ML17088A184

North Carolina State University - Annual Report for 2016

ML17088A184
Person / Time
Site:	North Carolina State University
Issue date:	03/28/2017
From:	Hawari A North Carolina State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17088A184 (26)

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College Of Engineering Campus Box 7909 NC STATE Department of Nuclear Engineering 2500 Stinson Drive Raleigh , NC 27695-7909 Nuclear Reactor Program UNIVERSITY www .ne.ncsu .edu/nrp P: 919.515.4598 28 March 2017 Document Control Desk US Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Re : Annual Reportfor2016 License No. R-120 Docket No. 50-297 In accordance with Technical Specification 6.7.4, the annual operating report for our facility is attached.

If you have any questions regarding this correspondence or require additional information, please contact Gerald Wicks at 919-5 15-4601 or wicks@ncsu.edu.

I declare under penalty of perjury that the forgoing is true and correct. Executed on 28 March 2017.

Ayman I. Hawari, Ph . D.,

Director, Nuclear Reactor Program North Carol ina State University

Enclosures:

Annual Operating Report for 2016 Attachment A: PULSTAR Reactor Environmental Radiation Surveillance Report

NORTH CAROLINA STATE UNIVERSITY DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT DOCKET NUMBER 50-297 For the Period: 01 January 2016 - 31 December 2016 The following annual report for 2016 is submitted in accordance with Section 6.7.4 of the North Carolina State University PULSTAR Reactor Technical Specifications:

6.7.4.a Brief Summary:

Reactor operations have been routine during this reporting period. During the period from May through November the reactor operated continuously, with brief shutdown periods, for 3500 hours0.0405 days <br />0.972 hours <br />0.00579 weeks <br />0.00133 months <br /> to accommodate the needs of a user.

i Operating experience including a summary of experiments performed.

The following is a brief summary of the types of experiments performed:

Teaching Laboratories, Short Courses, Research and Services:

• Core thermal power measurements

• Dynamic reactivity measurements

• Axial power and peaking factor measurements (flux mapping)

• Reactor power determination using photodiode arrays

• Neutron fluence and spectral measurements

• In-core detector certification

• Accelerated lifetime testing for nuclear detectors

• Neutron radiography

• Positron production facility

• Neutron Diffraction

• Isotope Production

• Crude oil

• Food samples

• Fish tissues

• Laboratory animal tissue

• Human hair, nails, and urine

• Polymers and plastics

• Sediment/soil/rocks

• Silicon crystals

• Textiles

• Water 1

Figure 1 - Reactor Utilization by Protocol Utilization Hours Percent Education 666 11%

Research 700 12%

Surveillance 141 2%

Service 857 15%

1 Special 3500 60%

2 TOTAL 5864 100%

1 NOTES: Non-routine 3500 hour0.0405 days <br />0.972 hours <br />0.00579 weeks <br />0.00133 months <br /> continuous test.

2 Utilization hours (5864 h) exceeded critical hours (4132.4 h) since there was typically more than one user of the reactor facility at a given time.

ii Changes in Performance Characteristics Related to Reactor Safety:

None iii Results of Surveillance, Tests, and Inspections:

The reactor surveillance program has revealed no significant or unexpected trends in reactor systems performance during this reporting period. The Reactor Safety and Audit Committee (RSAC) performed its annual audit for the facility and determined that all phases of operation and supporting documents were in compliance.

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6.7.4.b Energy Output and Critical Hours:

Total Energy Output in 2016: 166.7 Megawattdays Critical hours in 2016: 4132.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Cumulative Total Energy Output Since Initial Criticality: 1799.1 Megawattdays 6.7.4.c Number of Emergency and Unscheduled Shutdowns:

Emergency Shutdowns - NONE Unscheduled Shutdowns - Six 5-JUN-2016 Low Flow SCRAM. On June 5, 2016, at approximately 19:54 a Low Flow SCRAM was received in the control room. The RO followed procedure and confirmed that a SCRAM occurred and verified that the reactor had shutdown and was in a safe condition. The RO then notified the DSRO as required.

Upon inspection of the flow trend on the data recorder it was determined that flow indication experienced a downward step change just prior to the SCRAM actuation. It is concluded that air, trapped in the delay tanks, escaped down the hot leg piping and entered the annubar, causing a low flow indication. This was confirmed when the annubar was vented and flow indication returned to normal. The delay tanks and the piping after the heat exchanger will be vented during the next maintenance period to determine if air is actually accumulating in the primary system.

The reactor was authorized for restart on June 5, 2016 at 22:15.

27-AUG-2016 Low Flow SCRAM. On August 27, 2016, at approximately 03:28 a Low Flow SCRAM was received in the control room. The RO followed procedure and confirmed that a SCRAM occurred and verified that the reactor had shutdown and was in a safe condition. The RO then notified the DSRO as required.

