ML042450066

Ncsu Pulstar Annual Report for Period July 1, 2003 Through June 30, 2004

ML042450066
Person / Time
Site:	North Carolina State University
Issue date:	08/27/2004
From:	Cook A North Carolina State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML042450066 (41)

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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 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 2004 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 2003 through 30 June 2004. Please feel free to contact me at (919) 515-4602 if you have any questions or comments.

Sincerely, Andrew T Cook Associate Director Nuclear Reactor Program 409-0 74 C-)T--)I

U. S. Nuclear Regulatory Commission Document Control Desk 27 August 2004 Ref: NCSU PULSTAR Annual Report Docket No. 50-297 copy w/attachments:

Dr. Nino A. Masnari, Dean College of Engineering Dr. Cynthia Hemenway, Chair Radiation Safety Committee Dr. Ayman I. Hawari, Chair 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. Mark Poirier ANI/MAELU Mr. Daniel Hughes Nuclear Regulatory Commission

NORTH CAROLINA STATE UNIVERSITY PULSTAR REACTOR ANNUAL REPORT TO UNITED STATES NUCLEAR REGULATORY COMMISSION for 01 July 2003 - 30 June 2004 NCSU NUCLEAR REACTOR PROGRAM 27 August 2004

Reference:

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

NORTH CAROLINA STATE UNIVERSITY DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT DOCKET NUMBER 50-297 For the Period: 01 July 2003 - 30 June 2004 The following report 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. The Associate Director position has been filled. After 35 years of service the Reactor Operations Manager retired on December 31 5', 2003. His duties were absorbed by the Associate Director. The Associate Director received a senior reactor operator license in December of 2003.

Five part-time reactor operators received their licenses in May 2004. One reactor operator received a senior reactor operator upgrade in May 2004 i Operating experience Including a summary of experiments performed.

(1) Reactor Operating Experience:

The NCSU PULSTAR Reactor has been utilized for the following:

Teaching and Short Courses 181.6 hours Faculty and Graduate Student Research 88.4 Isotope Production 0.2 Neutron Activation Analysis 340.2 Beam Tube and Irradiation Facilities 249.7 Nuclear Training (Utilities) 0.0 PULSTAR Reactor Training 78.6 Reactor Cal/Measurements, Surveillance & Ops 39.2 Reactor Health Physics Surveillance 19.9 Reactor Sharing 86.2 TOTAL 1084.2 Last reporting period: 1055.2 hours 1 of7

(2) A Summary of Experiments Performed In the Reactor:

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 diffusion length in graphite by foil activation

• Neutron fluence and spectral measurements

• Neutron transmutation doping of silicon

• In-core detector certification

• Radiation damage determination to fiber optic material

• Accelerated lifetime testing for nuclear detectors Neutron Activation Analysis

• Carbon fiber composite samples recovered from Shuttle Columbia

• Crude oil

• Food samples

• Fish tissues

• Laboratory animal tissue

• Human hair, nails, and urine

• Polymers and plastics

• Sediment/soil/rocks

• Silicon crystals

• Textiles

• Water ii Changes In Performance Characteristics Related to Reactor Safety:

None lii 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.

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.

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6.7.4.b Total Energy Output:

19.25 Megawatt-days Reactor was Critical:

772.369 hours0.00427 days <br />0.103 hours <br />6.10119e-4 weeks <br />1.404045e-4 months <br /> Cumulative Total Energy Output Since Initial Criticality:

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

Emergency Shutdowns - none Unscheduled Shutdowns - Five

1. 15-JUL-03: Manual SCRAM due to Fire Alarm. No actual fire, alarm due to contractor working in building. No corrective actions required.

2. 02-OCT-03: Operator error, secured primary pump without reset flow/flapper enabled circuit.

Reviewed procedure with operator.

3. 24-FEB-04: Flow/Flapper - Log N Enable SCRAM. Flapper not fully seated when starting primary pump after pump had been secured. Operator reminded to verify that the flapper is fully closed after evolutions involving the primary pump being secured.

