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Univ. of Missouri - Columbia - Transmittal of 2015 Reactor Operations Annual Report
	ML16060A211
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/25/2016
From:	Rhonda Butler, Fruits J; Univ of Missouri - Columbia
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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	Download: ML16060A211 (39)
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UNIVERSITY of MISSOURI RESEARCH REACTOR CENTER February 25, 2016 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station P 1-37 Washington, DC 20555-0001

REFERENCE:

Docket 50-186 University of Missouri-Columbia Research Reactor Amended Facility License R-103

SUBJECT:

University of Missouri Research Reactor 2015 Reactor Operations Annual Report Enclosed is a copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2015 through December 31, 2015.

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 FruitsJ(~missouri.edu or by calling (573) 882-5319.

ENDORSEMENT:

Reviewed and Approved John L. Fruits Ralph A. Butler, P.E.

Reactor Manager Director JLF/j lb Enclosure xc: Mr. Geoffrey Wertz, U.S. NRC Mr. Johnny Eads, U.S. NRC U

1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: www.murr.missouri.edu Fighting Cancer with Tomorrow's Technology

IVIQURR UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2015 - December 31, 2015

UNIVERSITY OF MISSOURI RESEARCH REACTOR FAC-ILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2015 through December 31, 2015 Compiled by the Research Reactor Staff of MURR Submitted by: __ __ _ __ _ __ __ _ __ _ __ __ _ __ _

Jo~hn L. Fruits Reactor Manager Reviewed and approved by:

Ralph A. Butler, PE Director

UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2015 through December 31, 2015 INTRODUCTION The University of Missouri Research Reactor (MUJRR) 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 commnercial sector. Scientific programs include research in archaeometry, epidemiology, health physics, human and animal nutrition, nuclear medicine, radiation effects, radioisotope studies, radiotherapy, boron neutron capture therapy and nuclear engineering; and research techniques including neutron activation analysis, neutron and gamma-ray scattering and neutron interferometry. The heart of this facility is a pressurized, reflected, open pool-type, light water moderated and cooled, heterogeneous reactor designed for operation at a maximum steady-state power level of 10 Megawatts thermal - the highest powered university-operated research reactor in the United States.

The Reactor Operations Annual Report presents a summary of reactor operating experience for calendar year 2015. Included within this report are changes to MURR reactor operations and health physics procedures, revisions to the Hazards Summary Report, facility modifications, new tests and experiments, reactor physics activities and environmental and health physics data.

This report is being submitted to the U.S. Nuclear Regulatory Commission (NRC) to meet the administrative requirements of MURR Technical Specification 6.1 .h (4).

ACKNOWLEDGMENTS The success of MURR and these scientific programs is due to the dedication and hard work of many individuals and organizations. Included within this group are: the University administration; the governing officials of the State of Missouri; the Missouri State Highway Patrol; the City of Columbia Police Department; the Missouri University Police Department (MUPD); the Federal Bureau of Investigation (FBI); our regulators; those who have provided funding including the Department of Energy (DOE) and the National Nuclear Security Administration (NNSA); Argonne National Laboratory (ANL); Idaho National Laboratory (IINL); Sandia National Laboratories (SNL); the researchers; the students; the Columbia Fire Department; the Campus Facilities organization; members of the National Organization of Test, Research and Training Reactors (TRTR); and many others who have made, and will continue to make, key contributions to our overall success. To these individuals and organizations, the staff of MURR wishes to extend its fondest appreciation.

Some of the major facility projects that were supported by Reactor Operations during this past calendar year included (1) replacement of the Emergency Diesel Generator control circuitry, (2) replacement of the Pool Coolant System Heat Exchanger HX-521 plates, (3) replacement of Graphite Reflector Element No. 6 with a new '6E' Element, and (4) 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, MUJRR submitted a request to the NRC to renew Amended I

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

Reactor Operations also submitted a request to the NRC to revise the facility Technical Specifications in order to produce the radiochemical sodium iodide (1-131). There are currently no competing modalities for its use as a therapy for thyroid dysfuinctions and no current supplier within the U.S. This Amendment would allow MURR to continue to perform a key role in the supply of critical medical radioisotopes, both domestically and internationally.

The faicility 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 (LIEU) 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, resources were focused on completing Phase 2 of the accident analyses for the proposed LEU conversion core. This included fmnalizing the Maximum Hypothetical, Loss of Coolant, Loss of Flow and Reactivity Insertion Accidents. Additionally, one PhD3 student assisted in the fuel conversion work this past year by supporting research in determining the material property changes in the beryllium reflector, and hence its lifetime, as a result of a fuel conversion.

Reactor Operations Management also wishes to commend the two individuals who received their Senior Reactor Operator certifications from the NRC. These individuals participated in a rigorous training program of classroom seminars, self-study and on-the-job training. The results of this training are confident, well-versed, decisive individuals capable of performing the duties of a licensed operator during normal and abnormal situations.

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TABLE OF CONTENTS Section TitlePae I. Reactor Operations Summary ........ : .....................-.......... I-1 through 6 II. MURR Procedures .......................................................... 11- 1 through 9 A. Changes to Reactor Operations Procedures B. Changes to the MvURR 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...............................rnI-i through 5 IV. Plant and System Modifications...........................................JIV-1 through 2 V. New Tests and Experiments ............................................... V-i VI. Special Nuclear Material and Reactor Physics Activities ............... VI-1 VII. Radioactive Effluent........................................................ VII-1 through 2 Table 1 - Sanitary Sewer Effluent Table 2 - Stack Effluent VIII. Environmental Monitoring and Health Physics Surveys ................ VIII-1 through 6 Table 1 - Summary of Environmental Set 87 Table 2 - Summary of Environmental Set 88 Table 3 - Environmental TLD Summary Table 4 -Number of Facility Radiation and Contamination Surveys IX. Summary of Radiation Exposure to Facility Staff, Experimenters and Visitors.................................................................. IX-1

SECTION I REACTOR OPERATIONS

SUMMARY

January 1, 2015 through December 31, 2015 The following table and discussion summarizes reactor operations during the period from January 1, 2015 through December 31, 2015.

Full Power % of Total Full Power % of Month Full Power Hours Megawatt Days Time Scheduled01 )

January 679.73 283.42 91.4 102.3 February 607.63 253.40 90.4 101.3 March 657.96 274.41 88.4 99.0 April 652.25 271.93 90.6 101.6 May 674.87 281.54 90.7 101.6 June 628.37 262.22 87.3 97.9 July 670.34 279.51 90.1 100.9 August 650.38 271.19 87.4 97.9 September 652.88 272.34 90.7 101.7 October 665.58 277.62 89.5 100.2 November 616.28 257.06 85.6 96.0 December 679.66 283.36 91.4 102.3 Ttlfr7835.93 3268.00 89.45 % 100.21 %

Note 1: MURR is scheduled to average at least 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months of full power operation per week. Total time is the number of hours in the month listed or the year.

January 2015 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.

On January 25, with the reactor operating at 10 MW in the automatic control mode, a "Power Level Interlock or FIRST" scram was automatically initiated when the FIRST Support Rig was inadvertently bumped while performing a routine sample handling evolution. The immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. The flux trap sample holder was verified to be latched to the inner reactor pressure vessel and the FIRST Support Rig was visually inspected. The operators involved were counseled on the importance of proper sample handling techniques near the FIRST Support Rig. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included: loading new de-ionization bed 'F' and placing it on pool coolant system service; and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-17(B)."

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February 2015 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements and one unscheduled/unplanned power reduction.

On February 9, shortly after the reactor reached 10 MW and had been placed in the automatic control mode, a "Reactor Loop Low Pressure" scram was automatically initiated on low primary coolant system pressure. The immediate actions of reactor emergency procedure REP-3, "Primary Coolant System Low Pressure or Flow Scram,"

were performed. Immediately prior to the scram, the duty operators observed the opening of Pressurizer Drain Valve 527A and a pressurizer low pressure annunciation. Investigation determined that pressurizer liquid level had increased due to an increase in primary coolant temperature during the reactor startup to a level at which valve 527A opened. The associated pressure drop caused by valve 527A opening initiated an automatic scram from Reactor Core Outlet pressure transmitters PT-944A or PT-944B. Pressurizer liquid level was lowered to the normal operating band and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

Note: On February 16, during the next scheduled maintenance day, testing was performed to determine the optimal throttle position of Pressurizer Drain to Drain Collection System Valve 51 5AA. This valve is located downstream of valve 527A and serves to control the primary coolant drain rate from the pressurizer. The throttle position of valve 515AA was changed from 1.5 turns open to 0.5 turns open from the fully closed position. The system was tested to ensure proper operations.

Major maintenance items for the month included: performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim Blade, RTP-i11(D);" and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-20 1, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-17(B)."

March 2015 The reactor operated continuously in March with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and one unscheduled/unplanned power reduction. An NRC inspector arrived at the facility for a routine inspection of the Radiation Protection and Shipping Programs.

On March 21, with the reactor operating at 10 MW in the automatic control mode, a "Channel 4, 5 or 6 Downscale" annunciation was received. No additional annunciations were received and no control rod motion was in progress.

