ML15090A194

North Carolina State University, Submittal of Annual Operating Report for Calendar Year 2014

ML15090A194
Person / Time
Site:	North Carolina State University
Issue date:	03/26/2015
From:	Hawari A I North Carolina State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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North Carolina State University is a land-Grant university and a constituent institution Of The University of North CarolinaAn Equal Opportunity/Affirmative Action EmployerNuclear Reactor ProgramI NC STATENuclear Reactor ProgramCampus Box 7909Raleigh, North Carolina 27695DirectorOffice(Fax)919.515.4598 919.515.7294 919.513.1276 Shipping Address:NC State University 2500 Stinson Dr.Raleigh, NC 27695http://www.ne.ncsu.edu/nrp/index.html 26 March 2015Attn: Document Control DeskUS Nuclear Regulatory Commission 11555 Rockville PikeRockville, MD 20852Re: Annual Report for Calendar Year 2014License No. R-120Docket No. 50-297In accordance with Technical Specification 6.7.4, the annual operating report for our facility isattached.

If you have any questions regarding this correspondence or require additional information, pleasecontact 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 26 March 2015.Ayman I. Hawari, Ph. D.,Director, Nuclear Reactor ProgramNorth Carolina State University

Enclosures:

Annual Operating Report for 2014Attachment A: PULSTAR Reactor Environmental Radiation Surveillance ReportA oqo NORTH CAROLINA STATE UNIVERSITY DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORTDOCKET NUMBER 50-297For the Period: 01 January 2014 -31 December 2014The following annual report for 2014 is submitted in accordance with Section 6.7.4 of the North Carolina StateUniversity PULSTAR Reactor Technical Specifications:

6.7.4.a Brief Summary:Reactor operations have been routine during this reporting period.i Operating experience including a summary of experiments performed.

Reactor operations have been routine during this reporting period. The following is a brief summary ofthe types of experiments performed:

Teaching Laboratories, Short Courses, and Research* 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 Neutron Activation Analysis* Crude oil* Food samples* Fish tissues* Laboratory animal tissue* Human hair, nails, and urine* Polymers and plastics* Sediment/soil/rocks

• Silicon crystals* Textiles* Water1 2014 Reactor Utilization HoursService45%Research32%Figure 1 -Reactor Utilization by ProtocolUtilization Education ResearchSurveillance ServiceHours39675916410842403Percent16%32%7%45%100%TOTALNOTE: Utilization hours (2403 h) exceeded critical hours (1254 h) since there was typically more thanone user of the reactor facility at a given time.ii Changes in Performance Characteristics Related to Reactor Safety:Noneiii Results of Surveillance, Tests, and Inspections:

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

2 6.7.4.b Energy Output and Critical Hours:Total Energy Output in 2014:49.17 Megawatt.days Critical hours in 2014:1254.68 hour7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br />sCumulative Total Energy Output Since Initial Criticality:

1594.24 Megawatt.days 6.7.4.c Number of Emergency and Unscheduled Shutdowns:

Emergency Shutdowns

-NONEUnscheduled Shutdowns

-Five02-JAN-2014 04-SEP-2014 14-NOV-2014 17-NOV-2014 17-DEC-2014 Low Flow SCRAM. SCRAM caused by closing of secondary pump discharge check valve S6with the flow measuring system calibration manometer on service.

When the check valvecloses a pressure wave is transmitted through the heat exchanger and into the primarycoolant system. This pressure wave caused a variation in the manometer and in turn thetransmitter for the flow measuring system. A low flow condition did not exist only a lowflow indication.

Corrective action was to take the manometer was taken off service exceptduring the performance of the flow calibration procedure.

SCRAM due to the loss of commercial power. Maintenance workers were performing activities in the Burlington Laboratories electrical switchgear and caused the main breakerto trip when using a 2-way radio while in close proximity.

Corrective action was to placesignage prohibiting radio transmissions while in proximity to the switchgear.

Flapper NOT Closed SCRAM. Flapper was verified close. Microswitch was cleaned andlubricated.

