ML20056G084
| ML20056G084 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 06/30/1993 |
| From: | Dudziak D, Mayo C, Perez P North Carolina State University, RALEIGH, NC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20056G085 | List: |
| References | |
| NUDOCS 9309020030 | |
| Download: ML20056G084 (9) | |
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"~M North Carolina State University I e :n g 2
1 Nuclear Reactor Program j Department of Nuclear Engineering l l
Box 7909 )
Raleigh, NC 2"695-7909 (919) 515-2321 FAX (919) 515 5115 31 August 1993 )
l i U.S. Nuclear Regulatory Commission '
l ATTN: Document Control Desk Washington, DC 20555
Subject:
NCSU PULSTAR Annual Report .
Docket No. 50-297 l i
Dear Sir:
In compliance with Section 6.7.5 of the Nonh Carolina State University ;
l PULSTAR Technical Specifications, our Nuclear Reactor Program staff has prepared the l attached Annual Report for the period 01 July 1992 through 30 June 1993. Please feel >
free to contact Mr. Perez at 515-4602 if you have any questions or comments. !
Sincerely,
$>& 6. h l Pedro B. Perez l Associate Director i Nuclear Reactor Program C
Charles W. Mayo N lho -
U
, Donald J. Dudzid l Director, Nuclear Reactor Program Head, Department of Nuclear Engineering PBP/C%Rsb l copy w/ attachments-J l
Director of Regulatory Operations, Region H Mr. Stephen J. Bilyj i U. S. Nuclear Regulatory Commission Reactor Operations Manager Dr. Frederick J. Fuller, Chairman Mr. David Rainer, Director Radiation Protection Committec EnvironmentalIIcalth and Safety Center Dr. James A. Mulholland, Chairman Mr. D. William Morgan Reactor Safeguards Advisory Group Radiation Protection Ofruer Dr. Tildon II. Glisson, Interim Dean Mr. Mark Poirier CoDege of Engincenng ANI/MA11U
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k North Carolina state Unit:ersity is a land-grant university and a constituent institution of The Unit,ersitit of North Carolina.
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DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT For the Period: 01 July 1992 - 30 June 1993 The following report is submitted in accordance with Section 6.7.5 of the PULSTAR Technical Specifications:
6.7.5.a .Brief Sumnuu:X (1) Reactor Operating Exnerience:
The NCSU PULSTAR Reactor has been utilized for the following:
- a. Teaching and Short Courses 134.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> $
- b. Faculty and Graduate Student Research 766.0
- c. Neutron Activation Analysis 1,257.0
- d. Beam Tube Facilities 15.2
- e. Nuclear Training (Utilities) 334.7
- f. PULSTAR Reactor Training 33.1
- g. Reactor Cal / Measurements & Surveillance 104.0
- h. Reactor Health Physics Surveillance 13.2
- i. Reactor Sharing 7.0 TOTAL 2,664.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Same reporting period 1991-1992 2,716.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A cross section of exneriments performed in the reactor include:
- a. Neutron Activation Analysis of filters, animal tissue, bone, protein ,
solutions, hair, sediments / soil, rain / river water, vegetation, wood pulp, dyes, paper, electronic components, fibers, glass, plastics, resins, quartz, coal, fly ash, graphite, steel, etc.
- b. Reactor thermal power measurements for teaching laboratories.
- c. Neutron diffusion length measurements in grapliite.
- d. Neutron Radiography of B 4C absorber rods and carbon cloth. l
- e. Prompt gamma analysis of silicon wafers. l
- e. Neutron fluence and spectral measurements.
- f. Excess reactivity measurements using a beryllium reflector.
- g. Excess reactivity measurements replacing eight original fuel assemblies with new fuel. ,
- h. Transmutation of silicon for semiconductor research. !
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- PUISrAR REACroR ANNUAL REPORT 2 !
01 July 1992 - 33 June 1993 (2) fhanges in Performance Characteristics Related to Reactor Safety:
None (3) Results of Surveillance. Tests. and Inspections:
l The reactor surveillance program has revealed no significant nor l unexpected trends in reactor systcnis performance during this report l period.
6.7.5.b Total Enercy Output:
798.4 Megawatt hours 33.3 Megawatt days l I
Pulse Operations:
None l Reactor was Critical:
l 1,051.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Cumulative Total Enerev Output since Initial Criticality:
18,464.9 Megawatt hours 739.4 Megawatt days 6.7.5.c Number of Emergency and Unscheduled Shutdowns:
Unscheduled Shutdowns - 7 total ,
(1) Suspended object in pool fell on thermal column extension.
(2) Unable to transfer to Intermediate Range (2). i (3) Imss of secondary cooling.
(4) Irradiation facility malfunction.
(5) Estimated criticality calculation error.
(6) Improper instrumentation response.
Inadvertent SCRAMS - 8 total (7) Operator error - 4 (8) Spurious signals - 3 -
(9) Manual SCRAM - 1 l
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- PU15rAR REACTOR ANNUAL REPORT 3 01 July 1992 - 30 June 1993 Explanation of (1) above:
A epoxy test specimen suspended along the East wall of the pool settled j on the thermal column extension near the core when its string broke.
