt rating resistors for improved longevity. The previous resistors had a history of failure from overheating that resulted in multiple unscheduled reactor shutdowns. The new resistors have a higher current rating and are less susceptible to overheating, thereby increasing system reliability.
MODIFICATION RECORD 16-02 Replacement of Primary Coolant Pressure Instrument Channel PT-943 Control Room Meter-Relay (BEEDE Model MR4) with Rosemount BG 241 Meter Readout and API 1000 G Dual Alarm Trip Unit This Modification Record documents the replacement of the Primary Coolant Pressure Instrument Channel for primary coolant heat exchanger outlet pressure transmitter PT-943 Meter-Relay Trip Unit.
This provides an indication of Primary Coolant System pressure as well as a Scram input to the "Green Leg" of the Reactor Safety System. The previous model has become obsolete and repair parts are extremely difficult to procure. Additionally, the new configuration has better indicatiqn and a quicker response.time than the previous meter-relay unit.
MODIFICATION RECORD 16-03 Replacement of Primary Coolant Pressure Instrument Channels. PT-944A and PT~944B Control Room Meter-Relays (BEEDE Model 3324) with Rosemount BG 241 Meter Readouts and API 1000 G Dual Alarm Trip Units This Modification Record documents the replacement of the Primary Coolant Pressure Instrument Channels for reactor core outlet pressures transmitters PT~944A and PT-944B Meter-Relay Trip Units. These provide indications of Primary Coolant System pressure and upon a low pressure condition will de-energize relays, which will interrupt power to the control blade electro-magnets, secure power to the primary coolant pumps, close the primary coolant isolation valves, and open the anti-siphon system isolation valves. The previous model has become obsolete and repair parts are extremely difficult to procure. Additionally, the new configuration has better indication and a quicker response time than the previous meter~relay unit.
IV-2
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- SECTIONV NEW TESTS AND EXPERIMENTS January 1, 2016 through December 31, 2016 New tests or experiments approved during this period under a Reactor Utilization Request (RUR) were as follows:
RUR 448, AS AMENDED Bismuth Irradiation This RUR amendment authorizes an increase in fluence for the irradiation of bismuth metal in the graphite reflector region of the reactor for research and development activities.
RUR 451, AS AMENDED Uranium Oxide Irradiation This RUR amendment authorizes the addition of chlorine gas to a natural uranium oxide irradiatiop. encapsulation in support ofmolybdenum-99 research and development activities.
.RUR453 Irradiation of Silicon Micro-particles This RUR authorizes the irradiation of up, to 10.0 grams of doped silicon micro-particles in the flux trap region of the reactor in support of research and development activities.
RUR454 Uranium Oxide Irradiation This RUR authorizes the long-term irrad!ati~n of up to 50.0 milligrams of natural uranium oxide discs in support of 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. Specificatfons. The safety evaluations have been reviewed by the Reactor Manager, Reactor Health Physics Manager, Assistant Reactor Manager-Physics, and the Reactor Safety Subcommittee, as applicable.
V-1
SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2016 through December 31, 2016 INSPECTIONS There was one NRC inspection reviewing Special Nuclear Material (SNM) activities. All records and activities were found to be in compliance with NRC rules and regulations. No violations were noted.
REACTOR CHARACTERISTIC MEASUREMENTS Fifty-four (54) refueling evolutions were completed in 2016. Excess reactivity verifications were pe1Jormed for each refueling. The largest measured excess reactivity was 3.33%. MURR Technical Specification 3.1.a. requires excess reactivity to be less than 9.8%.
REACTIVITY MEASUREMENTS Differential blade-worth measurements of four (4) shim control blades were performed following either a planned replacement of a control blade or characterization of the bum-in effect of a new control blade.
Five (5) reactivity measurements were performed to determine the reactivity worth of all samples, including the sample holder, loaded in the flux trap region.
One (1) reactivity measurement was performed to determine the reactivity worth of 28.0 gram natural uran.ium (U02) target irradiated in the P~2 location of the graphite reflector region.
VI-1
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SECTION VII RADIOACTIVE EFFLUENT January 1, 2016 through December 31, 2016 TABLE 1 SANITARY SEWER EFFLUENT Descending Order of Activity Released for Nuclide Totals > l.OOOE-05 Ci Nuclide Activity (Ci)
H-3 7.618E-02 S-35 6.838E-03 Co-60 3.857E-03 Zn-65 l.030E-03 P-32 6.884E-04 Ca-45 5.842E-04 Lu-177 4.072E-04 Na-24 3.715E-04 Sc-46 3.069£-04 Tc-99m 2.470E-04 Sb-124 l.363E-04 Mo-99 1.239E-04 Fe-59 8.071E-05 Lu-177m 4.792E-05 W-181 2.679E-05 Cu-67 2.175E-05 Mn-54 l.243E-05 Total H-3 7.618E-02 Total Other 1.478E-02 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal by Release into Sanitary Sewerage."
