ML20246N678
| ML20246N678 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 06/30/1989 |
| From: | Bray T, Geoffrey Miller North Carolina State University, RALEIGH, NC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8909080231 | |
| Download: ML20246N678 (38) | |
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.. $Y m.. l North Carolina State University Nuclear Reactor Program Department of Nuclear Engineering L
l - Box 7909 Raleigh, NC 27695-7909 (919) 737-2301
' August 31,1989
.U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC .20555 Docket No. 50-297 ANNUAL REPORT
Dear Sir:
In compliance with Section 6.7.5 of the North Carolina State University PULSTAR Technical Specifications, our Nuclear Reactor Program staff has prepared the attached Annual Report for the period 1 July 1988 through 30 June 1989.
Sincerely, gn<f b c$Y{h Garry D. Miller Associate Director TCB/GDM:vg copy to: All with attachments:
- 1. USNRC Director of Regulatory Operations, Region II
- 2. Dr. J. Richard Mowat, Chairman Radiation Protection Council 4
- 3. Dr. Hayne Palmour, IIL Chshman Reactor Safeguards Advisory Committee
- 4. Dr. D. W. Morgan Radiation Protection Officer
- 5. Dr. L K. Monteith, Dean College of Engineering
- 6. Dr. Thomas S. Elleman, Ilead Department of Nuclear Engineering 8909080231 890630 PDR ADOCK 05000297 R PDC
'i g North Carolina State University is a land-grant university and a constituent institution of The University of North Cholina.
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PULSTAR' ANNUAL REPORT TO UNITED STATE NUCLEAR REGULATORY COMMISSION for the Period 1 July 1988 - 30 June 1989
- Submitted by G. D. Miller, Associate Director NCSU NUCLEAR REACTOR PROGRAM Prepared by Thomas C. Bray PULSTAR Reactor Operations Manager
Reference:
PULSTAR Technical Specifications Section 6.7.5 Docket No. 50 297 Department of Nuclear Engineering North Carolina State University Raleigh, North Carolina 27607
.. v Augtsi 31,1989 m
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s DEPARTMENT OF NUCLEAR ENGINEERING <
PULSTAR REACTOR ANNUAL REPORT l
For the Period: 1 July 1988 - 30 June 1989 The following report is submitted in accordance with Section 6.7.5 of the PULSTAR Technical Specifications:
6.7.5.a Reactor Operatine Exnerience:
(1) The NCSU PULSTAR Reactor has been utilized for the following:
- a. Teaching and Short Courses 75.02 hours
- b. Grnduate Research 18.10 hours
- c. Faculty Research 98.65 hours
- d. Isotope Production 3.17 hours
- e. Neutron Radiography 0.40 hours
- f. Neutron Activation Analysis 2346.00 hours
- g. NPP Reactor Operator Training 738.98 hours
- h. PULSTAR Reactor Operator Training 33.42 hours
- i. Reactor Calibrations and Measurements 25.68 hours
- j. Reactor Health Physics Surveillance 7.77 hours TOTAL 3347.19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> Same reporting period 1987-1988 3250.41 hours4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> A cross section of experiments performed in the reactor relate to these areas:
- a. Neutron Activation Analysis of animal tissue, fly ash, sediments, rain / river water, filters, resins, coal, milk, graphite, textile fiber, etc.
- b. Reactor thermal power measurements for teaching laboratories.
- c. Isotope Production
- d. Thor aal neutron depth profiling of Boron-implanted silicon.
- a. Nevtron diffusion length sensurements in grapnite.
- f. Neutron Radiography.