Required post maintenance surveillance was performed and switched testedsatisfactorily.

Flapper NOT Closed SCRAM. Flapper was verified closed. Microswitch was replaced with aspare. The proper operation of the flapper was verified with an underwater camera.Required post maintenance surveillance was performed and switched tested satisfactorily.

Upon further investigation it was determined that the Flapper NOT Closed SCRAM wascaused by the secondary pump discharge check valve S6 closing when the secondary pumpwas secured.

A slight adjustment to the ramp-down time of the secondary pump VFDslowed the closing force of the check valve and alleviated the issue. Check valve operation was tested and confirmed to operate smoothly and quietly.Flapper NOT Closed SCRAM. Flapper was verified closed. SCRAM caused by secondary pump discharge check valve S6 not closing properly.

The valve was removed and inspected.

Debris, from the initial construction of the system, had accumulated in the hingemechanism of the valve. The mechanism was thoroughly cleaned and its operation wasnotably improved.

A temporary corrective action was to identify the valve cleaning as amaintenance item and to place it on the maintenance schedule.

It is being evaluated if thevalve can be removed permanently to prevent this from occurring in the future.6.7.4.d Corrective and Preventative Maintenance:

Preventative maintenance, tests and calibrations are scheduled, performed and tracked utilizing thePULSTAR Surveillance File System. Each major component of the Reactor Safety System defined in Section3 3.3, and all surveillance required by Section 4 of the Technical Specifications are monitored by this filesystem to ensure that maintenance and calibrations are performed in a timely manner. All historical datarelating to those components, in addition to many other sub-systems, are maintained in these files.795 Secondary Coolant Pump -Secondary pump VFD ramp-down time was adjusted to reduce theclosing force of the secondary pump discharge check valve.796 Safety No. 1 and Safety No. 2 Control Rods -The shock absorbers on the Safety No. 1 and SafetyNo. 2 control rods were replaced due to age. Required post maintenance surveillance wasperformed.

797 Source Range Monitor -Replaced faulty preamp cable. Required post maintenance surveillance was performed.

798 Waste Tank Control Panel -The pneumatic control valve for waste tank 2 was replaced due to afaulty seal.799 Flapper Microswitch

-The microswitch was lubricated and returned to service.

Required postmaintenance surveillance was performed.

800 Flapper Microswitch

-The Microswitch was faulty and replaced.

Required post maintenance surveillance was performed.

801 Linear Channel Monitor -Bi-stable Trip card and EMI filter replaced due to electronic noise.Required post maintenance surveillance was performed.

802 Secondary Coolant System -The secondary coolant pump discharge check valve S6 was notclosing properly.

Upon removal debris was noted in the hinge mechanism.

The debris wascausing binding and not allowing the valve to close properly.

The valve was cleaned and returnedto service and tested satisfactorily.

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

Facility ChangesDesign changes to the reactor facility were reviewed to determine whether or not a 10CFR50.59 evaluation was required.

There were three design changes in 2014, DC768 and DC769 and DC774, andbased on the screening reviews none required a full 10CFR50.59 evaluation.

The following design changes were made:768 Control Console Annunciator Modification Phase 2 -This design modification added a "LowOxygen Level" alarm associated with the oxygen monitors in the Mechanical Equipment Room tothe control console annunciators.

769 Auxiliary Pool Fill Line -This design modification added an auxiliary pool fill line that makes itpossible to add water to the pool during abnormal conditions from a secured exterior connection while requiring minimal entry into the reactor building.

774 Reactor Power Recorder Replacement

-Replacement of the power recorder with a new modelthat will allow for additional inputs for potential expansion.

Document ChangesProcedure changes were reviewed to determine whether or not a 10CFR50.59 evaluation was required.

Based on the screening reviews none required a full 10CFR50.59 evaluation.

4 766 NRP-OP-105

-Response to SCRAMS, Alarms and Abnormal Conditions

-This procedure revisionadded reactor operator response instructions for "Low Oxygen Level" alarm and naturalphenomena such as tornadoes and earthquakes.

