Text

Annual Rept,Jul 1979 to Jul 1980.
	ML19344E607
Person / Time
Site:	North Carolina State University
Issue date:	08/27/1980
From:	Bray T, Cockrell R; North Carolina State University, RALEIGH, NC
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O PULSTAR ANNUAL REPORT TO UNITED STATES NUCLEAR REGULATORY COMMISSION for the Period of 1 July 1979 - 30 June 1980 Submitted by R.C. Cockrell, Director NCSU NUCLEAR REACTOR PROGRAM Prepared by Thomas C. Bray PULSTAR Reactor Operations Manager

Reference:

PULSTAR Technical Specifications ,

Sec tion 6. 7. 5 Docket Ib. 50-297 Department of Nuclear Engineering North Carolina State University Raleigh, North Carolina 27650 August 27, 1980 j

40000'M03

DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT For the Period: 1 July 1979 - 30 June 1980 The following report is submitted in accordance with Section 6.7.5 of the PULSTAR Technical Specifications:

6.7.5.(a) Reactor Operating Experience (1) The NCSU PULSTAR reactor has been utilized for the following;

a. Teaching and Short Courses 143.32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months

b. Graduate Research 86.65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months

c. Isotope Production 343.70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months

d. Neutron Activation Analysis 1300.62 hours7.175926e-4 days 0.0172 hours 1.025132e-4 weeks 2.3591e-5 months

e. Neutron Radiography 27.70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months

f. NPP Reactor Operator Training 993.62 hours7.175926e-4 days 0.0172 hours 1.025132e-4 weeks 2.3591e-5 months

g. PULSTAR Reactor Operator Training 14.68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months

h. Reactor Calibrations and Measurements 13.82 hours9.490741e-4 days 0.0228 hours 1.35582e-4 weeks 3.1201e-5 months

1. Reactor Health Physics Surveillance 4.00 hours0 days 0 hours 0 weeks 0 months J. Tours and Visitors 64.47 hours5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months

k. Eaculty Research 83.29 hours3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months TOTAL 3075.87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months Same reporting period 1978-1979 2842.13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months A cross section of experiments performed relate to these areas:

a. Beam Tube Collimation Tests

b. Ball FKiling and other flow / tracer studies

c. PVC Radiation Damage determination

d. Reactor Noise Measurements using fuel assembly vibrator and beam tube reactivity oscillator

e. Prompt Gamma analysis of sulfur, polyethylene and polystyrene

f. Reactor Core delta-T measurements

g. Neutron Activation analysis of fly ash, animal tissue, rain / river water, coal, asbestos, milk, feathers, etc.

h. Free-convection flow delta-T measurements 1

(2) Design Chan';es Accomplished:

No. 79-8 Install Reactor Bay "Open Door" alarm --- Provision for alerting reactor operator to entry and departure of personnel via reactor bay doors.

No. 79-9 Add Running-time Meters to Confinement Fans --- Makes possible accurate determination of air flow exposure time of charcoal filters in confinement filter train.

No. 79-10 Correct error in Control Rod Magnet Power Supply current meter indication --- Eliminated factory error in current metering circuit.

No. 79-11 Install backup / replacement Low Voltage Power Supply Corrected problem of intermittant voltage output from S/U Channel P/S which could not otherwise be identified and repaired.

(3) Changes in Performance Characteristics and Operating Procedures related to Reactor Safety:

a. Change to existing Calorimetric Power Calibration procedure (P.C. 6-79) resulted in adding a reference to the Technical Specifications and adding a verification check- of f for 500 gpm primary flow. Also added a Reactor Engineer file reference to the acceptance criteria.

b. Change to existing Linear and Safety Power Channel calibra-tion procedures (P.C. 7-79) as a result of shif t from 5x5 Reflected Core #1 to 5 x 5 R.C. #3. Added reference to the Technical Specifications in section 2 of Surveillance Procedure PS-1-03-4:S1 and PS-1-05-3:SI.

(4) Results of Surveillance Tests and Inspections The reactor surveillance program has revealed no significant nor unexpected trends in reactor systems performance during the past year and all inspections have yielded routine results.

