ML032450038

NCSU Pulstar Annual Report

ML032450038
Person / Time
Site:	North Carolina State University
Issue date:	08/27/2003
From:	Wicks G North Carolina State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML032450038 (39)

Text

P-North Carolina State University is a land-grant university and a constituent institution of The University of North Carolina Nuclear Reactor Program OMMZM

Department of Nuclear Engineering Campus Box 7909 Raleigh. NC 27695-7909 919.515.7294 919.513.1276 (fax)

URLwww.ne.ncsu.edu/NRP/reactor._

program.html 27 August 2003 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 2002 through 30 June 2003. 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

Page Two U. S. Nuclear Regulatory Commission Document Control Desk 27 August 2003 Ref:

NCSU PULSTAR Annual Report Docket No. 50-297 copy w/attachments:

Dr. Nino A. Masnari, Dean College of Engineering Dr. D. Keith Cassel, 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 ANI/MAELU Mr. Daniel Hughes Nuclear Regulatory Commission

DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT DOCKET NUMBER 50-297 For the Period: 01 July 2002 - 30 June 2003 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 mostly routine during this reporting period. During the months of January through March there was a slight increase in unaccounted water loss from the primary cooling system. Actions required by Special Procedure 5.10 "Primary Water Inventory" were followed and reactor operations were not impacted. No official notification was required by the facility license to the NRC. Unaccounted primary water loss rates were not detectable twelve weeks later. Contractors with expertise in locating small leaks have been contacted to provide assistance if needed. One part-time reactor operator received her license in November 2002. The Reactor Health Physicist is currently serving as the interim Associate Director.

(i)

(1) Reactor Operating Experience:

The NCSU PULSTAR Reactor has been utilized for the following:

S 0

0 0

a 0

Teaching and Short Courses Faculty and Graduate Student Research Isotope Production Neutron Activation Analysis Beam Tube and Irradiation Facilities Nuclear Training (Utilities)

PULSTAR Reactor Training Reactor Cal/Measurements, Surveillance & Ops Reactor Health Physics Surveillance Reactor Sharing 192.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 103.9 0.2 473.9 113.7 0.0 30.8 47.5 21.4 70.9 TOTAL 1,055.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Last reporting period:

1,517.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (2) A Summary of Experiments Performed in the Reactor:

a 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

PULSTAR REACTOR ANNUAL REPORT 2

DOCKET NUMBER 50-297 01 July2002 -30 June 2003 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 cereal/grain animal feed food samples fish and laboratory animal tissue human hair and nails urine and excrement sediment/soil/rocks water dyes polymers and plastics textiles crude oil silicon crystals carbon fiber samples recovered from Shuttle Columbia (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.

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:

13.2 Megawatt-days Reactor was Critical:

556.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Cumulative Total Energy Output Since Initial Criticality:

936.1 Megawatt-days

PULSTAR REACTOR ANNUAL REPORT 3

DOCKET NUMBER 50-297 01 July 2002 - 30 June 2003 6.7.4.c Number of Emergency and Unscheduled Shutdowns:

1.

Emergency Shutdowns - none

2.

Unscheduled Shutdowns - none 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:

1.

Design Changes (DC)

a.

DC 02-3 replaces a 30 year old SCRAM logic and magnet power supply.

2.

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

a.

PC 2-02 was Revision 32 to the PULSTAR Operations Manual incorporating changes required by DC 02-3 described in l.a above. Also, typographical errors were corrected.

b.

PC 3-02 was Revision 1 to Security Procedure 6.0.

c.

MC 02-6 was Revision 3 to Special Procedure 5.10 "Primary Water Inventory" making data entry more intuitive on the approved spreadsheet.

d.

MC 02-7 was Revision 8 to Emergency Procedure 2 "Off-site Notification" providing clarification for responsibility when completing forms and updated Authentication Code List.

e.

MC 02-8 was Revision 12 to Emergency Procedure 1 "Emergency Plan Activation, Response, and Action" updating building evacuation notice, alternate Emergency Coordinator and call out list.

f.

MC 03-1 was Revision 33 to the PULSTAR Operations Manual changing the sequence in the preoperational checklist to ensure that certain steps will not be inadvertently missed.