- g. Therral neutron diffusion in oils
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. PULSTAR REACTOR ANNUAL REPORT 2 sJ JULY 888 - 30 JUNE '89
.s (2) Chances in Perfortnance Characteristics Related to Reactor Safety:
l None (3) Results of Surveillance. Tests. and Inspections:
The reactor surveillance program has revealed no significant nor unexpected trends in reactor systems performance during this report period.
l 6.7.5.b Total Enerry Output:
1174.934 Megawatt-hours 48.955 Megawatt-days Pulse Operations:
0 Reactor was Critical:
1522.433 hours0.00501 days <br />0.12 hours <br />7.159392e-4 weeks <br />1.647565e-4 months <br /> Cumulative Total Energy Output since Initial Criticality:
14,838.479 Megawatt-hours 618.270 Megawatt-days t
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F C TAR REACTOR ANNUAL REPORT 3
._ 1 JULY '88 - 30 JUNE '89 6.7.5.c Number of Emergency and Unscheduled Shutdowns:
Unscheduled shutdowns - 3 total (1) Secondary coolant pump would not start from the remote switch in Control Room.
(2) Irradiation basket string broke while loading.
(3) ECP outside allowed window Inadvertent scrams - 13 total i (4) Operator error 8 L (5) Flow / Flapper scram at 100 KW 1 (6) Manual scram switch 1 (7) Manual scram - false fire alarm 1 (8) Low primary flow 1 (9) Campus electrical power interruption 1 Explanation of (1) above:
Lock-out ring had been left in stop position following maintenance.
Explanation of (2) above:
Handling' string, from which the irradiation basket was suspended, parted as basket was being lowered in the vertical exposure port. Basket descended inside exposure port and came to rest where it would have had the string not parted. Operator discretion cause of manual scram; action not required by procedure.
Explanation of (3) above:
l Experimenter had overestimated value of negative reactivity effect of a l -*ven irradiation target and that error caused the ECP window of 200 l pem to be exceeded. Shutdown following a missed ECP window is required j by operating procedure. After reactivity estimate was corrected, the
- ACP was satisfactory.
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Explanation of (4) :bove:
Eisadjustment of the Linear power channel range switch by NPP and NRP l operator trainees.
I Explanation of (5) above:
l Reacto: was operating iu fece convection mode with flapper open and primary pump cecured. Scrar annunciator displayed a ficu/ flapper ft.ilure but reh was r,ot the case under free convection condition.
Cause attributen to spurious Log N or Safety channel picoammeter mit ral.
l Explanation of (6) above:
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- tu.suR REACTOR A WUAL REPORT 4 l ,,
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e manual scram switch developed an open-contact condition and caused u am. Switch was determined faulty and was replaced by exact spare in stuik.
l Explanation of (7) above:
Fire alarm pull box was activated as a student prank while reactor was operating. Operating procedures require reactor shutdown by manual b scram (followed by building evacuation) when fire alarm sounds.
l-Explanation of (8) above:
Primary coolant flow rate trip switch activated at a conservative 485 gpm rather than the 475 gpm designated setpoint. Small flow rate l variations of brief time duration are normal in the primary cooling system.
Explanation of (9) above:
A campus electrical power interruption will result in an automatic reactor scram due to RSS design.
6.7.5d. Maior Maintenance Operations:
None during this reporting period 6.7.5e. Chances in Facility. Procedures. Tests. and Experiments:
(1) Design Change 88-3, Seal Material Chance in Primary Pool Hole-Sealinc Device Following the pool hole-sealing device installation on 4/15/88, periodic sealing material inspections conducted thereafter revealed undesirable shrinkage of the sealing material. Closed-cell EFDM foam selected for the original sen1 was responding to the pool water pressure by progressive thrinkage but thne w4.s Jesa evidence of structural causae to the foam from rediation exposure than was anticipated.' Consequently, a new sealing nr.terial, neoprene with a Shore */." herfness of 5 to 10 durcaeter, was ;
recommended by NCSU Katerials Science department.. The new sealing material, irstalled 6/13/08, has performed satisfactorily to dr.te.
Saf.efty Evaluation "Reantor operational safety will not be affectnd by chit change. l'ooi vater level change., assuming l the seal failed completely, could be maintained quite easily by the reactor Service Water System thus ptoviding ample time for seal replacement."