The Lead Senior Reactor Operator (LSRO) directed a second operator to the reactor bridge to inspect conditions near the control and regulating blade drive mechanisms. The operator discovered the drive chain for the regulating blade Rod Position Indication (RPI) encoder had disengaged from the slave sprocket for the regulating rod rotary limit switch assembly and was bound in the drive sprocket preventing movement of the regulating blade. The LSRO immediately initiated a manual reactor scram and all actions of reactor emergency procedures REP-2, "Reactor Scram," and REP-7, "Rod Position Indication System Failure," were completed. Troubleshooting determined that a sufficient minor misalignment had occurred over an extended period of time to allow the chain tension to become variable with the rotational motion of the RPI encoder sprockets. This lack of correct, consistent tension allowed the drive chain to disengage from the RPI encoder sprocket. A complete alignment was performed on the chain drives and sprocket assemblies for the regulating blade RPI encoder, rotary limit switch assembly and regulating blade drive 1-2

assembly and idler arms. Chain tension was adjusted on all drive chains after the alignments were completed. The applicable sections of the "Regulating Blade Operation And Rod Run-In Function Test" portion of form FM-57, "Long Form Startup Checksheet," were completed satisfactorily to verify proper operation of the regulating blade rotary limit switch assembly and regulating blade RPI. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

Failure of the regulating blade to be operable resulted in a deviation from Technical Specification 3.2.a. Licensee Event Report No. 15-01 was submitted to the U.S. Nuclear Regulatory Conmmission on April 15, 2015.

Major maintenance items for the month included: replacing the pump/motor coupling of Pool Coolant Circulation Pump P-508A; flooding Beamport 'D' with super demineralized water for repairs on the monochromator; replacing the regulating blade Rod Position Indication encoder sprocket shaft and brake bushings and alignment of the drive chains and sprocket assemblies; draining Beamport 'D' and backfilling with helium; and loading new de-ionizing bed

'G' and placing on pool coolant system service.

April 2015 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 Control Blade 'A' Offset Mechanism and associated retesting; performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim blade, RTP-1 1(D);" completing Modification Record 01-02, Addendum 12, "Intercom and Paging System Changes in NOA Rooms 2045 & MIB Room 299R;"

and completing Modification Record 14-04, "Lab Impex Iodine Duct Monitor."

May 2015 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one shutdown for physics measurements. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: replacing the rubber gasket sealing material for the reactor containment building backup doors; replacing the power supply for nuclear instrumentation signal processor drawer No. 2; replacing the primary coolant system fission product monitor detector; completing compliance procedure CP-

-26, "Containment Building Compliance Test;" and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-17(B)."

June 2015 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and/or refueling, one shutdown for physics measurements, one shutdown for operator training and one I-3

unscheduled/unplanned power reduction. An NRC inspector arrived at the facility for a routine inspection of Security and Material Control and Accountability.

On June 29, with the reactor operating at 10 MW in the automatic control mode, the control room operator initiated a manual rod run-in as part of performing compliance procedure CP-10, "Rod Drop Times." Immediately after the rod run-rn was initiated, the control room operator noted that shim control blade 'A' was not driving in the inward direction. The immediate actions of reactor emergency procedure REP-8, "Control Rod Drive Mechanism Failure or Stuck Rod," were performed. Subsequent investigation determined that control rod drive mechanism (CRDM) 'IN' relay K1l had failed. The relay was replaced and operability checks were performed satisfactorily, including CP-10.

The reactor remained shutdown until the regularly scheduled maintenance day activities were completed. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently restarted to 10 MW operation.

Failure of the CRDM to be operable resulted in a deviation from Technical Specification 3.2.a. Licensee Event Report No. 15-02 was submitted to the U.S. Nuclear Regulatory Commission on July 27, 2015.

Major maintenance items for the month included: replacing the emergency diesel generator battery charger and alarm circuit board; replacing the K1 'IN' relay on control rod drive mechanism 'A;' performing a reactivity worth measurement in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-17(B);" and conducting the annual emergency preparedness drill.

July 2015 The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: loading new de-ionization bed 'U' and placing it on pool coolant system service; replacing the controller time delay relays on Laboratory Exhaust Fans EF-l3 and EF-14; replacing the control rod drive mechanism 'IN' (K1) and 'OUT' (K2) relays on all four shim control blades; and completing Modification Record 88-06, Addendum 2, "Emergency Diesel Generator Control Replacement."

August 2015 The reactor operated continuously in August with the following exceptions: five shutdowns for scheduled maintenance and/or refueling, three shutdowns for reactor physics measurements and one unscheduled/unplanned power reduction.

On August 31, with the reactor operating at 10 MW in the automatic control mode, a reactor shutdown was initiated after the duty operator observed a greater than normal lowering of pressurizer liquid level of approximately 1 inch per hour and an associated rise in reactor pool water level. This abnornal change in liquid levels was observed shortly after a reactor startup. A reactor refueling had been performed earlier in the day. Subsequent investigation did not reveal a specific source of leakage; however, the source was from either the pressure vessel head packing gland seal, which provides the seal between the pressure vessel head and inner reactor pressure vessel, or- the pressure vessel head flange. Note: The pressure vessel head is removed and then subsequently replaced and tightened after refueling the core has been completed. The fiexitallic gasket between the pressure vessel head flange was replaced and the I-4

packing gland was tightened. The primary coolant system was restarted and primary coolant system integrity was verified. Permission to restart the reactor was obtained from the Reactor Manager. The reactor was subsequently returned to 10 MW operation.

Major maintenance items for the month included: replacing the plates of pool coolant heat exchanger HX-52 1; replacing the batteries in the Uninterruptible Power Supply; replacing control rod operate switch 1S$4; replacing the pico-ammeter on the Nuclear Instrumentation Wide Range Monitor; completing Modification Record 08-03, Addendum 1, "Replacement of the Number 6 Graphite Reflector Element;" performing reactivity worth measurements in accordance with reactor procedure RP-RO-201, "Measurement of Reactivity Worth of Flux Trap Loading or Individual Samples, RTP-17(B)," for the irradiation positions in the new graphite reflector element; and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim blade, RTP-1 1(D)."

September 2015 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: replacing the air actuator for Pressurizer Nitrogen Addition Isolation Valve V526; and completion of Modification Record 15-0 1, "Additional Coupling Joint for Anti-Siphon System Isolation Valves V543A and V543B."

October 2015 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and/or refueling and one unplanned/unscheduled power reduction.

On October 10, with the reactor operating at 10 MW in the automatic control mode, a scram was automatically initiated by a Nuclear Instrument Anomaly from Nuclear Instrumentation Signal Processor No. 2. All immediate actions of reactor emergency procedure REP-2, "Reactor Scram," were performed. Subsequent investigation revealed that the low voltage (+15 vdc) power supply had failed. The entire signal processor drawer was replaced and compliance procedure CP-35B, "Nuclear Instrumentation Signal Processor No. 2," was completed satisfactorily.

The reactor was refueled and permission to restart the reactor was obtained from the Lead Senior Reactor Operator.

The reactor was subsequently restarted to 10 MW operation.

Major maintenance items for the month included: perfonning the biennial change-out of Control Blade 'C' Offset Mechanism and associated retesting; replacing the Flux-trap Irradiation Reactivity Safety Trip (FIRST) device sensor switches and associated cabling; replacing Nuclear Instrumentation Signal Processor Drawer No. 2; and performing a reactivity worth measurement in accordance with reactor procedure RP-RO-200, "Measurement of Differential Worth of a Shim blade, RTP-11 (D)."

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November 2015 The reactor operated continuously in November with the following exceptions: five shutdowns for scheduled maintenance and/or refueling and one unscheduled/unplanned power reduction.

On November 24, with the reactor operating at 10 MW in the automatic control mode, a scram was manually initiated by the duty operator after noting that the "Control Rod Operate" switch (1 S4) did not return to its neutral position following a routine shimming evolution after the operator had released control of the switch. 1S4 is a 3-position (In-Normal-Out), spring return to neutral position switch that is used to withdraw or insert the shim control blades manually. Although failure of the switch spring did not prevent the shim control blades from operating in both directions. either manually or automatically, the Lead Senior Operator was not positive of the exact failure mode and immediately initiated a manual scram. All immediate actions of reactor emergency procedure REP-2 "Reactor Scram," were completed. Subsequent investigation of the switch assembly revealed that the torsion return spring had failed. The torsion spring for switch 1S4 was replaced and operational checks were completed satisfactorily. The reactor was refueled and permission to restart the reactor was obtained from the Reactor Manager. The reactor Was subsequently restarted to 10 MW operation.

Major maintenance items for the month included: loading new de-ionization bed 'B' and placing it on pool coolant system service; replacing the remote indication gain potentiometer and squaring amplifier circuit board All on Nuclear Instrumentation Power Range Channel No. 4; replacing primary coolant recirculating pump P-501A; completing Modification Record 01-09, Addendum 6, "MUJRR Industrial Building Emergency Distribution Center (EDC-2);" completing Modification Record 0 1-02, Addendum 7, "Intercommunication and Paging System Changes in support of Laboratory Clean Rooms 242C, 299D and 299F;" and replacing Control Rod Operate Switch 1S$4.

December 2015 The reactor operated continuously in December with the following exceptions: four shutdowns for scheduled maintenance and three shutdowns for operator training and requalification. There were no unscheduled/unplanned power reductions this month.

Major maintenance items for the month included: performing a zero, span and calibration of primary coolant flow transmitter FT-9 12H and removal of the unused nuclear instrumentation channel 2 (IIRM) CIC detector drywell (Modification Record 95-01).

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SECTION II MURR PROCEDURES January 1, 2015 through December 31, 2015 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, 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.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 fifty-two (52) revisions issued to the reactor operations procedures, forms and operator aids.