PULSTAR REACTOR ANNUAL REPORT 4

DOCKET NUMBER 50-297 01 July2002 -30 June 2003 Summary:

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

,uCi Liters Liters LCi 01 Jul - 30 Sep 02 0

0 0

0 0

01 Oct - 31 Dec 02 1

9 2,840 1.5E4 7

01 Jan - 31 Mar 03 1

13 3,420 9.92E4 3

01 Apr - 30 Jun 03 3

8 3,120 0

8 (6) 18 pCi of tritium was released during this reporting period.

(7) 30 FLCi 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 10-5 ILCi/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.

'Basedon gross beta activity only. Tritium did not require further dilution.

PULSTAR REACTOR ANNUAL REPORT 5

DOCKET NUMBER 50-297 01 July 2002 - 30 June 2003

2. Gaseous Waste (summarized monthly)

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

(1) Gases:

Total Time Year Period In Hours Curies 2002 01 Jul - 31 Jul 744 0.207 01 Aug-31 Aug 744 0.081 01 Sep - 30 Sep 720 0.139 01 Oct-31 Oct 744 0.069 01 Nov - 30 Nov 720 0.015 01 Dec - 31 Dec 744 0.022 2003 01 Jan-31 Jan 744 0.112 01 Feb - 28 Feb 672 0.147 01 Mar-31 Mar 744 0.133 01 Apr-30 Apr 720 0.169 01 May-31 May 744 0.142 01 Jun - 30 Jun 720 0.029 Totals 8,760 hours0.0088 days <br />0.211 hours <br />0.00126 weeks <br />2.8918e-4 months <br /> 1.265 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 tl12 >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 1.265 curies.

The yearly average concentration of argon-41 released from the PULSTAR reactor facility exhaust stack during this period was 3.8x109 I

Ci/cc. This is below the regulatory limit of Ilx I O'Ci/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 10 CFR 20.

(2) Particulates:

See gaseous waste i.(2) above.

PULSTAR REACTOR ANNUAL REPORT 6

DOCKET NUMBER 50-297 01 July 2002 - 30 June 2003

3. Solid Waste from Reactor2 Total volume of solid waste - 66 ft3 (1.87 m3)

• Total activity of solid waste - 0.25 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 Jul 02 and 17 Jan 03.

6.7.4.g Personnel Radiation Exposure Report:

Twenty-seven individuals were monitored for external radiation dose during the reporting period. Collective dose for this reporting period was 1.374 person-rem.

Individual doses ranged from 0.009 to 0.136 rem with an average of 0.051 rem. No visitors required official monitoring during this reporting period.

6.7.4.h Summar 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 plrem/h) contamination was not detectable Net external radiation levels ranged up to 40 jprem/h in some areas when the reactor was operating at power. However, external radiation levels were at background levels in routinely occupied spaces.

2Solid waste generated by the PULSTAR Reactor is transferred to the NCSU Radiation Safety Division for storage or disposal.

ATTACHMENT A PULSTAR REACTOR ENVIRONMENTAL RADIATION SURVEILLANCE REPORT FOR THE PERIOD JULY 1, 2002 -JUNE 30, 2003 NORTH CAROLINA STATE UNIVERSITY ENVIRONMENTAL HEALTH AND SAFETY CENTER RADIATION SAFETY DIVISION by Ralton J. Harris Environmental Health Physicist

TABLE OF CONTENTS

1.

INTRODUCTION Table 1 Environmental Monitoring Programs for the PULSTAR Reactor

2.

AIR MONITORING Table 2.1 Location of Air Monitoring Stations Table 2.2 Aerially Transported Gamma Activity (LLD Values)

Figures 2a-2e Airborne Gross Beta Activities Table 2.3 Regulatory Limits, Alert Levels and Background Levels for Airborne Radioactivity

3.

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

4.

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

5.

VEGETATION Tables 5.1A Gross Beta Activity in Campus Vegetation Table 5.2 LLD Values for Gamma Emitters in Vegetation

6.

THERMOLUMINESCENT DOSIMETERS Table 6.1 Environmental TLD Exposures

7.

QUALITY CONTROL INTERCOMPARISON PROGRAM Tables 7.1a - 7.1d

8.

CONCLUSIONS APPENDIX I APPENDIX 2 PAGE NO.

I 2

3 3

4 5 - 9 10 11 12 13 14 15 16 17 18 19 -22 23 24 -28 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.

1

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 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.