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{. FULSTAR E ACTOR ANNUAL M PCT $
1 JULY '88 - 30 JC E '89 (2) Design Change 89-1, PULSTAR Evacuation Horns for Burlincron Labs South Wing Following decommissioning of the R-63 facility in the South Wing, all evacuation horns and circuitry associated with the R-63 were removed. Since that time, many spaces in the
! South Wing have been converted to offices and laboratories and the personnel occupation level is such now that building complex evacuation notice to those occupants is considered appropriate. An additional reason for restoring evacuation horns in the South Wing is evident from the pedestrian traffic standpoint; many people enter Burlington Engineering Laboratory building via the adjoining South Wing. During an l evacuation sequence, traffic control can be simplified if I
pedestrian entry to the building is minimized and South Wing evacuation horns will be effective in that respect.
Safety Evaluation: " Preliminary tests verify that additional evacuation horns connected as proposed do not affect performance of existing evacuation horns."
(3) Procedure Changes Special Procedures 2.1 through 9.4 (24 total) were revised to reflect editorial and minor technical changes. All were approved by the campus review group in April 1989.
Special Procedures 3.2, 4.5, 5.8 and 5.9 are new documents composed of instructions previously contained in surveillance files and the Operations Manual. All were approved by the campus review group in April 1989.
Health Physics Procedures 20-16, 20-17, 20-18, 20-19, 20-21 and 30-2 are new documents and revised documents. All were approved by the campus review group in March and April 1989.
Environmental Procedures EkS HV, ERS-MP, ERS-M, ERS-SW, ERS-CF, ERS-CV. ERS-TLD and ERS-RWW are surveys / analyses conducted by the NCSU Radiation Protection Office. There procedures were recently written; representing a fonaalizccion of activities routinely oerformed for many years in connectier with NC3U PULETAF Technical Specifications. The campus review group approved these piocedures in April 1989.
The procedures enumerated above are assembled in manual / binder form and the index for each procedure category is attached to this report. j
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_SPECIAL PROCEDURES INDEX M REV TITLE 2.1 2 Reviewing Proposed Changes to Components, Systems, Structures, and Procedures 2.2 1 Reactor Operator Assistant Qualification 2.3 2 Reactor Operator Qualification 2.4 3 PULSTAR Drawing Control System 2.5 1 PULSTAR Reactor Surveillance 2.6 4 PULSTAR Operator Requalification 3.1 3 Removal and Installation of Control Rods and Control Rod Drive Mechanisms
-+ 3.2 0 Control Rod Drive Mechanisms Post Maintenance Testing 3.3 2 Fuel Handling Procedures 3.4 1 Fuel Pin inspection 4.1 3 Test of Pulse Interlocks 4.2 4 Pre-Pulse Checks 4.3 1 Routine Pulsing 4.4 1 Pulsing Er Measurment by Gold Foil Irradiation
-+ 4.5 0 Startup Channel Discrirr.;nator Curve 5.1 1 Draining the Primary System 5.2 2 Removal and installation of Valve Pit Shields 5.3 1 Draining the Secondary System 5.4 1 Purification System Startup 5.5 1 Purification System Shutdown 5.6 4 Purification System Resin Change 5.7 2 Filling and Draining Beam Tubes
+ 5.8 0 Service Water System