767 Oxygen Deficiency Monitor Verification

-This new procedure provides instructions on how toperform the weekly and semi-annual checks for the oxygen monitors installed in the Mechanical Equipment Room.771 Core Flux Mapping -PS-8-03-1

-This new procedure provides instructions on how to properlymeasure the flux distribution in the reactor core as required by Technical Specification 3.1.f.772 NRP-OP-301

-Reactor Fuel Handling

-This new procedure provides instructions on how toproperly measure fuel assembly worth as required by Technical Specification 3.1.e.773 NRP-OP-101

-Reactor Startup and Shutdown

-This revision added the weekly oxygen monitorchecks to the startup checklist.

775 Reactor Power Recorder

-PS-1-03-6:S$

-This procedure revision modified the instructions onhow to verify that the recorder is operational.

This revision was necessary due to the reactorpower recorder replacement, see design change 774.776 Process Radiation Monitoring Channel Calibration

-PS-6-17-2:Al

-This procedure revisionupdated sampling locations, tritium analysis frequency and reference for Rocky Branch Creek.777 ERS-TRBCW Tritium in Rocky Branch Creek -This procedure revision adds reference to the use ofNST traceable source and their serial numbers.

It also specifies the range of the recorder.

778 Emergency Procedure 2 -Offsite Notification

-This minor change to the procedure updated thebiennial authentication code list.Test and Experiments 765 Testing of the UCN Facility with Nonflammable Gases -This experiment approval allows for thetesting of the UCN facility with nonflammable gases. The experiment is positioned in an initialtesting location outside of the biological shield and does not interact with the reactor.

Thepurpose of this test was to confirm system responses and to generate final system procedures before the use of flammable gases. Testing with flammable gases will be treated as a separaterequest.Other Changes770 License and Technical Specification Amendment

-This license and technical specification amendment would permit the use of 4% and/or 6% U-235 fuel in the reactor core. Thisamendment request was approved by the appropriate campus committees in 2014 and wassubmitted to the Nuclear Regulation Commission in 2015.6.7.4.f Radioactive Effluent:

Liquid Waste (summarized by quarters)

i. Radioactivity Released During the Reporting Period:Releases to the sanitary sewer are given below:5 Period (1) (2) (3) (4)' (5)Number of Total Total Diluent Tritium2014 Batches [Ci Volume Liters I.10Bth C Liters iters__Ci 01 JAN -31 MAR 2 85 6.40E3 7.36E4 7701 APR -30 JUN 4 170 1.37E4 8.15E4 16001 JUL -30 SEP 5 384 1.65E4 8.76E4 37301 OCT- 31 DEC 3 178 9.78E3 1.43E4 1762014 786 IiCi of tritium was released during this year.2014 817 pICi of total activity was released during this year.'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 2x105 gICi/ml.

Isotopic analysesof these batches indicated low levels of typical corrosion and activation products.

No fission productswere detected.

iii. Disposition of Liquid Effluent not Releasable to Sanitary Sewer System:All liquid effluent met the requirements of 10CFR20 for release to the sanitary sewer.Gaseous Waste (summarized monthly)I. Radioactivity Discharged During the Reporting Period (in Curies) for:(1) Gases:Total TimeYear Month CuriesHoursJANUARY 744 1.058FEBRUARY 672 0.624MARCH 744 0.696APRIL 720 0.913MAY 744 1.283JUNE 720 1.1932014 JULY 744 0.370AUGUST 744 0.368SEPTEMBER 720 0.491OCTOBER 744 0.371NOVEMBER 720 0.136DECEMBER 744 0.233TOTAL 8760 7.7366 (2) Particulates with a half-life of greater than eight days:Particulate filters from the Stack Particulate Monitoring Channel were analyzed upon removal.

There wasno 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 7.736 curies in 2014.The yearly average concentration of argon-41 released from the PULSTAR reactor facility exhaust stack in2014 was 3.7x108 IiCi/ml.