Additionally, one (1) new form was issued. The majority of the revisions were strictly format or editorial in nature, such as cover page changes. The following is a list of the new and revised procedures, forms and operator aids:

iAP-RO-130 Crane Operation 7 6/2/2015 Minor Editorial SEX-RO-105 Reactor Irradiation Experiments 21 9/2/2015 Minor Editorial SEX-RO-122 Beamport "C" Operation ................. 13 9/2/2015 Minor Editorial i FM-15 10 CFR 50.59 Qualified Reviewers List 19 6/19/2015 Minor Editorial

[ FM-16 Primary - Pool Coolant Water Analysis 1 9 ...... 5/22/2015 ....... MiorEditorial....

S FM-19 ]..Unscheduled Power Reduction Rep*ort"........ 5 ]12/29/2015 Minor Editorial .

i FM-21 ARMS Trip Setpoints 10 9/11/2015 Minor Editorial 5 FM-43 Nuclear and Process Data Sheet 20 2/23/2015 Minor Editorial i FM-56 Reactor Routine Patrol 18 12/29/20 15 Minor Editorial FM4 MURR Irradiations Encapsulation Evaluation 0 6/18/2015 MNewPocEdutrea iFM-127 Worksheet MnrEioa

_ _ T-14 1/M Graph 0 6/821 _ rcdue..

__w FM-143 ]1/M Graph 1 ]12/3/2015 Minor Editorial I RR-PSO-100 Scheduling Flux .TraP.Tubes J 7.................

........ 5/6/20 15 .Minor Editorial ...

iLRR-PSO-lO6 TargetMaterialCoontrolChecks.................... ... 1.0.........1/23/20 15 ......... MinorEditorial. .

]IRR-PSO-111i Customer Sample Pre-Encapsulation Evaluation ...... 8 .........6/18/2005 Minor......

0Editorial ....

OA-4 fValve OPeration Air Compressor .8 ] 12/7/20 15 ] Cover* Page 11 OA-5 TEmergency Air Compressor ~8 12/7/2015 Cover Page OP-RO-100 Main Air Sy~stem J 11 12/16/2015 j. Cover Page .....

SOP-R0-!00 .... Main Air System 1...............

2 ........10/23/2015 jMinor Editorial .....

_.. _p_. __!.0. In.....

stru entAirSYstem .......................... . .... 11 , 2/26/20O1_5 ,o Cover Page

]OP-RO-210 fReactor Startup - Normal j 14 9/2/2015 .MinorEditorial iOP-RO-211i Reactor Startup -HotJ13 9/11/20 15 Cover Page 1I-1

OP-R0-2 12 1Reactor Startup - Recovery from Temporary Power 12 12/7/2015 Cover Page

___________________ Reduction

!OP'RO-220 Reactor Shutdown or Power Reduction 91... 9/!11/201.5 .......... Cover Page,.......

.(P-RO-230 O Changing Reactor Power Level 9 j9/11/2015 ,. .... Cover Page .

SOP-RO-350 Reactor Power Calculator Flow Potentiometer 9 9/11/2015 Cover Page

________ Adjustment ______

Op_-RO,410-

DA

Primary Coo1ant System .12 .5/22/20.15 *Minor Editorial iiOP-RO-420 Primary and Pool Water Analysis 7 2../1.9/2015i ........ nr Editorioal.....

i .*N 0-- --°1Coolan Poo System .7TwP P-0eain16 ..... 7/2/2015 .. ........ ver Page.......

i.OP-RO-461!.... Pool Coolant System - One Pump Operation ]16 7/2/2015 Cover Page

iOP-RO-461 Pool Coolant System - One Pump Operation 17 12/7/2015 Minor Editorial

iOP-RO-515 Emergency Air System 11 10/19/20 15 Cover Page

-----.-iOP-RO-520 Emergency Diesel Generator 12 10/19/2015 Minor Editorial

IOP-RO-525 Chill Water System 8 1/30/20 15 Minor Editorial OP-RO-.530 Demiera!'ized Water Suppl!y .System ......7/2/2_015 ........... Cover Page....

1.................!5 OP-RO-53 1 Primary and Pool. Sample Station 13 8/12/20 15 Mvinor Editorial

iOP-RO-532 Drain Collection System 10 8/18/2015 Co ver Page j Oi

. P -RO-5 33 ... Skimmer Sy stem . ...... .. .......... 8 9 /11/2 0 15 C ove r P ag e J SOP-R0-710 R..Padiation Monitoring - Area Monitors ........ 9 ........ 10/19/2015 .... Minor Editorial ....

OP-RO-720 Radiation Monitoring - Stack Monitor 12 9/11/2015 Cover Page

. . . ...... ............. O p e rational Check .... ..... .... ......

OP-RO-730 Facility Exhaust System 16 5/22/2015 Minor Editorial OPR-41 WseTakSstm............. 6 2/921 MnrEdtra IOP-RO-741 Waste Tank System 16 2/19/20 15 Minor EditorialJ OP-RO-741 jWaste Tank System 17 5/22/2015 Minor EditorialJ iREP-RO-100 Reactor Emergency Procedures 17 5/29/2015 Minor Editorial RM-RO..-400 ... W.aste.Ta~nko Sy~stem .Filter Replace~menti................. 8 ...... 12_/2.9/2015 Min... or Editorial....

?iSM-RO-0 11 Beryllium Reflector Replacement ........... ____1027/201 MinorEditorial_

SM-RO-105 Replace Primary and Pool Coolant System Heat 2 13/05 CvrPg

____ Exchangers and Piping_ __ _ _ _

5MR0300 Control Console And Instrument Panel - 1 /12 5 CvrPg

_______Securing Power ______________

___SM-RO-420 Pressurizer Operation - Maintenance & Test 5 5/29/2015 Minor Editorial SM-RO-660 Replacement of Inner and Outer Pressure Vessel f5 2/20/2015 Cover Page SMRO_661 instructions Tank Welding Repair2 5/901 MioEdtra B. CHANGES TO THlE 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.

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There were eleven (11) revisions issued to the emergency procedures, forms and operator aids. The majority of the revisions were strictly format or editorial in nature. The following is a list of the revised procedures, forms and operator aids:

i"EP-RO-002 ...Emergency.Respo nsibilitiies ............ 5 2/23/2015 Minor Editorial EP-RO-004 Fire 6 6/8/2015 Minor Editorial EP-RO-006 Radiological Emergency 7__ 6/8/2015 Minor Editorial EP-RO-007 Severe Natural Phenomenon 5 8/17/2015 Minor Editorial_

IEP-RO-013 fFacility Evacuation 17 2/23/2015 jMinor Editorial FM- 104 Emergency Call List 25 2/23/20 15 Minor Editorial FM- 104 Emergency Call List 26 7/8/2015 Minor Editorial I OA-l0 Fire Extinguisher Locations and Types 11 j2/23/20 15 Minor Editorial ....

OA-10 Fire Extinguisher Locations and Types 112' 6/8/2015 jMinor Editorial OA-10___ Fire Extinguisher Locations and Types* 13 ___!2_20!5 __MirEd___al.....

...A-20 ........ Emergency Equipment O 19 22/05 Minor Editorial C. CHANGES TO HEALTH PHYSICS PROCEDURES, BYPRODUCT MATERIAL SHIPPING PROCEDURES, AND PREPARATION OF BYPRODUCT MATERIAL FOR SHIPPING PROCEDURES As required by the MU]R1 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 thirty-three (133) revisions issued to the health physics, radioactive materials shipping, and preparation for shipping procedures and forms. Additionally, sixteen (16) new procedures and six (6) new forms were issued, and two (2) procedures and two (2) 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:

'AP-HP-105 Radiation Work Permit " i12 ]8/10/2015 Minor Editorial APH-i6 Health Physics.Emergency Equipment Checks J0 J8/10/20 15 New Procedure IAP-HP-1l5 Ilodine 131 Bioassay 0 7/20/2015 New Procedure AP-HP-1 19 ]High Radiation Area Access 17 6/18/2015 Minor Editorial IAiP-HP-124 AP-HP-125

~Ordering Assigning Dosimetry IReview of Unplanned Radiation Exposure ............. 6 0 12/2/2015 J2/15/20 15 New Procedure

] ........ Cover Page_......

AP-HP-129 IHot Cell, HC-01 Control ............... i 2/18/2015 .J Minor Editorial AP-HP-129 IHot Cell, HC-0 1 Control J 12 5/6/2015 J Minor Editorial AP-H-P-140 Bagging and Labeling of Non-Waste Radioac~tive 1 1/23/2015 Minor Editorial

____________Material_______ _________

AP-HP-140 Bagging and Labeling of Non-Waste Radioactive 2 6/18/2015 Minor Editorial

____________Material ______

AP-SH-001 *Adminiistrative Procedure - Radioactive Material 8I /1/215 Minor Editorial iAP-SH-002

_ Shipping Ij-ous Radioactive Shipping Request Form j5 8/17/20 15 JMinor _ _ _

Editorial 11-3

BP-H00Receipt Inspection of Type B Byproduct Material 5 61/01 io dtra

__________Shipping Package ______________

HPi S 00Receipt Inspection of Type B Byproduct Material 1/721 io dtra

,BPB-SH-021'

_ _ S hippin g Pack ag e.. . ... ........ ... .. ...............................

~20WC-1 All-Thread Rod Replacement .........