2

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 21.6 fCiM 3 at the Riddick Hall station during the week of 09/16/02 to 09/23/02. 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' BROUGHTON

• DAVID CLARK LABS LIBRARY RIDDICK WITHERS EH & S CENTER NORTH HALL SOUTHWEST WEST NORTHWEST SOUTHEAST NORTHEAST WEST NORTHEAST DISTANCE2 (meters) 125 500 192 99 82 1230 402 ELEVATION 3 (meters)

-17

-18

+11

-14

-6

-3

-4

'DIRECTION - DIRECTION FROM REACTOR STACK 2DISTANCE - DISTANCE FROM REACTOR STACK 3ELEVATION - 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 1996-2003.

3

Table 2.2 Aerially Transported Gamma Activit LLD values fCi/cubic meter NUCLIDES SAMPLING PERIOD Co-57 Co-60 Nb-95 Zr-95 Ru-103 Ru-106 Cs-137 Ce-141 Ce-144 2002 09/16 - 09/23 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 2003 1

l I

i 02/26-03/04 0.17 0.37 0.32 0.53 0.32 2.49 l

0.23 l

0.42 1.42 06/02-06/08 0.17 0.31 0.31 0.51 0.36 l

2.43 l

0.26 l

0.38 1.41

25 T Broughton Hall Airbome Gross Beta Activity Figure 2a 20+

a-E)

.)

.0 15 +

09/16-09/23 2002 06/02-06/08 2003 un 10 +

11/01-11/08 2002 02/26-0/04 2003 5 +/-

0 -

I I

I 1

2 3

4 Quarters per Year

Withers Hall 25 -

Airbome Gross Beta Activity Figure 2b 02/26-03/04 2003 20 11/01-11/08

~~~~~~~~~~~2002 5X 1

1--111 09/16-09/23

.2 2002 O 10