Dose calculations for the year were performed using methods given in the FinalSafety Analysis Report. Dose calculations gave results less than the 10 CFR 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 Reactori. Total Volume of Solid Waste PackagedTotal volume of solid waste was 41.3 ft3.34 ft3 of dry uncompacted waste7.3 ft3 of ion exchange resinsii. Total Activity InvolvedTotal activity for solid waste was 4.74 mCi.2.96 mCi of dry uncompacted waste1.78 mCi of ion exchange resinsiii. Dates of shipments and disposalA total of three transfers to the university broad scope radioactive materials license were made in 2014.The University Environmental Health and Safety Center arranges disposal of hazardous wastes.6.7.4.g Personnel Radiation Exposure Report:Twenty-six individuals were monitored for external radiation dose during the reporting period. Internaldose monitoring was not required for any individual.

Collective deep dose-equivalent for 1 Jan 2014 to 31Dec 2014 was 2.200 person-rem.

Individual deep dose-equivalent ranged from 0.001 rem to 0.556 remwith a median of 0.045 rem and average of 0.081 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.

7 Contamination in most areas was not detectable.

When contamination was detected, the areaor item was confined or decontaminated.

6.7.4.1 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 10p.rem/h).

0 Contamination was not detectable.

• Net radiation readings ranged from 0 to 50 prem/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 were analyzed in 2014 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 is routinely performed inaccordance with facility procedures.

8 ATTACHMENT APULSTAR REACTORENVIRONMENTAL RADIATION SURVEILLANCE REPORTFOR CALENDAR YEAR 2014[JANUARY 1, 2014 -DECEMBER 31, 2014]NORTH CAROLINA STATE UNIVERSITY ENVIRONMENTAL HEALTH ANDSAFETY CENTERRADIATION SAFETY DIVISIONbyRalton J. HarrisEnvironmental Health Physicist 9

TABLE OF CONTENTS1. INTRODUCTION Table 1 Environmental Monitoring Programs for the PULSTAR Reactor2. AIR MONITORING Table 2.1 Location of Air Monitoring StationsTable 2.2 Airborne Gross Beta Activities Table 2.3 Airborne Gamma Activities (LLD Values)Table 2.4 Regulatory Limits, Alert Levels and Background Levelsfor Airborne Radioactivity

3. MILKTable 3.1 1-131 in Cow's Milk4. SURFACE WATERTable 4.1 Gross Alpha and Beta Activity in Surface WaterTable 4.2 LLD Values for Gamma Emitters in Surface Water5. VEGETATION Table 5.1 Gross Beta Activity in Campus Vegetation Table 5.2 LLD Values for Gamma Emitters in Vegetation

6. OPTICALLY STIMULTATED DOSIMETERS Table 6.1 Environmental Dosimeter Doses7. QUALITY CONTROL INTERCOMPARISON PROGRAMTables 7.1a -7.1e8. CONCLUSIONS PAGE NO.11121313131414151617181819202121-242510 INTRODUCTION The Environmental Radiation Surveillance Program exists to provide routine measurements of theuniversity environment surrounding the PULSTAR Reactor.

The specific objectives of this programinclude:" 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.

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

(~ MONTHLY)

CITY OF RALEIGHTRITIUM ORDINANCE AIR PARTICLES GROSS BETA RSD WEEKLY QUARTERLY 10 CFR 20AT 4 CAMPUS GAMMA RSD WEEKLY QUARTERLY 10 CFR 20STATIONS1 EMITTERSAIR DOSE AT 7 TLD RSD QUARTERLY QUARTERLY 10 CFR 20CAMPUS DOSIMETER STATIONS2SURFACE GROSS BETA RSD QUARTERLY QUARTERLY NCSUWATER ROCKY GAMMA RSD QUARTERLY QUARTERLY NCSUBRANCH EMITTERSCREEKTRITIUM N.E. QUARTERLY 10 CFR 20VEGETATION GROSS BETA RSD SEMI- EVERY OTHER NCSUNCSU GAMMA RSD ANNUALLY YEAR NCSUCAMPUSMILK 1-131 RSD MONTHLY EVERY OTHER NCSULOCAL DAIRY YEARABBREVIATIONS USED IN TABLE:N.E. = NUCLEAR ENGINEERING/REACTOR FACILITY; RSD/EHSC

= RADIATION SAFETY DIVISION.