BPB-SH-022 ,*Painting USA DOT 20WC-10Overpack 3

J,,5/15/2015

//05 ]..

f Obsoleted Obsoleted IBPB-SH-024 Type B(U) F-458 Series P'ackaging of Type B3 6/19/2015 Mior Editorial Radioactive Material BPB-SH-024 Type B(U) F-458 Series Packaging of Type B 15 9/25/2015 Cver Page Material J9221

___________Radioactive _________

BPB-SH-025 ~Packaging of Type B Radioactive material Using 3 92015 M~or Editorial

__________ USA/0562/B(U)-96 (BEATRICE)

_ _ _SH02 Type B(U) F-327 Series packaging of Type B Non- _ _2//21 Cove_ _ _g BPB-SH-0 ast Radioactive Material13 12705 CoerPg BPB-SH-027 I _________

Survey and Decontamination of Returned Shipping Containers 1 2 1 5/15/2015

~I________

Mior Editorial BP-H07Survey and Decontamination of Returned Shipping BPB-S-027Containers______

3 6/19/20 15 Minor Editorial Type B(U) U5A/9337/B(U)-96 (SAKEG-LS) and BPB-SH-028 USA/9338/B(U)-96 (SA!FKEG-HS) Packaging of 3 5/15/2015 Minor Editorial

___________Radioactive material______

BPB-SH-029 Packaging of Type B Radioactive Material Using 11 6/4/2015 Minor Editorial USA/0656/B(U)-96 (GANUK)______

BPB-SH-030 Receipt Inspection of New Type B Byproduct 1 5/15/2015 Minor Editorial

_____________Material Shipping Packages____________________

BP-SH-005 Packaging of Type A Radioactive Material Using 0 5/15/20 15 New Procedure BP-SH-010 i:* .

SAFKEG-LS and SAFKEG-HS Packaging Radioactive Material in Excepted Packages 151 i16 5/15/2015 JMinor Editorial BP-SH-010 Packaging Radioactive Material in Excepted 9/5215 CvrPg BP-SH-010__ Packages 6 __9/25/2015 Cover_____age BP-H-0 1 BP-S__-011 Packaging of Type A Radioactive Material Using

~USA DOT 7A 55-Gallon If 6 5/1/2.1.MnorEdtoia

/*zl I Minor__Editorial BP-S-013 Packaging and Shipment of Radioactive Materials B-H03 Using Reusable Type A Package (5 to 30-Gallon 8 9/2/2015 Minor Editorial

____ ~rum) _ _ _ _

BP-SH-014 Pa'agn and Shipment of Radioactive Material 6 6/4/2015 Minor Editorial BP-SH-016 Using an Overpack

~Packaging and Shipment of Radioactive Material Using USA DOT 7A Model H or I Package Using_Tracerco LS-6 Reusable Type A Package j 81/05 8/17/2015_

CvrPg Cover____Page_

BPS-01 Packaging adSimn of Radioactive Material ot~a 2sn 127210io dtra iBP-SH-0 18 PcaigoRaiatvmaeilUigNrhar 0 1/29/2015 New Procedure

_______Medical Radioisotopes Type A Package________________

SBP-SH-018 {Packaging of Radioactive material Using NorthStar f1 121/01 ior Editorial Medical Radioisotopes Type A Package124/05 M BP-SH-03 1 DOT akgn~~pAai~cieaeilsn7A 20WC-1 0 5/15/20 15 New Procedure SBP-SH-03 1 Packaging of Type A Radioactive Material UsingJ 1/425[MioEdtra II-4

____________ DOT 7A 20WC-1_____________j B- -02 Radioactive Material Shipment Package 14 9/11/2015 Minor Editorial

__________Documentation and Labeling _____.___

BP-SH-059 apctivee MatervicsRuabl e Packaging of Type A 5 6/4/2015 Minor Editorial

_______RadioacieMtra BH32 Packaging "ofType A Radioactive Material Using 6 5//21 MioEdtra FM-09 ........ Gemstone Irradiation Sheet . ................. 6 12/15/2015 . ..Cover Page FM-27* ....

....... n..-House Radioactive Shipping Request Form ...... 15 _._5/5/01 _MiorEdtoia FM-27 In-House Radioactive Shipping Request Form, ],.14 4 5/15/2015 .... Minor Editorial FM-29 ...... Dosimetry, ,Re~questPacket ... .......... 8.... 2/26/2015 ... Minor Editorial FM-39 Control Checksheet for Packaging of Radioactive 12 5/15/2015_ Miojdtra FM-39

....Material..Using ana Excepted Package12 Control Checksheet for Packaging of Radioactive Material. Using an Ex~cepted Packag~e ...........................

13 J9/25/2015 55/05 MioEdtra Minor Editorial FM Control Checksheet for Documentation and 52 Labeling of Radioactive Material Shipment 1 /121 io dtra FM 541 iiiReportof PersonnelContamnation ........... .7 .5/6/2015 J Cover Page

.FM-54 .....RePort of Personnel Contamination . ..........8..... 7/20/20 15 j Minor Editorial ...

F-9 FM S9 Control Checksheet for Spectratek Services 8 6/4/2015 Reusable Type A Package Radioactive M aterial ......................... ... ....................

IMinor Editorial M-7 M-7 Receipt of Radioactive Gemstone Shipping Containers4 8

1 6/16/2015 Cover Page Control Checksheet for Packaging of Type A FM-69

_________Gallon Radioactive Material Using USA DOT 7A S-to 30-Drum I__I_____

11 8/17/2015 Minor Editorial FM-70

~Control Checksheet for Packaging of Type A

~Radioactive Material Using Tracerco LS-6 Reusable J2 12/7/2015 Minor Editorial FM-76 IPersonnel Contamination Log ..... 3 6/18/20 15 Minor Editorial ...

FM-91. *Declaration of Pregnancy ........ 6 5/15/20 15 ... Minor Editorial ...

FM-94 Exclusive Use Shipment Controls 8 .6/4/2015 Cover Page FM-98 Control Check Sheet for MURR Shipment Using 8 /521 ioIdtra FM-98 USA DOT 7A MURR Model 6 or 12 8 51/01 io dtra FM17 Control Check*sheet for P'ackaging Type A .7 6/4/2015 Minor Editorial FM-107 Radioactive Material in an Overpack ______________

.,FM-120 .Individual Type B QA Training Certification 5 2/5/2015 .. Cover page FM18 Control Check Sheet for MUIRR Shipment Using 4 2/20/2015 Cover Page

__M-128 USA DOT 7A MURR Model HorI ____

FM- 129 ~ Control Checksheet for Receipt Inspection of Type 6/19201 Mior Editorial

________ B. Byproduct Material Shipping Package ..... _______ 1......_____

FM-135 Control Checksheet for Packaging of Type B Radioactive Materials Using USA/b(U)-96 4 9/2/2015 1Minor Editorial T BRICe (BEA37 u ) !dShp~rLs 6421 Min~.~ il.....

S FM-13 7 _ Type B Qualified Shipper List 8/17/2015S Minor Editorial II-S

FM-137 °Type B Qualified Shipper..List ............ 8 9/2/2015 Minor Editorial

Control Checksheet for Leak Testing of the S FM- 138 SAFKEG-LS or SAFKEG-HS Shipping Package 4 4/6/2015 Minor Editorial i .................. ....Using the CALT Le~aka ge Testing Device ............. .................. ........................ ... ...........

! Control Checksheet for packaging of Type A

! FM-141 Radioactive material Using SAFKEG-LS and 0 5/15/20 15 New Form SAFKEG-HS Control Checksheet for packaging of Type A FM-141 Radioactive material Using SAFKEG-LS and 1 9/2/2015 Minor Editorial

________SAFKEG-HS__ __ ___ ______

FM -142_..... En~d of Declaration .of Pregnan~cy-.....................

....... 0 ...6/18/20 15 ............New Form. .....

FM-149 iPersonnel Radiation Dose Estimate 1j 2/18/2015 Cover Page FM-1.50 .........Stat~ement of.Training ............................

........ ............. / 9_2 .5 .......

5/29/2015.. Cover.....ge ....

.PagerP FM-i 15

.Control Checksheet for USA DOT 7A 55-Gallon aiatv Mtra ~mn ~ 9~p 4/6/2015 JMinor Editorial EM-154 Control Checksheet for USA DOT 20WC-1 51/0 boee

__M-154__ iOverpack Rod Replacement 45/1/21 Oboee FM-155 FM-155 Quality Assurance Control Checksheet Exterior Painting of USA DOT WC-1, Type B Overpack 33 5//21Oboed 5//21boed ]

FM16

__________Type M-5

. FM-5 ...

Required Documentation for Non-MURR Owned B Shipping Packages 1Contro'lChecksheet for'Type B USA/0'69'7/B(U)-961 (F48Series) Radioactive Material.S~pment .. ]5 4 81/05 6/19/2015 Minor Editorial Minor Editorial

]....