This is a reoccurrence of the SCRAM that occurred on June 5, 2016. To prevent this from occurring in the future, new annubar mounting hardware to relocate the annubar is awaiting installation. The installation of permanent vents for the delay tanks are also being evaluated.

The reactor was authorized for restart on August 27, 2016 at 04:39.

17-SEPT-2016 Shutdown due to Low Natural Gas Pressure Alarm. On September 17, 2016, at approximately 16:44 a Low Natural Gas Pressure was received in the control room. The RO followed procedure and proceeded to shutdown the reactor. Once shutdown, the RO secured the reactor. The RO then notified the DSRO as required.

On its own accord, natural gas pressure restored to normal levels, and the console annunciator cleared.

The reactor was authorized for restart on September 17, 2016 at 19:00.

17-SEPT-2016 Shutdown due to Unannounced Fire Drill. On September 29, 2016, at approximately 10:34 a fire alarm was received in the control room. The RO followed procedure and proceeded to shutdown the reactor. Once shutdown, the RO secured the reactor. The RO then notified the DSRO as required and verified that the Reactor Building was evacuated. The RO then exited the control room and proceeded to the designated rendezvous point.

The fire alarm was caused by an unannounced fire drill.

The reactor was authorized for restart on September 29, 2016 at 11:35.

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8-OCT-2016 SCRAM due to Loss of Commercial Power. On October 8, 2016, at approximately 16:31 a power flicker caused the reactor to SCRAM. The RO followed procedure and confirmed that a SCRAM occurred and verified that the reactor had shutdown and was in a safe condition.

The RO then notified the DSRO who was present in the control room at the time.

The power flicker was due to the storm and moderate winds from the remnants of Hurricane Matthew passing through the area which caused numerous power outages throughout the area.

The reactor was authorized for restart on October 8, 2016 at 17:18.

7-DEC-2016 Shutdown due to Low Natural Gas Pressure Alarm. On December 7, 2016, at approximately 14:38 a Low Natural Gas Pressure was received in the control room. The RO followed procedure and proceeded to shutdown the reactor. Once shutdown, the RO secured the reactor. The RO then notified the DSRO as required.

On its own accord, natural gas pressure restored to normal levels, and the console annunciator cleared.

The reactor was authorized for restart on December 7, 2016 at 15:40.

6.7.4.d Corrective and Preventative Maintenance:

Preventative maintenance, tests and calibrations are scheduled, performed and tracked utilizing the PULSTAR Surveillance File System. Each major component of the Reactor Safety System defined in Section 3.3, and all surveillance required by Section 4 of the Technical Specifications are monitored by this file system to ensure that maintenance and calibrations are performed in a timely manner. All historical data relating to those components, in addition to many other sub-systems, are maintained in these files.

819 PS-1-14 Confinement System Isoprobe - The actuator for the confinement system sampling isoprobe stuck in the open position. The actuator was removed and upon inspection it was found that the gear box was binding. The gear box was cleaned and new grease was added. The actuator was reinstalled and returned to service.

820 PS-7 Pneumatic Transfer System Blower - The blower for the Pneumatic Transfer System (PN) was replaced with a new unit. This was done as a proactive replacement in preparation for conversion to a nitrogen based system.

821 PS-1-14 R63 Ventilation Fan - The paddle switch that provides flow status for the control console annunciator was found to be stuck in the closed position. The switch was replaced and tested satisfactory.

822 PS-3-02 Secondary Filter System - The seal for the Secondary Filter System was found to be leaking. The pump was removed and the seal was replaced. The front shaft bearing was also found to be excessively noisy and was replaced. The system was returned to service.

823 NOT USED 824 PS-3-02-5A - Secondary Cooling Tower - The cooling tower fan motor stopped operating and upon inspection the wire for one phase in the junction box on the motor had come loose. The motor was rewired and returned to service.

825 PS-2-01-1A - Reactor Air Compressor - The reactor air compressor stopped operating due to a blown fuse. Upon inspection, it was determined that the fuse blew due to a failed high pressure cutout switch. The switch was replaced and the compressor was returned to service.

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826 PS-1 Pool RTD - The pool RTD was removed from the pool for a scheduled calibration. Upon inspection the tubing was found to be cracked and the wiring was damaged from contact with the water. The RTD was temporarily replaced with an old spare RTD while an order was placed for a new RTD. The temporary RTD was calibrated and placed into service.

6.7.4.e Changes in Facility, Procedures, Tests, and Experiments:

Facility Changes Design changes to the reactor facility are reviewed to determine whether or not a 10 CFR Part 50.59 evaluation was required. Evaluations were performed all design changes.

800 Modification of Fuel Assembly for Secondary Identification Method - The original fuel boxes had been modified to provide a secondary means of identification of the serial number without having to remove the fuel assembly from the reactor grid plate. This design change allows for the same modification to the new fuel boxes for the 6% enriched fuel assemblies.