Explanation of (2) above:
The Intermediate Range compensation voltage was set too high. This prevented observing proper overlap between the Source Range and the ,
Intermediate Range Channels during a routine startup. The voltage was properly set and the reactor run was continued. l Explanation of (3) above:
Building water was secured for maintenance by Physical Plant personnel.
During that time the cooling tower make-up water was supplied by a 5/8 inch hose. The reactor operator received a high temperature alarm from the secondary side of the heat exchanger. The make-up flow rate was adjusted and the reactor run was continued.
Explanation of (4) above:
The rotational exposure ports irradiation facility drive gear disengaged.
The gear train was realigned and the facility was returned to service. i Explanation of (5) above: l l
The reactor operator did not allow for the reactivity gain associated with the replacement 3raphite reflectors and criticality occurred just below the Estimated Criticality Position.
Explanation of (6) above:
The Linear Power Channel recorder responded too slowly to power l changes. The recorder feedback gain was adjusted for the proper response and I the reactor run was continued.
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- PULSTAR REACIDR ANNUAL REPORT 4 l 01 July 1992 30 June 1993 l
Explanation of (7) above: l Improper operation of the Linear Ixvel Power Channel range switch by i Nuclear Power Plant trainees (NT) and PULSTAR Reactor trainees (PRT) (4). !
Explanation of (8) above: l l
Set point drift of a pressure-electric switch occurred in the Primary Coolant ,
Flow Measuring Channel (3).
Explanation of (9) above:
Burlington Engineering Laboratories was evacuated by fire alarm because of a natural gas leak in the South Wing.
6.7.5.d Maior Maintenance Operations:
None 6.7.5.e fhanges in Facility. Procedures. Tests. and Exoeriments:
- 1. Design Changes (a) DC 91-4 installed a new radiation monitoring equipment in the i PULSTAR Reactor Buildmg. l t
- 2. Procedure Changes ;
I (a) PC 17-93 was Revision 9 to the PULSTAR Operations Manual. This document change was required by the relocation of a liquid nitrogen tank away from the reactor bridge and added new requirements to the PULSTAR Bay contamination surveys. j l (b) PC 26-93 is Revision 10 to the PULSTAR Operations Manual. This revision is awaiting approval by the Radiation Protection Committe.e.
(c) In all, twenty-two procedures have been revised (most just minor editorial changes) and one new procedure was written to verify the ;
reactivity worths of all the control rods (gang). Most have already l been reviewed and approved.
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- PULSrAR REACIOR A%'UAL REPORT 5
- 01 July 1992 - 30 June 1993 1
6.7.5.f Radioactive Effluents:
Liquid Waste (summarized by quarters) l 1. Radioactivity released during the reportmg period:
I l l (a) (b) (c) (d) (e) i No. of Total Tot. Vol. Diluent Tritium l Period Batches pCi Liters Liters pCi !
5 01 Jul - 30 Sep 92 1 88.69 6.84 x 10' 2.14 x 10 52.66 01 Oct - 31 Dec 92 3 13138 1.25 x 10' 3.15 x 105 102.29 l 01 Jan - 31 Mar 93 0 - - - -
5 01 Apr - 30 Jun 93 1 56.10 5.46 x 10' 136 x 10 55.4 (f) 276.90 pCi total activity released during this reporting period.
(g) 210.35 pCi of tritium were released during this reporting period.
l 2. Identification of Fission and Activation Products:
l l The gross al less than 4 x 10'pha-beta-gamma activityactivity Ci/ml (the maximum specific of thegiven batches in (a) above were in Health ,
l Physics Procedure HP 20-2). An isotopic analysis of these batches mdicated only background activity.
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- 3. Disposition of liquid effluent not releasable to Sanitary Sewer System:
l All batches of 1(a) above when diluted by campus water (2.80 x 10' liters; the minimum daily campus intake) resulted in activity considerably less than 4 x 10 4 Ci/ml (10 CFR 20 limit). Therefore, all batches were released to the sanitary sewer system.
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l - FULSTAR REACIOR ANNUAL REPORT 6 01 July 1992 30 June 1993 Gaseous Waste (summarized monthly)
- 1. Radioactivity discharged during the reporting period (in Curies) are as follows:
(a) Gases:
Total Time
_ Year Period In Hours Curies 1992 22 Jun - 22 Jul 743.81 0.904 22 Jul - 20 Aug 695.42 0323 20 Aug - 21 Sep 792.58 0.412 21 Sep - 20 Oct 719.25 0369 20 Oct - 18 Nov 722.16 0.265 ;
18 Nov - 17 Dec 722.25 0311 l
17 Dec - 15 Jan 713.25 0317 1993 15 Jan - 12 Feb 696.25 0331 12 Feb - 12 Mar 67733 0.283 12 Mar - 07 Apr 646.75 0.218 07 Apr - 06 May 723.16 0.427 06 May - 01 Jun 615.50 0.182 01 Jun - 01 Jul 720.00 0.269
- Totals 8,577.71 4.611 (b) Particulates with a half-life of greater than eight days
- )
Filters from the particulate monitoring channel were analyzed upon removal and again the following week. There was no particulate activity ((b) above) indicated on any filter during this reporting period.
