ML022480095

North Carolina State Univ (Ncsu) - Pulstar Annual Report for the Period July 1, 2001 Through June 30, 2002

ML022480095
Person / Time
Site:	North Carolina State University
Issue date:	08/27/2002
From:	Wicks G Univ of North Carolina
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML022480095 (42)

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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 NC TT* NIESBT-Department of Nuclear Engineering Campus Box 7909 Raleigh, NC 27695-7909 919 515 7294 919 513.1276 (fax)

URL www ne ncsu edu/NRP/reactor_

program html 27 August 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

NCSU PULSTAR Annual Report Docket No. 50-297 Dear Sir or Madam" In compliance with Section 6.7.4 of the North Carolina State University PULSTAR Technical Specifications, our Nuclear Reactor Program staff has prepared the attached Annual Report for the period 01 July 2001 through 30 June 2002. Please feel free to contact me at (919) 515-4601 if you have any questions or comments.

Sincerely, Gerald D. Wicks Acting Associate Director Nuclear Reactor Program Aoo

PULSTAR REACTOR ANNUAL REPORT TO UNITED STATES NUCLEAR REGULATORY COMMISSION for 01 July 2001 - 30 June 2002 NCSU NUCLEAR REACTOR PROGRAM 27 August 2002

Reference:

PULSTAR Technical Specifications Section 6.7.4 Docket No. 50-297 Department of Nuclear Engineering North Carolina State University Raleigh, North Carolina 27695

Page Two U. S. Nuclear Regulatory Commission Document Control Desk 27 August 2002 Ref: NCSU PULSTAR Annual Report Docket No. 50-297 copy w/attachments:

Dr. Nino A. Masnari, Dean College of Engineering Dr. Jim E. Riviere, Chairman Radiation Safety Committee Dr. Ayman I. Hawari, Chairman Reactor Safety and Audit Committee Dr. Paul J. Turinsky, Head Department of Nuclear Engineering Dr. Ayman I. Hawari, Director Nuclear Reactor Program Mr. David Rainer, Associate Vice Chancellor Environmental Health and Public Safety Ms. Amy C. Orders Radiation Safety Officer Mr. Stephen J. Bilyj Reactor Operations Manager Mr. Mark Poirier ANIIMAELU Mr. Daniel Hughes Nuclear Regulatory Commission Mr. Craig Bassett Nuclear Regulatory Commission

DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT DOCKET NUMBER 50-297 For the Period: 01 July 2001 - 30 June 2002 The following report is submitted in accordance with Section 6.7.4 of the PULSTAR Technical Specifications:

6.7.4.a Brief Summary:

Reactor operations have been routine during this reporting period. Due to the events of 11 September, public access to the facility has been greatly restricted. The position of the Director of the Nuclear Reactor Program was filled in January 2002. The Reactor Health Physicist is still serving as the interim Associate Director. A personnel search is currently under way for the replacement for the Associate Director position. A staff member received his senior operator license in June 2002. One part-time reactor operator also received her license at the same time.

(i) (1) Reactor Operating Experience:

The NCSU PULSTAR Reactor has been utilized for the following:

S Teaching and Short Courses 80.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> S Faculty and Graduate Student Research 372.7 S Isotope Production 30.8 S Neutron Activation Analysis 788.8 S Beam Tube and Irradiation Facilities 26.7 S Nuclear Training (Utilities) 0.0 S PULSTAR Reactor Training 105.5 S Reactor Cal/Measurements & Surveillance 76.3 S Reactor Health Physics Surveillance 24.8 S Reactor Sharing 10.8 TOTAL 1,517.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Last reporting period: 1,428.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (2) A Summary of Experiments Performed in the Reactor:

• Teaching laboratories, short courses, and research reactor thermal power measurements dynamic reactivity measurements axial power and peaking factor measurements (flux mapping) photoneutron effects on power decay after dropped rod

PULSTAR REACTOR ANNUAL REPORT 2 DOCKET NUMBER 50-297 01 July 2001 - 30 June 2002 reactor power determination using photodiode arrays neutron diffusion length in graphite by foil activation neutron fluence and spectral measurements neutron transmutation doping of diamond neutron transmutation doping of silicon in-core detector certification radiation damage determination to fiber optic material Neutron Activation Analysis cereal/grain animal feed food samples fish and laboratory animal tissue human hair and nails (support for forensic work of Medical Examiner's office in a nearby city) urine and excrement sediment/soil water dyes polymers and plastics textiles fly ash crude oil fertilizers silicon crystals dust from World Trade Center (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 Reactbr Safety and Audit Committee (RSAC) performed its annual audit for the facility and determined that all phases of operation and supporting documents were satisfactory.

Health physics surveillance of reactor primary coolant water showed no fission products and that activity is below 10 CFR 20, App. B, Table 3 limits.

6.7.4.b Total Energy Output:

19.4 Megawatt-days Reactor was Critical:

762.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

PULSTAR REACTOR ANNUAL REPORT 3 DOCKET NUMBER 50-297 01 July 2001 - 30 June 2002 Cumulative Total Energy Output Since Initial Criticality:

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

1. Emergency Shutdowns - none

2. Unscheduled Shutdowns - 6

a. July - Shutdown due to dropped rod

b. December - Shutdown due to dropped rod

c. January - SCRAM in response to fire alarm

d. April - SCRAM due to range switching error

e. June - Shutdown due to incorrect compensating voltage

f. June - SCRAM in response to fire alarm Explanation of 2a. above:

A control rod dropped into the core during routine operations. The reactor operator initiated a reactor shutdown to drive the magnets to the down position.