4. 25-FEB-04: Shutdown by GANGED INSERT due to evacuation alarm caused by starting the pneumatic blower after N2 purge gas had ran out. Reviewed alarm bypassing procedure with operator.

5. 08-APR-04: Bumping and dropping of regulating control rod while loading of experiment.

Reactor operator assistant told to be more careful during evolutions on the bridge.

6.7.4.d Corrective and Preventative Maintenance:

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

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

Summary:

Design Changes DC 03-1 Catwalk Modification for Reactor Bay to accommodate a climate controlled modular office.

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Document Changes MC 03-2 Revision 34 of PULSTAR Operations Manual.

MC 03-3 Revision 3 of Health Physics Procedure HP10 Calibration, Operation, and Maintenance of Radiation Survey and Chemistry Instruments.

PC 03-1 Revision 4 of Health Physics Procedure HP1 Radiation Protection Program. Reflects new regulations in 49CFR.

MC 03-4 Revision I of Health Physics Procedure HP4 Radiation Protection Program Self Assessment. Reflects new regulations in 49CFR.

PC-03-5 Revision I of Health Physics Procedure HP6 Transportation of Radioactive and Hazardous Material. Reflects new regulations in 49CFR.

MC 04-1 Revision 13 of Emergency Procedure 1. Update of emergency contact numbers.

PC 04-1 Revision 5 of PS 6-17-2:Al Process Radiation Monitoring Channel Calibration.

Relocation of waste radiation monitoring and a change in the calibration method.

PC 04-2 Revision 5 of Health Physics Procedure HPI Radiation Protection Program to revise ALARA policy statements as requested by American Nuclear Insurers.

PC 04-3 Revision I of Health Physics Procedure HP3 Radiological Surveys. Reworded statements for clarity.

PC 04-4 Revision 2 of Health Physics Procedure HP8 Radiation Work Permit. Updated definitions, changed RWP requirements and reworded statement for clarity.

PC 04-5 Revision 4 of Health Physics Procedure HP10 Calibration, Operation, and Maintenance of Radiation Survey and Chemistry Instruments. Updated definitions, references and reworded statements for clarity.

Other Changes Implementation of Security Plan for Shipment of Hazardous Material per 49CFR172.

Service Water System Modification to make it vendor serviceable.

Fueled Experiments at the PULSTAR Nuclear Reactor. Protocol for performing Fueled experiments as allowed in Technical Specification 3.8.

Installation of the Prototype Positron Facility.

Gamma Irradiation Facility Protocol.

6.7.4.f Radioactive Effluent:

Liquid Waste (summarized by quarters)

i. Radioactivity Released During the Reporting Period:

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

Period Number of Total Total Diluent Tritium Batches pCi Volume Liters pCi Liters 01 JUL - 30 SEP 03 2 27 6840 0 26.8 01 OCT-31 DEC 03 0 0 0 0 0 01 JAN - 31 MAR 04 1 23 3420 0 22.9 01 APR - 30 JUN 04 2 54 5710 212 53.5 4 of 7

(6) 103 pCi of tritium was released during this reporting period.

(7) 104 pCi of total activity was released during this reporting

'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 (1) above were less than 2x1045 pCi/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.

Gaseous Waste (summarized monthly)

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

(1) Gases:

Year Month Total Time Curies Hours 2003 JULY 744 0.030 AUGUST 744 0.073 SEPTEMBER 720 0.223

-OCTOBER 744 0.110 NOVEMBER 720 0.073 DECEMBER 744 0.065 2004 JANUARY 744 0.140 FEBRUARY 696 0.222 MARCH 744 0.312 APRIL 720 0.156 MAY 744 0.138 JUNE 720 0.016 TOTAL 8784 1.558 (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 t1/ 2>8days 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 1.558 curies.

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The yearly average concentration of argon-41 released from the PULSTAR reactor facility exhaust stack during this period was 4.6x10 9 pCi/cc. This is below the regulatory limit of 1xlo08 pCi/cc given in 10 CFR 20 Appendix B. Dose calculations for the fiscal year were performed using the "COMPLY" code with results less than the 10 mrem constraint level given in 10CFR20.