- 2. Gases and particulates discharged during this reporting period:
(a) Gases:
The yearly average concentration of argon-41 released from the PULSTAR reactor facility exhaust stack during this period was 1.46 x 104 pCi/cc.
- PUISTAR REACIDR ANNUAL REPORT 7 01 July 1972 - 30 June 1993 (b) Particulates:
)
See gaseous waste 1(b) above. j i
Solid Waste from Reactor l
- 1. Total volume of solid waste - 0.2 m' (7 ft.3)
- 2. Total activity of solid waste - 0.009 mci
- 3. Dates of shipments and disposal:
30 March 1993 Chem-Nuclear Systems Inc. (CNSI) l 1 i
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- PUL5 TAR REACIUR ANNUAL REPORT g 01 July 1992 30 June 1993 6.7.5.g Personnel Radiation Exoosure Report' Twenty three members of the faculty and staff were monitored for external radiation exposure during the reporting period. Fourteen of the twenty-three-received measurable exposure which ranged from 0.010 to 0.080 Rem. Total exposure for the faculty and staff was 0.430 Rem.
Approximately 252 film badges were issued to graduate students and temporary staff,209 for short courses, and 341 film badges were issued for visitors. No significant radiation exposures were reported. The majority of these exposures were in the "no measurable exposure" range.
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I cornpiled and prepared by the Radiation Protection office.
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- PUISrAR REACrOR AMMUAL REPORT 9 01 July IW2 - 30 June 1993 6.7.5.h Summary of Radiation and Contamination Surveys Within the Facility l
Neither the radiation nor the contamination surveys indicated any trend or l shift of data from past experience or surveys.
i 6.7.5.i Description of Environmental Surveys Outside of the Facility i
See Attachment A NOTE: The July to September 1992 data in Table 6.1 of the Emironmental Report for Attachment A was lost by the contractor. The PULSTAR records ;
for gaseous effluent were carefully examined for that same reporting period.
The data displayed predictable levels well within the historical release rates.
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i RADIATION PROTECTION OFFICE NORTH CAROLINA STATE UNIVERSITY ENVIRONMENTAL RADIATION SURVEILLANCE REPORT FOR THE PERIOD JULY 1,1992 - JUNE 30,1993 l
RALTON J. HARRIS ENVIRONMENTAL HEALTH PHYSICIST I
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l TABLE OF CONTENTS PAGENO.
- 1. INTRODUCTION 1
- 2. AIR MONITORING 2 l Table 2.1 Location of Air Monitoring Stations 2 I
Figures 2a-2e Airborne Gross Beta Activities 3-7 Table 2.2 Aerially Transported Gamma Activity 8-9 Table 2.3 Regulatory Limits, Alert Levels and Background Levels for Airborne Radioactivity 10 t
- 3. MILK Table 3.1 11
- 4. SURFACE WATER I
Table 4.1 Gross Alpha and Beta Activity in Surface Water 12 i Table 42 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. OUALITY CONTROL INTERCOMPARISON PROGRAM 18 Tables 7.1a - 7.1g 19 - 25
- 8. CONCLUSIONS 26
- 9. ACKNOWLEDGMENTS 26 APPENDIX 1 27 l
- 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; j
- 2) Meeting requirements of regulatory agencies;
- 3) Verifying radionuclide containment in the reactor facility; f
- 4) Meeting legal liability obligations; and 4
- 5) Providing public assurance and acceptance.
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] 2. AIR MONITORING (TABLES 2.1,2.2, AND 2.3; FIGURES 2a THRU 2e)
)
{ Figures 2a thru 2e show bar graphs of gross beta activity (fCi/ cubic meter vs. week number). The highest gross beta activity observed was 23.6 fCi m-3 and the yearly campus average was 14.8 fCi m-3. Missing data for the Clark station (week #51 - 06/15/93 to 06/22/93) is due to an j electric motor malfunction. Missing data for the Riddick station (weeks #7 & 8 - 08/11/92 to j 08/25/92) is due to two separate electric power outages. Missing data for the Withers station 3
(week #17 - 10/21/92 to 10/27/92) is due to roofing work which prevented access to the
! sampling station.
J l Table 2. 2. lists LLQ values for several gamma emitters which would be indicative of fission product j activity. LLD values, for the period 03/03/93 to 06/29/93, are increased by a factor of approximately 2 to 3 for the radionuclides in Table 2.2. This is due to a planned reduction in the sampiing rate in an attempt to minimize the chances of pump malfunctions. These increased LLD values are far below any action level. No camma activity due to any of these radionucHdes was detoctod.
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f TABLE 2.1 LOCATION OF AIR MONITORING STATIONS ,
E DIAECT10N1 DISTANCE 2 ELB/ATION3 (meters) (rneters)
BROUGHTON SOUTHWEST 125 -17 '
DAVID CLAPX LABS WEST 500 -18 UBRARY NORTHWEST 192 +11 RIDDICK SOUTHEAST 99 -14 ,
WITHERS NORTHEAST 82 -6 i
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1 DIRECTION-DIRECTION FROM REACTOR STACK !