~~~~~~~~~~~~~~~~~~~~~~~~~~06/

010

~~~~~~~~~~~~~~~~~~~~~~~~20 5

0 I

1 2

3 4

Quarters per Year

Riddick Hall Airbome Gross Beta Activity A "9/23 Figure 2c 2002 06/02-MOB 2003 11/01-11/08 2002 r

02126-=04 2003 I

I i

I

-1 1

2 3

4 Quarters per Year I

D.H. Hill Library 25 Airbome Gross Beta Activity Figure 2d 20 06/0206/08 2003 09/16-09/2'3 02/26-0304 20 2002 2003 a.i 11/01-11/08 E

2002

.)

o 10 -

5 0

I i

1 2

3 4

Quarters per Year

25 -r Environmental Health & Safety Center Airbome Gross Beta Activity 11/01-11/08 Figure 2e 2002 06/02-06/08 2003 20 +

4-20E

.0 0

15 +

02/26-03/04 2003 10 +

09/16-09/23 2002 5 -I 0

I

- I-I

-H 1

2 3

4 Quarters per Year

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

REGULATORY LIMIT ALERT LEVEL AVERAGE N.C.

BACKGROUND LEVEL NUCLIDE GROSS ALPHA GROSS BETA*

Cs-I 37 Ce-144 Ru-1 06 1-131 20 10 4

1000 5 x 10I 2 X 10I 2 X 105 I x l05 500 14.7; 3.1*

10 2

100 0

30 0

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 2003 and 2001 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" DCi Liter-'

DATE Campus Creamery Lake Wheeler

<3 June 2003 TABLE 3.1B 1-131 IN COW'S MILK (pCI Liter" '

2 a) LLD -

3 pCI Liter 4 DCi Liter -'

DATE Campus Creame~

< 3 Lake Wheeler

<3 May 2001 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 Liter1. 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 Liter1'.

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!

• 2o)

• LLD, - 0.4 pCi Liter' LLDp - 0.4 pCi Liter' pCi Liter' GROSS ALPHA DATE THIRD QUARTER 2002 FOURTH QUARTER 2002 FIRST QUARTER 2003 SECOND QUARTER 2003 LOCATION ON OFF ON OFF ON OFF ON OFF GROSS BETA

<0.4

<0.4 2.5 +/- 0.7 2.8 +/- 0.7

<0.4

<0.4 5.1 +/- 0.8 1.5 +/- 0.6 2.2 + 0.5

<0.4 3.2 + 0.7 3.0 + 0.7

<0.4

<0.4 2.8 + 0.7 2.8 + 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 6.1 GROSS BETA ACTMTY IN CAMPUS VEGETATION

• LLD - 0.6 pCi g-'

SAMPLE DATE SAMPLE LOCATION (pCi g-1 +/- 2a) 03/14/2003 03/14/2003 03/14/2003 03/14/2003 NORTH CAMPUS SOUTH CAMPUS EAST CAMPUS WEST CAMPUS 11.1 +/- 0.2 6.7 +/- 0.2 2.4 +/- 0.1 3.0 +/- 0.1 14

TABLE 5.2 LLD VALUES FOR GAMMA EMITTERS IN VEGETATION NUCLIDE LLD (vCi -ram-')

Co-60 0.01 Zn-65 0.02 Cs-1 37 0.01 Cs-1 34 0.01 Sr-85 0.01 Ru-103 0.01 Nb-95 0.01 Zr-95 0.02 15

6.

THERMOLUMINESCENT DOSIMETERS (TLIDs)

(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 quarteryear. 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 UNCSU 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 are a routine part of the quarterly monitoring schedule.

16

TABLE 6.1 ENVIRONMENTAL TLD EXPOSURES (mrem/QUARTER YEAR)

DATE WITHERS RIDDICK BROUGHTON DH HILL* EH&S PULSTAR STACK NORTH CONTROL 2002 07101-09/30 M

M M

M,M,M M

M M

MM 10/01-12/31 M

14 4

13,18,22 9

8 10 M,6 2003 01/01-03/31 M

8 M

9,15,25 3

M M

M,M 04/01-06/30 M

5 M

7,13,13 M

M M

M,2

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

_i The "CONTROL" column indicates the use of dual control dosimeters for all the monitoring periods.

r'-

The designation "M" is used by the contract vendor for reporting dose equivalents below the minimum measurable quantity which is I millirem for gamma radiation and 10 millirem for beta radiation I

I I

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 57) 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 57 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 15n and 85"' percentile of the cumulative normalized distribution, which can be viewed as the middle 70% of all historic measurements. The acceptable with warning criteria, aWn, is between the 5 th and 1 5th percentile and between the 85th and 95th percentile. In other words, the middle 90% of all reported values are acceptable, while the outer 5t-15 (10%) and 85 f-95 g

percentiles (10%) are in the warning area. The not acceptable criteria, 'N", is established at less than the 5t percentile and greater than the 9 5th 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 s 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.

18

TABLE 7.1a GROSS ALPHA & BETA ACTIVITY AIR FILTER--INTERCOMPARISON STUDY 01 September 2002 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 Bqlfilter.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide

• Reported Value

• Reported Error EML Value EML Error Reported Gross Alpha 0.277 0.062 0.287 0.029 0.965 Gross Beta 0.912 0.187 0.871 0.087 1.047 QAP 57 Statistical Summary Radionuclide EML EML Mean Median Std. Dev.

No. Of Reported Value Error Values Gross Alpha 0.287 0.029 1.054 1.025 0.143 88 Gross Beta 0.871 0.087 0.921 0.904 0.099 88 QAP 57 Control Limits by Matrix Radionuclide Lower Limit Lower Middle Upper Middle Upper Limit Limit Limit Gross Alpna Gross Beta U. 14 0.76 U.A4 0.85 1.Z1 1.21 1.43 1.36 Control Limits are reported as: the ratio of Reported Value vs. EML Value 19

TABLE 7.1b MULTINUCLIDE AIR FILTER - INTERCOMPARISON STUDY 01 September 2002 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 Co6O Cs137 Mn54

• Reported Value 33.912 53.429

• Reported Error 1.645 2.216 EML Value 32.500 62.200 EML Error 0.059 0.777 1.170 Reported WEL 1.043 1.024 QAP 57 Statistical Summary Radionuclide EML Value EML Error Mean Median Std. Dev.

No. Of Reported Values Co6O 23.000 0.059 1.014 1.013 0.073 131 Csl 37 32.500 0.777 1.045 1.038 0.095 134 Mn54 52.200 1.170 1.047 1.040 0.103 129 QAP 57 Control Limits by Matrix Radionuclide Lower Limit Lower Middle Upper Middle Upper Limit Limit Limit Co6O Cs137 Mn54 0.80 0.80 0.80 0.90 0.90 0.90 1.11 1.17 1.19 1.26 1.32 1.35 Control Limits are reported as: the ratio of Reported Value vs. EML Value 20

TABLE 7.1c MULTINUCLIDE WATER SAMPLE - INTERCOMPARISON STUDY 01 September 2002 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 BqILiter.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide

• Reported Value

• Reported Error EML Value EML Error Reported EML Co6O Cs137 Cs134 273.998 77.639 56.137 8.614 4.170 2.062 268.670 81.430 60.200 9.710 4.280 1.860 1.020 0.953 0.933 QAP 57 Statistical Summary Radionuclide EML Value EML Error Mean Median Std. Dev.

No. Of Reported Values Co6O 268.670 9.710 1.022 1.021 0.053 145 Cs1 37 81.430 4.280 1.032 1.029 0.055 151 Cs1 34 60.200 1.860 0.977 0.972 0.076 135 QAP 57 Control Limits by Matrix Radionuclide Lower Limit Lower Middle Upper Middle Upper Limit Limit Limit Co6O Cs137 Cs134 0.80 0.80 0.80 0.90 0.90 0.90 1.10 1.12 1.14 1.20 1.22 1.30 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 2002 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/Llter.

• NCSU - ENVIRONMENTAL LABORATORY RESULTS Radionuclide

• Reported Value

• Reported Error EML Value EML Error Reported EML Gross Alpha Gross Beta 207.070 901.840 30.495 210.000 100.555 900.000 21.000 90.000 0.986 1.002 QAP 57 Statistical Summar, Radionuclide EML Value EML Error Mean Median Std. Dev.

No. Of Reported Values Gross Alpha 210.000 21.000 1.032 1.052 0.139 74 Gross Beta 900.000 90.000 0.960 0.944 0.113 92 QAP 57 Control Limits by Matrix Radionuclide Lower Limit Lower Middle Upper Middle Upper Limit Limit Limit Gross Alpha 0.58 0.79 1.13 Gross Beta 0.61 0.81 1.29 Control limits are reported as: the ratio of Reported Value vs. EML Value 1.29 1.43 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 I 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 3H/Liter on September 24, 1974 Expected laboratory precision = a = 357 pCi/liter SamDle Result X1 3060 pCiAiter X2 3060 pCiAiter X3 3240 pCi/iter Mean = x

_E X.,

9360 x

=

X=i

=

3

=

3120 pCiAiter N

where N = number of results = 3 Experimental sigma = s IN~_(X 1

(I Xi) 2 s

=

i)2-_

N-8

~N-1 (3060)2+(3060) 2+ (3240) 2_ (3060+3060+3240) 2 I