All magnet faces and their respective armatures were cleaned and inspected. The control rod extension was lubricated with a silicone spray. The reactor was returned to routine operation.

Explanation of 2b. above:

A control rod dropped into the core during routine operations. The reactor operator initiated a reactor shutdown to drive the magnets to the down position.

Guide bearings were adjusted on the Regulating Rod and all magnet faces and their respective armatures were cleaned and inspected. The reactor was returned to routine operation.

Explanation of 2c. above:

The reactor operator initiated a Manual SCRAM in response to a building fire alarm. The alarm originated in a machine shop in an area external to the Reactor Building. Fumes from hot cutting oil triggered a smoke sensor.

Explanation of 2d. above:

While performing a routine startup with the Linear Channel on a milliwatt range, a reactor operator trainee started shimming out too close to the autoranging setpoint causing the power indication to exceed 120% of range before the autoranging circuit could change ranges. An automatic SCRAM occurs at 120% of any range on this channel. When performing a reactor startup and power level is near the range change setpoint, trainees as well as reactor operators have been advised to allow the autoranging circuit to change ranges prior to shimming out the control rods.

Explanation of 2e. above:

While performing the second startup of the day two hours after the reactor had been at 90% power for several hours, the second reactor operator set the

PULSTAR REACTOR ANNUAL REPORT 4 DOCKET NUMBER 50-297 01 July 2001 - 30 June 2002 compensating voltage incorrectly (under compensated) for the Intermediate Range (Log N Channel). The value displayed on the readout was approximately 1. IEl watts. It should be 1. IE-1 to 1.3E-1 watts when the compensating voltage is properly set. The reactor operator failed to notice that the minus sign was not present in the display. After several minutes into the startup and while still in the source range, the reactor operator noticed the error and shut down the reactor by Ganged Insert. The compensating voltage was increased until the display read the proper value. A startup was performed and the reactor was returned to routine operation. All reactor operators have been advised to compare the instrument indication with the Log N chart recorder to confirm that proper compensating voltage is set.

Explanation of 2f. above:

The reactor operator initiated a Manual SCRAM in response to a building fire alarm. The alarm originated at a pull station damaged by a contract worker in an area external to the Reactor Building.

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 minor components, are maintained in these files.

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

1. Design Changes (DC)

a. DC 01-1 modifies an existing design of four 2.5 inch diameter rotating vertical irradiation facilities. Two of the four will be replaced with a rectangular sleeve which will allow 4 inch diameter samples to be irradiated.

b. DC 02-1 replaces a nine year old recorder for reactor building radiation monitors with a new paperless recorder by the same manufacturer.

c. DC 02-2 replaces a 30 year old conductivity/resistivity measuring system required for the primary coolant. It also adds a new pH measuring equipment. Installation is pending.

2. Procedure Changes (NP = New Procedure, PC = Procedure Change, MC = Minor Change)

a. NP 02-1 is a new Special Procedure 2.7 "Unplanned Event Notification and Reporting" providing guidance and references for determination if an

PULSTAR REACTOR ANNUAL REPORT 5 DOCKET NUMBER 50-297 01 July2001 - 30 June 2002 unplanned event requires an immediate or special notification and/or report to ensure technical specification reporting requirements are met.

b. NP 02-2 is a new Surveillance Procedure PS-1-12 "Operation and Calibration of Installed Primary Coolant pH and Resistivity Monitoring Channels" providing instruction for the operation and calibration of the pH and resistivity monitoring channels to be installed by DC 02-2 described in 1.c above.

c. NP 02-3 is a new Security Procedure 6 "Heightened Security Levels" which offers guidance for management when security levels are put into effect by the Nuclear Regulatory Commission.

d. PC 10-0 1 was Revision 4 to Special Procedure 9.2 for the "Installation and Removal of Experimental Facilities, Vertical Exposure Ports (VEPs)"

implementing changes required by DC 01-1 described in L.a above.

e. PC 1-02 was Revision I to Special Procedure 5.10 "Primary Water Inventory" implementing trending measurements, dose assessment, and notification and actions associated with detectable net unaccounted primary coolant water losses.

f. MC 02-1 updated the implementing Emergency Procedure 1 "Emergency Plan Activation, Response, and Actions" for the PULSTAR Emergency Plan with current names and telephone numbers for callout list as well as organizational names. Also, typographical errors were corrected.

g. MC 02-2 was Revision 31 the PULSTAR Operations Manual providing updated checklist steps for the new Radiation Monitoring recorder installed by DC 02-1 described in 1.b above.

h. MC 02-3 was Revision 2 to Special Procedure 5.10 "Primary Water Inventory" making data entry more intuitive on the approved spreadsheet.

i. MC 02-4 was Revision 4 for Surveillance Procedure PS-17-6-1:A1 "Area Radiation Monitoring Channel Calibration" providing updated calibration steps required for the new Radiation Monitoring recorder installed by DC 02-1 described in 1.b above.

j. MC 02-5 was Revision 4 for Surveillance Procedure PS-17-6-2:A1 "Process Radiation Monitoring Channel Calibration" providing updated calibration steps required for the new Radiation Monitoring recorder installed by DC 02-1 described in 1.b above.