2 DISTANCE-DISTANCE FROM REACTOR STACK l 3 ELEVATION-ELEVATION RELATIVE TO THE TOP OF THL REACTOR STACK i
2
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AIRBORNE CROSS BETA ACTIVITY REGULATORY LIMIT =1000 fCi/CUIIIC H N. C. STATE UNIVERSITY CAMPUS ALERT MEL=500 fCi/CuilIC M CLARK 20 -
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FIGURE 2b C TAhE tlI F SI Mt S e\ R I EV L CU ff
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TABLE 2.2 1992-93 TABLE 2.2 AERIALLY TilANSPORTED GAMMA ACilVifY (ICI m E-3)
NUCLIDES SAMPLitK3 PERIOD Co 57 Co 60 Hb 95 Zr 95 ilu 103 Ru 106 Cs 137 Ce-141 Ce 144 1992-93 12/20 - 01/05 0.09 0.17 0.17 0.28 0.18 1.20 0.14 0.24 0.69 01/05 01/11 0.08 0.15 0.15 0.26 0.15 1.00 0.13 0.20 0.66 01/11 01/19 0.07 0.13 0.11 0.20 0.10 0.84 0.10 0.14 0.47 01/10 - 01/26 0.08 0.15 0.12 0.20 0.11 1.00 0.13 0.16 0.59 01/26 - 02/01 0.09 0.17 0.15 0.24 0.13 1.1 0.14 0.18 0.67 02/01 - 02/09 0.08 0.12 0.13 0.22 0.14 0.97 0.11 0.21 0.57 02/09 - 02/17 0.08 0.16 0.14 0.24 0.15 1.2 0.12 0.20 0.65 02/17 - 02/24 0.11 0.18 0.16 0.27 0.17 1.4 0.15 0.24 0.04 02/24 - 03/02 0.12 0.21 0.21 0.36 0.23 1.7 0.18 0.35 1.00 03/02 - 03/09 0.10 0.15 0.17 0.33 0.22 1.3 0.14 0.31 0.76 03/09 - 03/16 0.09 0.18 0.17 0.30 0.19 1.2 0.14 0.27 0.74 03/16 - 03/23 0.11 0.18 0.16 0.28 0.19 1.4 0.16 0.27 0.79 03/23 - 03/30 0.09 0.16 0.13 0.24 0.16 1.2 0.13 0.19 0.68 03/30 - 04/07 0.16 0.33 0.25 0.46 0.26 2.2 0.26 0.37 1.3 0.25 0.36 0.64 0.39 3.4 0.37 0.49 m 04/07 - 04/13 0.41 __ 1.9 04/13 - 04/20 0.19 0.36 0.28 0.48 0.27 2.5 0.28 0.35 s.5 04/20 - 04/27 0.18 0.34 0.26 0.44 0.26 2.2 0.25 0.32 1.3 04/27 05/04 0.18 0.32 0.48 0.76 0.55 2.5 0.29 0.87 1.60 05/04 - 05/11 0.17 0.34 0.43 0.73 0.50 2.6 0.28 0.76 1.5 05/11 - 05/18 0.17 0.33 0.37 0.64 0.46 2.5 0.26 0.65 1.4 05/18 - 05/25 0.16 0.33 0.33 0.54 0.41 2.3 0.27 0.59 1.4 05/25 - 06/02 0.11 0.20 0.21 0.34 0.21 1.7 0.18 0.28 0.97 06/02 - 06/08 0.14 0.23 0.25 0.40 0.24 2.00 0.21 0.31 1.2 06/08 - 06/15 0.13 0.27 0.23 0.39 0.26 1.9 0.21 0.34 1.1 06/15 - 06/22 0.20 0.38 0.32 0.48 0.33 2.8 0.33 0.38 1.4 06/22 - 06/29 0.22 0.43 0.33 0.52 0.34 3.00 0.35 0.43 1.9 ALL 11ATA IN TAlli.E 2.2 ARE Lt.D VALUES.
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TABLE 2.3 REGULATORY LIMITS, ALEHT LEVELS, AND BACKGROUND LEVELS FOR AIRBORNE RADIOACTIVITY (fCl m-3)
REGUI.ATORY ALERY AVERAGE N.C.
NUCUDE 11M_LT LEVEL BACKGROUND LEVEL >
GROSSALPPA 20 10 4 l
GROSSBETA 1000 500 100 Cs-137 5 x 105 10 2
( Ce-144 2 x 105 100 o
( .
Ru-106 2 x 105 30 0 1 131 1 x 105 10 0 i i
Reference:
Environmental Radiation Surveillance Report 1986-88, State of N.C.
Radiation Protection Section i
a e
I 10
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- 3. MILK (TABLE 3.1)
Milk samples are collected each month from the Campus Creamery, the Lake Wheeler Road Dairy and the Rar dieigh Dairy Farm. !