1THESE 4 STATIONS INCLUDE:WITHERS,

DANIELS, POLK, AND ENVIRONMENTAL HEALTH & SAFETY CENTER.2THESE 7 STATIONS INCLUDE:

PULSTAR REACTOR, A CONTROL STATION (EH&S) AND THE 4 AIRSAMPLING

STATIONS, AND NORTH HALL.12

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. Thedata in Table 2.2 are for gross beta activity levels measured during the year. The highest gross beta activityobserved was 24.5 fCi/cubic meter at the Withers Hall station during the week of 09/15/2014 to09/22/2014.

The annual campus average was 14.9 fCi/cubic meter.Beginning in the 2nd Quarter of 2014 the monitoring stations at Broughton Hall and D.H. Hill Library wereeliminated due to on-going building renovations actions.

One (1) new monitoring station was established on the rooftop of Polk Hall.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 STATIONSSITE DIRECTION 1 DISTANCE2 ELEVATION 3METERS METERSBROUGHTON SOUTHWEST 125 -17DH HILL NORTHWEST 192 +11DANIELS SOUTHEAST 90 -8WITHERS NORTHEAST 82 -6EH & S CENTER WEST 1230 -3NORTH HALL NORTHEAST 402 -4POLK HALL WEST 100 -71DIRECTION FROM REACTOR STACK2DISTANCE FROM REACTOR STACK3ELEVATION RELATIVE TO THE TOP OF THE REACTOR STACKTABLE 2.2 AIRBORNE GROSS BETA ACTIVITY (fCi.m-3 meter +/- 2o)2014 BROUGHTON DH HILL POLK DANIELS WITHERS EH&S03/11-03/18 10.1 +/- 0.9 14.9 +/- 1.1 7.6 + 0.8 5.8 + 0.8 8.3 + 0.906/20-06/27 15.6 +/- 1.1 13.3 +/- 1.0 12.2 +/- 1.0 13.1 +/- 1.009/15-09/22 23.6 +/- 1.3 13.5 + 1.1 24.5 + 1.4 24.2 + 1.311/13-11/20 14.6 +/- 1.0 14.6 + 1.0 22.0 +/- 1.3 14.5 + 1.0Broughton and DH Hill Library stations were eliminated after the 1st quarter of 2014.Polk station was added for the 2nd quarter of 2014.13 TABLE 2.3 AIRBORNE GAMMA ACTIVITY LLD VALUES (fCi-m3)PERIOD2014 CO-57 CO-60 NB-95 ZR-95 RU-103 RU-106 CS-137 CE-141 CE-144201403/11- 03/18 0.21 0.35 0.29 0.47 0.27 2.37 0.26 0.38 1.2206/20 -06/27 0.20 0.37 0.28 0.48 0.28 2.48 0.29 0.34 1.2809/15 -09/22 0.18 0.35 0.31 0.54 0.33 2.51 0.29 0.43 1.4011/13 -11/20 0.17 0.37 0.37 0.50 0.32 2.41 0.29 0.39 1.41TABLE 2.4 REGULATORY LIMITS, ALERT LEVELS, AND BACKGROUND LEVELS FOR AIRBORNERADIOACTIVITY (fCi.m-3)NUCLIDE REGULATORY LIMIT INVESTIGATION AVERAGE N.C.LEVEL BACKGROUND LEVELGROSS BETA 1000 500 20CS-137 2 X 105 100 2CE-134 2 X 10s 100 0NB-95 2 X 106 100 0ZR-95 400 100 0THIS DATA REPRESENTS AN AVERAGE VALUE MEASURED IN NORTH CAROLINA AT VARIOUS LOCATIONS.