~~~~~~~~~~3 s

=

2 s

=

103.9 pCi/liter Range

=

r r

=

I maximum result - minimum result I r

=

13240 - 30601 r

=

180 pCiAiter 25

Range Analysis (RNG ANLY)*

Mean range R

=

R d2a where d2** = 1.693 for N = 3

=

(1.693) (357)

R Control limit CL

=

604.4 pCi/liter

=

CL

=

R+3aR

=

D4R where D4** = 2.575 for N = 3

=

(2.575) (604.4)

CL

=

1556 pCi/liter Standard error of the range

=

CR OR

=

(R + 3aR - R). 3

=

(D4R - R)

• 3

=

(1556 - 604.4) -- 3 YR

=

317.2 pCi/liter Let Range = r = wR + xaR = 180 pCiliter Define normalized range = w + x for r R, w = 1 then r = wR+xaR = R -i-xoR r -oR or x = --------------

aFR therefore w+x = 1 +x = 1 +

CYR

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

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

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

26

for r.R, x= 0 then r = wR+xaR = wR r

or w=

R r

therefore w+x = w+O =

since r < Ft, (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 = -153pCi/liter Standard error of the mean = am a

am =

ON 357 13 Om = 206.1 pCi/liter D

ND =

-153 206.1 ND =-0.7 Control limit = CL CL = (p i 3o,)

27

Warning limit = WL WL = (+/- a2a,)

Experimental sigma (all laboratories) = s st -

N-1 162639133 _ (49345)2 15 14 s,

= 149 pCi/liter Grand Average = GA N

E X 1 GA 1 =1 N

49345 15 GA

3290 pCilliter 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' DI

-170 206.1 ND'

= -0.8 28

Appendix 2 Joint Frequency Distribution Based on Hourly Observations from Raleigh-Durham Airport July 1, 1996 - August 24, 2003 N

W E

10.56 S

e =EZW91 0.1 3

6 12 18 24 Wind Speed (Miles Per Hour)

Calms included at center.

Rings drawn at 5% Intervals.

Wind flow Is FROM the directions shown.

No observations were missing.

Wind Rose Courtesy of Ryan Boyles of the State Climate Office of North Carolina.

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