FM157 Control Checksheet for Type B USA/0697/B(U)-96 6 /521 CvrPg FM-159 FM-15 ConrolChecksheet for Health Physics Review of Radioactive Material Shipment Documentation 14 4

//05

_56/01 1 CvrPg CovePag Control Checksheet for Type B Radioactive FM-163 Material Using USA/9337/B(U)-96 (SAFKEG-LS) 5 5/15/2015 Minor Editorial

________and USA/9338/B3(U)-96 (DAFKEG-HS) ____ _ _ _ _ _

FM-164 Authorization For Use of North Office Addition 2 41/05 MnrEioa Authorization For Use of North Office Addition .3.72/01 io dtra FM-164 West Passageway (C2001)

FM-164 uoratoFoUsofNrhOfcAdion 4 8/31/2015 Minor Editorial

_ _.......... W est Passagewa~y .(C2001). ........ __ __

Control Checksheet for Packaging of Type B FM-167 Radioactive Material Using USA/0656/B(U)-96 1 6/4/2015 Minor Editorial (Ganuk )______________ _____________________

FM-169 Control Checksheet for Packaging of Type A 1 21/05 Mio dtra FM-169 Radioactive Material Using USA DOT 7A 20WC-1 0 51/05NwFr jControl Checksheet for NotIa eia FM- 169 Rdoiooe Packaging of Type A 1aiatv 12/4//2015 Mnor Edioria RdocieMaterial UigUADT7 OC1__ _____

Control Checksheet for' NorthStar Medical ....

FM- 170 iadioisotopes Packaging of Type A Radioactive 12/14/2015 Minor Editorial II-6

SControl Checksheet for Receipt Inspection ofI

] FM-175 Customer Owned Type B Material Shipping 0 10/27/2015 New Form

_ _ _PackageI

]Control Checksheet for Receipt Inspection ofI i FM-177 :SAFKEG LS & HS Type B Material Shipping 0 10/27/2015 New Form

_______Package_______I_________

HC-PSO-002 Hot Cell Preparation of Radioactive Material for 13 /2205 MnrEtoa

_.......... Shipment 1 _ in rE__2/2itra HCot00 Celi Preparation of Radioactive Material for 14 68/05 MioEdtra HC-PSO-002 Shipment 1410 6/23/2015 MnrEditorial SHot HC-PSO-002

__,,_Shipment_

SGlove Cell Preparation of Radioactive Material for Box Preparation of Radioactive Material for 15 10 91/01 12321 I591121 io Minor__Editorial Minor Editorial

"'HC-PSO-005_ Hot Cell! Loading of H~ost.Cans............................. 13 6/18/2015 Minor Editorial .....

{*HC-PSO-o05_ *Hot Cell Loadig of Host Cans .................... 14 ...... 9/11/2015 Mino....

0r Editorial_

iIC-HP-305 ICalibration - electrostamtic Discharge Dosimeter 9 ,j 5/7/2015 jMinor Editorial.....

SCalibration- Eberline Model PING 1A Stack 7 5721 io dtra SI-P30 Monitor - Particulate Channel 7 _57/215_inrEitoia Calibration - Eberline Model PING 1A Stack 18 5721 io dtra

__C-HP-311_ Monitor - Iodine Channel 8 __5_7/2015 Minor__Editorial ICalibration Eberline Model PING 1A Stack LIC-I-P-3 12 ~Mntr-GsCanl17 -

5/7/2015 Minor Editorial I C.........13.

I-P33

.. Calibration Eberline' PCM- 1 Contamination Monitor

- 0 1222 1//01 15 e e

rcdr rcdr iC-P36 Calibration - Lab Impex Smart MCA Continuous 0 6//21 NePrcde ICH-38

! I-HP348 Calibration - Canberra S5XLB-G & Tennelec Series 5 with Gamma, & Tennelec Series 3 17 7 6//2151 616/01_Coer CvrPg ag

~Calibration - Lab Impex Stack Monitor - I IC-HP-349 IParticulate Channel 5 5/7/20 15 I Minor Editorial

IC-HP-350 JCalibration - Lab Impex Stack Monitor - Iodine 3 1/23/2015 1 Cover Page

~Calibration - Lab Impex Stack Monitor - Gas 3 1/23/2015 Cover Page ICH-31 Channel ____________

IC.... ....... Calibration - Lab"Imp'ex Stack Monitor - Flow ~ 5721 io dtra IC-HP-359 :Calibration - Ludlum Model 177 Frisker 1 6/16/20 15 Minor Editorial IC-HP-360 Caibrtin- Eberline AMS-3 Continuous Air

~Monitor I0 5/7/2015 New Procedure IC-I-P-3 61 iCalibration - Canberra GEM V Portal Monitor 10 }5/7/20 15 jNew Procedure IC-HP-36I iCalibration,- Canberra GEM VPortal,,,Monitor J1"i~i 8/31/2015J' Minor Editorial IC-HP-362 Calibration - Eberline/thermos Model AMS-4 0

II 5/7/2015 NePrcde

___________Continuous Air Monitor, Radial Sampling Head NePrcde IC-I-P-3 64 ICalibration - Ludlum Model 3030 Swipe Counter 0 1 2/2/2015 New Procedure OP;*:i2-HP-222 Air Sampling -Containment Building Ar-41 .... ... 5201i5

/71 ............Minor Editorial ...

..... ......He~alth P~hysic~s _Daily F~acili~ty C*h'ecksi. ............... 1[_6...1 .... 5/6/20_15 .......... MiorEditorial° ....

II1-7

OP-HP-306 Health Physics Daily Facility Checks 7 8/31/2015 Cover Page OP-HP-350__ .Eberline Model PING lA - Filter Change ... ..... 6 ..... 5/7/2015 Minor Editorial .

OP-HP-358_ ~Air Monitor Filter Change and Source Check 0 _12/2/2015! Ne Procedure___

OP-HI-P-600 Europium' Source Creation ....... ...... 3 j9/11/2015'""" Cover Page ...

IQAB-SH-003 Materi~al!.Control for Type B Shipping Program 5 .... 5/15/2015 ... Minor Editori~ali. ...

...QA-H-0 Type B Program Vendor Qualification ........ 5 ..... 5/15/2015 Minor Editorial

...QAB-SH-006. rType B Shipping Program Quality Audits 2 6/4/2015 Minor Editorial Leak Testing of the SAFKEG-LS or SAFKEG-HS QAB-SH-007 iShipping Package Using the CALT Leakage 3 .4/6/2015 Minor Editorial

___________Testing Device________________

J QAB-S-008 Training for Type B Shipment Leak Test QP-H08 erformers 1 5/15/2015 Mior Editorial Pre-Shipment leak Testing of the Type B __ j i QAB-SH-009 USA/0656/B(U)-96 (Ganuk) Shipping Package 1 8/17/2015 Mior Editorial Sodium Iodide Spectral Analysis for Excepted, QA-SH-002 License-to-License, Type A, and Type B 6 1/30/2015 Minor Editorial

__ _ _Radioactive Materials Shipments ................

RP-HP-l100 Contamination Monitoring - Performing a Swipe 7 .7/20/2015 Cover P*age .........

..... P-*1 05...... Tranfer of.Radioactive Material -InFlacility .... .I1/23/20!5. Minor....

0Editorial......

HP-10.5 .... Transfer of Radioactive Material - In Facility 101] 4/2/2015 ...... inor Editorial ....

RP-HP-I05 ITransfer of Radioactive Material - In Facility J 1117/2/2015 Minor Editorial

_____-_____ l ~L~ead Pigs to service 6 5/6/2015 Min."or.Editoria~l..

(([RP-HP-1215 PRetrsningl RaiatvIotmnto 9 _5/6/2015 MinorEditorial RP-HP-120 ~Personnel Radioactive Contamination J19 56/182015 Minor Editorial RPU-2 Radiation Monitoring - Performing and 1 //01[io dtra RP-_P-125_ JDocumenting a Survey 1 5/6/015_inorEditria RdainMonitoring - Performing and 2 1 8/10/20 15 Minor Editorial RHP15 Documenting a Survey I _____t R-P15 Radiation Monitoring - Performing and 3 10/22/2015 Minor Editorial R__-_P-125_ Documenting a Survey ______________

1 RP.* -HP-130 ..... Receipt of Unirdated Fuel....... .......... . . 7 .. ..6/18/20Q15 M in........

or .Editorial .....

~RP-HP-130 ...Receipt of Unirradiated Fuel .8 10/22/2015 Minor Editorial 1RP-I-P-137 ~Handling Radioactive Material in the Reactor Pool 13 5/6/2015 fMinor Editorial RP-P-,1,37 ......HandligRadioactive Material in the Reactor Pool 14

.... 8/31/2015 Mior Editorial PHP19 Beamport Radiation Level Monitorig Durinig S /0/05 oer Page R~eactor Startup . F.....

u ...............

.S I-P .S O-0 0 9 .....Op era tio n oC f t h*e D~e ni s o n Can Pr es s ... . . ..... . .... ... ... . ...1. . .. ..6/18 /2 0 1 5 F ul R evi ew SReactor Chemistry Isotope Counter Trending and /72 5fMio dtra [

I IBuilding Exhaust Stack Effluent - Tritium 5 91/05 MnrE itra

!SV-HP-119 PropertyrnReeae9/10/2015 Minor Editorial

__"_""SV __HP-117 __Se _ndaryColantandSump _WaterAnalysi 8 12/21/2015 Minor Editorial [

V-P11_Property Releas_ . e ......... _2/2201 MinorEditorial II-8

SVUP12 Building Exhaust Stack Effluent - AR-416 6//21 MioEdtra iSV-HP-121 Buidig Exhaust Stack Effluent- AR-41

~M onitoring .................. . . . .... .....