EXCERPTED FROM 2009 ENVIRONMENTAL SURVEILLANCE REPORT PRODUCED BY THE NC DEPARTMENT OFENVIRONMENT

& NATURAL RESOURCES DIVISION OF ENVIRONMENTAL HEALTH RADIATION PROTECTION SECTION.14

3. MILK (TABLE 3.1)Milk samples are collected every other year from the Campus Creamery and the Lake Wheeler Road Dairy asprocessed milk and raw milk and analyzed for 1-131. No samples were collected for 2014.TABLE 3.1 1-131 IN COW'S MILK (pCi.Liter-

+/- 2a) LLD -3 pCi.Liter-PCI LITER-1DATE CAMPUS CREAMERY LAKE WHEELER2014 NO DATA NO DATA15

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 betaactivities 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 is50 pCi Liter-1.

Gamma analysis of all samples was also performed.

All the results are consistent with thepresence 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

+/- 2a)LLD. -0.4 pCi.Liter' LLDp -0.4 pCi.Liter

-'pCi Liter-1DATE LOCATION GROSS ALPHA GROSS BETAFIRST QUARTER 2014 ON 0.08+/-0.1 3.6+/-0.6OFF 0.05+/-0.1 3.2+/-0.6GYM 0.20+/-0.2 1.4+/-0.5SECOND QUARTER 2014 ON 0.05+/-0.2 2.9+/-0.6OFF 0.00+/-0.2 2.6+/-0.6GYM 0.03+/-0.2 0.4+/-0.4THIRD QUARTER 2014 ON 0.03+/-0.2 2.5+0.6OFF 0.05+/-0.2 2.6+0.6GYM 0.20+/-0.2 2.9+0.6'FOURTH QUARTER 2014 ON 0.03+/-0.1 1.4+0.5OFF 0.10+/-0.2 1.4+0.5GYM 0.20+/-0.2 2.7+0.616 TABLE 4.2 LLD VALUES FOR GAMMA EMITTERS IN SURFACE WATERNUCLIDE LLD (pCi.Liter" 1)Co-60 0.4Zn-65 0.7Cs-137 0.3Cs-134 0.4Sr-85 0.4Ru-103 0.3Ru-106 3.0Nb-95 0.4Zr-95 0.517

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 valuesfor several gamma emitters.

The vegetation sampling is performed every other year. No samples were collected for 2014.TABLE 5.1 GROSS BETA ACTIVITY IN CAMPUS VEGETATION

• LLD -0.5 pCi'g"1DATE SAMPLE LOCATION (pCi.g"1 +/- 2a)2014 NORTH CAMPUS No Data2014 SOUTH CAMPUS No Data2014 EAST CAMPUS No Data2014 WEST CAMPUS No DataTABLE 5.2 LLD VALUES FOR GAMMA EMITTERS IN VEGETATION NUCLIDE LLD (pCi-gram" 1)Co-60 0.01Zn-65 0.02Cs-137 0.01Cs-134 0.01Sr-85 0.01Ru-103 0.01Nb-95 0.01Zr-95 0.0218

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 thePULSTAR Reactor facility.

A control dosimeter is located in the Environmental Health & Safety Center. Table 6.1gives 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) arereported by the contract vendor with the designation "M". The observed readings are typically within theexpected range for natural background radiation levels.The monitoring stations at D.H. Hill Library and Broughton Hall were discontinued at the conclusion of the 1stQuarter of 2014 due to building renovations.

A new monitoring station was installed at Polk Hall.19 TABLE 6.1 ENVIRONMENTAL DOSIMETER DOSESDATE CONTROL BROUGHTON DH HILL POLK WITHERS DANIELS EH&S NORTH PULSTAR201401/01- 33 1 18,36 M 4 M 1 2503/3105/10- 24 1,12 4, M 1,14 2 3 206/3007/01- 31 M,M 1,M 22 3 3 2109/3010/01- M,M M,M 16 5 4 2012/31All 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 theminimum measurable quantity which is 1 millirem for gamma radiation and 10 millirem for betaradiation.

