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 North Carolina State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15090A194 (26)

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North Carolina State University is a land- Nuclear Reactor Program Grant university and a constituent institution Of The University of North Carolina I NC STATE An Equal Opportunity/Affirmative Action Employer Nuclear Reactor Program Campus Box 7909 Raleigh, North Carolina 27695 Director 919.515.4598 Office 919.515.7294 (Fax) 919.513.1276 Shipping Address:

NC State University 2500 Stinson Dr.

Raleigh, NC 27695 http://www.ne.ncsu.edu/nrp/index.html 26 March 2015 Attn: Document Control Desk US Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Re: Annual Report for Calendar Year 2014 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 919-515-4601 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 Program North Carolina State University

Enclosures:

Annual Operating Report for 2014 Attachment A: PULSTAR Reactor Environmental Radiation Surveillance Report Aoqo

NORTH CAROLINA STATE UNIVERSITY DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT DOCKET NUMBER 50-297 For the Period: 01 January 2014 - 31 December 2014 The following annual report for 2014 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.

i Operating experience including a summary of experiments performed.

Reactor operations have been routine during this reporting period. The following is a brief summary of the 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

• Water 1

2014 Reactor Utilization Hours Service 45%

Research 32%

Figure 1 - Reactor Utilization by Protocol Utilization Hours Percent Education 396 16%

Research 759 32%

Surveillance 164 7%

Service 1084 45%

TOTAL 2403 100%

NOTE: Utilization hours (2403 h) exceeded critical hours (1254 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 2014: 49.17 Megawatt.days Critical hours in 2014: 1254.68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> Cumulative Total Energy Output Since Initial Criticality: 1594.24 Megawatt.days 6.7.4.c Number of Emergency and Unscheduled Shutdowns:

Emergency Shutdowns - NONE Unscheduled Shutdowns - Five 02-JAN-2014 Low Flow SCRAM. SCRAM caused by closing of secondary pump discharge check valve S6 with the flow measuring system calibration manometer on service. When the check valve closes a pressure wave is transmitted through the heat exchanger and into the primary coolant system. This pressure wave caused a variation in the manometer and in turn the transmitter for the flow measuring system. A low flow condition did not exist only a low flow indication. Corrective action was to take the manometer was taken off service except during the performance of the flow calibration procedure.

04-SEP-2014 SCRAM due to the loss of commercial power. Maintenance workers were performing activities in the Burlington Laboratories electrical switchgear and caused the main breaker to trip when using a 2-way radio while in close proximity. Corrective action was to place signage prohibiting radio transmissions while in proximity to the switchgear.

14-NOV-2014 Flapper NOT Closed SCRAM. Flapper was verified close. Microswitch was cleaned and lubricated. Required post maintenance surveillance was performed and switched tested satisfactorily.

17-NOV-2014 Flapper NOT Closed SCRAM. Flapper was verified closed. Microswitch was replaced with a spare. 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 was caused by the secondary pump discharge check valve S6 closing when the secondary pump was secured. A slight adjustment to the ramp-down time of the secondary pump VFD slowed the closing force of the check valve and alleviated the issue. Check valve operation was tested and confirmed to operate smoothly and quietly.

17-DEC-2014 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 hinge mechanism of the valve. The mechanism was thoroughly cleaned and its operation was notably improved. A temporary corrective action was to identify the valve cleaning as a maintenance item and to place it on the maintenance schedule. It is being evaluated if the valve 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 the PULSTAR Surveillance File System. Each major component of the Reactor Safety System defined in Section 3

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.

795 Secondary Coolant Pump - Secondary pump VFD ramp-down time was adjusted to reduce the closing 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 Safety No. 2 control rods were replaced due to age. Required post maintenance surveillance was performed.

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 a faulty seal.

799 Flapper Microswitch - The microswitch was lubricated and returned to service. Required post maintenance 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 not closing properly. Upon removal debris was noted in the hinge mechanism. The debris was causing binding and not allowing the valve to close properly. The valve was cleaned and returned to service and tested satisfactorily.