1 7

~ 91/05 9/11/2015 Mnrdtra

___...................... M inor Editorial _

iSV-HP-130 ~Emergency Air Sampling of Exhaust Plum 7 8/31/2015 Minor Editorial iSV-HP- 135 CnametAir - Emergency Remote Sampling 5 6/16/20 15 Minor Editorial WM-SH-100 Radioactive Waste - Preparation and Storage 8 6/4/2015 Minor Editorial

!WM-SII-104 Solidification of Radioactive Liquid for Shipment 0 9/25/20 15 4New Procedure SWM-SH-105 Radioactive Waste Processing 11. 9/11/2015 4Minor Editorial iWM-SH-110 adDsol0 6//2015 New Procedure iW-H10Radioactive Waste - Barrel Analysis for Shipment 0 6/

............ adioact.e.Waste.-.Ba.rel.AalysisaforDShipmen 1 9/2/2015 1Minor Editorial WM-SH-300Exclusive Use Shipment of LSA or SCO 1 //05 io dtra WM-SH300 Radioactive Waste 13 9205 MioEdtra 1 UseShipment of LSA or SCO WM-SH-300 RaoaivWst14 10/23/2015 Minor Editorial 1I-9

SECTION IHI REVISIONS TO TILE HAZARDS

SUMMARY

REPORT January 1, 2015 through December 31, 2015 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, page 3-12, Figure 3.2, Grade Level Plan (as revised by the 1972-1973, 1979-1980, 1990-1991, 1995, 1996, 2012, 2013 and 2014 Reactor Operations Annual Reports):

Replace with: Updated Figure 3.2, Grade Level (MURR Dwg. No. 1145, Sheet 2 of 5, dated 04/16/15)

Original HSR, page 3-13, Figure 3.3a, Third Level Plan (as revised by the 1995, 1996 and 2012 Reactor Operations Annual Reports):

Replace with: Updated Figure 3.3a, Third Floor (MURR Dwg. No. 1145, Sheet 3 of 5, dated 06/13/08)

Original HSR, page 3-14, Figure 3.3b, Fourth Level Plan (as revised by the 1995, 1996 and 2012 Reactor Operations Annual Reports):

Replace with: Updated Figure 3.3a, Fourth Floor (MURR Dwg. No. 1145, Sheet 4 of 5, dated 04/13/06)

Original HtSR,, paige 3-15, Figure 3.3b, Fifth Level Plan (as revised by the 1995, 1996 and 2012 Reactor Operations Annual Reports):

Replace with: Updated Figure 3.3a, Fifth floor, Cooling Tower & SARB (MURR Dwg. No.

1145, Sheet 5 of 5, dated 11/02/1 1)

Original HSR, pages 7-21, Section 7.2.9, Table 7.2 (as revised by the 1995, 2001, 2007, 2009, 2011, 2012, 2013 and 2014 Reactor Operations Annual Reports):

Delete:

TABLE 7.2 PAGING SYSTEM SPEAKER LOCATIONS Containment Building North Office Addition Room 101 (3) Corridor C2000 Room 2009A Containment Building Third Level Corridor C2002 (2) Room 2011 Containment Building Grade Level (2) Room 2005 Room 2015 (17)

Containment Building Fourth Level Room 2006 Room 2041 Room 2007 Room 2045A Room 2008 Room 2045B Shinping and Receiving Building Room 2008A Room 2046 Room 2008C Room 2047A III-1

Room 101 (2) Rom11()Room 2009 Room 2048 Reactor Laboratory Building Cooling Tower Grade Level Room 212 Room 246 Room 299D Outside Room 114 Room 213 Room 247 Room C299D Room 199 (2) Room 215A Room 25 1 Room 299F Outside Room 214A Room 216 Room 255 Room 299N Outside Room 224 Room 218 Room 257 Room 2990 Outside Room 228 Room 224 Room 258 Room 299P Outside Room 241 Room 225 Room 259 Room 299Q Outside Room 244 Room 227 Room 260 Room 299U Outside Room 258 Room 231 Room 269 Room C299U Outside Room 264 Room 231lA Room 271 Room 299T Outside Room 288 Room 231C Room 273 Room 299V Outside Room 293 Room 232B Room 278 (2) TOB -l Room 103 Room 238 Room 280 TOB-2 Room 110 Room 241 Room 281 TOB-3 Room 111 Room 242 Room 288 TOB-4 Room 202 Room 244 Room C299A TOB-5 Room 210, Lobby Room 245 Replace with:

TABLE 7.2 PAGING SYSTEM SPEAKER LOCATIONS Containment Building North Office Addition Room 101 (3) Corridor C2000 Room 2015 (17)

Containment Building Third Level Corridor C2002 (2) Room 2041 Containment Building Grade Level (2) Room 2005 Room 2045 Containment Building Fourth Level Room 2006 Room 2045A Room 2007 Room 2045B Room 2008 Room 2045C Room 2008A Room 20451D Shipping and Receiving Building Room 2008C Room 2046 Room 2009 Room 2047A Room 101 (2) Room 2009A Room 2048 Room 2011 Reactor Laboratory Building Cooling Tower Grade Level Room 212 Room 246 Room C299D Outside Room 114 Room 213 Room 247 Room 299F Room 199 (2) Room 215A Room 251 Room 299N Outside Room 214A Room 216 Room 255 Room 2990 Outside Room 224 Room 218 Room 257 Room 299P Outside Room 228 Room 224 Room 258 Room 299Q Outside Room 241 Room 225 Room 259 Room 299R Outside Room 244 Room 227 Room 260 Room 299U Outside Room 258 Room 231 Room 269 Room C299U Outside Room 264 Room 231A Room 271 Room 299T Outside Room 288 Room 231C Room 273 Room 299V Outside Room 293 Room 232B Room 278 (2) TOB-1 Room 103 Room 238 Room 280 TOB-2 Room 110 Room 241 Room 281 TOB-3 Room 111 Room 242 Room 288 TOB-4 Room 202 Room 244 Room C299A TOB-5 Room 210, Lobby Room 245 Room 299D I11-2

ADDENDUM 1 - HAZARDS

SUMMARY

REPORT (FEBRUARY 1966)

HSR, Addendum 1, Figure 3.22.1, page 103, Diagram of Laboratory and Containment Building Ventilation System (as revised by 1995, 2002 and 2009 Reactor Operations Annual Reports):

Replace with: Updated Figure 3.22.2, MURR Supply Air Schematic (MURR Dwg No. 1125, Sheet 2 of 4, dated 01/26/15)

HSR, Addendum 1, Figure 3.22.2, page 104, Ventilation Air Flow Diagram for the East Tower (as revised by 1995, 2004 and 2010 Reactor Operations Annual Reports):

Replace with: Updated Figure 3.22.2, MURR Supply Air Schematic (MURR Dwg No. 1125, Sheet 2 of 4, dated 01/26/15)

HSR, Addendum 1, Section 3.8, paragraph 4, page 24, (as revised by the 1989-90, 2002, 2004, 2010 and 2014 Reactor Operations Annual Reports):

Add: "7) A distribution panel which feeds through a transformer and a 120/208 volt distribution panel, to supply the MURk Industrial Building systems."

Delete: "The emergency bus is routed through the automatic transfer switch to an Emergency Distribution Panel (CTR-1) shown on Figure 3.8.1. This distribution panel feeds the following emergency electrical loads:"

Replace with: "The emergency bus is routed through the automatic transfer switch to two Emergency Distribution Panels (Emergency Distribution Center and Emergency Distribution Center - 2) as shown on Figure 3.8.1. These distribution panels feed the following emergency electrical loads."

HSR, Addendum 1, page 25a, Figure 3.8.1, Emergency Generator Load Diagram (as revised by the 1989-90, 2002 and 2004 Reactor Operations Annual Reports):

Replace with: Updated Figure 3.8.1, Electrical Distribution Elem. Diagram (MURR Dwg No.

2272, Sheet 1 of 1, dated 8/17/15)

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 and 2014 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.a, Electrical Distribution Reactor/Laboratory (MUIRR Dwg.

No. 522, Sheet 1 of 7, dated 06/11/15)

HSR, Addendum 3, page 19, Figure 2.3.b, Electrical Distribution (as added by the 1995 and revised by the 2001, 2002, 2003, 2004, 2005, 2007, 2009, 2010, 2011, 2012 and 2013 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.b, Electrical Distribution Reactor/Laboratory Panels (MURk Dwg No. 522, Sheet 2 of 7, dated 06/11/15) 111-3

HSR, Addendum 3, page 19A, Figure 2.3., Electrical Distribution (as added by the 2004 and revised by the 2005, 2007, 2009, 2010, 2011, 2012, 2013 and 2014 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.c, Electrical Distribution Reactor/Laboratory Panels-2 (MURR Dwg No. 522, Sheet 3 of 7, dated 06/11/15) 11S1, 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 and 2014 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.d, Electrical Distribution emergency Electrical Power System (MUIRR Dwg No. 522, Sheet 4 of 7, dated 11/09/15)

HSR, Addendum 3, page 19C, Figure 2.3.e, Electrical Distribution (as added by the 2007 and revised by the 2009, 2010, 2011, 2012 and 2013 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.3.e, Electrical Distribution Emergency & UPS Panels (MUIRR Dwg No. 522, SheetS5 of 7, dated 11/09/15)

HSR, Addendum 3, page 19D, Figure 2.3.f, Electrical Distribution Add: New Figure 2.3.f, Electrical Distribution North Office Addition (MURR Dwg No. 522, Sheet 6 of 7, dated 06/11/15)

HSR, Addendum 3, page 19E, Figure 2.3.g, Electrical Distribution Add: New Figure 2.3.g, Electrical Distribution North Office Addition Panels (MURR Dwg No. 522, Sheet 7 of 7, dated 06/11/15)

ADDENDUM 4 - HtAZARDS

SUMMARY

REPORT (OCTOBER 1973)

HSR, Addendum 4, page A-29, Figure A.11, Schematic Diagram of Laboratory and Containment Buildings Ventilation System (as revised by the 1995, 2002, 2005, 2009, 2010, 2011, 2012, 2013 and 2014 Reactor Operations Annual Reports):

Replace with: Updated Figure A. 11, Schematic Diagram of Laboratory and Containment Buildings Ventilation System (MURR Dwg No. 1125, Sheet 1 of 4, dated 03/20/15)

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 and 2014 Reactor Operations Annual Reports):

Replace with: Updated Figure 2.1, Electrical Distribution Reactor/Laboratory (MURR Dwg No. 522, Sheet 1 of 7, dated 06/11/15) 111-4

11SR, Addendum 5, Section 2.2, Paragraph 4, Page 3 (as revised by the 1990, 2004 and 2010 Reactor Operations Annual Reports):

Delete: "The emergency bus is routed through the automatic transfer switch to an emergency distribution panel located on the wall in the north inner corridor of the laboratory building. This feed panel distributes power to the following (see Figure 2.1):"

Replace with: "The emergency bus is routed through the automatic transfer switch to two emergency distribution panels. These feed panels distribute power to the following circuits (see Figure 2.1)."