802 Temperature Measuring Channel Modification - This modification upgraded the temperature measuring channel recorder to a new unit with more channel inputs and for the installation of stand-alone analog alarm modules to perform alarm setpoint and relay functions.

805 Removal of Secondary Check Valve S6 - This design change removes the backflow preventing check valve S6 and installs an anti-rotational device in the impellor of the secondary pump as per manufacturer recommendations. The purpose is to eliminate the potential for water hammer that is sometimes generated by the closing of the check valve while at the same time ensuring that any backflow in the system will not damage the secondary pump.

807 Modification of Pneumatic Transfer System, Phase 1 - This is Phase 1 of the modification that will convert the pneumatic transfer system from air to nitrogen to reduce the amount of argon-41 that is produced during reactor operation. Phase 1 consisted of the replacement of the solenoid cabinet and tubing for the pneumatic sample shuttle.

809 Modification of Pneumatic Transfer System, Phase 2 - This modification replaces the obsolete analog components with new readily available analog equivalents.

Document Changes Procedure changes were reviewed to determine whether or not a 10 CFR Part 50.59 evaluation was required.

Based on the screening reviews none required a full 10 CFR 50.59 evaluation.

In anticipation of the upcoming license renewal in 2017, a procedure review process commenced in 2015. All procedures are being evaluated, revised, reaffirmed, or retired. This process is scheduled to be completed prior to the issuance of the license renewal.

803 PS-4-07 Verification of keff of the In-pool Fuel Storage Racks for the Storage of 6% Enriched Fuel Assemblies - This procedure will be used to transfer the 6% enriched PULSTAR fuel assemblies from dry storage to the in-pool storage racks and verify that the keff is below the limits specified in Technical Specification 5.3. This procedure is based on the original Startup Procedure 2.12 -

Installation of Neutron Source and Fuel in Pool.

804 PS-4-07 Acceptance Procedure for the PULSTAR Fuel Boxes for the Use of 6% Enriched Fuel - This procedure will be used when performing the acceptance inspections for the new PULSTAR fuel boxes for the use of 6% enriched fuel.

806 PS-1-10:S1 - Temperature Measuring Channel Calibration, Revision 8 - This procedure revision provides the steps necessary to calibrate and adjust the Temperature Measuring Channel following the modifications that were completed in Design Change 802.

810 Emergency Procedure 2 - Offsite Notification, Revision 20 - The notification form and instructions 5

were revised by the State of North Carolina. This revision incorporates these changes.

813 PS-6-13-1:BW1/M1/A1 - Primary and Secondary Water Chemistry, Revision 3 - Revised procedure to make purification system decontamination factor assessment optional. Performing a decontamination factor assessment on the demineralizer when the reactor is operating continuously becomes problematic and poses an unnecessary and significant radiation hazard to personnel. Other minor changes were made regarding sampling equipment and updating valve numbers.

814 Emergency Procedure 2 - Offsite Notification, Revision 21 - Update for the North Carolina Emergency Authentication Code list.

815 Health Physics Procedure 9 - Respirator Use and Bioassay - Donning of respirator is maintained in annual training program. Quarterly donning of respirator is optional.

Test and Experiments Procedure changes were reviewed to determine whether or not a 10 CFR Part 50.59 evaluation was required. Based on the screening reviews Control Numbers 799 and 801 required an evaluation.

799 NRP-OP-411 - Deuterium System Procedures, Revision 2 - This change to the procedure added (1) instruction on how to flush the palladium filter with deuterium, (2) revised instructions to allow for sections of the gas handling system to be exhausted as necessary, (3) and clarified a procedural step to explicitly allow for the storage of deuterium in the ballast tank, which was one its original design functions.

801 NRP-XP-104 - Position Oxygen Cleaning System, Original Issue - The purpose of this experimental procedure is to provide the means to safety perform the in-situ cleaning of the position moderator with oxygen. The cleaning is expected to increase the intensity of the positron beam. Before being implemented, the system was inspected and associated procedure were reviewed by the NCSU Environmental Health and Safety Division and approved by both safety committees as required for experiments of a new type.

808 NRP-OP-411 - Deuterium System Procedures, Revision 2.1 - This revision added two steps to Section 6 to direct the experimenter to use Section 12 when evacuating the liquid nitrogen traps. These should have been included in the previous revision. This is classified as a minor change.

811 NRP-XP-105 - Measurement of Short Reactor Periods, Original Issue - To provided instructions on how to increase reactor power on periods shorter than 10 seconds. Periods shorter than 10 second are desirable for specific nuclear engineering laboratory exercises.

812 NRP-XP-104 - Position Oxygen Cleaning System, Revision 1 - A few steps in the original issue of the procedure had to be performed within a given timeframe otherwise the process would not function most efficiently. Reordering two steps in the procedure removed any critical timing aspects for the process.