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

Facility Changes Design 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, and based 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 "Low Oxygen Level" alarm associated with the oxygen monitors in the Mechanical Equipment Room to the control console annunciators.

769 Auxiliary Pool Fill Line -This design modification added an auxiliary pool fill line that makes it possible 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 model that will allow for additional inputs for potential expansion.

Document Changes Procedure 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.

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766 NRP-OP-105 - Response to SCRAMS, Alarms and Abnormal Conditions - This procedure revision added reactor operator response instructions for "Low Oxygen Level" alarm and natural phenomena such as tornadoes and earthquakes.

767 Oxygen Deficiency Monitor Verification - This new procedure provides instructions on how to perform the weekly and semi-annual checks for the oxygen monitors installed in the Mechanical Equipment Room.

771 Core Flux Mapping - PS-8-03 This new procedure provides instructions on how to properly measure 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 to properly 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 monitor checks to the startup checklist.

775 Reactor Power Recorder - PS-1-03-6:S$ - This procedure revision modified the instructions on how to verify that the recorder is operational. This revision was necessary due to the reactor power recorder replacement, see design change 774.

776 Process Radiation Monitoring Channel Calibration - PS-6-17-2:Al - This procedure revision updated 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 of NST 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 the biennial authentication code list.

Test and Experiments 765 Testing of the UCN Facility with Nonflammable Gases - This experiment approval allows for the testing of the UCN facility with nonflammable gases. The experiment is positioned in an initial testing location outside of the biological shield and does not interact with the reactor. The purpose 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 separate request.

Other Changes 770 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. This amendment request was approved by the appropriate campus committees in 2014 and was submitted 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:

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

Number of Total Total Diluent Tritium 2014 Batches [Ci Volume Liters I.10 Bth C Liters iters__Ci 01 JAN - 31 MAR 2 85 6.40E3 7.36E4 77 01 APR - 30 JUN 4 170 1.37E4 8.15E4 160 01 JUL - 30 SEP 5 384 1.65E4 8.76E4 373 01 OCT- 31 DEC 3 178 9.78E3 1.43E4 176 2014 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 2x10 5 gICi/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 10CFR20 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 1.058 FEBRUARY 672 0.624 MARCH 744 0.696 APRIL 720 0.913 MAY 744 1.283 JUNE 720 1.193 2014 JULY 744 0.370 AUGUST 744 0.368 SEPTEMBER 720 0.491 OCTOBER 744 0.371 NOVEMBER 720 0.136 DECEMBER 744 0.233 TOTAL 8760 7.736 6

(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 7.736 curies in 2014.

The yearly average concentration of argon-41 released from the PULSTAR reactor facility exhaust stack in 2014 was 3.7x10 8 IiCi/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 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 41.3 ft 3.

34 ft 3 of dry uncompacted waste 7.3 ft3 of ion exchange resins ii. Total Activity Involved Total activity for solid waste was 4.74 mCi.

2.96 mCi of dry uncompacted waste 1.78 mCi of ion exchange resins iii. Dates of shipments and disposal A 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. Internal dose monitoring was not required for any individual. Collective deep dose-equivalent for 1 Jan 2014 to 31 Dec 2014 was 2.200 person-rem. Individual deep dose-equivalent ranged from 0.001 rem to 0.556 rem with 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.

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Contamination in most areas was not detectable. When contamination was detected, the area or 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 10 p.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 in accordance with facility procedures.

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ATTACHMENT A PULSTAR REACTOR ENVIRONMENTAL RADIATION SURVEILLANCE REPORT FOR CALENDAR YEAR 2014

[JANUARY 1, 2014 - DECEMBER 31, 2014]

NORTH CAROLINA STATE UNIVERSITY ENVIRONMENTAL HEALTH AND SAFETY CENTER RADIATION SAFETY DIVISION by Ralton J. Harris Environmental Health Physicist 9

TABLE OF CONTENTS PAGE NO.