The FDA's Preventive Action Guide (PAG) for 1-131 is 1.5 X 10 4 pCi/ liter for infants. All analyses during this period show activities at least three (3) orders of magnitude below the PAG.
The analyses are performed in duplicate and the higher value is reported in each case. ,
l
}
TABLE 3.1 1-131 IN COWS' MILK {pCIliter-1 1 a) LLD - 3 pCi liter-1 pCiliter -1 l DATE CAMPUSCREAMERY LAKE WHEELER RANDL9GH JULY 1992 s 2.0 s 2.0 s 2.0
{
AUGUST 1992 s 2.0 s 2.0 s 2.0 i SEPTEMBER 1992 s 2.0 s 2.0 s 2.0 OCTOBER 1992 s 2.0 s 2.0 < 2.0 l
NOVEMBER 1992 s 2.0 s 2.0 s 2.0 DECEMBER 1992 sit.0 s 2.0 s 2.0 JANUARY 1993 s 3.0 s 3.0 s 3.0 FEBRUARY 1993 s 3.0 s 3.0 s 3.0 :
MARCH 1993 s 3.0 s 3.0 s 3.0 l APRIL 1993 s 3.0 s 3.0 s 3.0 MAY 1993 s 3.0 s 3.0 s 3.0 I 1
JUNE 1993 s 3.0 s 3.0 s 3.0 i i
l -
11 i
- 4. SURFACE WATER (TABLES 4.1 AND 4.2) .
Table 4.1 gives the gross alpha and beta activities for water tom Rocky Branch at points where it enters (ON) and exits (OFF) the campus. The LLD vdues for gross alpha and beta activities are
- 0.4 pCiliter1 and - 0.4 pCiliter1, respectively. For gross alpha activity the Alert Levelis 5 pCiliter1 and the Regulatory Umit is 15 pCiliter1. For gross beta activity the Alert Levelis ;
12.5 pCi liter 1 and the Regulatory Limit is 50 pCi liter 1. Samples with gross alpha or beta l activities exceeding these Alert Levels would require gamma analysis to identify the radionuclides present. The LLD values in Table 4.2 are for the second quarter of 1993. !
l t
i TABLE 4.1 GROSS ALPHA AND BETA ACTIVITY IN SURFACE WATER (pCiliter-1 2 c) !
- LLD a - 0.4 pCI liter-1 LLDp - 0.4 pCl liter-1 oCiliteri GGS G OSS r DAE LOCATION ALPHA BETA ,
THIRD OUARTER 1992 ON < 0.3 1.4 0.3 OFF < 0.3 < 0.4 i FOURTH OUARTER 1992 ON < 0.3 < 0.4 OFF < 0.3 1.7 : 0.4 FIRST OUARTER 1993 ON < 0.4 1.6 : 0.4 OFF < 0.4 0.44 : 0.3 SECOND QUARTER 1993 ON < 0.4 1.7 0.4 OFF < 0.4 < 0.5
'LLD VALUES ARE Dei LRMINED QUARTERLY j i
12
5 TABLE 4.2 LOWER LIMITS OF DETECTION FOR SEVERAL GAMMA EMITTERS IN SURFACE WATER FROM NCSU ERSL ANALYSIS NUCL!DE LLD (oCi literi)
~
Co-60 0.4 Zn-65 0.7 Cs-137 0.3 Cs-134 0.4 ,
Sr-65 0.4 Ru-103 0.3 Ru-106 3.0 Nb-95 0.4 l Zr-95 0.5
- LLD VALUES ARE FOR THE 2ND QUARTER OF 1993 i
6 h
l 13
1 1
- 5. VEGETATION (TABLE 5.1 and 5.2)
Table 5.1 gives gross beta activities for grass samples collected on the NCSU Campus. The reported activities are all below the Alert Level of 20 pCi gram -1. Table 5.2 lists LLD values fcr several gamma emitters. No gamma activity due to any of these radionuclides has been observed in campus t vegetation. The beta and garnma activities are reported as pCl per gram of green vegetation.
TABLE 5.1 GROSS BETA ACTIVITY IN CAMPUS VEGETATION *LLD - 0.5 pCl g-1 SAMPLC DATE SAMPLE LOCATION (DC) c-1 _2g]
DECEMBER 1992 NORTH CAMPUS 2.4 0.1 DECEMBER 1992 SOUTHCAMPUS 4.0 0.2 DECEMBER 1992 EASTCAMPUS 2.8 0.1 1 DECEMBER 1992 WESTCAMPUS 2.4 : 0.1 APRll1993 NORTH CAMPUS 2.4 0.1 APRll1993 SOUTHCAMPUS 3.8 : 0.2 APRIL 1993 EASTCAMPUS 2.3 : 0.1 APRll1993 WESTCAMPUS 2.3 0.1 i
- LLD values are determined semiannually 14
^
2 j Table 5.2 LLD VALUES FOR GAMMA EMITTERS IN VEGETATION 1
1 l NUCLIDE LLD (oCi oram-1)* l Co-60 0.01 4
Zn-65 0.02 Cs-137 0.01 :
Cs-134 0.01 :
Sr-85 0.01 Ru-103 0.01 Nb-95 0.01 Zr-95 0.02 t
- LLD VALUES ARE FOR THE 2ND OUARTER OF 1993 l
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15 i
i
- 6. THERMOLUMINESCENT DOSIMETERS (TLDs) (TABLE 6.1) i TLD analysis is contracted to Tc!edyne Isotopes for determination of ambint gamma exposures. The dosimeters are CaSO4doped with dysprosium and have a manufacturer-shted sensitivity of :
e 0.5 0.15 mR (90% C.L). Exposures are integrated over a three-month period at each of the five air monitor stations listed in Table 2.1 and also at the top of the PULSTAR Reactor stack. A control i station is located in 214 David Clark Laboratories. Table 6.1 gives the data for these seven (7) i sampling locations. Data for the period 07/13/92 to 09/30/92 was lost by the contractor and is not l available.