Add: "(6) A distribution panel which feeds through a transformer and a 120/208 volt distribution panel, to supply the MUJRR Industrial Building systems."

1111-5

SECTION IV PLANT AND SYSTEM MODIFICATIONS January 1, 2015 through December 31, 2015 For each facility modification described below, MUIRR has on file the safety screen or evaluation, as well as the documentation of review, performed in accordance with 10 CFR 50.59.

Modification 08-03, Addendum 1:

Replacement of Number 6 Graphite Reflector Element This addendum to Modification Record 08-03, "Replacement of Graphite Reflector Elements 1, 2, 3, 4, 6, 7, 8, and 9," documents the replacement of graphite reflector element "6D" with a new element "6E," which incorporated three (3) new irradiation positions (two 1-inch and one 2-inch position).

Modification 88-06, Addendum 2:

Emergency Diesel Generator Control Replacement This addendum to Modification Record 88-06, "Emergency Electrcal Power Upgrade (Replacing Emergency Generator and Automatic Transfer Switch)," documents the replacement of the diesel generator controls for the Emergency Electrical Generator. The existing control system has demonstrated problematic to service and repair parts are no longer available. The Cummins Power Generation PowerCommand 1302 controller replacement kit is a standard retrofit model recommended by the vendor. An additional bar graph display (HMIl 112) replaced the individual analog gauges with a single segmented LED bar graph display providing the same parameters as the original controller.

Modification 01-02, Addendum 7:

Intercom and Paging System Changes in Support of Laboratory Clean Rooms 242C. 299D and 299F This addendum to Modification Record 0 1-02, "Installation of a New Reactor Facility Intercommunication and Paging System," documents changes to the MURR Intercommunication and Paging System that enhance communications in rooms 242C, 299D and 299F through the addition of three (3) paging speakers.

Modification 01-02, Addendum 12:

Intercom and Paging System Changes in NOA Room 2045 and MIB Room 299R This addendum to Modification Record 0 1-02, "Installation of a New Reactor Facility Intercommunication and Paging System," documents changes to the MUJRR Intercommunication and Paging System that enhance communications in the North Office Addition (NOA) and the MURR Industrial Building (MIB) through the addition of four (4) paging speakers.

Modification 01-09, Addendum 6:

MURR Lndustrial Building Emergency Distribution Center (EDC-2)

This addendum to Modification Record 01-09, "Installation of Emergency Lighting Panel No. 1," documents the addition of an emergency electrical distribution panel in the MURR Industrial Building (MIB) portion of the Laboratory Building. The addition includes a remote-operated circuit breaker, standard fused disconnects, an Emergency Distribution Panel (EDC-2), a step-down transformer and an Emergency Lighting Panel (ELP-3).

IV-1

Modification 14-04:

Lab lImpex Iodine Duct Monitor This Modification Record documents the installationa of a permanently installed Lab lInpex Iodine Duct Monitoring System for detection of radioactive airborne iodine discharged through the MURR Industrial Building (MIB) Expansion ventilation system to the Laboratory and Containment Building Exhaust Ventilation System. The monitoring equipment consists of a single-channel radiation detection system designed to measure airborne concentrations of radioactive iodine in the exhaust air that is sampled by a shrouded probe in the ventilation ducting downstream of all of the hot cell and room filtrations systems.

Modification 15-01:

Additional Couplingz Joint for Anti-Siphon System Isolation Valves V543A and V543B This Modification Record documents the addition of a coupling joint to the drive tube of the Anti-Siphon System Isolation Valves V543A and V543B. These joints facilitate the adjustment of the valve position with respect to the actuator travel with the reactor pool water level just below the refuel bridge.

IV-2

SECTION V NEW TESTS AND EXPERIMENTS January 1, 2015 through December 31, 2015 New tests or experiments approved during this period under a Reactor Utilization Request (RUR) were as follows:

RUR 284, as amended: Selenium Dioxide (Se0 2)

Description:

This RUR was amended to authorize the irradiation of enriched Selenium-74 in the form of selenium dioxide (SeO 2) in the graphite reflector region in support of research and development activities.

RUR 440, as amended: Tellurium Dioxide (TeO2 )

Description:

This RUR was amended to authorize the irradiation of natural tellurium dioxide with only a single encapsulation leak check in the graphite reflector region in support of research and development activities.

RUR 446: Samarium

Description:

This RUR authorizes the irradiation of up to five (5) milligrams of natural or enriched samarium metal in the graphite reflector region in support of research and development activities.

RUR 448: Bismuth Preliminary Irradiations

Description:

This RUR authorizes the irradiation of up to 600 grams of bismuth metal for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in the graphite reflector region in support of research and development activities.

RUR 448, as amended: Bismuth Irradiations

Description:

This RUR was amended to authorize an increase in fluence up to 3.7E20 n/cma2 for irradiation of up to 600 grams of bismuth metal in the graphite reflector region with in support of research and development activities.

RUR 451: 31 grams Uranium Oxide (U0 2 -Natural U)

Description:

This RUR authorizes the irradiation of up to 31.0 grams of natural uranium dioxide in a specific tubular encapsulation in the graphite reflector region 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 Specifications.

The safety evaluations have been reviewed by the Reactor Manager, Reactor Health Physics Manager, Assistant Reactor Manager-Physics, and the Reactor Safety Subcommittee, as applicable.

V-1

SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2015 through December 31, 2015 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-six (56) refueling evolutions were completed in 2015. Excess reactivity verifications were performed for each refueling. The largest measured excess reactivity was 4.03%. MUJRR Technical Specification 3.1(f) requires excess reactivity to be less than 9.8%.

Reactivity Measurements:

Differential blade-worth measurements of four (4) shim control blades were performed following either a planned replacement of a control blade or characterization of the bum-in effect of a new control blade.

Four (4) reactivity measurements were performed to determine the reactivity worth of all samples, including the sample holder, loaded in the flux trap region.

Two (2) reactivity measurements were performed to determine the reactivity worth of the newly installed graphite reflector element No. 6E (Position 6) and the sample irradiation positions associated with the new reflector element.

VI-1

SECTION VII RADIOACTIVE EFFLUENT January 1, 2015 through December 31, 2015 TABLE 1 SANITARY SEWER EFFLUENT January 1, 2015 through December 31, 2015 Descending Order of Activity Released for Nuclide Totals > 1.000E-05 Ci Nuclide Activity (Ci)

H-3 1.037E-01 S-35 7.628E-03 Co-60 5 .594E-03 Zn-65 1.283E-03 Ca-45 7.093E-04 P-32 6.7 13E-04 Lu-177 3.849E-04 Tc-99m 3.574E-04 Mo-99 2.478E-04 Sc-46 2.407E-04 Sb-124 2.03 1E-04 Re-186 1.967E-04 Ag-illin 7.054E-05 1-131 7.003E-05 Mn-54 6.365E-05 Fe-59 4.742E-05 Se-75 2.963E-05 Cr-5i 2.027E-05 Lu-177m 1.084E-05 Total 1=1-3 1.037E-01 Total Other 1.783E-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, 2015 through December 31, 2015 Ordered by % Technical Specification (TS) Limit Isotope Isoop AverageOCi/ml)

Concentration Total(Ci)

Release T hi TS Liit utpirT Mutiplir % T Ar-41 1.64E-06 7.35E+02 350 48.8571 1-131 1.91E-12 8.51E-04 1 0.9529 H-3 1.88E-08 8.40E+00 350 0.0537 C-14 1.49E-11 6.67E-03 1 0.0050 Os-191 9.38E-15 4.19E-06 1 0.0005 Te-123m 3.18E-15 1.42E-06 1 0.0004 Hf-181 8.67E-16 3.87E-07 1 0.0001 Note: C-14 activity is calculated based on the ratio of argon to nitrogen in the air and the (n, p) reaction cross sections for the activation of N-14 to C-14.

Isotopes observed at < 0.0001% Technical Specification limit are not listed.

Stack Flow Rate = *~30,000 cein Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor, Amended Facility License No. R-103 Technical Specifications.

