ML18092A036

N.C. State University - Annual Report for 2017

ML18092A036
Person / Time
Site:	North Carolina State University
Issue date:	03/29/2018
From:	Hawari A North Carolina State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML18092A036 (28)

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Nuclear Reactor Program Ca mpus Box 7909 NC STATE Department of Nuclear Eng ineering 2500 Stinson Drive Raleigh , NC 27695-7909 UNIVERSITY www .ne.ncsu .edu/nrp 919.515.7294 (voice) 919.513.1276 (fax) 29 March 2018 Document Control Desk US Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Re : Annual Report for 2017 License No . R-12 0 Docket No . 50-297 In accordance with Technical Specification 6.7.4, the annual operating report fo r our facility is attached .

If you have any questions regarding this correspondence or require additional information, please contact Gerald Wicks at 919-515-4601 or wicks@ncsu .edu.

I declare under penalty of perjury that the forgoing is true and correct. Executed on 29 March 2018.

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Director, Nuclear Reactor Program North Carolina State University

Enclosures:

Annual Operating Report for 2017 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 2017 - 31 December 2017 The following annual report for 2017 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 3293 hours0.0381 days <br />0.915 hours <br />0.00544 weeks <br />0.00125 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 651 12%

Research 482 9%

Surveillance 131 2%

Service 990 18%

1 Special 3293 59%

2 TOTAL 5547 100%

1 NOTES: Non-routine 3293 hour0.0381 days <br />0.915 hours <br />0.00544 weeks <br />0.00125 months <br /> continuous test.

2 Utilization hours (5547 h) exceeded critical hours (3284.8 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 2017: 127.7 Megawattdays Critical hours in 2017: 3284.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Cumulative Total Energy Output Since Initial Criticality: 1926.9 Megawattdays 6.7.4.c Number of Emergency and Unscheduled Shutdowns:

Emergency Shutdowns - NONE Unscheduled Shutdowns - Twelve 13-FEB-2017 Linear Level Over-Power SCRAM. On February 13, 2017, at approximately 18:07 a Linear Level Over-Power 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.

The SCRAM occurred during the increase in reactor power from 28 watts to 50 kW. The SCRAM was due to the Linear Level Monitor not auto-ranging and at no time did an over power condition exist.

The reactor was authorized for restart on February 13, 2017 at 19:10.

16-FEB-2017 Electronic Noise SCRAM. On February 16, 2017, at approximately 13:48 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.

The Low Flow SCRAM was the result of operating the Emergency Hand-Hand Radio (Walkie-Talkie) in close proximity to the control console. The cause and effect was repeatable. A tag was attached to the radio to warn personnel to not use the radio near the control console.

The reactor was authorized for restart on February 16, 2017 at 13:51.

11-SEPT-2017 Shutdown due to Fire Drill. On September 11, 2017, at approximately 7:27 a fire alarm was received in the control room. The RO followed procedure and proceeded to shutdown the reactor. The RO then notified the DSRO as required and at this time was informed that the fire alarm was a drill.

The reactor was authorized for restart on September 11, 2017 at 7:33.

13-SEPT-2017 Shutdown due to Air in Flow Annubar. On September 13, 2017, at approximately 2:03 the reactor operator noticed a sudden decrease in primary flow indication which is indicative of air in the flow annubar. The RO proceeded to shutdown the reactor. The RO then notified the DSRO as required.

The flow annubar was vented and flow indication returned to normal.

The reactor was authorized for restart on September 13, 2017 at 8:30.

15-SEPT-2017 SCRAM due to Air in Flow Annubar. On September 15, 2017, at approximately 23:12 a Low Flow SCRAM was received in the control room. The reactor operator 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.

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The SCRAM was caused by air being trapped in the flow annubar resulting in a false low flow indication. Actual flow was nominally 500 gpm. The flow annubar was vented and flow indication returned to normal.

The reactor was authorized for restart on September 15, 2017 at 23:54.

1-OCT-2017 SCRAM due to Loss of Commercial Power. On October 1, 2017, at approximately 20:21 a power flicker caused the reactor to SCRAM. The reactor operator 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.

The loss of commercial power was due to a transformer malfunction at the campus substation.