- The observed exposures are those expected to be produced by background radiations in this area of North Carolina. The data of Table 6.1 agrees well with the state-wide average exposure rate of .
20 mR per quarter year.
i I
i i
i
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l 16
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- T l' T T " A H H 1
B H I I 2 0 0 D L E S S 0 / 0 7
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l
- 7. QUALITY CONTROL INTERCOMPARISON PROGRAM The Environmental Radiation Surveillance Laboratory of the Radiation Protection Office has ]
participated in the U. S. EPA Environmental Laboratory Intercomparison Studies Program 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 results of the l intercomparison studies are given in Table 7.1 a-g. All samples are analyzed in triplicate and reported as an average value with an experimental sigma (1s).
Appendix 1 gives an explanation of the quantities listed in the tables and an example calculation.
4 i
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l 18 l I
l TAB LE 7.1a GROSS ALPHA ACTIVITY AIR FILTER-INTERCOMPARISON STUDY
- 28 AUGUST 1992 )
I The known value for gross alpha activity is 30.0 pCi/ filter with an expected laboratory precision of 6.0 (1s,1 determination).
i NCSU - ENVIRONMENTAL LABORATORY RESULTS ALPHA Exper. Rng anal Normalized deviation LP.b Rae. 1 M Ros.3 Sigma (R + SR) Averace (crand-ava) (known)
Q4 29.0 28.0 29.0 0.58 0.074 28.67 -0.48 -0.29 STATISTICAL
SUMMARY
OF 189 PARTICIPANTS Statistic Resoondents Non-outfiers Mean 31.25 Grand Avg 30.87 Std. Dev. 6.10 5.27 Variance 37.20 27.77
% Coef. of Var. 19.52 17.07
% deviation of mean from known value 4.17 2.92 Norm. dev. of mean from known value 0.21 0.17 Median 30.00 30.00
% deviation of median from known value 0.00 0.00 Norm. dev. of median from known value 0.00 0.00 i
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19
i l
'I TAB LE 7.1 b GROSS BETA A; ITY AIR FILTER-INTERCOMPARISON STUDY-28 AUGUST 1992 l The known value for gross beta activity is 69.0 pCi/ filter with an expected laboratory precision of
{ 10.0 (1s,1 determination).
t NCSU - ENVIRONMENTAL LABORATORY RESULTS BETA Exper. Rng anal Normalized deviation ,
Lab Ras 1 Res 2 BEL 1 Sicma (R + SR) Averace (crand-avoVknown) l, CA 75.0 75.0 73.0 1.15 0.118 74.33 0.41 0.92 STATISTICAL
SUMMARY
OF 189 PARTICIPANTS !
t Statistic Resoondents Non-outliers Mean 72.79 Grand Avg 71.98
. Std. Dev. 11.62 6.43 Variance 134.92 41.38
% Coef. of Var. 15.96 8.94
% deviation of mean from known value 5.49 4.32 :
Norm. dev. of mean from known value 0.33 0.46 Median 72.00 71.83 .
% deviation of median from known value 4.35 4.11 j Norm. dev. of median from known value 0.26 0.44 ;
e i
4 20
.- . -. ,-. ~. .--
1 TABLE 7.1 c 137Cs ACTIVITY AIR FILTER INTERCOMPARISON STUDY-28 AUGUST 1992 The known value for Cesium-137 activity is 18.0 pCi/ filter with an expected laboratory precision of 5.0 (1s,1 determination).
l NCSU - ENVIRONMENTAL LABORATORY RESULTS l 137 Cs Exper. Rng anal Normalized deviation Lab MM M Sigma (R + SR) Averace (crand-avo)(known)
CA 17.00 17.00 17.00 0.00 0.000 17.00 -0.93 -0.35 STATISTICAL
SUMMARY
OF 189 PARTICtPANTS Statistic Pescondents Non-outliers l
Mean 235.16 Grand Avg 19.68 Std. Dev. 1954.83 2.94 Variance 3821351.09 8.62
',, Coef. of Var. 831.29 14.92 l % deviation of mean from known value 1206.42 9.32 l Norm. dev. of mean from known value 0.11 0.57 Median 19.67 19.67 j
% deviation of median from known value 9.26 9.26 l Norm. dev. of median from known value 0.00 0.57 )
\ l l
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21
- , - . - - ~ .