Dual dose entries indicate two (2) independent dosimeters assigned at the indicated station.20

7. QUALITY CONTROL INTERCOMPARISON PROGRAMThe Environmental Radiation Surveillance Laboratory (ERSL) in the Radiation Safety Division has analyzedsamples 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 thisprogram is to provide laboratories performing environmental radiation measurements with unknowns to testtheir 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 arelative bias:%Bias = (1 00)(Laboratory Re sult -RESL Re ferenceValue)

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 STUDY01 August 2014NCSU -ENVIRONMENTAL LABORATORY RESULTSRADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGEGROSS ALPHA 0.37 0.02 0.53 0.16 -0.90GROSS BETA 0.95 0.04 1.06 0.53 -1.59THE 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 VALUESAND THE KNOWN VALUES ARE GIVEN IN BQO/FILTER.

21 TABLE 7.1b MULTINUCLIDE AIR FILTER -INTERCOMPARISON STUDY01 August 2014NCSU -ENVIRONMENTAL LABORATORY RESULTSRADIONUCLIDE 1REPORTED 1REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGECo60 1.13 0.03 1.10 0.77 -1.43Cs137 1.14 0.04 1.20 0.84-1.56 Cs134 0.85 0.02 0.96 0.67 -1.35Co57 1.25 0.04 1.43 1.00 -1.86Mn54 0.78 0.03 0.75 0.53-0.98 Zn65 0.85 0.06 0.76 0.53 -0.99THE SAMPLE CONSISTS OF ONE 50 MM DIAMETER GLASS FIBER FILTER WHICH HAS BEEN SPIKED WITH ASOLUTION AND DRIED. THE REPORTED VALUES AND THE KNOWN VALUES ARE GIVEN IN BQIFILTER.

22 TABLE 7.1c MULTINUCLIDE WATER SAMPLE -INTERCOMPARISON STUDY01 August 2014NCSU -ENVIRONMENTAL LABORATORY RESULTSRADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGECo60 12.35 0.40 12.4 8.7 -16.1Cs137 17.62 0.67 18.4 12.9 -23.3Cs134 -6.8 7.0 False + TestCo57 27.62 0.94 24.7 17.3 -32.1Mn54 13.50 0.52 14.0 9.8- 18.2Zn65 11.56 0.97 10.9 7.6 -14.2THE SAMPLE CONSISTS OF A SPIKED ALIQUOT OF ACIDIFIED WATER (-5 % HNO3). THE REPORTED VALUESAND THE KNOWN VALUES ARE GIVEN IN BQ/LITER.

NOTE: THE ENTRY "-".......

INDICATES NO ANALYTE WAS PRESENT FOR PURPOSES OF CONDUCTING AFALSE POSITIVE

(+) TEST.TABLE 7.1d GROSS ALPHA AND BETA WATER SAMPLE -INTERCOMPARISON STUDY01 August 2014NCSU -ENVIRONMENTAL LABORATORY RESULTSRADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGEGross Alpha 1.25 0.21 1.4 0.42 -2.38Gross Beta 5.66 0.25 6.50 3.25 -9.75THE SAMPLE CONSISTS OF A 5% HNO3 MATRIX FREE SOLUTION.

THE REPORTED VALUES AND THE KNOWNVALUES ARE GIVEN IN BQ/LITER.

23 TABLE 7.1e MULTINUCLIDE VEGETATION SAMPLE -INTERCOMPARISON STUDY01 August 2013NCSU -ENVIRONMENTAL LABORATORY RESULTSRADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGECo60 5.20 0.15 6.11 4.28-7.94 Cs137 6.49 0.25 8.14 5.70-10.58 Cs134 6.52 0.14 7.38 5.17-9.59 Co57 7.68 0.20 9.20 6.4- 12.0MnS4 5.91 0.23 7.10 4.97-9.23 Zn65 5.08 0.33 6.42 4.49-8.35 THE SAMPLE CONSISTS OF A SPIKED SAMPLE OF VEGETATION.

THE REPORTED VALUES AND THE KNOWNVALUES ARE GIVEN IN BQ/SAMPLE.

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8. CONCLUSIONS The data obtained during this period do not show any fission product activities.

The observedenvironmental radioactivity is due primarily to radon progeny, primordial radionuclides (e.g. K-40) andthose 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 doesnot release fission product materials into the environment.

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