The reactor was authorized for restart on October 1, 2017 at 22:45.

2-OCT-2017 SCRAM due to Loss of Commercial Power. On October 2, 2017, at approximately 4:16 a power flicker caused the reactor to SCRAM. The reactor operator 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.

The loss of commercial power was due to repair activities at the campus substation resulting from the transformer malfunction the previous day.

The reactor was authorized for restart on October 2, 2017 at 5:35.

1-NOV-2017 SCRAM due to Air in Flow Annubar. On November 1, 2017, at approximately 6:03 a Low Flow SCRAM was received in the control room. The reactor operator 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.

The SCRAM was caused by air being trapped in the flow annubar resulting in a false low flow indication. Actual flow was nominally 500 gpm. The flow annubar was vented and flow indication returned to normal.

The reactor was authorized for restart on November 1, 2017 at 8:10.

1-NOV-2017 SCRAM due to Air in Flow Annubar. On November 1, 2017, at approximately 23:55 a Low Flow SCRAM was received in the control room. The reactor operator 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.

The SCRAM was caused by air being trapped in the flow annubar resulting in a false low flow indication. Actual flow was nominally 500 gpm. The flow annubar was vented and flow indication returned to normal.

The reactor was authorized for restart on November 2, 2017 at 00:35.

2-NOV-2017 SCRAM due to Air in Flow Annubar. On November 2, 2017, at approximately 20:46 a Low Flow SCRAM was received in the control room. The reactor operator 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.

The SCRAM was caused by air being trapped in the flow annubar resulting in a false low flow indication. Actual flow was nominally 500 gpm. The flow annubar was vented and flow indication returned to normal.

The reactor was authorized for restart on November 2, 2017 at 23:45.

3-NOV-2017 SCRAM due to Air in Flow Annubar. On November 3, 2017, at approximately 6:49 a Low Flow SCRAM was received in the control room. The reactor operator followed procedure 4

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.

The SCRAM was caused by air being trapped in the flow annubar resulting in a false low flow indication. Actual flow was nominally 500 gpm.

The reactor was shutdown pending an investigation into the cause and mitigation of the air being trapped in the flow annubar.

The reactor was authorized for restart on November 8, 2017 at 7:15.

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.

827 PS-1 Pool RTD - T2 - On November 9, 2016 under Maintenance Number 826 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. A new RTD was ordered, received, calibrated and placed into to service on Jan 31, 2017. The polyethylene tubing was replaced with stainless tubing to prevent this type of failure from occurring in the future.

828 PS-1-11 Pool Temperature Switch - The existing pool temperature switch was replaced with a new unit. The existing unit was performing satisfactory but was aging. This was not a corrective maintenance due to equipment failure but was a planned maintenance activity. The new unit was calibrated and placed into service.

829 PS-6-06-2A - Stack Gas Radiation Monitor - The pre-amplifier to the stack gas detector failed on February 9, 2017 and was replaced with the pre-amplifier from the Filter GM detector on March 7, 2017. The stack gas detector was calibrated and returned to service on March 7, 2017. While out of service, the Auxiliary GM monitor was used to meet Technical Specification 3.5.

830 PS-3-02 Secondary Filter System - The filter differential pressure transducers failed giving a false DP causing excessive back-flushing of the filters. Transducers were replaced and the DP readings returned to normal.

831 PS-6-08-2A - Filter GM Radiation Monitor - The pre-amplifier from the Filter GM detector was used to replace the failed pre-amplifier for the Stack Gas Radiation Monitor on March 7, 2017. The Filter GM detector is not a required channel and was taken out of service.

832 PS-7-02-1A - Auxiliary Generator - The auxiliary generator battery was reading low. Battery was replaced.

833 PS-3-02-5A - Cooling Tower Solenoid Bleed Valve - The cooling tower solenoid bleed valve was stuck open causing a continuous blowdown of the cooling tower basin. The valve was replaced.

834 PS-5-01-1A - Main HVAC Supply Damper Actuator- During the startup checklist the actuator for the Main HVAC Supply Damper failed in the closed position. The actuator determined to be faulty and was replaced.