-+ 5.9 0 Pool Fill Procedure 9.1 1 Beam Tube Shielding Plugs Handling Procedure 9.2 3 Insta!!ation and Removal of Experimental Facilities, Vertical Exposure Ports (VEPs) 9.3 3 Installation and Removal of the Neutror? Rarfography Facility 9.4 3 Routine Operation of the Neutron Radiccraphy Facility 1ssued by the NRP Administrative Office April 28,1989 4
,e l HEALTH PHYSICS PROCEDURES INDEX '
MCL RIN TITLE 11 0 Training Requirements for Selected Emergency Team Members Who Wear Self-Contained Breathing Apparatus (SCBA) 12 0 Maintenance of Self-Contained Breathing Apparatus (SCBA) 10-1 2 Inventory and Location of Special Nuclear Material 10-2 2 Special Nuclear Material (SNM) Accountability 10-3 2 Radiation Work Permit 10-4 0 Receipt of Radioactive Materials (yet to be issued) 10-5 2 Transfer and Shipment of Radioactive Material 20-1 2 Servicing Continuous Fifte. Air Sampler' PULSTAR Off-line Air Sampler 20-2 2 Release of Radioactive Wastes to the Sanitary Sewer System 20-3 2 Sampling Waste Water Tanks 20-4 2 Water Samples From PULSTAR Pool Surface 20-5 2 Water Samples From Piping Vafves 20-6 2 PULSTAR Deep Pool Water Samples l 20-7 2 Water Sample Preparation for Neutron Activation Analysis 20-8 2 Water Sample Preparation for Gross Beta / Gamma Counting l 20-9 2 pH Determination Using Corning 125 Digital Meter 20-10 2 Resistivity Measurements Using YSI Model 31 Meter 20-11 2 Preparation of Air Sample Filters for Laboratory Proportional Counting l 20-12 2 Changing Continuous Air Monitors (CAM) Filters
- l. 20-13 2 Calibration of Eberline Continuous Air Monitor (CAM) 20-14 2 Radiation and Contamination Surveys of PULSTAR Bay 20-15 2 Determine Efficiency and Operating Plateau Gas Flow Proportional Counters
- 20-16 1 Calibration (Electronic) and Efficiency checks for RM-14 Monitors
-+ 20-17 0 Drin and Response Checks for Meet Readout Dosimeters i -+ 20.18 0 Decontamination l 19 0 Lower Limit of Detection (LLD) and Minimum Detectabte Concentration (MDC) 20-20 0 Gample Analysis Using The Nuclear (yet to be issued)
Services Gemma Spectroscopy System
--+ 20-21 0 Tritixn Analysis of Waste Water l 20-22 0 GM Detector Sensidvity 16 Argon-41 (ChhnnEl #5) '
30-1 2 Access to Restricted Areas
--* 30-2 0 Radiation Safety Training e
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ENVIRONMENTAL PROCEDURES INDEX MQ BE TITLE ERS-HV O Hi-Vol Filters ERS MP O Millipore Filters ERS-M 0 Milk ERS-SW 0 Surface Water ERS-CF 0 Charcoal Filters ERS-CV O Campus Vegetation ERS-TLD 0 Use of Thermoluminescent Dosimeters for Environmental Radiation Levels ERS RVAV O Reactor Waste Water issued by NRP Administrative Office May 24,1989 a
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.I% STAR REACTOR ANNtJ.L REPORT 6 1 JULY '88 - 30 JUNE '89 6.7.5(F) Radioactive Effluents:
Liould Waste (summarized by quarters)
- 1. Radioactivity released during the reporting period.
(a) (b) (c) (d) (e) no. of total tot vol. Diluent Tritium Ouarter Period batches pCi . in ltrs Irrs uCi Ist 1 Jul - 30 Sep 88 14 44.06 4.77 E4 6.25 E4 37.80 2nd 1 Oct - 31 Dec 88 6 70.98 2.05 E4 1.57 ES 66.35 3rd 1 Jan - 31 Mar 89 6 82.59 2.04 E4 1.86 ES 77.60 4 th 1 Apr - 30 Jun 89 6 162.25 2.05 E4 3.85 E5 104.44 (f) 286.19 Ci were released during this reporting period.
(g) 359.88 Ci were released during this reporting period.
- 2. Identification of Fission and Activation Products.
The gross alpha-beta-gamma activity of the batches in (a) above were less than 4 x 10 4 pCi/ml. An isotopic analyais of these batches indicated only background activity.