Other Changes There were no other changes in 2016.

6.7.4.f Radioactive Effluent:

Liquid Waste (summarized by quarters)

i. Radioactivity Released During the Reporting Period:

Releases to the sanitary sewer are given below:

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Period (1) (2) (3) (4)1 (5)

Total Number of Total Diluent Tritium 2016 Volume Batches µCi Liters µCi Liters 01 JAN - 31 MAR 1 164 3.37E3 2.25E5 141 01 APR - 30 JUN 4 763 1.35E4 6.88E5 693 01 JUL - 30 SEP 5 591 1.68E4 6.89E4 583 01 OCT - 31 DEC 2 381 6.74E3 2.09E4 378 2016 1795 µCi of tritium was released during this year.

2016 1899 µCi of total activity was released during this year.

1 Based on gross beta activity only. Tritium did not require further dilution.

ii. Identification of Fission and Activation Products:

The gross beta-gamma activity of the batches in (i) above were less than 2x10-5 Ci/ml. Isotopic analyses of these batches indicated low levels of typical corrosion and activation products. No fission products were detected.

iii. Disposition of Liquid Effluent not Releasable to Sanitary Sewer System:

All liquid effluent met the requirements of 10 CFR Part 20 for release to the sanitary sewer.

Gaseous Waste (summarized monthly)

i. Radioactivity Discharged During the Reporting Period (in Curies) for:

(1) Gases:

Total Time Year Month Curies Hours JANUARY 744 0.481 FEBRUARY 696 0.168 MARCH 744 0.374 APRIL 720 0.766 MAY 744 1.586 JUNE 720 1.831 2016 JULY 744 1.656 AUGUST 744 1.622 SEPTEMBER 720 1.478 OCTOBER 744 3.259 NOVEMBER 720 0.400 DECEMBER 744 0.232 TOTAL 8784 13.852 7

(2) Particulates with a half-life of greater than eight days:

Particulate filters from the Stack Particulate Monitoring Channel were analyzed upon removal. There was no particulate activity with a half-life greater than 8 days indicated on any filter during this reporting period.

ii. Gases and Particulates Discharged During the Reporting Period:

(1) Gases:

Total activity of argon-41 released was 13.852 curies in 2016.

The yearly average concentration of argon-41 released from the PULSTAR reactor facility exhaust stack in 2016 was 6.7x10-8 Ci/ml. Dose calculations for the year were performed using methods given in the Final Safety Analysis Report. Dose calculations gave results less than the 10 CFR Part 20 constraint level of 10 mrem. These results are consistent with environmental monitoring data given in Attachment A.

(2) Particulates:

Refer to gaseous waste i.(2) above. Low levels of naturally occurring radioactivity were detected.

Solid Waste from Reactor

i. Total Volume of Solid Waste Packaged Total volume of solid waste was 29 ft3.

ii. Total Activity Involved Total activity for solid waste was 0.3 mCi.

iii. Dates of shipments and disposal Transfer of solid radioactive waste to the university broad scope radioactive materials license was made in May 2016 and Sep 2016. The University Environmental Health and Safety Center arranges disposal of hazardous wastes.

6.7.4.g Personnel Radiation Exposure Report:

Thirty one individuals were monitored for external radiation dose during the reporting period. Internal dose monitoring was not required for any individual. Collective deep dose-equivalent for 1 Jan 2016 to 31 Dec 2016 was 2.329 person-rem. Individual deep dose-equivalent ranged from 0.001 rem to 0.396 rem with a median of 0.069 rem and average of 0.075 rem.

6.7.4.h Summary of Radiation and Contamination Surveys Within the Facility:

Radiation and contamination surveys performed within the facility indicated that:

• Radiation in the majority of areas was 5 mrem/h or less.

• Radiation in the remaining areas was higher due to reactor operations.

• Contamination in most areas was not detectable. When contamination was detected, the area or item was confined or decontaminated.

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6.7.4.i Description of Environmental Surveys Outside of the Facility:

Refer to Attachment A for results of environmental sampling and analysis.

Radiation surveys performed in unrestricted areas near the reactor facility indicated that:

• Radiation was at background levels for most areas (average background is approximately 10

µrem/h).

• Contamination was not detectable.

• Net radiation readings ranged from 0 to 30 µrem/h while the reactor was operating at power.

However, radiation was at background levels in all routinely occupied spaces.

• Water samples from Rocky Branch Creek and an on-site ground water monitoring well were analyzed in 2016 for tritium, gross beta activity, gross alpha activity, and gamma radiation. All sample results were consistent with background radioactivity. Environmental monitoring of Rocky Branch Creek and groundwater is routinely performed in accordance with facility procedures.