1. INTRODUCTION 11 Table 1 Environmental Monitoring Programs for the PULSTAR Reactor 12

2. AIR MONITORING 13 Table 2.1 Location of Air Monitoring Stations 13 Table 2.2 Airborne Gross Beta Activities 13 Table 2.3 Airborne Gamma Activities (LLD Values) 14 Table 2.4 Regulatory Limits, Alert Levels and Background Levels for Airborne Radioactivity 14

3. MILK Table 3.1 1-131 in Cow's Milk 15

4. SURFACE WATER Table 4.1 Gross Alpha and Beta Activity in Surface Water 16 Table 4.2 LLD Values for Gamma Emitters in Surface Water 17

5. VEGETATION Table 5.1 Gross Beta Activity in Campus Vegetation 18 Table 5.2 LLD Values for Gamma Emitters in Vegetation 18

6. OPTICALLY STIMULTATED DOSIMETERS 19 Table 6.1 Environmental Dosimeter Doses 20

7. QUALITY CONTROL INTERCOMPARISON PROGRAM 21 Tables 7.1a - 7.1e 21-24

8. CONCLUSIONS 25 10

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 N.E. (~ MONTHLY) (~ MONTHLY) 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 STATIONS 1 EMITTERS AIR DOSE AT 7 TLD RSD QUARTERLY QUARTERLY 10 CFR 20 CAMPUS DOSIMETER STATIONS 2 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 1-131 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 24.5 fCi/cubic meter at the Withers Hall station during the week of 09/15/2014 to 09/22/2014. The annual campus average was 14.9 fCi/cubic meter.

Beginning in the 2 nd Quarter of 2014 the monitoring stations at Broughton Hall and D.H. Hill Library were eliminated 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 STATIONS 3

SITE DIRECTION 1 DISTANCE 2 ELEVATION METERS METERS BROUGHTON SOUTHWEST 125 -17 DH HILL NORTHWEST 192 +11 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 FROM REACTOR STACK 2DISTANCE FROM REACTOR STACK 3ELEVATION RELATIVE TO THE TOP OF THE REACTOR STACK TABLE 2.2 AIRBORNE GROSS BETA ACTIVITY (fCi.m-3 meter +/- 2o) 2014 BROUGHTON DH HILL POLK DANIELS WITHERS EH&S 03/11-03/18 10.1 +/- 0.9 14.9 +/- 1.1 7.6 + 0.8 5.8 + 0.8 8.3 + 0.9 06/20-06/27 15.6 +/- 1.1 13.3 +/- 1.0 12.2 +/- 1.0 13.1 +/- 1.0 09/15-09/22 23.6 +/- 1.3 13.5 + 1.1 24.5 + 1.4 24.2 + 1.3 11/13-11/20 14.6 +/- 1.0 14.6 + 1.0 22.0 +/- 1.3 14.5 + 1.0 Broughton and DH Hill Library stations were eliminated after the 1st quarter of 2014.

Polk station was added for the 2 nd quarter of 2014.

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

PERIOD 2014 CO-57 CO-60 NB-95 ZR-95 RU-103 RU-106 CS-137 CE-141 2014 CE-144 03/11- 03/18 0.21 0.35 0.29 0.47 0.27 2.37 0.26 0.38 1.22 06/20 - 06/27 0.20 0.37 0.28 0.48 0.28 2.48 0.29 0.34 1.28 09/15 - 09/22 0.18 0.35 0.31 0.54 0.33 2.51 0.29 0.43 1.40 11/13 - 11/20 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)

NUCLIDE REGULATORY LIMIT INVESTIGATION AVERAGE N.C.

LEVEL BACKGROUND LEVEL GROSS BETA 1000 500 20 CS-137 2 X 10 5 100 2 CE-134 2 X 10s 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 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-1 DATE CAMPUS CREAMERY LAKE WHEELER 2014 NO DATA NO DATA 15

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 +/- 2a)