VII-1
TABLE2 ST ACK EFFLUENT Ordered by % Technical Specification (TS) Limit
- ':Average Concentratioi(
Total Rele~se
- ,\\
7' Isotope (uCi/ml)
(Ci) 1:;S Limit Multiplier
-%TS Ar-41 l.18E-06 5;28E+02 350 33.7143 1-131 5.82E-12 2.61E+03 1
2.9094 H-3 l.30E-08 5.80E+06 350 0.0370 Co-60 4.17E-15 1.87E+OO 1
0.0083 1-125 l.17E-14 5.26E+OO 1
0.0039 C-14*
l.07E-11 4.80E-03 1
0.0036 Kr-79 6.91E-10 3.09E+05 350 0.0028 Xe-13 lm l.93E-08 8.65E+06 350 0.0028 Os-191 4.70E-15 2.1 lE+OO 1
0.0002 Hf-181 l.37E-15 6.14E-01 1
0.0002 1-133 6.43E-13 2.88E+02 350 0.0002 Kr-87 7.81E-12 3.50E+03 350 0.0001 S-35 2.53E-15 l.13E+OO 1
0.0001 As-76 4.45E-13 l.99E+02 350 0.0001 Br-82 9.51E-13 4.26E+02 350 0.0001 C-14 activity is calculated based on the ratio of argon to nitrogen in the air and the (n, p) reaction cross sections for the activation ofN-14 to C-14.
Isotopes observed at< 0.0001 % Technical Specification limit are not listed.
Stack Flow Rate = ~30,000 cfm Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, Amended Facility License No. R-103 Technical Specifications.
VIl-2
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- SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2016 through December 31, 2016 Environmental samples are collected two times per year at eight (8) locations and analyzed for radioactivity. Soil and vegetation samples are also taken at each location. Water samples are taken at three (3) locations while subsurface soil samples are taken at six ( 6) locations each period. Analytical results are shown in Tables 1 and 2.
Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2016. All doses are approximately 15 mrem/year or less, except monitor numbers 8 and 9. These monitors are located at or near loading dock areas where packages containing radioactive material are loaded or traverse prior to being placed 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 minimal environmental impact exists from the operation of the MURR facility.
The number.ofradiation and contamination surveys performed each month is provided in Table 4.
TABLE 1
SUMMARY
OF ENVIRONMENTAL SET 89-Spring 2016 Detection Limits.
Matrix Alpha Beta Gamma Tritium Water 0.00 pCilg 5.82 pCi/g 188.55 pCi/L 5.06 pCi/mL of sample Soil 1.04 pCilg 2.51 pCilg 0:57 pCilg NIA Vegetation 0.00 pCilg 7.90 pCi/g 1.68 pCilg 5.52 pCi/mL of distillate Subsurface Soil 0.00 pCilg 3.79 pCilg 0.58 pCilg NIA Activity Levels - Vegetation Alpha Beta Gamma H-3 Sample*
(pCilgram}
(pCilgram}
(pCilgram}
(pCilmL}
1V89 0.32 24.62
< 1.68
< 5.52 2V89 0.00 22.06
< 1.68
< 5.52 3V89 0.32 21.96
< 1.68
< 5.52
- 4V89 0.66 31.25
< 1.68
< 5.52
. 5V89 0.61 33.55
< 1.68
< 5.52 6V89 0.32 26.28
< 1.68
< 5.52 7V89 0.62 20.46
< 1.68
< 5.52 10V89 0.63 31.95
< 1.68
< 5.52 VIII-1
TABLE 1 (Cont'd)
SUMMARY
OF ENVIRONMENTAL SET 89 - Spring 2016 Activity Levels - Soil Alpha Beta Gamma Sample (pCi/gram)
(pCi/gram)
(pCi/gram) 1S89
< 1.04 15.49 3.33 2S89 1.72 17.76 4.18 3S89
< 1.04 13.53 2.11 4S89
< 1.04 12.43 2.83 5S89 1.10 16.14 3.36 6S89
< 1.04 15.33 2.62 7S89
< 1.04 11.03 3.31 10S89 1.75 16.63 3.54 Activity Levels - Water Alpha Beta Gamma H-3 Sample (pCi/gram)
(pCi/gram)
(pCi/L)
(QCi/mL) 4W89 0.32
< 5.82
< 188.55
<5.06 6W89 0.47
<5.82
< 188.55
<5.06 10W89 0.32 6.20
< 188.55
<5.06 Activity Levels - Subsurface Soil Alpha Beta Gamma:
Sample (QCi/gram)
(pCi/gram)
(QCi/gram)
SWSS89 2.11 26.22 3.53 NESS89 1.23 22.66 3.59 NSS89 1.59 21.16 3.79 WSS89 2.lF 26.60 4.12 ESS89 1.22 21.88 3.46 SSS89 0.88 20.42 3.88
- Gamma and tritium analyses are based on wet weights while. alpha and beta are based on dry weights. HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity (MDA).