Summary:

Procedures were written or revised covering the calibration of installed equipment, reactor operations, surveillance, and Health Physics. These procedures have been

PULSTAR REACTOR ANNUAL REPORT 6 DOCKET NUMBER 50-297 01 July 2001 - 30 June 2002 reviewed and/or approved by the Reactor Safety and Audit Committee (RSAC) and where required, approved by the Radiation Safety Committee (RSC).

6.7.4.f Radioactive Effluent:

1. Liquid Waste (summarized by quarters)

i. Radioactivity Released During the Reporting Period:

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

No. of Total Tot. Vol. Diluent Tritium Period Batches [iCi Liters Liters [10 01 Jul - 30 Sep 01 1 13 3,420 3.0E4 9 01 Oct - 31 Dec 01 0 0 0 0 0 01 Jan - 31 Mar 02 0 0 0 0 0 01 Apr - 30 Jun 02 2 61 6,200 6.0E4 55 (6) 64 p.Ci of tritium was released during this reporting period.

(7) 74 iiCi total activity was released during this reporting period.

ii. Identification of Fission and Activation Products:

The gross beta-gamma activity of the batches in (1) above were less than 2 x 10' [lCi/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 20 for release to the sanitary sewer.

2. Gaseous Waste (summarized monthly)

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

(1) Gases:

Total Time Year Period In Hours Curies 2001 01 Jul- 31 Jul 744 0.281 01 Aug- 31 Aug 744 0.092 01 Sep - 30 Sep 720 0.202 on gross beta activity only. Tritium did not requirefurther dihltion.

PULSTAR REACTOR ANNUAL REPORT 7 DOCKET NUMBER 50-297 01 July 2001 - 30 June 2002 01 Oct- 31 Oct 744 0.153 01 Nov - 30 Nov 720 0.129 01 Dec - 31 Dec 744 0.165 2002 01 Jan-31 Jan 744 0.099 01 Feb - 28 Feb 672 0.407 01 Mar- 31 Mar 744 0.294 01 Apr- 30 Apr 720 0.064 01 May - 31 May 744 0.281 01 Jun - 30 Jun 720 0.588 Totals 8,760 hours0.0088 days <br />0.211 hours <br />0.00126 weeks <br />2.8918e-4 months <br /> 2.755 curies (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 t,,2 >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 release was 2.755 curies.

The yearly average concentration of argon-41 released from the PULSTAR reactor facility exhaust stack during this period was 8.2x10. I.Ci/cc. This is below the regulatory limit of Ix 1 0 - i.Ci/cc given in 10 CFR 20 Appendix B. Dose calculations were performed using the "COMPLY" code for the fiscal year. "COMPLY" code results were less than the 10 mrem constraint level given in 10 CFR 20.

(2) Particulates:

See gaseous waste i.(2) above.

3. Solid Waste from Reactor'

"* Total volume of solid waste - 10 ft3 (0.28 M3)

"* Total activity of solid waste - 0.06 mCi

"* Dates of shipments and disposal - All waste is transferred to the NCSU Environmental Health and Safety Center for temporary storage and disposal under the NCSU state license. Transfers were made on 09 Mar 02.

2 Solidwaste generatedby the PULSTAR Reactor is transferredto the NCSU RadiationSafety Divisionfor storage or disposal.

PULSTAR REACTOR ANNUAL REPORT 8 DOCKET NUMBER 50-297 01 July 2001 - 30 June 2002 6.7.4.g Personnel Radiation Exposure Report:

Twenty individuals were monitored for external radiation doke during the reporting period. Collective dose for this reporting period was 0.950 person-rem. Individual doses ranged from 0.001 to 0.080 rem with an average of 0.048 rem. No visitors required official monitoring during this reporting period.

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

Radiation and contamination surveys performed within the facility by the PULSTAR staff indicated that:

"* external radiation levels in the majority of areas were 2 mrem/h or less

"* external radiation levels in the remaining areas were 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:

See Attachment A prepared by the Radiation Safety Division of the Environmental Health and Safety Center at the end of this document.

Perimeter surveys were performed adjacent to the Reactor Building by the PULSTAR staff and indicated that:

"* external radiation levels were at background levels for most areas (10 prem/h)

"* contamination was not detectable

"* Net external radiation levels ranged up to 40 prem/h in some areas when the reactor was operating at power. However, external radiation levels were at background levels in routinely occupied spaces.