- 3. Disposition of liqui.d effluents not releasable to Sanitary Sewer System. All batches of 1(a) above when diluted by campus water resulted in activity considerably less than 4 x 10-7 pCi/ml. Therefore all batches sere released to the sanitary sewer system.
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IHL51AR REACTOR ANNUAL REPORT 7
, 5 JULY *BB - 30 JUNE '89 Gaseous Waste (summarized monthly)
- 1. Radioactivity discharged during the reporting period (in Curies) for:
- a. Cases Total Time Xgar Period In Hours curies 1988 01 Jul - 29 Jul 673.92 .343 30 Jul - 29 Aug 741.50 .45 30 Aug - 28 Sep 719.00 .66 29 Sep - 27 Oct 704.50 .36 28 Oct - 28 Nov 760.75 .44 29 Nov - 31 Dec 792.00 .32 1989 01 Jan - 03 Feb 815.50 .47 04 Feb - 06 Mar 744.50 .20 07 Mar - 05 Apr 743.50 .23 06 Apr - 03 May 671.25 .27 04 May - 01 Jun 728.75 .35 02 Jun - 03 Jul 735.50 .21_
8830.67 4.343 (b) Particulate whose half-life is greater than (8) days.
Filters from the particulate monitoring channel were annlyzed upon removal again the following week. There was no particulate activity ((b) above) indicated on any filter during this reporting period.
- 2. Gases and particulate discharged during this reporting period.
Gases:
The yearly average concentration of ArgondIreleased from the PULSTAR reactor facility exhaust stack during this period was 1.4 x 10* Ci/ml.
Particulate:
See gaseous waste 1(b) above.
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l IESTAR REACTOR ANNUAL REPORT 8 1 JULY '88.- 30 JUNE '09 SOLID WASTE FROM REACTOR
- 1. total volume of solid waste - 58 ft3
- 2. total activity of solid waste - 0.085 mci
- 3. Dates of shipments and disposal:
11 Aug 1988 CNSI 03 Apr 1989 CNSI 05 Apr 1989 CNSI 19 Jul 1989 CNSI
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% 6.7.5.G: P;rsonnel Radiation Exposure R: port (R; porting P:riod 05/01/88-05/31/89) - l 4 Facultv and Staff Totaf Exoosure (remi BIDDY, Oscar D. 0.010 BILYJ, Stephen J. 0.040 BRACKIN, Thomas L 0.030' BRAY, Thomas C. 0.010 CAVES,' John R. 0.030
'. DAVIS, Glenda 0.030 DOSTER,J. Michael 0.020 ELLEMAN, Thomas S. 0.020' GARDNER, Robin P. 0.010 GILLIGAN, John 0.040 GRADY, Stanley M. 0.060
, HANKINS, Orlando H. 0.020 L JOHNSON, Charles M. 0.040 KOHL, Jerome 0.0
' LAMBERT, Joseph P. F. 0.010 LODGE, Phillip S 0.050 MANI,Kolam V. 0.010
' MILLER, Gury D. 0.010 MUNN, R. Hugh 0.0 MURTY, K. Linga ' O.020 RAYNO, DONALD R. 0.010 STAM,E. 0.020 STRICKLAND, David D. 0.010
' TITTLE, Charles 0.020
~ TURINSKY, Paul J. 0.050 VERGHESE, Kuruvilla 0.010 WEAVER, Jack N. 0.010 WEHRING, Bernard 0.010 WILSHIRE, Frank W. 0.020 OTHER.
27 film badges were issued monthly to graduate students and temporary staff; 71 film badges were issued for student laboratories; 130 filtn badges were issued for short courses; 333 film badges were issued for visitors.
No significant radiation exposures were reported; the majority of these radiation exposures were j in the "no measurable exposure" range.
TUI. STAR REACTOR A MUAL REPORT - 10 1 JULY *B8 - 20 JUNE '89 6.7.5.h Summary of Radiation and Contamination Surveys Within the Facility Neither the radiation nor the contamination surveys indicated any trend or shift of data from past experience / surveys.