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ATTACHMENT A PULSTAR REACTOR ENVIRONMENTAL RADIATION SURVEILLANCE REPORT FOR CALENDAR YEAR 2016

[JANUARY 1, 2016 - DECEMBER 31, 2016]

NORTH CAROLINA STATE UNIVERSITY ENVIRONMENTAL HEALTH AND SAFETY CENTER RADIATION SAFETY DIVISION by Ralton J. Harris Environmental Health Physicist 10

TABLE OF CONTENTS PAGE NO.

1. INTRODUCTION 12 Table 1 Environmental Monitoring Programs for the PULSTAR Reactor 13

2. AIR MONITORING 14 Table 2.1 Location of Air Monitoring Stations 14 Table 2.2 Airborne Gross Beta Activities 14 Table 2.3 Airborne Gamma Activities (LLD Values) 15 Table 2.4 Regulatory Limits, Alert Levels and Background Levels for Airborne Radioactivity 15

3. MILK Table 3.1 I-131 in Cows Milk 16

4. SURFACE WATER Table 4.1 Gross Alpha and Beta Activity in Surface Water 17 Table 4.2 LLD Values for Gamma Emitters in Surface Water 18

5. VEGETATION Table 5.1 Gross Beta Activity in Campus Vegetation 19 Table 5.2 LLD Values for Gamma Emitters in Vegetation 19

6. OPTICALLY STIMULTATED DOSIMETERS 20 Table 6.1 Environmental Dosimeter Doses 21

7. QUALITY CONTROL INTERCOMPARISON PROGRAM 22 Tables 7.1a - 7.1e 22-25

8. CONCLUSIONS 26 11

1. INTRODUCTION The Environmental Radiation Surveillance Program exists to provide routine measurements of the university environment surrounding the PULSTAR Reactor. The specific objectives of this program include:

• Providing information that assesses the adequacy of the protection of the university community and the public-at-large;

• Meeting requirements of regulatory agencies;

• Verifying radionuclide containment in the reactor facility;

• Meeting legal liability obligations;

• Providing public assurance and acceptance.

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TABLE 1 ENVIRONMENTAL MONITORING PROGRAMS FOR THE PULSTAR REACTOR AT NORTH CAROLINA STATE UNIVERSITY SAMPLE ACTIVITY CONDUCTED PREVIOUS CURRENT BASIS FOR MEASURED BY FREQUENCY FREQUENCY MEASUREMENT STACK GASES GROSS N.E. CONTINUOUS CONTINUOUS 10 CFR 20 GAMMA T.S. 6.7.4 STACK GROSS BETA N.E. MONTHLY MONTHLY 10 CFR 20 PARTICLES GAMMA N.E. T.S. 6.7.4 EMITTERS WATER FROM GROSS BETA N.E. PRIOR TO PRIOR TO 10 CFR 20 REACTOR GROSS N.E. DISCHARGE DISCHARGE T.S. 6.7.4 FACILITY GAMMA (~ MONTHLY) (~ MONTHLY)

N.E. CITY OF RALEIGH TRITIUM ORDINANCE AIR PARTICLES GROSS BETA RSD WEEKLY QUARTERLY 10 CFR 20 AT 4 CAMPUS GAMMA RSD WEEKLY QUARTERLY 10 CFR 20 STATIONS1 EMITTERS AIR DOSE AT 7 TLD RSD QUARTERLY QUARTERLY 10 CFR 20 CAMPUS DOSIMETER STATIONS2 SURFACE GROSS BETA RSD QUARTERLY QUARTERLY NCSU WATER ROCKY GAMMA RSD QUARTERLY QUARTERLY NCSU BRANCH EMITTERS CREEK TRITIUM N.E. QUARTERLY 10 CFR 20 VEGETATION GROSS BETA RSD SEMI- EVERY OTHER NCSU NCSU GAMMA RSD ANNUALLY YEAR NCSU CAMPUS MILK I-131 RSD MONTHLY EVERY OTHER NCSU LOCAL DAIRY YEAR ABBREVIATIONS USED IN TABLE:

N.E. = NUCLEAR ENGINEERING/REACTOR FACILITY; RSD/EHSC = RADIATION SAFETY DIVISION.

1 THESE 4 STATIONS INCLUDE:

WITHERS, DANIELS, POLK, AND ENVIRONMENTAL HEALTH & SAFETY CENTER.

2 THESE 7 STATIONS INCLUDE: PULSTAR REACTOR, A CONTROL STATION (EH&S) AND THE 4 AIR SAMPLING STATIONS, AND NORTH HALL.

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2. AIR MONITORING (TABLES 2.1, 2.2, 2.3 and 2.4)

Air monitoring is performed continually for one week during each of four (4) quarters during the year. The data in Table 2.2 are for gross beta activity levels measured during the year. The highest gross beta activity observed was 36.2 fCi/cubic meter at the Environmental Health & Safety Center station during the week of 11/15/2016 to 11/22/2016. The annual campus average value was 16.3 fCi/cubic meter.