VII-2

SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2015 through December 31, 2015 Environmental samples are collected two times per year at eight (8) locations and analyzed for radioactivity. Soil and vegetation samples are also taken at each location. Water samples are taken at three (3) of the eight (8) locations. Subsurface soil 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 2015. All doses are approximately 18 mR/year or less, except monitor numbers 9 and 15. 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 confirmns that minimal environmental impact exists from the operation of the MURR facility.

The number of radiation and contamination surveys performed each month is provided in Table 4.

TABLE 1 SUMMVARY OF ENVIRONMENTAL SET 87 - Spring 2015 Detection Limits' Matrix Beta Gammla Tritium Water 1.16 pCi/L 5.09 pCi/L 186.03 pCi/L 5.49 pCi/mE of sample Soil 1.03 pCilg 3.55 pCi/g 0.63 pCi/g N/A Vegetation 1.46 pCi/g 8.90 pCi/g 1.52 pCi/g 5.66 pCi/mL of distillate Subsurface Soil 0.82 pCi/g 5.26 pCi/g 0.48 pCi/g N/A Activity Levels - Vegetation Alpha Beta Gammla H-3 Sample (pCi/2ramf) (pCi/gram) (pCi/gram)

< 5.66V 1V87 < 1.46 27.49 1.65

< 5.66 2V87 < 1.46 19.69 < 1.52

<5.66 3V87 < 1.46 14.97 < 1.52

< 5.66 4V87 < 1.46 38.36 1.84

< 5.66 5V87 < 1.46 32.61 1.97

< 5.66 6V87 < 1.46 26.95 < 1.52

< 5.66 7V87 < 1.46 23.15 2.75 10V87 < 1.46 30.94 3.36 < 5.66 VIII-1

TABLE 1 (Cont'd)

SUMMvARY OF ENVIRONMENTAL SET 87 - Spring 2015 Activity Levels - Soil Alpha Beta Gamma Sample (pCi/gram) (pCi/gram) (p~i/ 'm) 1S87 < 1.03 15.65 2.70 2S87 1.09 18.89 3.60 3S87 1.29 19.80 3.03 4S87 < 1.03 16.96 2.53 5S87 < 1.03 16.30 3.72 6S87 1.09 15.82 3.08 7S87 1.24 16.94 2.68 10S87 1.27 20.91 2.97 Activity Levels - Water Alpha Beta Gammi~a H-3 Sample (pCi/gram) (pCi/gram) (pCi/gram)

< 5.49l 4W87 < 1.16 5.87 < 186.03

<5.49 6W87 < 1.16 <5.09 < 186.03

< 5.49 10W87 < 1.16 6.85 < 186.03 Activity Levels - Subsurface Soil Alpha Beta Gammlla (pCi/gram) (pCi/gram) (pCi/gram)

Sample SWSS87 1.07 19.77 3.37 NESS 87 1.96 15.99 3.19 NSS87 1.57 15.67 3.68 WSS87 1.76 22.38 3.65 ESS87 2.47 18.45 3.46 SSS87 1.22 18.77 4.13 Note 1: Gamma and tritiumn 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

TABLE 2

SUMMARY

OF ENVIRONMENTAL SET 88 - Fall 2015 Detection Limits' Matrix Alpha Beta Gammnna Tritium Water 0.00 pCi/L 3.79 pCi/L 183.85 pCiiL 5.11 pCi/mL of sample Soil 0.00 pCi/g 2.51 pCi/g 0.61 pCi/g N/A Vegetation 2.55 pCi/g 10.42 pCi/g 1.80 pCi/g 4.92 pCi/mL of distillate Subsurface Soil 0.00 pCi/g 3.76 pCi/g 0.59 pCi/g N/A Activity Levels - Vegetation Alpha Beta Gamm~a H-3 Sample (pCi/gram) (pCi/gram) (pCi/,ram') (pCi/mi) 1V88 <2.55 26.53 < 1.80 < 4.92 2V88 < 2.55 < 10.42 < 1.80 < 4.92 3V88 <2.55 12.57 < 1.80 < 4.92 4V88 <2.55 12.98 < 1.80 < 4.92 5V88 <2.55 < 10.42 < 1.80 < 4.92 6V88 <2.55 < 10.42 < 1.80 < 4.92 7V88 <2.55 < 10.4*2 < 1.80 < 4.92 10V88 <2.55 15.98 2.10 < 4.92 Activity Levels - Soil Alpha Beta Gammlza (pCikram) (pCi/2ram) (pCi/gram)

Sample 1S88 0.78 20.98 3.08 2S88 1.43 14.82 1.88 3S88 2.05 18.75 1.84 4S88 1.27 18.11 3.53 5S88 1.42 21.68 3.58 6S88 1.25 15.50 2.26 7S88 1.58 15.65 2.67 10S88 1.42 25.60 3.10 VIII-3

TABLE 2 (Cont'd)

SUMMvARY OF ENVIRONMENTAL SET 88 - Fall 2015 Activity Levels - Water Alpha Beta Gamman H-3 (pCi/gram) (pCi/gram) (pCi/gram)

<5.11ml 4W88 0.79 14.18 < 183.85

<5.11 6W88 0.63 6.20 < 183.85

<5.11 low88 0.95 14.02 < 183.85 Activity Levels - Subsurface Soil Alpha Beta Gammna (pCi/gram) (oCi/gram) (pCi/gram)

SWSS88 2.82 22.48 3.71 NESS88 1.57 22.81 4.06 NSS88 1.05 22.07 3.85 WSS88 2.42 22.22 4.88 ESS88 1.05 20.58 4.78 SSS88 0.88 23.97 3.85 Note 1: Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.

HPGE spectral analysis was performed on any sample with a gamma activity greater than Minimum Detectable Activity (MDA).

VIII-4

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TABLE 4 NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS January 1, 2015 through December 31, 2015 Radiation Surface Contamination* Air Samples** RWP's January 109 109 62 15 February 70 70 58 17 March 96 96 63 24 april 83 83 66 25 May 118 118 54 19 June 125 125 62 10 July 107 107 63 21 August 84 84 '61 16 September 72 72 62 15 October 76 76 60 14 November 83 83 55 16 December 10._1 10__1 61 10 TOTALS 1124 1124 727 211

In addition, general building contamination surveys are conducted each normal work day.

- Air samples include exhaust stack Ar-41, containmentibuilding Ar-41, sump entries, and hot cell entries.

Miscellaneous Notes Nathan Hogue assumed the responsibilities of the Reactor Health Physics Manager in April 2015.

Chris Schnieders was promoted to the position of Health Physics Supervisor in December 2015.

During calendar year 2015, MURR shipped 629 cubic feet of low-level radioactive waste containing 657 mCi of activity.

VIII-6

SECTION IX Summary of Radiation Exposure to Facility Staff, Experimenters and Visitors January 1, 2015 through December 31, 2015 TOTAL PERSONNEL DOSE (MREM) BY DOSIMETRY GROUP AC BCS DO FOE HP IlUR NA NS NSP OPS PRO QA RiES RP HC/SH SRL TEE WC Total January o 9 o o 221 12 3 4 0 1502 125 42 0 36 574 219 1 42 2790 February o 5 o 3 154 9 10 94 0 1307 84 67 10 34 348 199 0 20 2344 March 3 0 o 0 228 24 2 70 0 1418 174 65 11 56 325 150 1 56 2583 April o 3 0 9 137 1 4 57 0 1547 146 46 5 3 392 163 1 123 2637 May 5 0 o 20 167 4 13 147 34 1547 92 95 33 8 557 186 2 38 2948 June 21 0 0 14 491 0 15 103 0 1515 138 72 44 11 490 176 3 25 3118 July 12 0 6 18 235 0 7 58 0 1336 137 72 0 6 343 173 2 42 2447 August 28 0 11 17 259 12 19 34 0 1840 125 166 0 0 533 230 19 79 3372 September 38 2 0 14 755 0 2 69 0 1439 97 99 6 2 1018 170 4 197 3912 October 2 19 2 0 112 7 4 6 0 1508 163 36 6 9 358 137 4 31 2404 November 15 8 0 25 89 0 2 60 0 1296 197 50 7 5 430 110 0 113 2407 December 5 3 0 25 82 0 8 3 0 1151 250 46 3 0 315 108 13 35 2047 Total for Year 129 49 19 145 2930 89 89 705 34 17406 1728 856 125 170 5683 2021 50 801 33009 Monthly Avg 11 4 2 12 244 6 7 59 3 1451 144 71 10 14 474 168 4 67 2751 Highest WB 117 32 9 38 1115 25 38 218 31 975 474 294 22 45 2098 1356 15 254 (annual)

High Extremity 303 331 NM 182 2269 157 1972 839 175 3060 5361 1843 551 984 4283 2996 948 1252 (annual)

AC-Analytical Chemistry IRR-Irradiations PRO-Isotope Processing SRL-Silicon BCS-Business & Central Services NA-Nuclear Analysis QA-Quality Assurance TEE-Trace Elemental Epidemiology DO-Director's Office NS-Neutron Scattering RES-Research WC-Work Control FOE-Shops & Support NSP-North Star Pharmaceutical RP-Radiopharmaceutical HP-Health Physics OPS-Operations HC/SH-I-ot Cell/Shipping VWB=Whole Body NMV=Not Monitored Analysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA.

Radiation workers who are not full time staff members have radiation exposures which are generally lower than full time radiation workers.

NOTES:

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

The North Star Pharmaceutical (NSP) Dosimetry Group was added in 2015.