(2) Particulates:

See gaseous waste i.(2) above.

Solid Waste from Reactor' I. Total Volume of Solid Waste Packaged 0 ft3 ii. Total Activity Involved 0.0 Ci iii. Dates of shipments and disposal No shipments were made during this reporting period.

'Solid waste was collected during this reporting period and is being processed for disposal.

6.7.4.g Personnel Radiation Exposure Report:

Twenty-eight individuals were monitored for external radiation dose during the reporting period.

Collective dose for this reporting period was 2.096 person-rem. Individual doses ranged from 0.030 to 0.222 rem with an average of 0.091 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.

6.7.4.1 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.

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

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ATTACHMENT A PULSTAR REACTOR ENVIRONMENTAL RADIATION SURVEILLANCE REPORT FOR THE PERIOD JULY 1, 2003 - JUNE 30, 2004 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 Airbome Radioactivity 10

3. MILK Table 3.1 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 Table 5.1 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.

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Table 1:

Environmental Monitoring Programs for the PULSTAR Reactor at North Carolina State University Sample Activity Conducted Previous Current Basis For Measured By Frequency Frequency Measurement Stack Gross N.E. Continuous Continuous 10 CFR 20 Gases Gamma T.S. 6.7.4 Stack Gross Beta N.E. Monthly Monthly 10 CFR 20 Particles Indiv. N.E. T.S. 6.7.4 Gamma Emitters Water from Gross Beta N.E. Prior to Prior to 10 CFR 20 Reactor Gross N.E. Discharge Discharge T.S. 6.7.4 Facility Gamma N.E. (- Monthly) - Monthly City of Tritium Raleigh Ordinance Air/Particles Gross Beta RSD/EHSC Weekly Quarterly 10 CFR 20 at 5 Indiv. RSD/EHSC Weekly 10 CFR 20 Campus Gamma Stations* Emitters Air/Dosage TLD RSD/EHSC Quarterly Quarterly 10 CFR 20 at 8 Dosimeter Campus Stations+

Surface Gross Beta RSD/EHSC Quarterly Quarterly NCSU Water Indiv. RSD/EHSC Quarterly Quarterly NCSU Rocky Gamma Branch Emitters Creek Vegetation Gross Beta RSD/EHSC Semi- Alternate years NCSU NCSU Gamma RSD/EHSC annually Alternate years NCSU Campus I I I I _I Milk 1-131 RSD/EHSC Monthly Alternate years NCSU Local Dairy 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 25.6 fCiM 3 at the D.H. Hill Library station during the week of 09/02/03 to 09/09/03. The annual campus average was 12.3 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.

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

BROUGHTON SOUTHWEST 125 -17 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 A wind rose is included in Appendix 2 to indicate the prevailing wind direction trends for the years 1996-2003.

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Table 2.2 Aerially Tr nsported Gamma Actisity LLD values fCicubic meter l l 3 NUCLIDES .

SAMPLING PERIOD Co-57 Co-60 Nb-95 Zr-95 Ru-103 Ru-106 Cs-137 Ce-141 Ce-144 2003 09/02 - 09/09 0.21 0.44 0.29 0.46 0.27 2.25 0.33 0.36 1.21 10/02 - 10/09 0.21 0.44 0.28 0.48 0.28 2.48 0.35 0.34 1.28 2004 0.17 0.37 0.32 0.53 0.32 2.49 0.23 0.42 1.42 02/23-03/01 05/03-05/10 0.17 0.31 0.31 0.51 0.36 2.43 0.26 0.38 1.41

Broughton Hall 25 Airborne Gross Beta Activity Figure 2a 20 05/03-05/10 02/23-03/01 2004 2004 h-0 15 Ea uLI 09/02-09/09 2003 Uc 10 10/02-10/09 2003 5

0 1 2 .3 4 Quarters per Year

Withers Hall 25 Airborne Gross Beta Activity Figure 2b 02 20 L-2 15 E

0

.0 1

5 0

1 2 3 4 Quarters per Year

Riddick Hall 25 Airborne Gross Beta Activity Figure 2c 05103-05/10 2004 20 215 E N-C) 09/02-09/09