LLD. - 0.4 pCi.Liter' LLDp - 0.4 pCi.Liter -'

pCi Liter-1 DATE LOCATION GROSS ALPHA GROSS BETA FIRST QUARTER 2014 ON 0.08+/-0.1 3.6+/-0.6 OFF 0.05+/-0.1 3.2+/-0.6 GYM 0.20+/-0.2 1.4+/-0.5 SECOND QUARTER 2014 ON 0.05+/-0.2 2.9+/-0.6 OFF 0.00+/-0.2 2.6+/-0.6 GYM 0.03+/-0.2 0.4+/-0.4 THIRD QUARTER 2014 ON 0.03+/-0.2 2.5+0.6 OFF 0.05+/-0.2 2.6+0.6 GYM 0.20+/-0.2 2.9+0.6

'FOURTH QUARTER 2014 ON 0.03+/-0.1 1.4+0.5 OFF 0.10+/-0.2 1.4+0.5 GYM 0.20+/-0.2 2.7+0.6 16

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 17

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. The vegetation sampling is performed every other year. No samples were collected for 2014.

1 TABLE 5.1 GROSS BETA ACTIVITY IN CAMPUS VEGETATION *LLD - 0.5 pCi'g" DATE SAMPLE LOCATION (pCi.g"1 +/- 2a) 2014 NORTH CAMPUS No Data 2014 SOUTH CAMPUS No Data 2014 EAST CAMPUS No Data 2014 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 18

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.

The monitoring stations at D.H. Hill Library and Broughton Hall were discontinued at the conclusion of the 1st Quarter of 2014 due to building renovations. A new monitoring station was installed at Polk Hall.

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TABLE 6.1 ENVIRONMENTAL DOSIMETER DOSES DATE CONTROL BROUGHTON DH HILL POLK WITHERS DANIELS EH&S NORTH PULSTAR 2014 01/01- 33 1 18,36 M 4 M 1 25 03/31 05/10- 24 1,12 4, M 1,14 2 3 2 06/30 07/01- 31 M,M 1,M 22 3 3 21 09/30 10/01- M,M M,M 16 5 4 20 12/31 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:

%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 STUDY 01 August 2014 NCSU - ENVIRONMENTAL LABORATORY RESULTS RADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE GROSS ALPHA 0.37 0.02 0.53 0.16 - 0.90 GROSS BETA 0.95 0.04 1.06 0.53 - 1.59 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 BQO/FILTER.

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TABLE 7.1b MULTINUCLIDE AIR FILTER - INTERCOMPARISON STUDY 01 August 2014 NCSU - ENVIRONMENTAL LABORATORY RESULTS RADIONUCLIDE 1REPORTED 1REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE Co60 1.13 0.03 1.10 0.77 - 1.43 Cs137 1.14 0.04 1.20 0.84-1.56 Cs134 0.85 0.02 0.96 0.67 - 1.35 Co57 1.25 0.04 1.43 1.00 - 1.86 Mn54 0.78 0.03 0.75 0.53-0.98 Zn65 0.85 0.06 0.76 0.53 - 0.99 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 BQIFILTER.

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TABLE 7.1c MULTINUCLIDE WATER SAMPLE - INTERCOMPARISON STUDY 01 August 2014 NCSU - ENVIRONMENTAL LABORATORY RESULTS RADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE Co60 12.35 0.40 12.4 8.7 - 16.1 Cs137 17.62 0.67 18.4 12.9 - 23.3 Cs134 -6.8 7.0 False + Test Co57 27.62 0.94 24.7 17.3 - 32.1 Mn54 13.50 0.52 14.0 9.8- 18.2 Zn65 11.56 0.97 10.9 7.6 - 14.2 THE SAMPLE CONSISTS OF A SPIKED ALIQUOT OF ACIDIFIED WATER (-5 % HNO 3). 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 August 2014 NCSU - ENVIRONMENTAL LABORATORY RESULTS RADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE Gross Alpha 1.25 0.21 1.4 0.42 - 2.38 Gross Beta 5.66 0.25 6.50 3.25 -9.75 THE SAMPLE CONSISTS OF A 5% HNO 3 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 August 2013 NCSU - ENVIRONMENTAL LABORATORY RESULTS RADIONUCLIDE REPORTED REPORTED MAPEP ACCEPTANCE VALUE ERROR VALUE RANGE Co60 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- 12.0 MnS4 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 KNOWN VALUES 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 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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