ATTACHMENT A PULSTAR REACTOR ENVIRONMENTAL RADIATION SURVEILLANCE REPORT FOR THE PERIOD JULY 1, 2001 - JUNE 30, 2002 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 Aerially Transported Gamma Activity (LLD Values) 4 Figures 2a-2e Airborne Gross Beta Activities 5-9 Table 2.3 Regulatory Limits, Alert Levels and Background Levels for Airborne Radioactivity 10

3. MILK Tables 3.1A & 3.1B 1-131 in Cow's Milk 11

4. SURFACE WATER Table 4.1 Gross Alpha and Beta Activity in Surface Water 12 Table 4.2 LLD Values for Gamma Emitters in Surface Water 13

5. VEGETATION Tables 5.1A & 5.1B Gross Beta Activity in Campus Vegetation 14 Table 5.2 LLD Values for Gamma Emitters in Vegetation 15

6. THERMOLUMINESCENT DOSIMETERS 16 Table 6.1 Environmental TLD Exposures 17

7. QUALITY CONTROL INTERCOMPARISON PROGRAM 18 Tables 7.1a - 7.1d 19-22

8. CONCLUSIONS 23 APPENDIX 1 24-28 APPENDIX 2 29

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.

In November 2000 a member of the Radiation Safety Committee, Professor David DeMaster, performed an audit of the environmental sampling program and provided comments/suggestions regarding this program and the annual report. In response, the following actions have been taken and are reflected in this report:

1) A revised value for the "Average NC Gross Beta Activity Background Level" has been obtained from the State of North Carolina Division of Radiation Protection and included in this report in Table 2.3.

2) Specific activity data for 1-131 in milk from the alternate year analysis will be included in each annual report for comparison with current year data.

3) Specific activity data for vegetation from the alternate year analysis will be included in each annual report for comparison with current year data.

4) The anomaly of higher TLD exposures at D.H. Hill Library was investigated for the possibility that it may be the result of radon daughter products. A passive radon detector was placed at this site and integrated for a seven-month exposure.

5) A wind rose has been included in Appendix 2 to show the wind field distribution expected in the vicinity of the reactor facility. Historical wind data for the RDU Airport Station # 13722 is provided since the NCSU campus meteorological data was not available at the time of this report.

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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 Gamma N.E. Continuous Continuous 10 CFR 20 T.S. 6.7.4 Stack Particles Gross Beta N.E. Monthly Monthly 10 CFR 20 Indiv. Gamma N.E. T.S. 6.7.4 Emitters Water from Gross Beta N.E. Prior to Prior to Discharge 10 CFR 20 Reactor Gross Gamma N.E. Discharge - Monthly T.S. 6.7.4 Facility Tritium N.E. (~ Monthly) City of Raleigh Ordinance Air/Particles at Gross Beta RSD/EHSC Weekly Quarterly 10 CFR 20 5 Campus Indiv. Gamma RSD/EHSC Weekly 10 CFR 20 Stations* Emitters Air/Dosage at 8 TLD Dosimeter RSD/EHSC Quarterly Quarterly 10 CFR 20 Campus Stations+

Surface Water Gross Beta RSD/EHSC Quarterly Quarterly NCSU Rocky Branch Indiv. Gamma RSD/EHSC Quarterly Quarterly NCSU Creek Emitters Vegetation Gross Beta RSD/EHSC Semi-annually Alternate years NCSU NCSU Campus Gamma RSD/EHSC Alternate years NCSU Milk 1-131 RSD/EHSC Monthly Alternate years NCSU Local Dairy I I I Abbreviations Used in Table:

N.E. = Nuclear Engineering/Reactor Facility; RSD/EHSC = Radiation Safety Division.

• These 5 stations include:

Withers, Riddick, Broughton, Hill Library and Environmental Health & Safety Center.

+These 8 stations include: the PULSTAR stack, a control station (EHSC) and the 5 air sampling stations, and North Hall.

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2. AIR MONITORING (TABLES 2.1,2.2, AND 2.3; FIGURES 2a THROUGH 2e)

Air monitoring is performed continually for one week during each of four (4) quarters during the year. The data shows the normal fluctuations in gross beta activity levels expected during the year. Figures 2a through 2e show bar graphs of gross beta activity (fCi/cubic meter vs. sampling quarters per year). The highest gross beta activity observed was 19.9 fCiM-3 at the Environmental Health & Safety Center station during the week of 08/14/01 to 08/21/01. The annual campus average was 11.4 fCiM- 3 .

Table 2.2 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 2.3 lists regulatory limits, alert levels, and average background levels for airborne radioactivity.

A passive track-etch detector was placed at the D.H. Hill Library station during the period 05/10/01 to 12/12/01 to determine if some previously higher dosimeter exposures were attributable to radon gas. The detector analysis provided by Key Technology Inc. indicated an average radon level of 0.9 pCi/liter during the period.

The average radon level in U.S. homes is reported to be - 1.3 pCi/liter.

TABLE 2.1 LOCATION OF AIR MONITORING STATIONS DIRECTION1 DISTANCE 2 ELEVATION 3 SITE (meters) (meters)

BROUGHTON SOUTHWEST 125 -17

• DAVID CLARK LABS WEST 500 -18 LIBRARY NORTHWEST 192 +11 RIDDICK SOUTHEAST 99 -14 WITHERS NORTHEAST 82 -6 EH & S CENTER WEST 1230 -3 NORTH HALL NORTHEAST 402 -4

'DIRECTION - DIRECTION FROM REACTOR STACK 2 DISTANCE - DISTANCE FROM REACTOR STACK 3 ELEVATION - ELEVATION RELATIVE TO THE TOP OF THE REACTOR STACK

• The station at David Clark Labs was relocated to the EH & S Center in January 1996, however a TLD monitor is maintained at David Clark Labs for the State of N.C. Division of Radiation Protection.