.0 2003 02/23-03101 10/02-10/09 2004 o 10 2003 5

0 1 2 3 4 Quarters per Year

09/02-09/09 2003 D.H. Hill Library 25 - Airborne Gross Beta Activity Figure 2d 20 - 0 o 15 -

E 10 10/02-10/09 05/03-05/10 2003 02/23-03/01 2004 2004 0 _

1 2 3 4 Quarters per Year

Environmental Health & Safety Center Airborne Gross Beta Activity 25 Fiaure 2e 20

. 15 E

C)

O 10 5

0 1 2 3 4 Quarters per Year

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-137 5 X 105 10 2 Ce-144 2 X 105 100 0 Ru-1 06 2 X 105 30 0 1-131 1 X 109 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 3.1)

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 year 2003 shows that no 1-131 activity was detected. The next sample collection will be in 2005.

TABLE 3.1A 1-131 IN COW'S MILK (pCi Liter"1 2 a) LLD - 3 pCi Liter' PCi Liter-DATE Campus Creamery Lake Wheeler June 2003 <3 <3 11

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) 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'. 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

• 2a)

• LLD, - 0.4 pCi Liter' LLDp - 0.4 pCi Liter' pCi Liter' GROSS GROSS DATE LOCATION ALPHA BETA THIRD QUARTER 2003 ON <0.4 2.6 +/- 0.7 OFF <0.4 2.2 +/- 0.7 FOURTH QUARTER 2003 ON <0.4 3.0 +/- 0.7 OFF <0.4 3.1 +/- 0.7 FIRST QUARTER 2004 ON <0.4 2.9 + 0.7 OFF <0.4 2.9 + 0.7 SECOND QUARTER 2004 ON <0.4 3.9 + 0.7 OFF <0.4 3.6 + 0.7 12

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

Co-60 0.4 Zn-65 0.7 Cs-1 37 0.3 Cs-1 34 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 5.1 & 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 in alternate years.

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 2005.

TABLE 5.1 GROSS BETA ACTIVITY IN CAMPUS VEGETATION

• LLD - 0.5 pCi g4 SAMPLE DATE SAMPLE LOCATION (pCi Q' e 2a) 03/14/2003 NORTH CAMPUS 11.1 +/-0.2 03/14/2003 SOUTH CAMPUS 6.7 + 0.2 03/14/2003 EAST CAMPUS 2.4 +/- 0.1 03/14/2003 WEST CAMPUS 3.0 +/- 0.1 14

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

Co-60 0.01 Zn-65 0.02 Cs-1 37 0.01 Cs-134 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 ". The observed readings are all within the expected range for natural background radiation levels.

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 are included at the D.H. Hill Library station to supplement the existing dosimeter. These two additional dosimeters are 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 2003 07/01-09/30 M 7 3 20,24,23 11 6 5 M,7 10/01-12/31 M 7 5 18,25,14 4 2 5 M,5 2004 01/01-03/31 M 9 6 21,19,21 10 4 8 M,4 04/01-06/30 M 5 M 17,11,7 M M M M,1

• The entries for D.H. Hill are for three (3) independent dosimete readinas for that station.

The *CONTROLM column indicates the use of dual control dosimeters for all the monitoring periods.

Mis used by the contract vendor for reporting dose equivalents below the minimum measurable auantitv I The desigrnation OM which is 1 millirem for gamma radiation and 10 millirem for beta radiation 1 l

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 60) 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 60 were developed from the percentiles of data distributions for the years 1997-2002.

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 15th and 85t percentile of the cumulative normalized distribution, which can be viewed as the middle 70% of all historic measurements. The acceptable with warning criteria, 'WO, is between the 5th and 15' percentile and between the 85th and 95t percentile. In other words, the middle 90% of all reported values are acceptable, while the outer 5T 1 51h (10%) and 8 5mh- 9 5 t percentiles (10%) are in the warning area. The not acceptable criteria, "N", is established at less than the 5't percentile and greater than the 95th 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 QC 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 March 2004 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 1.063 0.111 1.200 0.120 0.886 Gross Beta 2.537 0.257 2.850 0.280 0.890 The Department of Energy's (DOE) Quality Assessment Program (QAP), managed by the Environmental Measurements Laboratory (EML), was terminated after the report for this current performance sample distribution (QAP 60).