TABLE 7.1d GROSS ALPHA ACTIVITY IN WATER -INTERCOMPARISON STUDY
-18 SEPTEMBER 1992 1
The known value for gross alpha activity is 45.0 pCi/ liter with an expected laboratory precision of 11.0 (1s,1 determination).
NCSU - ENVIRONMENTAL LABORATOAY RESULTS i
GROSS ALPHe Exper. Rng anal Normalized deviation Lab Res.1 Res.2 Res.3 Sicma (R + SR) Averace (crand-avcWknown)
CA 43.0 45.0 43.0 1.15 0.107 43.67 1.14 -0.21 f
STATISTIC AL
SUMMARY
OF 219 PARTICIPANTS Statistic Resoondents Non-outfiers ,
Mean 37.75 Grand Avg 36.46 l Std. Dev. 15.78 11.52 Variance 248.99 136.73
% Coef.of Var. 41.80 31.59
% deviation of mean from known value -16.12 -18.97 Norm. dev. of mean from known value -0.46 -0.74 Median 35.00 34.67
% deviation of median from known value - 22.22 - 22.96 Norm. dev. of median from known value -0.63 -0.90 i
l
( 22
l TABLE 7.1e GROSS BETA ACTIVITY IN WATER -INTERCOMPARISON STUDY
-18 SEPTEMBER 1992 The known value for gross beta activity is 50.0 pCi/ liter with an expected laboratory precision of 5.0 (1s,1 determination).
NCSU - ENVIRONMENTAL LABORATORY RESULTS l
GROSS BETA Exper. Rng anal Normalized deviation Lat2 RM1 M Ros,3 Sigma (R + SR) Averace (crand-ava)(known)
G 48.0 49.0 48.0 0.577 0.118 48.33 -0.097 -0.579 l
STATISTICAL
SUMMARY
OF 219 PARTICIPANTS Statistg_ Resoondents Non-outliers Mean 59.38 Grand Avg 48.61 -
Std. Dev. 114.45 9.14 Variance 13098.83 83.51
% Coef. of Var. 192.75 18.80
% deviation of mean from known value 18.76 -2.78 Norm. dev. of mean from known value 0.08 -0.15 Median 49.00 48.67 ,
% deviation of median from known value -2.00 -2.67 Norm. dev. of median from known value -0.01 -0.15 l
l 1
i r
l l l 23 f
,.y --r. ,,y
_~ . . . ._.. _ _ _ . - _ _ _ _ _ _ _ _ _ - _ _
l r
TABLE 7.1f TRITIUM IN WATER - INTERCOMPARISON STU DY - 23 OCTOBER 1992 The known value for tritium activity is 5962.0 pCi/ liter with an expected laboratory precision of l 596.0 {1s,1 determination).
NCSU - ENVIRONMENTAL LABORATORY RESULTS 3g j Exper. Rng anal Normalized deviation :
Latt M Res.2 M Sicma (R + SR) Averace (crand-avovknown)
CA 4402.0 4379.0 3936.0 262.6G 0.462 4239.00 -5.11 -5.01 ;
STA~iSTIC AL
SUMMARY
OF 172 P ARTICIPANTS Statistic Resoondents Non-outliers Mean 6201.84 Grand Avg 5997.40 i Std. Dev. 4667.63 565.83 Variance 21786750.49 320164.99
% Coef.of Var. 75.26 9.43
% deviation of mean from known value 4.02 0.59 Norm. dev. of mean from known value 0.05 0.06 Median 5953.33 5961.67 ,
% deviation of median from known'salue
- G.15 0.01 Norm. dev. of median from known value 0.00 0.00 l
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24
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TABLE 7.1g TRITIUM IN WATER - INTERCOMPARISON STUDY - 19 JUNE 1992*
l The known value for tritium activity is 2125.0 pCi/ liter with an expected laboratory precision of 347.0 (1s,1 determination).
l l
NCSU - ENVIRONMENTAL LABORATORY RESULTS 3H Exper. Rng anal Normalized deviation L& PM.1 Pes.2 Pes. 3 Sicma (R + SR) Averace (crand-avo)(known)
G 2468.0 2564.0 2539.0 49.81 0.163 2523.67 2.11 1.99 I
i STATISTICAL
SUMMARY
OF 179 PARTICIPANTS Statistic Resoondents Non-outfiers Mean 2188.82 Grand Avg 2101.61 Std. Dev. 814.49 221.34 Variance 663389.97 48993.22 l
% Coef. of Var. 37.21 10.53 i
% deviation of mean from known value 3.00 -1.10 Norm. dev. of mean from kncwn value 0.08 -0.11 l Median 2094.33 2090.00
% deviation of median from known value -1.44 -1.65 Norm. dev. of median from known value -0.04 -0.16
- These results have been included in this report as they were received after submission of the 1991-92 report.