A wind rose is included in Appendix 2 to indicate the prevailing wind direction trends for the years 1961-1990.

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Table 2.2 Aerially Transported Gamma Activity LLD values fCVcubic meter NUCLIDES SAMPLING PERIOD Co-57 Co-60 Nb-95 Zr-95 Ru-103 Ru-106 Cs-137 Ce-1 41 Ce-144 2001 08/14 - 08/21 0.21 0.44 0.29 0.46 0.27 2.25 0.33 0.36 1.21 11/01 - 11/08 0.21 0.44 0.28 0.48 0.28 2.48 0.35 0.34 1.28 2002 02/22-02/28 0.17 0.37 0.32 0.53 0.32 2.49 0.23 0.42 1.42 05/13-05/20 0.17 0.31 0.31 0.51 0.36 2.43 0.26 0.38 1.41

Broughton Hall Airborne Gross Beta Acitivity Figure 2a 25 20 0 V22 - 02/28 05/13 - 05/20 S15 2002 2002 E 08/14 - 08/21 o2 2001 11/01 - 11/08 S10 2001 5 ./

05 - --- -I0-000 2 3 4 Monitoring Period

Withers Hall Airborne Gross Beta Activity Figure 2b 25 20 08/14 - 08/21 11/01 - 11/08 15 2001 2001 02/22 - 02/28 2002 10- 05/13- 05/20 2002 50 12 3 4 Monitoring Period

D. H. Hill Library Airborne Gross Beta Activity Figure 2d 25 20 05/13 - 05/20 2002 15 11/01 - 11/08 02/22 - 02/28 2002 E 2001

~10-p 08/14 - 08/21 2001 0*

2 3 4 Monitoring period

Environmental Health & Safety Center Airborne Gross Beta Activity Figure 2e 25 08/14 - 08/21 2001 20 05/13- 05/20 S15 2002 0, E

o 11/01 - 11/08 2001 02/22 - 02/28 2002 5

0- -10 0I-------

2 3 4 Monitoring Period

TABLE 2.3 REGULATORY LIMITS, ALERT LEVELS, AND BACKGROUND LEVELS FOR AIRBORNE RADIOACTIVITY (fCi M-3 ).

REGULATORY ALERT AVERAGE N.C.

NUCLIDE LIMIT LEVEL BACKGROUND LEVEL GROSS ALPHA 20 10 4 GROSS BETA* 1000 500 14.7 ; 3.1" Cs-1 37 5 X 105 10 2 Ce-1 44 2 X 105 100 0 Ru-1 06 2 X 105 30 0 1-131 1 X 105 10 0

• These data represent a range of annual average values measured in North Carolina.

Data courtesy of Dale Dusenbury of the N.C. Division of Radiation Protection.

Reference:

Environmental Radiation Surveillance Report 1986-88, State of N.C. Radiation Protection Section 10

3. MILK (TABLES 3.1A and 3.1B)

Milk samples are collected in alternate years from the Campus Creamery and the Lake Wheeler Road Dairy and analyzed for 1-131. Data given for the years 2001 and 1999 shows that no 1-131 activity was detected. The next sample collection will be in 2003.

TABLE 3.1A 1-131 IN COW'S MILK (pCi Liter' +/- 2 a) LLD - 3 pCi Liter" pCi Liter' DATE Campus Creamery Lake Wheeler May 2001 <3 TABLE 3.1B 1-131 IN COW'S MILK (pCi Liter'"+/-2 a) LLD - 3 pCi Liter' pCi Liter -1 DATE Campus Creamery Lake Wheeler April 1999 <3 <3 11

4. SURFACE WATER (TABLES 4.1 AND 4.2)

Table 4.1 gives the gross aloha and beta activities for water from Rocky Branch at points where it enters (ON) and exits (OFF) the campus. The LLD value for gross alpha and beta activities is 0.4 pCi Liter'. For gross alpha activity the Alert Level is 5 pCi Liter' and the Regulatory Limit is 15 pCi Liter 1 . For gross beta activity the Alert Level is 5 pCi Liter' and the Regulatory Limit is 50 pCi Liter'. Samples with gross alpha or beta activities exceeding these Alert Levels would require gamma analysis to identify the radionuclides present. 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'"+/- 20)

• LLDa - 0.4 pCi Liter' LLD, - 0.4 pCi Liter' pCi Liter' GROSS GROSS DATE LOCATION ALPHA BETA THIRD QUARTER 2001 ON <0.4 3.3+/-0.7 OFF 1.6 +/- 0.5 2.9 +/- 0.7 FOURTH QUARTER 2001 ON < 0.4 2.6 +/- 0.7 OFF < 0.4 2.4 +/- 0.7 FIRST QUARTER 2002 ON < 0.4 2.8+0.7 OFF < 0.4 2.6+0.7 SECOND QUARTER 2002 ON 2.6+0.6 10.4+1.0 OFF 3.6+0.4 10.7+1.0 12

TABLE 4.2 LLD VALUES FOR GAMMA EMITTERS IN SURFACE WATER NUCLIDE LLD (pCi Liter')

Co-60 0.4 Zn-65 0.7 Cs-137 0.3 Cs-134 0.4 Sr-85 0.4 Ru-1 03 0.3 Ru-1 06 3.0 Nb-95 0.4 Zr-95 0.5 13

5. VEGETATION (TABLE 5.1A, 5.1B AND 5.2)

Tables 5.1A and 5.1B give 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 in alternate years. The data given is for the years 2001 and 1999 for comparison. All the results are consistent with the presence of naturally-occurring radionuclides and none of the gamma emitters listed in Table 5.2 were detected. The next sample collection will be in 2003.