6.7.5.i Description of Environmental Surveys outside of the Facility (See Attachment A) l l
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l RADIATION PROTECTION OFFICE NORTH CAROLINA STATE UNIVERSITY
'ENVIRONf
- ENTAL RADIATION SURVEILLANCE REPORT FOR THE PERIOD AUGUST 1988 - JULY 1989 RALTON J. HARRIS ENVIRONMENTAL HEALTH PHYSICIST
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- 1. IfiTRODUCTION h . In accordance with recommendations issued by the Environmental Audit Committee in 1987, several issues have been addressed in the PULSTAR environmental monitoring program. These items are
' briefly discussed below:
- 1) . Data for th? environmental thermch.ninescent dosimeters (TLDs) placed at each monitoring station will be included in the annual environmental radiation surveillance report.
- 2) The positive displacement pumps recommended to replace the current air sampling equipment have not been obtained due to budgetary restrictions. An increased maintenance program has been proposed to extend the monitoring capability of the current equipment until funding can be acquired for new equipment;
- 3) Gamma analysis of surface water wil now be performed utilizing ion exchange techniques rather than the previous method involving evaporation of large v91umes of water.
- 4) Strontium-90 analysis of cows' milk is being discontinued in favor of I-131 analysis.
Future environmental reports will reflect this change.
- 5) . Analysis of campus soil has been discontinued since it does not provide data pertinent to any reactor effluent releases.
- 6) Campus vegetation will be analyzed semiannually for both gross beta and gamma activities.
As a necessary consequence of these changes, the environmentallaboratory procedures have been complete rewritten in considerable detail.
The Environmental Radiation Surveillance Laboratory of the Radiation Protection Office has joined the U.S. Environmental Protection Agency Environmental Laboratory Intercomparison Studies Program during this reporting period. A major objective of this program is to assist laboratories involved in environmental radiation measurements to develop and maintain both an intralaboratory and inter.
laboratory quality control program, in part, this is accomplished through an extensive laboratory intercomparison studies program lavolving environmental media (milk, water, and air) and a variety of radionuclides with activities at or near environmental levels. Simulated environmental samples containing known amounts of one or more radionuclides are prepared and periodically distributed to the participating laboratory. The required analyses are performed and the results are returned to the Nuclear Radiation Assessment Division for statistical analysis and comparison with known values as well as with analytical values obtained by other participating laboratories. In addition, the Environmental Radiation Surveillance Laboratory has been able to establish a formalized schedule with the State of North Carolina Division of Facility Services for split-sample comparison of environmental samples.
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- 2. AIRMONITORING Table 2.1 shows the locations of the air monitoring stations. Figures 2a-2f give a graphical repre-sentation of the gross beta activities observed during this reporting period. Gross beta activities are determined by counting Millipore air filters which are collected on a weekly basis from the five (5) campus monitor stations. Due to recurring operational difficulties, data is not available for several weeks during the sampling period. These instances have been indicated on the graphs as " sampler inoperative
- The stations at David Clark, Riddick, and D. H. Hill Library show higher than usual activities during the period 12/06/88 to 12/20/88. This behavior is repeated again during the period 01/10/89 to 01/24/89. The stations at Broughton and Withers do not reflect this trend. This brief period of increased activity would appear to be due to naturally occurring radon progeny since gamma analysis has indicated only the presence of radon progeny, naturally occurring Be-7 and Cs-137 fallout activity at or below the average North Carolina background level of - 2 fCi m-3during this period.
These increased gross beta activity levels are not of concern since they are at least a factor of five (5) below the alert levelvalue of 500 fCi m-3. As a point of information, the Alert Levelindicates a level of observed radioactivity which warrants further sample analysis to confirm its presence. The term " Alert" carri9c D2 implication of health or safety hazards.