Table 2.3 lists LLD values for several gamma emitters which would be indicative of fission product activity.

No gamma activity due to any of these radionuclides was detected.

Table 2.4 lists regulatory limits, alert levels, and average background levels for airborne radioactivity.

TABLE 2.1 LOCATION OF AIR MONITORING STATIONS SITE DIRECTION1 DISTANCE2 ELEVATION3 METERS METERS DANIELS SOUTHEAST 90 -8 WITHERS NORTHEAST 82 -6 EH & S CENTER WEST 1230 -3 NORTH HALL NORTHEAST 402 -4 POLK HALL WEST 100 -7 1

DIRECTION FROM REACTOR STACK 2

DISTANCE FROM REACTOR STACK 3

ELEVATION RELATIVE TO THE TOP OF THE REACTOR STACK TABLE 2.2 AIRBORNE GROSS BETA ACTIVITY (fCi*m-3 meter +/- 2) 2016 POLK DANIELS WITHERS EH&S 03/09-03/16 19.1+/-1.3 11.7+/-1.1 14.3+/-1.2 13.5+/-1.2 06/16-06/23 11.5+/-1.1 11.7+/-1.1 11.4+/-1.1 11.8+/-0.9 09/29-09/26 6.5+/-0.9 11.5+/-1.0 12.0+/-1.0 10.6+/-1.1 11/15-11/22 12.0+/-1.1 31.7+/-1.5 35.3+/-1.5 36.2+/-1.5 14

TABLE 2.3 AIRBORNE GAMMA ACTIVITY LLD VALUES (fCi*m-3)

PERIOD CO-57 CO-60 NB-95 ZR-95 RU-103 RU-106 CS-137 CE-141 CE-144 2016 03/09-03/16 0.21 0.35 0.29 0.47 0.27 2.37 0.26 0.38 1.22 06/16-06/23 0.20 0.37 0.28 0.48 0.28 2.48 0.29 0.34 1.28 09/29-09/26 0.18 0.35 0.31 0.54 0.33 2.51 0.29 0.43 1.40 11/15-11/22 0.17 0.37 0.37 0.50 0.32 2.41 0.29 0.39 1.41 TABLE 2.4 REGULATORY LIMITS, ALERT LEVELS, AND BACKGROUND LEVELS FOR AIRBORNE RADIOACTIVITY (fCi*m-3)

AVERAGE N.C.

NUCLIDE REGULATORY LIMIT INVESTIGATION LEVEL BACKGROUND LEVEL GROSS BETA 1000 500 20 CS-137 2 X 105 100 2 5

CE-134 2 X 10 100 0 NB-95 2 X 106 100 0 ZR-95 400 100 0 THIS DATA REPRESENTS AN AVERAGE VALUE MEASURED IN NORTH CAROLINA AT VARIOUS LOCATIONS. EXCERPTED FROM 2009 ENVIRONMENTAL SURVEILLANCE REPORT PRODUCED BY THE NC DEPARTMENT OF ENVIRONMENT &

NATURAL RESOURCES DIVISION OF ENVIRONMENTAL HEALTH RADIATION PROTECTION SECTION.

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3. MILK (TABLE 3.1)

Milk samples are collected every other year from the Campus Creamery and the Lake Wheeler Road Dairy as processed milk and raw milk and analyzed for I-131. No samples were collected for 2016.

TABLE 3.1 I-131 IN COWS MILK (pCi*Liter 1 +/- 2) LLD ~ 2 pCi*Liter 1 pCi*Liter 1 DATE CAMPUS CREAMERY LAKE WHEELER 2016 NO DATA NO DATA 16

4. SURFACE WATER (TABLES 4.1 AND 4.2)

Table 4.1 gives the gross alpha and beta activities for water from Rocky Branch at points:

1. where it enters campus (ON).

2. behind Carmichael Gymnasium (GYM).

3. where it exits campus(OFF).

The LLD value for gross alpha and beta activities is ~ 0.4 pCi Liter-1. For gross alpha activity the Investigation Level is 5 pCi Liter-1 and the Regulatory Limit is 15 pCi Liter-1. For gross beta activity the Investigation Level is 12.5 pCi Liter-1 and the Regulatory Limit is 50 pCi Liter-1.

Gamma analysis of all samples was also performed. All the results are consistent with the presence of naturally-occurring radionuclides and none of the gamma emitters listed in Table 4.2 were detected.