25
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j 8. CONCLUSIONS
! i j The data obtained during this period do not show any fission product activities. The observed j environmental radioactivity is due primarily to radon progeny, primordial radionuclides (e.g.,
K-40) and those radionuclides (e.g., Be-7) 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, d
3 4 9. ACKNOWLEDGMENTS i This office is greatly indebted to Mr. Bill Crocker for his untiring efforts in collecting the ,
i environmental samples. Great appreciation is also expressed to Mr. Thomas Bracfdn for his work in
] repairing the air samplers.
l 4 The graphs in this report are available due to the assistance of Mr. Worth Bowman, and the entire ,
arrangement and typing are due to the excellent efforts of Mrs. Ginger Davis.
1 l
t 1
26
APPENDlX 1 l The vertical columns in Tables 7 are identified as columns 1-8 from left to right.
Column 1: Laboratory identification code (e.g., OA).
Columns 2,3,4: Laboratory results given in triplicate. l l
Column 5: Standard deviation (1s) of the experimental results.
Column 6: Normalized range value in "mean range + standard error of the range",
i
! Column 7: Average value of the triplicate analysis.
l Column 8: Normalized deviation from the grand average value of alllaboratories expressed in omunits.
! Column 9: Normalized deviation from the known value expressed in m o units. f i
I The following example calculation gives a set of data, the maan 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 'hrough 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 waming levels. The accuracy of the data is acceptable. -
Finally, the experimental error of aii laboratories, the grand average, and the normalized deviation from the grand average are calculated in order to ascertain the performance of all the laboratories as a group. Any bias in methodology or instrumentation may be indicated by these resultr..
l l
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)
- 27 l 1
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EXAMPLE CALCULATIONS !
Experimental data:
Known value = p = 3273 pCi 3H / liter urine on September 24, 1974 Expected labcratory precision = e = 357 pCi/ liter Laboratory Sarol e_ Resul t D x1 3060 pCi/ liter 0 x2 3060 pCi/ liter D x3 3240 pCf/ liter Mean = ii ,
~
N I xi i=1 9360 li = = = 3120 pCi/ liter N 3 where N = number of results = 3 Experimental sigma = s N
/"
g I 2
N \i-1 xj)l I (xj)2 -
i=1 N s =
N-1 i 2 2 2 (3CoS + 3060 + 3240)2 (3060) + (3060) + (3240) - --
3 l
s = '
2 j s = 103.9 pCi/ liter i
Range = r r = l maximum result - minimum result l l
r = l3240-3060l = 180 pCf / liter
- 28 i l !
l for r<R, x = 0 then r = wI + xen = wl ;
r or w = -
7 r
therefore w+x = w+0 - -
K ,
i since r < Y, (180 < 604.4) I 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 = em em
/7 357 3
4 .
em = 206.1 pCi/ liter D
ND = -
em
. - 153 T66'T ND = - 0.7 Control limit = CL CL = (p 3em)
Warning Limit = WL WL = (p 2am) 29
A p a l
l Range Analysis (RNG ANLY)*
Mean range = X E= de 2 where d2 ** = 1.693 for N = 3
~
i
= (1.693) (357)
Y= 604.4 pCi/ liter Centrol limit = CL
=
CL I + 3eR
= D74 where D4 ** = 2.575 for N = 3 l
(2.575) (604.4) l CL = 1556 pCi/ liter Standard errer of the range = eg ca
(R + 3cn - R) t 3
= (D4 I - 7) t 3
= (1556 - 604.4) t 3 eg = 317.2 pCf / liter Let range wT + xen = 180 pCi/ liter
~
r
Define normali:ed range = w+x for r > T, w = 1 then r = wI + xeg = 7 + xeg r-T CT x =
eR r-I therefore w+x = 1+x = 1+
CR
- Rosenstein, M., and A. S. Goldin, " Statistical Techniques for Quality Centrol of Environmental Radioassay," AOCS Repcrt Stat-1, U.S. Department of Health Education and Welfare, PHS, Novemcer 1964.
- From table "Facters for Computing Centrol Limits," Handbook of Tables for Probability and Statistics, 2nd Edition, The Chemical Ruceer Co., Cleveland, 0010, 19c6, p. 454 30
- .. .m. .. ._ .._ . _ . . . _ . . _ _ _ _ _ _ _ _ _ . _
f i
Experimental sigma (all laboratories) = s (See Figure 2) ,
[N \2 I xt.
j N I (xj)2 -
ki"1 / -
l
' i=1 N :
st =
I N-1 l (49345)2 162639133 l 15 -!
ra :t Grand average = GA li
~
I N I xi i=1 i GA = j N t
. 49345
=
15 GA = 3290 pCi/ liter i
- Nermalized deviation frem the grand average = ND' i 1 l Deviation of the mean from the grand average = D' l r
D' = 7 - GA ,
i
= 3120 3290 ,
D' = - 170 pCi/ liter !
D' i
ND' = -
- 170
=
206.1 ND' = - 0.8 31 I
w----ry,-4 ,m - r +-r-- .,y, --a,,,,<
. .-..,--v, e n,w,r,,m- ,,www--w,,, -,e,,wewwww--+v-,e.-m.,-c s ,r w e
- w v,e e wr =- ' *, - --ww,*,--ae-