The data entries of Table 2.2 prefixed by "<" are the LLD values for each nuclide. During the period 11/01/88 to 11/15/88, several nuclides show elevated LLD values which resulted from problems with instrumentation and monitoring equipment. Other fluctuations in LLD values are attributable to variations in the volume of air sampled by the monitoring system. The data of Table 2.2 indicate that none of the listed radionuclides were present in detectable concentrations. Table 2.3 gives a listing of Regulatory Umits, Alert Levels, and average North Carolina background activity levels for those nuclides for which data is available. Environmental air is currently monitored for the presence of gaseous radiciodine using charcoal cartridges as the collection medium. At present the data derived from this monitoring is of limited utility due to the low volume of air which can be sampled, and, hence, an achievable detection limit which is too large relative to the Alert Level. For this reason radiciodine data has not been tabulated in this report. Hopefully, this problem can be solved in the future with the purchase of new equipment.
TABLE 2.1 LOCATION OF AIR MONITORING STATIONS SIE DIRECTION 1 DISTANCE 2 ELEVATION 3 (meters) (meters)
BROLGRON SOUTHWEST 125 -17 DAVID CLARK LABS WEST 500 -10 LIBRARY NORTHWEST 192 +11 RIDDICK SOJTHEAST 99 -14 WITHERS NORTHEAST 82 -6 1 DIRECTION-DIRECTION FROM REACTOR STACK 2 DISTANCE-DISTANCE FROM REACTOR STACK 3 ELEVATION-ELEVATION RELATIVE TO THE TOP OF THE REACTOR STACK i l
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TABLE 2.3 REGULATORY LIMITS, ALERT LEVELS, AND BACKGROUND LEVELS FOR
' AIRBORNE RADIOACTIVITY (fCi m 3)
REGULATORY ALERT AVERAGE N.C.
NUCUDE LIMIT 1. EEL SACKGROUND LEVEL GROSSALPHA 20 10' 4 GROSSBETA . 100 500' 100 Cs-137 ~ ' S x 105 10 2 o,
Ce 144 - 2 x 105 100 o 3-.
Ru-106 2 x 105 30 0
- I-131. 1 x'105 - 10 0
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Reference:
Environmental Radiation Surveillance Report 1984-85, State of N.C.
' Radiation Protection Section i
.-I f
. . . 12-
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- 3. MILK . (TABLE 3.1)
Monthly analyses for cows' milk from the Campus Creamery have shown concentrations of Sr-90 that are well below the FDA's Preventive Protective Action Guide value of 0.009 microcurie liter 1 for infants.- During the next reporting period, (1989-90), Sr 90 analysis will be discontinued in
~ favor of I-131 analysis pursuant to recommendations by the Environmental Audit Committee.
Several months of Sr 90 data are missing due to the repair of laboratory fume hoods necessary for this analysis. The available data show the activities to be at or below the LLD value of 4 pCiliter1 LLD values are determined quarterly.
1 TABLE 3.1 Sr-90 IN COWS' MILK (pCiliteri 11 o) LLD - 4 pCiliteri M))E ACTMTY AUGUST 1988. 54 SEPTEMBER 1988 s. 4 OCTOBER 1983 NO SAMPE NOVEMBER 1988 NOSAMPE DECEMBER 1SB8 NO SAMPE JANUARY 1989 NO SAMPE FEBRUARY 1989 NOSAMPE MARCH 1989 NO SAMPE APRIL 1989 s4 MAY 1989 54 l JUNE 1989 s4 l-
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.d, f 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 values for gross alpha and beta activities are
- 0.I pCi liter 1 and - 0.6 pCi liter 1 respectively. For gross alpha activity the Alert Levelis 5 pCiliter1 and the Regulatory Limit is 15 pCiliter1. For gross beta activity the Alert Levelis 12.5 pClliter1 and the Regulatory Limit is 50 pCi liter 1. Samples with gross alpha or beta
. activities exceeding these Alert Levels would require gamma analysis to identify the radionuclides present. Surface water samples analyzed during this period have not shown the presence of any gamma emitters above the detection limits specified in Table 4.2.