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835 PS-2-03A - Primary Flow Annubar- Entrained air in the primary piping is becoming trapped in the upstream side of the flow annubar causing a false low flow reading. This reading occasionally falls below the 475 gpm SCRAM setpoint causing a Low Primary Flow SCRAM. The primary flow reading will return to normal when the annubar is vented. To prevent this from happening in the future a design change is being evaluated to relocate the annubar.

836 PS-2-03A - Primary Flow Annubar- This is a repeat of the entrained air in the primary piping and is detailed in Maintenance Log Number 835. A sample of the entrained gas from the primary piping was taken and analyzed. It was determined that the gas was indeed air. Dissolved air concentrations in the primary water are slightly higher than normal due to a lower primary water temperature and increase in city water make-up. This slightly higher than normal dissolved air concentration along with the continuous operation allows the air to accumulate and become trapped in the flow annubar. A design change to relocate the annubar was approved in November 2017 and implemented in January 2018.

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 for all design changes.

818 Installation of Thermo Area Radiation Monitoring System - This modification will replace the obsolete Victoreen radiation monitors with Thermo radiation monitors. The design change package was approved on May 2, 2017. Installation is pending.

830 Relocation of Original Flow Annubar and Installation of an Additional Flow Annubar - This modification will relocate the original flow annubar to a location that is not susceptible to entrained air in the primary system. A second redundant flow annubar will be located downstream in the primary piping. The design change was approved in November 2017 and installation was completed in January 2018.

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.

Due to the license renewal that was submitted in April, 2017, a review of all procedures is ongoing. All procedures are being evaluated, revised, reaffirmed, or retired. This process is scheduled to be completed prior to the issuance of the license renewal.

817 PS-6-19 Thermo Radiation Monitor Calibration, Operation, and Maintenance, Revision 1 - This procedure was revised to incorporate the calibration of count rate equipment.

819 Special Procedure 2.7 - Unplanned Event Notification and Reporting, Revision 4 - This revision added the requirement for the prompt notification of the NRP Director, MEO and RHP for all events.

822 Emergency Procedure 1 - Emergency Plan Activation, Response, and Actions, Revision 19 - This procedure implement the newly approved Emergency Plan, Revision 10. Attachment 1 - PULSTAR Emergency Organizational Chart and Attachment 5 - Radiation Monitoring Systems and Reactor Instrumentation have been revised to reflect the new Emergency Plan.

823 Emergency Procedure 4 - Emergency Classification, Revision 7 - This procedure implements the newly approved Emergency Plan, Revision 10. Emergency Action Level (EAL) definitions and criteria have been revised to reflect the new Emergency Plan.

824 Emergency Procedure 6 - Training, Revision 7 - This procedure implements the newly approved Emergency Plan, Revision 10. Emergency training, drills, and equipment inventory are combined into 6

one procedure resulting the retirement of Emergency Procedures 7 and 9.

825 Emergency Procedure 10 - Determination of Concentration, Release Rate, and Off-Site Dose from Airborne Effluent, Revision 6 - This procedure implement the newly approved Emergency Plan, Revision 10.

Test and Experiments Experiment changes were reviewed to determine whether or not a 10 CFR Part 50.59 evaluation was required.

816 NRP-OP-411 - Deuterium System Procedures, Revision 2.2 -The procedure was revised to clarify procedural sequencing of steps to protect equipment and to verify the system is in a safe, secure configuration prior to leaving it unattended.

821 Production of Mo The purpose of this experimental review is to allow for the production of Mo-

99. This document sets the requirements and limitations for the production, handling and shipping of Mo-99.

Other Changes 820 License Renewal Package - The facility operating license renewal package for the PULSTAR with a power uprate to 2.6 MW was submitted to the NRC on March 29, 2017 and is currently under review.

826 Security Plan for Shipment of Hazardous Material - This plan has been updated to current regulatory requirements.

827 Emergency Plan - The Emergency Plan was revised and submitted as part of the license renewal package. The Plan was reviewed by the NRC and found to be compliant with the regulations. The Plan was implemented on October 1, 2017.