VIII-2
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- Matrix Water Soil Vegetation Subsurface Soil Sample 1V90 2V90 3V90 4V90 5V90
.6V90 7V90 10V90 Sample 1S90 2S90 3S90 4S90 5S90 6S90 7S90 10S90 TABLE2
SUMMARY
OF ENVIRONMENTAL SET 90 - Fall 2016 Detection Limits*
Alpha Beta Gamma Tritium 0.00 pCilg 6.33 pCilg 189.78 pCi/L 1.76 pCilmL of sample 1.23 pCi/g 2.74 pCi/g 0.66 pCilg NIA 0.00 pCilg 8.55 pCilg 1.61 pCilg
- 1. 70 pCilmL of distillate 0.00 pCilg 3.78 pCi/g 0.64 pCi/g NIA Activity Levels - Vegetation Alpha Beta Gamma H-3 (pCilgram)
(pCilgram)
(pCilgram)
(pCi/mL) 0.90 43.81
< 1.61
< 1.70 0.00 36.86
< 1.61
< 1.70 0.00 24.25
< 1.61
< 1.70 0,.00 32.63
< 1.61
< 1.70 0.00 26.60
< 1.61
< 1.70 0.31 60.65
< 1.61
< 1.70 0.31 19.51
< 1.61
< 1.70 0.00 31.57
< 1.61
< 1.70 Activity Levels - Soil Alpha Beta Gamma (pCi/gram)
(pCilgram)
(pCilgram)
< 1.23 15.61 2.42
< 1.23 17.73 2.19
< 1.23 -
31.43 2.69
< 1.23 21.46 3.30
< 1.23 24.12 4.06
< 1.23 -
7.45 1.66
< 1.23 16.49 3.19
< 1.23 20.93 3.00 VIII-3
Sample 4W90 6W90 10W90 Sample SWSS90 NESS90 NSS90 WSS90 ESS90 SSS90 TABLE 2 (Cont'd)
SUMMARY
OF ENVIRONMENTAL SET 90 - Fall 2016 Activity Levels - Water Alpha Beta Gamma (pCi/gram)
(pCi/gram)
(pCi/gram) 0.00 10.29
< 189.78 0.00 8.16
< 189.78 0.00 18.80
< 189.78 Activity Levels - Subsurface Soil Alpha Beta (pCi/gram)
(pCi/gram) 1.57 26.15 1.07 15.51 1.57 29.86 0.52 23.37
. 0.70 29.03 0.88 21.54 H-3 (pCi/mL)
< 1.76
< 1.76
< 1.76 Gamma (pCi/gram) 3.20 3.54 3.87 3.87 4.34 3.23 Gamma and tritium analyses are based* on wet weights while alpha and beta are based on dry weights. HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity (MDA).
VIII-4
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3 8
9 10 11 12 13 14 15**
16 17 18 29 30 31 32 33 34 35..
36 37 38 39 TABLE3 ENVIRONMENTAL TLD
SUMMARY
r.(i.fectiorifjMap Distanc~~irom
'from :; I MURR St~ck
>iMURR:~J (meters)~.:
I 72210 72210 72210 31 49 119 87 55 33 28 143 149 284 SE 320
299 NE 454
- NE 671 872 294 174 67 499 123.
318 174 496 NE 498
NIA 99 98 105 i>>'.Ist Qt~~~ '1* '2ntl Qtr.))3 3rd cj'.tr
'.~:. 2016~{'.... 2016 l 201r?.
(!!~t mrelhh (netmrem);ir(net m~em) 12.0 0.0 2.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0.
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1.0 0.0 0.0
. 0.0 0.0 0.0 0.0 5.0 0.0 0.0 0.0 0.0 1.0 0.0 0.0 0.0 0.0 0.0 0.0 6.0 2.0 3.0 0.0 0.0 0.0 0.0 0.0 o:o o.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
!ith Qt!).