TABLE 4.1 GROSS ALPHA AND BETA ACTIVITY IN SURFACE WATER (pCiliterl 2 c)
- LLD,- 0.1 pCiliteri LLDp - 0.6 pCiliter1 oCiliter1 GGS G OSS D61E LOCATON ALPHA BETA FOllRTH OUARTER 1988 ON 0.1 0.1 2.8 0.4 -
OFF 0.4 0.2 3.5 1 0.5 FIRST OUARTER 1989 ON 0.3 0.1 3.4 A 0.4 OFF 0.110.1 3.1 1 0.4 SECOND OUARTER 1989 ON 0.5 0.2 2.8 0.4 OFF 0.2 0.1 0.6 1 0.3
- LLD VALUES ARE DETERMINED OUARTERLY
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o-TABLE 4.2 LOWER UMITS OF DETECTION FOR SEVERAL GAMMA EMITTERS IN SURFACE WATER NUCLfDE LLD (oClliter1 )
Co-60 5.4 Zn-65 13.8 Cs-137 5.3 Cs-134 5.9 Sr-85 16.7 Ru 103 36.7 Ru 106 51.3 Nb-95 16.8 Zr-95 28.5
- LLD VALUES ARE DETERMINED OUARTERLY
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5.' VEGETATION (TABLE 5.1)
The data of Table 5.1 gives gross beta activities for grass samples coffected on the NCSU Campus.
The reported activities are all below the Alert Level of 20 pCi gram-1. In the past only gross beta L activity was generally reported for vegetation unless the activity exceeded the alert value. In these cases gamma analysis was performed to determine if any fission products were present. For future reports gamma analysis wi'l be included as a routine procedure on all vegetation samples.
I TABLE 5.1. GROSS BETA ACTIVITY IN CAMPUS VEGETATION *LLD - 0.5 pCi g-1 SAMPLE DATE SAMPLE LOCATION (oCia-1 m i, AUGUST 1988 NORTH CAMPUS 5.7 2.1 AUGUST 1988 SOLITHCAMPUS 4.2 2.2 AUGUST 1988 EASTCAMPUS 2.4 1 2.0 AUGUST 1988 WESTCAMPUS 9.7 1 2.6 JULY 1989 NORTHCAMPUS 10.910.5 JULY 1989 SOUTHCAMPUS 10.910.5 JULY 1989 EASTCAMPUS 11.010.5 JULY 1989 WESTCAMPUS 13.510.6
'LLD values are determined semiannually I
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- 6. THERMOLUMINESCENT DOSIMETERS (TLDs) (TABLE 6.1 AND FIGURE 6.1) l L . i analysis is contracted to Teledyne isotopes for determination of ambient gamma exposures. The b ximeters are CaSO 4doped with dysprosium and have a manufacturer-stated sensitivity of 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 station is located in 214 David Clark Laboratories. Table 6.1 and Figure 6.1 give the data for these seven (7) sampling locations for the period 07/06/88 to 07/05/89. Data for the PULSTAR stack monitoris missing for this same period due to an inoperable cranking device which allows positioning of the TLD holder. This problem has now been corrected.
The observed exposures are those expected to be produced by background radiations in this area of L ' North Carolina. The data of Table 6.1 agrees well with the state-wide average exposure rate of l
20 mR per quarter year.
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- 7. CONOLISONS The data obtained during this period do not show any fission product activities other than very low -
1- levels of Cs-137 which can be attributed to residual fallout. The observed environmental radio-activity is due to radon progeny, primordial radionuclides (e.g., K-40) and 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 in a manner which does not adversely affect the university environment.
- 8. ACKNOWLEDGMENTS
' Appreciation is expressed to Mr. Paul A. Shuping of the Radiation Protection Office staff for his assistance in producing the computer-generated graphs in this report.
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