TABLE 4.1 GROSS ALPHA AND BETA ACTIVITY IN SURFACE WATER (pCi*Liter 1 +/- 2)

LLD ~ 0.4 pCi*Liter-1 LLD ~ 0.4 pCi*Liter 1 pCi Liter 1 DATE LOCATION GROSS ALPHA GROSS BETA FIRST QUARTER 2016 ON 0.1+/-0.1 3.1+/-0.6 OFF 0.03+/-0.2 3.7+/-0.6 GYM 0.1+/-0.2 0.1+/-0.5 SECOND QUARTER 2016 ON 0.2+/-0.2 4.2+/-0.7 OFF 0.2+/-0.2 4.0+/-0.7 GYM 0.1+/-0.4 3.6+/-0.7 THIRD QUARTER 2016 ON 0.03+/-0.2 3.8+0.7 OFF 0.03+/-0.2 4.0+0.7 GYM 0.1+/-0.2 3.4+0.7 1

FOURTH QUARTER 2016 ON 0.4+/-0.3 4.1+0.7 OFF -0.03+/-0.2 2.2+0.6 GYM -0.03+/-0.2 2.3+0.6 17

TABLE 4.2 LLD VALUES FOR GAMMA EMITTERS IN SURFACE WATER NUCLIDE LLD (pCi*Liter-1)

Co-60 0.4 Zn-65 0.7 Cs-137 0.3 Cs-134 0.4 Sr-85 0.4 Ru-103 0.3 Ru-106 3.0 Nb-95 0.4 Zr-95 0.5 18

5. VEGETATION (TABLE 5.1 & 5.2)

Tables 5.1 gives gross beta activities for grass samples collected on the NCSU Campus. Table 5.2 lists LLD values for several gamma emitters. None of these gamma emitters were detected. The vegetation sampling is performed every other year. No samples were collected for 2016.

TABLE 5.1 GROSS BETA ACTIVITY IN CAMPUS VEGETATION *LLD 0.5 pCi*g-1 DATE SAMPLE LOCATION (pCi*g-1 +/- 2) 2016 NORTH CAMPUS NO DATA 2016 SOUTH CAMPUS NO DATA 2016 EAST CAMPUS NO DATA 2016 WEST CAMPUS NO DATA TABLE 5.2 LLD VALUES FOR GAMMA EMITTERS IN VEGETATION NUCLIDE LLD (pCi*gram-1)

Co-60 0.01 Zn-65 0.02 Cs-137 0.01 Cs-134 0.01 Sr-85 0.01 Ru-103 0.01 Nb-95 0.01 Zr-95 0.02 19

6. OPTICALLY STIMULATED DOSIMETERS (TABLE 6.1)

Dosimeter analysis is contracted to Landauer, Inc. for determination of ambient radiation exposures.

Exposures are integrated over a three-month period at each of the five air monitor stations listed in Table 2.1 and at the PULSTAR Reactor facility. A control dosimeter is located in the Environmental Health & Safety Center. Table 6.1 gives the dose equivalent data for these six (6) locations.

The PULSTAR dosimeter is located inside the reactor building at the reactor exhaust duct prior to the connection to the exhaust stack. Atmospheric dispersion reduces the dose equivalent to public areas. The observed readings for other dosimeters are within the expected range for natural background radiation levels.

TABLE 6.1 ENVIRONMENTAL DOSIMETER DOSES - millirem per quarter DATE CONTROL POLK WITHERS DANIELS EH&S NORTH PULSTAR 2016 01/01 - 03/31 38 M,M M,M 6,8 M M 16 04/01 - 06/30 33 M,M M,M 6,7 2 2 33 07/01 - 09/30 39 M,M M,M M,M M 1 24 10/01 - 12/31 38 M,M M,M M,M M M 25 All values are reported as Deep Dose Equivalent (DDE).

Control is the control dose used by the vendor company for evaluation of the dosimeter.

M is the designation used by the vendor company to report dose equivalents below the minimum measurable quantity which is 1 millirem for gamma radiation and 10 millirem for beta radiation.

Dual dose entries indicate two (2) independent dosimeters assigned at the indicated station.

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7. QUALITY CONTROL INTERCOMPARISON PROGRAM The Environmental Radiation Surveillance Laboratory (ERSL) in the Radiation Safety Division has analyzed samples provided by the U.S. DOE Mixed-Analyte Performance Evaluation Program (MAPEP Test Session 31)

Radiological and Environmental Sciences Laboratory (RESL) during this reporting period. The objective of this program is to provide laboratories performing environmental radiation measurements with unknowns to test their analytical techniques.

The MAPEP value listed in the Tables 7.1 (a-e) to which the ERSL results are compared is the mean of replicate determinations for each nuclide. The MAPEP uncertainty is the standard error of the mean.