- 2016 *;~*
(net.mrem).
. 32.0 30.0 30.0 0.0 0.0 0.0 1.0 0.0 3.0 20.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1.0 0.0 0.0 o:o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
- ** Monitor was relocated on April 1, 2016.
VIII-5
- 1fo;fa1 2016 (n~ttPirem)l 111.0 113.0 107.0 0.0 15.0 0.0 4.0 4.0 21.0
. 88.0 0.0 3.0 2.0 0.0 2.0 12.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1.0 0.0 0.0 o~o 0.0 1.0 1.0 0.0 5.0 1.0 0.0 0.0 12.0 0.0 0.0 0.0 0.0 0.0 0.0 26.0 3.0 0.0 6.0 0.0
TABLE4 NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS Radiation Surface Contamination*
Air Samples**
RWPs January 57 57 59 19
- February 66 66 62 23 March 65 65 70 21 April 72 72 61 31 May 64 64 67 22 June 84 84 70 25 July 55 55 61 17 August 70 70 69 27 September 75 75 69 21
- October 63 63 65 19 November 64 64 62 24 December 11 11 fil.
n TOTALS 806 806 776 270
~* In addition, general building contamination surveys are conducted each normal work day.
- Air samples include exhaust stack Ar-41, containment buildingAr-41, sump entries, and hot cell entries;
- Miscellaneous Note During calendar year 2016, MURR shipped 1,253 cubic feet of low-level radioactive waste containing 2,219 mCi of activity.
VIII-6
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I SECTION IX
SUMMARY
OF RADIATION EXPOSURE TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS January February March April May June July August September October November December Total for Year AC (PRD) 53 65 114 49 67 58 65 65 57 128 317 221 January 1, 2016 through December 31, 2016 Total :Personnel Dose (mrem) by Dosimetry Group BCS DO FOE HP 5
2 o*
129 8
0 4
170 20 0
0 310
- 20.
- 2 150 0
2 (j
176 23 0
0 108 4
0 0
114 10 0
0 240 3
0 2
141 8
0 0
166 0
0 0
218 30 0
56 157 IRR 0
0 o*
0 5
0 0
9 0
0 0
NA 2
14 12 5
3 12 3
14 11 0
8 NS NSP 22 0
17 0
8 0
4 0
10 9
65 16 0
0 1
31 6
8 3
15 38 0
29 0
OPS PRO QA RES RP 1325 380 39 0
4 1370 214 100
.10 4
1061 321 66 30 12 1222 183 43 14 7
1332 193 101 3
0 1441 172 76 4
21 1338 199 54 0
2 1688 249 118 6
6 1588 136 117 1
0 1239 33 108 8
0 1208 0
71 34 3
1670 20 128 3
5 SH 154 123 151 116 135 250 224 159 202 401 539 423 SIL TEE WC Total 106 0
25 2246 141 4
18 2262 190 7
13 2315 182 9
85 2092 166 3
8 2213 191 15 3
2455 189 3
12 2207 214 23 20 2845 162 5
57 2505 149 7
7 2272 133 11 119 2699 164 5
5 2917 131 6
63 2079 15 85 203 79 16482 2100 1021 113 64 2877 1987 92 372. 29028 Monthly Avg.
HighestWB (annual) 1259 105 528 11 48 1
5 173 1
8 7
17 7
1374 175 85 9
5 240 166 8
31 2419 2
6 738 28 57 91
. 996 1130 224 34 32 892 1217 24 66 High Extremity (annual) 4788 375 NM 394 1416 90 1338 414 548 2258 3125 1728 1686 1851 1673 3725 963 607 AC(PRD)-Analytical Chemistry (Productior IRR-Irradiations BCS-Busine.ss & Central Services NA-Nuclear Analysis DO-Director's Office NS-Neutron Scattering FOE-Shops & Support NSP-NorthStar Pharmaceutical HP-Health Physics OPS-Operations WB=Whole Body NM;,,Not Monitored PRO-Isotope Processing QA-Quality Assurance RES-Research RP-Radiopharmaceutical SH-Shipping SIL-Silicon TEE-Trace Elemental Epidemiolog)
WC-Work Control Analysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA.
No significant personnel exposures occurred during this monitoring year.
- NOTES:
Dosimetry serV'ices are provided by Mirion Technologies (except selfreading dosimetry).
The Analytical Chemistry Group (AC) was expanded and renamed the Production Group (PRD) in 2016.