TABLE 5.1A GROSS BETA ACTIVITY IN CAMPUS VEGETATION

• LLD - 0.5 pCi g-1 SAMPLE DATE SAMPLE LOCATION (pCi g-' +/- 2a) 05/03/2001 NORTH CAMPUS 10.7+/-0.5 05/03/2001 SOUTH CAMPUS 5.0 +/- 0.4 05/03/2001 EAST CAMPUS 12.7+/-0.6 05/03/2001 WEST CAMPUS 7.4 +/- 0.5 TABLE 5.1B GROSS BETA ACTIVITY IN CAMPUS VEGETATION

• LLD - 0.5 pCi g.1 SAMPLE DATE SAMPLE LOCATION (pCi g-1 +/- 2o) 04/15/1999 NORTH CAMPUS 2.3 +/-0.1 04/15/1999 SOUTH CAMPUS 2.6 +/- 0.1 04/15/1999 EAST CAMPUS 2.5 +/-0.1 04/15/1999 WEST CAMPUS 2.6 +/-0.1 14

TABLE 5.2 LLD VALUES FOR GAMMA EMITTERS IN VEGETATION NUCLIDE LLD (pCi gram')

Co-60 0.01 Zn-65 0.02 Cs-1 37 0.01 Cs-1 34 0.01 Sr-85 0.01 Ru-1 03 0.01 Nb-95 0.01 Zr-95 0.02 15

6. THERMOLUMINESCENT DOSIMETERS (TLDs) (TABLE 6.1)

TLD analysis is contracted to Landauer, Inc. for determination of ambient gamma exposures.

Exposures are integrated over a three-month period at each of the five air monitor stations listed in Table 2.1 and inside the PULSTAR Reactor stack and at North Hall. A control station is located in Room 107 of the Environmental Health & Safety Center. Table 6.1 gives the data for these eight (8) locations.

The exposures (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 millirems for beta radiations) are reported by the contract vendor with the designation "M ".

Historically, dosimeter readings for D.H. Hill Library monitoring station have often been higher than those for the other campus stations. Pursuant to a recommendation made in the "NCSU PULSTAR 2001 Annual Self Assessment", two additional TLDs have been added to the D.H. Hill Library station to supplement the existing dosimeter. These two additional dosimeters will become a routine part of the quarterly monitoring schedule.

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TABLE 6.1 ENVIRONMENTAL TLD EXPOSURES (mrem/QUARTER YEAR)

DATE WITHERS RIDDICK BROUGHTON DH HILL EH&S PULSTAR STACK NORTH CONTROL 2001 07/01-09/30 M 6 M 11 2 1 M M,M 10/01-12/31 M 7 M 12 5 5 M M,M 2002 01/01-03/31 2 2 M 6 M M M M,M 04/01-06/30 M 10 2 9 M 6 M M,2 04/15-06/30 3*

• The entry for D.H. Hill during the period 04/15/02 to 06/30/02 reflects an additional dosimeter reading for that station.

The third dosimeter could not be found and had app arently been vandalized.

The 'CONTROL" column indicates the use of multiple control dosimeters for four of the monitoring quarters.

"1"hc dA~inn~tinn NM" i.s useid by the contract vendor tor renornlna aose eu:uivaienis DelOW Inc minimurmiiurii[IabUdI u~ lUI~uy which is 1 millirem for gamma radiation and 10 millirem for beta radiation] r--4

7. QUALITY CONTROL INTERCOMPARISON PROGRAM The Environmental Radiation Surveillance Laboratory (ERSL) of the Radiation Safety Division has analyzed samples provided by the U.S. DOE Environmental Measurements Laboratory Quality Assurance Division Program (QAP 55) 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 'EML value' listed in the Tables 7.1 (a-d) to which the ERSL results are compared is the mean of replicate determinations for each nuclide. The EML uncertainty is the standard error of the mean.

All other uncertainties are as reported by the participants.

The control limit was established from percentiles of historic data distributions -(1982-1992). The evaluation of historic data and the development of the control limits are presented in DOE report EML 564. The control limits for QAP 55 were developed from the percentiles of data distributions for the years 1993-1999.

Participants' analytical performance is evaluated based on the historical analytical capabilities for individual analyte/matrix pairs. The criteria for acceptable performance, "A", has been chosen to be between the 15" and 85th percentile of the cumulative normalized distribution, which can be viewed as the middle 70% of all historic measurements. The acceptable with warning criteria, 'W", is between the 5" and 15u' percentile and between the 85th and 95t percentile. In other words, the middle 90%

of all reported values are acceptable, while the outer 5 t-h1 5 th (10%) and 85th-95" percentiles (10%) are in the warning area. The not acceptable criteria, "N", is established at less than the 5" percentile and greater than the 95t" percentile, that is, the outer 10% of the historical data.