Other Items Reportable Event On May 10, 2017 a reportable event occurred at the PULSTAR reactor involving failure to a have a licensed operator in the control room when the reactor key was in the reactor console. The Nuclear Regulatory Commission was notified and a written report was filed with the NRC on May 15, 2017. Corrective actions were identified resulting engineered and administrative controls being implemented to prevent a reoccurrence.

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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:

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

Total Number of Total Diluent Tritium 2017 Volume Batches µCi Liters µCi Liters 01 JAN - 31 MAR 2 518 6,550 24,400 515 01 APR - 30 JUN 4 853 13,400 172,500 834 01 JUL - 30 SEP 6 678 20,400 253,000 651 01 OCT - 31 DEC 4 492 13,300 23,400 488 2017 2,488 µCi of tritium was released during this year.

2017 2,541 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.

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Gaseous Waste (summarized monthly)

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

(1) Gases:

Total Time Year Month Curies Hours JANUARY 744 3.24E-01 FEBRUARY 672 8.54E-02 MARCH 744 1.78E-01 APRIL 720 8.95E-02 MAY 744 0.00E+00 JUNE 720 3.98E-01 2017 JULY 744 1.48E+00 AUGUST 744 7.63E-01 SEPTEMBER 720 1.31E+00 OCTOBER 744 1.38E+00 NOVEMBER 720 1.80E+00 DECEMBER 744 3.25E-01 TOTAL 8760 8.125 (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 most filters during this reporting period. Antimony-124 was detected in amounts below 0.1 percent of 10 CFR 20 Appendix B Table 2 effluent limit in air on some filters.

ii. Gases and Particulates Discharged During the Reporting Period:

(1) Gases:

Total activity of Argon-41 released was 8.125 curies in 2017.

The yearly average concentration of Argon-41 released from the PULSTAR reactor facility exhaust stack in 2017 was 3.9x10-8 Ci/ml. Dose calculations for the year were performed using methods given in the Final Safety Analysis Report and 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 and Antimony-124 at concentrations below 0.1 percent of the regulatory limit were detected.

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Solid Waste from Reactor

i. Total Volume of Solid Waste Packaged Total volume of solid waste was 45 ft3.

ii. Total Activity Involved Total activity for solid waste was 1.649 mCi.

iii. Dates of shipments and disposal Transfer of solid radioactive waste to the university broad scope radioactive materials license was made in Feb 2017, Aug 2017, and Oct 2017. The University Environmental Health and Safety Center arranges disposal of hazardous wastes.

6.7.4.g Personnel Radiation Exposure Report:

Thirty 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 2017 to 31 Dec 2017 was 1.465 person-rem. Individual deep dose-equivalent ranged from 0.001 rem to 0.588 rem with a median of 0.020 rem and average of 0.051 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.

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 (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 2017 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 THE PERIOD JANUARY 1, 2017 - DECEMBER 31, 2017 NORTH CAROLINA STATE UNIVERSITY ENVIRONMENTAL HEALTH AND SAFETY CENTER RADIATION SAFETY DIVISION by Ralton J. Harris Environmental Health Physicist

TABLE OF CONTENTS PAGE NO.

1. INTRODUCTION 1 Table 1 Environmental Monitoring Programs for the PULSTAR Reactor 2

2. AIR MONITORING 3 Table 2.1 Location of Air Monitoring Stations 3 Table 2.2 Airborne Gross Beta Activities 3 Table 2.3 Airborne Gamma Activities (LLD Values) 4 Table 2.4 Regulatory Limits, Alert Levels and Background Levels for Airborne Radioactivity 5

3. MILK Table 3.1 I-131 in Cows Milk 6

4. SURFACE WATER Table 4.1 Gross Alpha and Beta Activity in Surface Water 7 Table 4.2 LLD Values for Gamma Emitters in Surface Water 8

5. VEGETATION Table 5.1 Gross Beta Activity in Campus Vegetation 9 Table 5.2 LLD Values for Gamma Emitters in Vegetation 9

6. OPTICALLY STIMULATED DOSIMETERS 10 Table 6.1 Environmental Dosimeter Doses 10

7. QUALITY CONTROL INTERCOMPARISON PROGRAM 11 Tables 7.1a - 7.1c 12 -14

8. CONCLUSIONS 15

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:

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

2) Meeting requirements of regulatory agencies;

3) Verifying radionuclide containment in the reactor facility;

4) Meeting legal liability obligations; and

5) 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 Gross N.E. Continuous Continuous 10 CFR 20 Gases 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 N.E. (~ Monthly) (~ Monthly) City of Tritium Raleigh Ordinance Air Particles Gross Beta RSD Weekly Quarterly 10 CFR 20 at 4 Gamma RSD Weekly Quarterly 10 CFR 20 Campus Emitters Stations*

Air Dose at OSD RSD Quarterly Quarterly 10 CFR 20 7 Campus Dosimeter Stations+

Surface Gross Beta RSD Quarterly Quarterly NCSU Water Gamma RSD Quarterly Quarterly NCSU Rocky Emitters Branch 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 = Radiation Safety Division.

• These 4 stations include:

Withers, Daniels, Polk and the Environmental Health & Safety Center.

+These 7 stations include: PULSTAR Reactor and the 4 air sampling stations, North Hall and a control station (EH&S).

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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 27.3 fCi/cubic meter at the Daniels Hall station during the week of 09/19/2017 to 09/26/2017. The annual campus average value was 19.6 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 1DIRECTION - DIRECTION FROM REACTOR STACK 2DISTANCE - DISTANCE FROM REACTOR STACK 3ELEVATION - ELEVATION RELATIVE TO THE TOP OF THE REACTOR STACK

• • ONLY DOSIMETER MONITORING 3

TABLE 2.2 Airborne Gross Beta Activity (fCi/cubic meter +/- 2)

PERIOD Polk Daniels Withers EH&S 2017 03/21-03/28 10.0 +/- 1.1 18.7 +/- 1.3 18.6 +/- 1.3 17.3 +/- 1.3 06/22-06/29 14.2 +/- 1.2 13.5 +/- 1.1 15.0 +/- 1.3 12.9 +/- 1.3 09/19-09/26 15.5 +/- 1.3 27.3 +/- 1.7 26.4 +/- 1.5 26.4 +/- 1.6 12/05-12/12 26.1 +/- 1.6 26.4 +/- 1.6 23.5 +/- 1.5 22.2 +/- 1.5 TABLE 2.3 Airborne Gamma Activity LLD Values (fCi/cubic meter)

PERIOD Co-57 Co-60 Nb-95 Zr-95 Ru-103 Ru-106 Cs-137 Ce-141 Ce-144 2017 03/21- 03/28 0.21 0.35 0.29 0.47 0.27 2.37 0.26 0.38 1.22 06/22 - 06/29 0.20 0.37 0.28 0.48 0.28 2.48 0.29 0.34 1.28 09/19 - 09/26 0.18 0.35 0.31 0.54 0.33 2.51 0.29 0.43 1.40 12/05 - 12/12 0.17 0.37 0.37 0.50 0.32 2.41 0.29 0.39 1.41 4

TABLE 2.4 REGULATORY LIMITS, ALERT LEVELS, AND BACKGROUND LEVELS FOR AIRBORNE RADIOACTIVITY (fCi M 3).

REGULATORY INVESTIGATION *AVERAGE N.C.

NUCLIDE LIMIT LEVEL BACKGROUND LEVEL GROSS BETA 1000 500 20 Cs-137 2 X 105 100 2 Ce-134 2 X 105 100 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 Health and Human Services 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 I-131 was detected in these samples.

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 2017 Not Detected Not Detected 6

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 where it enters (ON), behind Carmichael Gymnasium (GYM) and exits (OFF) the campus. 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 GROSS GROSS DATE LOCATION ALPHA BETA FIRST QUARTER 2017 ON 0.05 +/- 0.2 2.9 +/- 0.7 OFF -0.03 +/- 0.2 4.0 +/- 0.7 GYM -0.03 +/- 0.2 2.7 +/- 0.7 SECOND QUARTER 2017 ON 0.2 +/- 0.2 2.1 +/- 0.6 OFF 0.1 +/- 0.2 3.0 +/- 0.7 GYM 0.1 +/- 0.2 2.3 +/- 0.6 THIRD QUARTER 2017 ON -0.1 +/- 0.2 5.5 + 0.8 OFF 0.1 +/- 0.2 3.2 + 0.7 GYM -0.05 +/- 0.2 3.9 + 0.7 FOURTH QUARTER 2017 ON 0.03 +/- 0.1 4.3 + 0.7 OFF 0.0 +/- 0.1 3.7 + 0.7 GYM 0.05 +/- 0.2 3.7 + 0.7 7

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 8

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.