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6.7.5.(b): Total Energy output t 820.02 Megawatt-hours 34.17 Megawatt-Days

Pulse Operations:

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Reactor was critical:

1195.16 lburs

Total Cumulative Energy Output since Initial Criticality 4742.93 Megawatt-hours 197.62 Megawatt-days 6.7.5.(c): Number of Emergency and Unscheduled Shutdowns one unscheduled shutdown was made on 29 January 1980 as a result of hign radiation alarm annunciations produced by a campus power transient. Reactor was shut down by operator manual scran. Reactor power level indications were not affected by the transient but administrative procedures require a manual shutdown should any two rad Lation alarms be received. This event did not constitute an abnormal occur-rence by Technical Specification definition.

Number' of Inadvertant Scrams 48 Reasons : (1) Operator error 31 (2) Linear Power Channel range switch 1 (3) . Low Primary Flow setpoint drift I (4) Safety Flapper position switch 13 (5) Campus Power interruptions and transients 2 1

Explanation of (1) above:

Nuclear Power Plant Reactor Operator Training (27)

NRP Staff operators (4)

Explanation of (2) above:

The range selector switch in the Linear Level power measuring channel had developed faulty contacts. Replacement of the picoammeter (Keithley 410A) with the approved spare picoammeter eliminated the range switch contact problem.

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Explcnctien of (3) Ebovat Primary coolant : flow rate trip switch activated at a conservative 490 gpm .rather than 475 gpm, the adjusting setpoint. Small indicated i fluctuations of .brief time duration are normal in the primary cooling system.

h Explanation. of (4)j above :

j I Flapper closure handle operates a flapper position signal switch in -

addition to - physically closing the flapper valve. The flapper i

closing sequence is ' flapper closure, then switch actuation'. Because this operating .sequenc'e requires a rather forceful pull on the flapper handle to operate the switch properly, on occasion an operstor will not exert sufficient force to close both flapper and switch. The flapper valve has never been observed 'open' when the ' position switch was indicating ' closed'.

] Explanation of (5) above:

Manual scram' initiated by operator because evacuation horns sounded

, due to campus electrical power transient. In this instance administra-

, . tive procedures require, whea operating, a reactor shutdown and l evacuation should any two radiation alarms be received.

I Another scram was generated, automatically, when a momentary power -

interruption caused the scram logic unit to release the control rods.

This was a normal response under the circumstance.

6.7.5.(d) Major Maintenance operations None during this reporting period i

6.7.5.(e) Changes in the Eacility,- Procedures, Tests and Experiments

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(1) Design Change 79-8 "PULSTAR Reactor Bay Loading Dock and

Northeast ' Door Open' Alarm" was proposed to provide an aural

and visual alert for the reactor operator when either of these 1 doors ,are opened. The doors cannot be viewed directly from the control room by the reactor operator and the dor open alarm augments his knowledge of personnel status in the bay.

Safety evaluation not required because change did not impact operating reactor safety.

l. (2): Design Change 79-9, " Add Running-Time Meters to PULSTAR Confinement Fans" was made to monitor actual operating time of each of two- confinement fans and the associated filter trains.

L The ' charcoal halogen filters for both confinement fans have a ,

i finite capacity and periodic testing of these filter systems i 'under the surveillance program can, over a long period of time, possibly deplete the filtering ability and capacity of these

units. - The running-time meters. enable the operating staff to 4

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i determine precisely the utilization to date of the currently installed charcoal filters.

Safety evaluation stated, " Indicator (running time meter) will be series fused ... to prevent inter-reaction with the fan motors."

(3) Design Change 79-10, " Change to Control Rod Electromagnet Current to Improve Accuracy" eliminated an "as built" error in the electromagnet power supply. For a measured magnet current of 40 ma. (the design valve), the corresponding current monitor meter indication was 44 ma.

Safety evaluation summary: "This proposed circuit modifi-cation will not create a ' sneak' path or other obscure circuit whereby failure of the proposed additional circuit components or wiring could result in inhibiting the Scram Logic Unit from acting to release the control rods upon demand."

(4) Design Change 79-11, " Backup / Replacement Lou Voltage Power Supply for Startup Channel Source Range Monitor." A critical spare for the S/U Channel LVPS wat purchased because a random intermittant in output voltage had been observed and corrective maintenance had not revealed the problem source.