The usual statistical summary for all participating laboratories was not supplied.

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TABLE 7.1 b MULTINUCLIDE AIR FILTER - INTERCOMPARISON STUDY 01 March 2004 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 Bqlfilter.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide *Reported *Reported EML EML Error Reported Value Error Value Co6s 36.606 1.25 0.850 17.034 Cs137 28.378 1.729 26.400 0.860 1.075 CsI34 15.423 0.443 18.200 0.402 0.847 The Department of Energy's (DOE) Quality Assessment Program (QAP), managed by the Environmental Measurements Laboratory (EML), was terminated after the report for this current performance sample distribution (QAP 60).

The usual statistical summary for all participating laboratories was not supplied.

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TABLE 7.1 c MULTINUCLIDE WATER SAMPLE - INTERCOMPARISON STUDY 01 March 2004 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 Value Error Value EML Co6O 156.500 5.378 163.200 5.900 0.959 Cs137 48.727 3.494 51.950 2.700 0.938 The Department of Energy's (DOE) Quality Assessment Program (QAP), managed by the Environmental Measurements Laboratory (EML), was terminated after the report for this current performance sample distribution (QAP 60).

The usual statistical summary for all participating laboratories was not supplied.

21 l

TABLE 7.1d GROSS ALPHA AND BETA WATER SAMPLE - INTERCOMPARISON STUDY 01 March 2004 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 EvM=

Gross Alpha 329.233 38.221 326.000 32.000 1.010 Gross Beta 1173.170 76.761 1170.000 117.000 1.003 The Department of Energy's (DOE) Quality Assessment Program (QAP), managed by the Environmental Measurements Laboratory (EML), was terminated after the report for this current performance sample distribution (QAP 60).

The usual statistical summary for all participating laboratories was not supplied.

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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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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, cR. 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.

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EXAMPLE CALCULATIONS Experimental Data:

Known value = p = 3273 pCi 3 HILiter on September 24, 1974 Expected laboratory precision a = 357 pCViiter Sample Result XI 3060 pCi/liter X2 3060 pCi/liter X3 3240 pCi/liter Mean = x N

_ SX19360 x = x=i = 3 = 3120 pCi/liter N

where N number of results = 3 Experimental sigma = s

.. .IN.

s = S N(Xi 2-w)2->N a N-1 (3060) 2+(3060)2+(3240)2_ (3060+3060+3240)2 3

s = 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 = S H = d2o where d2** = 1.693 for N =3

= (1.693) (357)

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

= D4R where D4** = 2.575 for N = 3

= (2.575) (604.4)

CL = 1556 pCi/liter Standard error of the range OR

= (R +3aoR - 3

= (D4 - R) - 3

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

OR r -E therefore w+x = 1 +x = 1 +

OR

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

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

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

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forrsFR, x=0 then r = wR + xa, = wFW r

or =

r therefore w + x = w+0 =

since r < A, (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-"

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

%N 357

/3 am = 206.1 pC/liter D

ND =

am

-153 206.1 ND =-0.7 Control lirriit = CL CL = (p* 3a,)

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Warning limit = WL WL = ( +/- 2oa)

Experimental sigma (all laboratories) s, St 5= I X 2=i

~N-1 162639133 - (49345)2

= 15 14 s, = 149 pCVliter GrandAverage = GA N

E Xi GA N

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

= 3120 - 3290 D'= -170 pCi/liter ND' = D'

-170 206.1 ND' = -0.8

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Joint Frequency Distribution Based on Hourly Observations from Raleigh-Durham Airport July 1, 1996 - August 24, 2003 N

1 W E 10.56 S

0.1 c

CalN 3 8 12 18 24 Calms Included at center.

Rings drawn at 5% Intervals.

Wind flow Is FROM the directions shown.

Wind Speed (Miles Per Hour) No observations were missing.

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