The following are recommended performance criteria for analysis of environmental levels of analytes:

Acceptable: Lower Middle Limit < A < Upper Middle Limit Acceptable with Warning: Lower Limit < W < Lower Middle Limit or Upper Middle Limit < W < Upper Limit Not Acceptable: N < Lower Limit or N > Upper Limit Control Limits are reported as the ratio of Reported Value vs. EML Value. The results of the intercomparison studies are given in Table 7.1 (a-d), and are stated in the SI unit becquerel (Bq) as required by the EML reporting protocol.

In addition to the EML Quality Assurance Program, the ERSL conducts an intralaboratory QOC program to track the performance of routine radioactivity measurements. The types of calculations employed for this program are shown in an example calculation in Appendix 1.

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TABLE 7.1a GROSS ALPHA & BETA ACTIVITY AIR FILTER--INTERCOMPARISON STUDY 01 September 2001 The sample consists of one 50 mm diameter simulated filter spiked with a matrix-free solution containing a single alpha and a single beta emitting nuclide. The reported values and the known values are given in Bq/filter.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide *Reported *Reported EML EML Error Reported Value Error Value EML Gross Alpha 4.973 0.188 5.362 0.536 0.927 Gross Beta 10.416 0.543 12.770 1.277 0.816 QAP 55 Statistical Summary Radionuclide EML EML Mean Median Std. Dev. No. Of Reported Value Error Values Gross Alpha 5.362 0.536 1.014 0.908 0.160 83 Gross Beta 12.770 1.277 0.908 0.903 0.077 78 ValueA QAP 55 Control Limits by Matrix Radionuclide Lower Limit Lower Middle Upper Middle Upper Limit Limit Limit

-7'4 Gross Alpha U.b( U.U;4 1.Z2 0.76 0.88 1.29 1.52 Gross Beta Control Limits are reported as: the ratio of Reported Value vs. EML Value 19

TABLE 7.1b MULTINUCLIDE AIR FILTER - INTERCOMPARISON STUDY 01 September 2001 The sample consists of one 7 cm diameter glass fiber filter which has been spiked with 0.10 gram of solution and dried. The reported values and the known values are given in Bq/filter.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide *Reported *Reported EML EML Error Reported Value Error Value EML Cs134 12.240 0.330 12.950 0.362 0.945 Co60 16.790 0.520 17.500 0.470 0.959 Cs137 18.060 0.880 17.100 0.580 1.056 Mn54 85.360 3.410 81.150 4.760 1.052 QAP 55 Statistical Summary Radionuclide EML EML Mean Median Std. Dev. No. Of Reported Value Error Values Cs134 12.950 0.362 0.976 1.001 0.103 126 Co60 17.500 0.470 1.019 1.017 0.076 136 Cs137 17.100 0.580 1.069 1.061 0.086 133 Mn54 81.150 4.760 1.074 1.059 0.097 128 QAP 55 Control Limits by Matrix Radionuclide Lower Limit Lower Middle Upper Middle Upper Limit Limit Limit Cs134 0.74 0.82 1.10 1.21 Co60 0.79 0.87 1.13 1.30 Cs137 0.78 0.88 1.16 1.35 Mn54 0.80 0.89 1.20 1.36 Control Limits are reported as: the ratio of Reported Value vs. EML Value 20

TABLE 7.1c MULTINUCLIDE WATER SAMPLE - INTERCOMPARISON STUDY 01 September 2001 The sample consists of a spiked, 455 mL aliquot of acidified water (-1 N HCI). The reported values and the known values are given in Bq/Liter.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide *Reported *Reported EML EML Error Reported VRI UA Error Value Or=M Valu Error~ Value Co60 211.717 6.13U ZUU.UUU I.46U I.9I4 2.711 45.133 2.467 0.984 Cs137 44.421 QAP 55 Statistical Summary Radionuclide EML EML Mean Median Std. Dev. No. Of Reported M

VaI W Ia IUi Co60 209.000 7.590 1.000 1.000 0.054 136 Cs137 45.133 2.467 1.041 1.041 0.058 135 QAP 55 Control Limits by Matrix Radionuclide Lower Limit Lower Middle Upper Middle Upper Limit Limit Limit Co60 0.80 0.90 1.1z 0.90 1.15 1.24 Cs137 0.80 Control limits are reported as: the ratio of Reported Value vs. EML Value 21

TABLE 7.1d GROSS ALPHA AND BETA WATER SAMPLE - INTERCOMPARISON STUDY 01 September 2001 The sample consists of a 4 mL aliquot of -1 N HCI matrix free solution. The reported values and the known values are given in Bq/Liter.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide *Reported *Reported EML EML Error Reported Value Error Value Gross Alpha 1139.190 125.840 1150.000 115.000 0.991 Gross Beta 7397.050 718.630 7970.000 800.000 0.928 QAP 55 Statistical Summary Radionuclide EML EML Mean Median Std. Dev. No. Of Reported Valnna I=rrnr Values Gross Alpha 1150.000 115.000 0.982 1.000 0.137 73 Gross Beta 7970.000 800.000 0.961 0.951 0.105 82 QAP 55 Control Limits by Matrix Radionuclide Lower Limit Lower Middle Upper Middle Upper Limit Limit Limit Gross Alpha 0.58 0.79 1.12 1.26 Gross Beta 0.56 0.75 1.33 1.50 Control limits are reported as: the ratio of Reported Value vs. EML Value 22

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.