TABLE 5.1 GROSS BETA ACTIVITY IN CAMPUS VEGETATION

• LLD 0.5 pCi g-1 SAMPLE DATE SAMPLE LOCATION (pCi g-1 +/- 2) 2017 NORTH CAMPUS 5.1 +/- 0.4 2017 SOUTH CAMPUS 4.4 +/- 0.3 20157 EAST CAMPUS 4.1 +/- 0.3 2017 WEST CAMPUS 4.1 +/- 0.3 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 9

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 six 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 eight (8) locations.

The dose equivalents are reported as millirem per quarter year. Readings which fall below the dosimeters minimum measurable quantities (i.e., 1 millirem for gamma radiations and 10 millirem for beta radiation) are reported by the contract vendor with the designation M. The observed readings are typically within the expected range for natural background radiation levels.

TABLE 6.1 ENVIRONMENTAL DOSIMETER DOSES - Millirem per Quarter Period Control Polk Withers Daniels EHS North PULSTAR 2017 01/01- 41 M,M M,M M,M M M 14 03/31 04/01- 49 M,M M,M M,M M M 12 06/30 07/01- 43 M,M M,M M,M M M 18 09/30 10/01- 46 M,M M,M M,M M M 22 12/31 10

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 37) 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. Due to DOE/MAPEP funding issues, cross-check test samples are currently not being supplied for gross alpha/beta water and gross alpha/beta air filter analyses.

The MAPEP value listed in the Tables 7.1 (a-c) 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%

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TABLE 7.1a MULTINUCLIDE WATER SAMPLE - INTERCOMPARISON STUDY 01 August 2017 The sample consists of a spiked aliquot of acidified water (~5 % HNO3). The reported values and the known values are given in Bq/Liter.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide *Reported *Reported MAPEP Acceptance Value Error Value Range Co60 9.5 0.8 10.7 7.5 - 13.9 Cs137 16.2 0.6 16.3 11.4 - 21.2 Cs134 9.9 0.4 11.5 8.1 - 15.0 Co57 9.2 0.7 12.1 8.5 - 15.7 Mn54 15.4 0.6 14.9 10.4 - 19.4 Zn65 14.9 1.0 15.5 10.9 - 20.2 12

TABLE 7.1b MULTINUCLIDE AIR FILTER - INTERCOMPARISON STUDY 01 August 2017 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.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide *Reported *Reported MAPEP Acceptance Value Error Value Range Co60 0.65 0.04 0.68 0.48 - 0.88 Cs137 0.84 0.03 0.82 0.57 - 1.07 Cs134 0.97 0.06 1.00 0.70 - 1.30 Co57 0.04 0.05 -------- False + Test Mn54 1.15 0.04 1.30 0.91 - 1.69 Zn65 1.01 0.06 1.08 0.76 - 1.40 Note: The entry ------ indicates no analyte was present for purposes of conducting a False Positive (+) Test.

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TABLE 7.1c MULTINUCLIDE VEGETATION SAMPLE - INTERCOMPARISON STUDY 01 August 2017 The sample consists of a spiked sample of vegetation. The reported values and the known values are given in Bq/sample.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide *Reported *Reported MAPEP Acceptance Value Error Value Range Co60 1.5 0.6 2.07 1.45 - 2.69 Cs137 0.4 0.5 -------- False + Test Cs134 1.9 0.3 2.32 1.62 - 3.02 Co57 0.8 0.2 2.8 2.0 - 3.6 Mn54 1.9 0.2 2.62 1.83 - 3.41 Zn65 4.9 0.3 5.37 3.76 - 6.98 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 product activities. The observed environmental radioactivity is due primarily to radon progeny, primordial radionuclides (e.g. K-40) and those radionuclides which 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 product materials into the environment.

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