For each reported radiological analyte, the laboratory result and the reference value may be used to calculate a relative bias:

(100)(Laboratory Re sult RESL Re ferenceValue)

%Bias =

RESL Re ferenceValue The relative bias will place the laboratory result in one of three categories:

Acceptable Bias 20%

Acceptable with Warning 20% < Bias 30%

Not Acceptable Bias > 30%

TABLE 7.1a GROSS ALPHA & BETA ACTIVITY AIR FILTER - INTERCOMPARISON STUDY 01 February 2016 NCSU - ENVIRONMENTAL LABORATORY RESULTS RADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE GROSS ALPHA 1.13 0.06 1.20 0.36 - 2.04 GROSS BETA 0.83 0.03 0.79 0.40 - 1.19 THE SAMPLE CONSISTS OF ONE 50 MM DIAMETER SIMULATED FILTER SPIKED WITH A MATRIX-FREE SOLUTION CONTAINING A SINGLE ALPHA AND A SINGLE BETA EMITTING NUCLIDE. THE REPORTED VALUES AND THE KNOWN VALUES ARE GIVEN IN BQ/FILTER.

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TABLE 7.1b MULTINUCLIDE AIR FILTER - INTERCOMPARISON STUDY 01 February 2016 NCSU - ENVIRONMENTAL LABORATORY RESULTS 1 1 RADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE Co60 4.02 0.06 4.02 2.81 - 5.23 Cs137 2.20 0.06 2.30 1.61 - 2.99 Cs134 0.03 0.05 ------ FALSE + TEST Co57 2.86 0.06 2.94 2.06 - 3.82 Mn54 4.13 0.06 4.53 3.17 - 5.89 Zn65 3.17 0.05 3.57 2.50 - 4.64 THE SAMPLE CONSISTS OF ONE 50 MM DIAMETER GLASS FIBER FILTER WHICH HAS BEEN SPIKED WITH A SOLUTION AND DRIED. THE REPORTED VALUES AND THE KNOWN VALUES ARE GIVEN IN BQ/FILTER.

NOTE: THE ENTRY ------ INDICATES NO ANALYTE WAS PRESENT FOR PURPOSES OF CONDUCTING A FALSE POSITIVE

(+) TEST.

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TABLE 7.1c MULTINUCLIDE WATER SAMPLE - INTERCOMPARISON STUDY 01 February 2016 NCSU - ENVIRONMENTAL LABORATORY RESULTS RADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE Co60 11.32 0.88 11.8 8.3 - 15.3 Cs137 21.45 0.83 21.2 14.8 - 27.6 Cs134 16.02 0.82 16.1 11.3 - 20.9 Co57 2.52 1.27 ------ False + Test Mn54 10.67 0.63 11.1 7.8 - 14.4 Zn65 15.05 0.99 13.6 9.5 - 17.7 THE SAMPLE CONSISTS OF A SPIKED ALIQUOT OF ACIDIFIED WATER (~5 % HNO3). THE REPORTED VALUES AND THE KNOWN VALUES ARE GIVEN IN BQ/LITER.

NOTE: THE ENTRY ------ INDICATES NO ANALYTE WAS PRESENT FOR PURPOSES OF CONDUCTING A FALSE POSITIVE

(+) TEST.

TABLE 7.1d GROSS ALPHA AND BETA WATER SAMPLE - INTERCOMPARISON STUDY 01 February 2016 NCSU - ENVIRONMENTAL LABORATORY RESULTS RADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE Gross Alpha 0.22 0.08 0.673 0.202 - 1.144 Gross Beta 2.04 0.24 2.15 1.76 - 5.28 THE SAMPLE CONSISTS OF A 5% HNO3 MATRIX FREE SOLUTION. THE REPORTED VALUES AND THE KNOWN VALUES ARE GIVEN IN BQ/LITER.

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TABLE 7.1e MULTINUCLIDE VEGETATION SAMPLE - INTERCOMPARISON STUDY 01 February 2016 NCSU - ENVIRONMENTAL LABORATORY RESULTS RADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE Co60 0.22 0.25 ------ False + Test Cs137 4.13 0.24 5.62 3.93 - 7.31 Cs134 8.00 0.19 10.62 7.43 - 13.81 Co57 8.67 0.20 11.8 8.3 - 15.3 Mn54 0.20 0.25 ------ False + Test Zn65 8.44 0.18 9.6 6.7 - 12.5 THE SAMPLE CONSISTS OF A SPIKED SAMPLE OF VEGETATION. THE REPORTED VALUES AND THE KNOWN VALUES ARE GIVEN IN BQ/SAMPLE.

NOTE: THE ENTRY ------ INDICATES NO ANALYTE WAS PRESENT FOR PURPOSES OF CONDUCTING A FALSE POSITIVE

(+) TEST.

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8. CONCLUSIONS The data obtained during this period do not show any fission or activation product activities. The observed environmental radioactivity is due primarily to radon progeny, primordial radionuclides (e.g. K-40) and those radionuclides that originate in the upper atmosphere as the result of cosmic ray interactions. These facts justify the conclusion that the PULSTAR Reactor facility continues to operate safely and does not release fission or activation products into the environment.

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