23

APPENDIX 1 The following example calculation gives a set of data, the mean value, the experimental sigma, and the range. These statistics provide measures of the central tendency and dispersion of the data.

The normalized range is computed by first finding mean range, R, the control limit, CL, and the standard error of the range, OR. The normalized range measures the dispersion of the data (precision) in such a form that control charts may be used. Control charts allow one to readily compare past analytical performance with present performance. In the example, the normalized range equals 0.3 which is less than 3 which is the upper control level. The precision of the results is acceptable.

The normalized deviation is calculated by computing the deviation and the standard error of the mean, am. The normalized deviation allows one to measure central tendency (accuracy) readily through the use of control charts. Trends in analytical accuracy can be determined in this manner.

For this example, the normalized deviation is -0.7 which falls between +2 and -2 which are the upper and lower warning levels. The accuracy of the data is acceptable. Any bias in methodology or instrumentation may be indicated by these results.

24

EXAMPLE CALCULATIONS Experimental Data:

Known value = p = 3273 pCi 3HILiter on September 24,1974 Expected laboratory precision = o = 357 pCliuter Sample Result X, 3060 pCi/liter X2 3060 pCi/liter X3 3240 pCi/liter Mean = x H

E 9360 x = x=i 3 3120 pCi/liter N

where N = number of results = 3 Experimental sigma = s s (Xý) 2- i=1

= = N-1 N (3060+3060+3240)2 (3060)2+(3060)2+(3240)2-3

=

2 s 103.9 pCi/liter Range r r = I maximum result - minimum result I r = 13240 - 30601 r = 180 pCi/liter 25

Range Analysis (RNG ANLY)*

Mean range = R R = d 2o where d2** = 1.693 for N = 3

= (1.693) (357)

R = 604.4 pCi/liter Control limit = CL CL = R + 3R

= D 4R where D4** = 2.575 for N = 3

= (2.575) (604.4)

CL = 1556 pCiliter Standard error of the range = OR oan = (R + 3oR - R) + 3

= (D4R-R) + 3

= (1556- 604.4) + 3 OR = 317.2 pCiliter Let Range = r = wR + XOR = 180 pCi/liter Define normalized range = w + x for r>- R, w = 1 then r = wR+xoa = R + xoR r-R or OR r-R therefore w+x = 1 +x = 1 +

aR

• Rosentein, M., and A. S. Goldin, "Statistical Techniques for Quality Control of Environmental Radioassay,"

AQCS Report Stat-1, U.S. Department of Health Education and Welfare, PHS, November 1964.

"**From table "Factors for Computing Control Limits," Handbook of Tables for Probability and Statistics, 2nd Edition, The Chemical Rubber Co., Cleveland, Ohio, 1968, p. 454.

26

for r:5 R, x=0 then r = wR+xoR = wR r

or W=

R r

therefore w+x = w+0 =

R since r < R, (180 < 604.4) 180 W+X=

604.4 w + x= 0.30 Normalized deviation of the mean from the known value = ND Deviation of mean from the known value = D D = x-p

= 3120 - 3273 D = -153 pCi/liter Standard error of the mean = a, a

Or=

VN 357 V/3 a= 206.1 pCi/liter D

ND =

-153 206.1 ND = -0.7 Control limit = CL CL = (p + 30m) 27

Warning limit = WL WL= (i+/- 2o*,)

Experimental sigma (all laboratories) = s 2

N, (*xi) x1= - 1==1N t

st N-I (49345)2 162639133 15 14 st = 149 pCiliter Grand Average = GA N

GA 1=1N 49345 15 GA = 3290 pCiliter Normalized deviation from the grand average = ND' Deviation of the mean from the grand average = D' D' = - GA

= 3120 - 3290 D' = -170 pCi/liter DI NDI a,

-170 206.1 ND' = -0.8 28

Appendix 2 Prevailing Wind Directions At Raleigh-Durham Airport 1961-1990 WINDROSEPLOT COMM*JENTS Station #13722 - RALEIGH/RALEIGH-DURHAM ARPT, NC PLTYEAR.OATETIWM 1961- 1990 I

Jan1- Dec31 Midnight - 11 PM ORIENTATION Direction VIndSpeed(K)

/I DISPLAY .21 Wind Speed 1-21 I / UNrT I I It-is I I Knots I I 7-tO 1 I CALMWINDS I I 827% 4-6 I I AVG WINDSPEED -3 4---

SWEST I EAST 7.25 Knots I I It I \

E

- I 1

8cUre -

WNPWTOtOBILS..Ee$...tAOeh.. .,..eeaI 1 knot = 1.15155 miles per hour Winds are mainly from the SouthWest (225 degrees) with a frequency - 9 %.

• • Wind Rose courtesy of Ryan Boyles of the State Climate Office of North Carolina 29