Safety evaluation stated . "The proposed replacement power supply has performance characteristics superior to those of the presently installed unit. The replacement P.S. will in no way inhibit the fail-safe features of the Startup Channel while the reactor is operating in the S/D to 4 watt range wherein the S/U Channel functions as a component part of the Reactor Safety System." I (5) Procedure Change 6-79 tc PS-3-01-4:S1, " Calorimetric Power Calibration" added a Technical Specification reference to Section 2, a verification check-off for 500 gpm primary flow to Section' 4 and an R.E. File reference to the acceptance criteria.

l Safety evaluation not required for this change because the calibration procedure steps were unaffected.

l (6) Procedure Change 7-79 to PS-1-03-4:S1 and PS-1-05-3:SI, l " Calibration of Linear or Safety Channel" added a Technical

! Specification reference to Section 2, a DMM type designation to I

( Section 3 and a data sheet change to conform to D.C. 79-1, Sec. 7, !

l Page 2, Para. 3, which was approved 24 April 1979. i I

Safety evaluation summary, "The RSAG gave consideration to all aspects of D.C. 79-1 and concluded that ' ... the institution of the necessary changes to the linear power channel may be conducted safely. '"

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(7) Procedure Change 10-79, "Special Procedure 9.3, Neutron Radiography Facility" was a new procedure created from a PULSTAR reactor experimental project description. The Neutron Radiography Unit (NRU), approved for experimental use, was re-fined for research and service use and is now the Neutron Radiography Facility (NRF).

Safety-evaluation summary, " Core reactivity effects of the installation A/O removal of the NRF are less than

'significant' as defined by the PULSTAR Operations Manual, Sec tion 3. 4. 5. 2 : ic, , 0.1% a k/k. "

(8) Procedure Change 1-80 was a revision to Special Procedure 9.2,

" Installation and Removal of Experimental Facilities" and was necessary due to redesign of the vertical irradiation ports located adjacent to the PULSTAR reactor core. From time to time, these exposure ports are transferred from the core region to a storage location, both within the reactor pool, and the specifics relating to handling this move is the subject of the SP revision.

Safety evaluation not appropriate to this change because operating reactor safety is not affected.

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6.7.5. (f): Radioactive Effluents Liquid Wastes (summarized by quarter)

1. Radioactivity Released Dur'ag the Reporting Period (a) (b) (c) (d) (e) (Period)

N.

o Total Volume Diluent Tritium Batches Activity Released Volume Activity Ci/ml liters liters # C1 20 13.29 6.27E4 6.72E6 2.16E-5 1 July - 30 Sept 1979 13 45.65 4.47E4 6.72E6 1.92E-5 1 Oct - 31 Dec 1979 ,

12 16.01 3.47E4 15.68E6 1 Jan - 31 Mar 1980 10 14.15 3.25E4 4.48E6 2.86E-5 1 April - 30 June 1980

f. Yearly activity release was 89.1 y Ci

g. Yearly tritium release was 139E-4 8 C1

2. Identification of Fission and Activation Products.

The maximum batch activity released this past year did not not exceed 4E-5 gCi/ml. Therefore analysis of any batch was not accomplished.

3. Disposition of Liquid Ef fluents not Releasable to the Sanitary Sewer System.

All batches of liquid wastes complied with 10CFR20, Appendix 2 and therefore, could be and were released to the Sanitary Sewer System. There was no other disposition of liquid waste.

(a)

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Data related to disposition of liquid waste N/A (c)

(d) 7 ,

6.7.5 Gaseous Wastes

1. Radioactivity Discharged During the Reporting Period in curies) for:

(a) Gases Period Time .

Ci/mi hrs. C1 1979 18 June - 18 July 1.45E-8 728.58 0.36 18 July - 16 Aug 1.28E-8 692.58 0.30 16 Aug - 16 Sept 1.57E-8 744.00 0.40 16 Sept - 15 Oct 1.49E-8 735.92 0.37 15 Oct - 12 Nov 1.74E-8 679.50 0.40 12 Nov - 12 Dec 2.76E-8 712.33 0.67 12 Dec ' 79 to 11 Jan '80 1.24E-8 720.08 0.30 1980 11 Jan - 11 Feb 1.47E-8 744.55 0.37 11 Feb - 11 Mar 2.70E-8 696.63 0.64 11 Mar - 9 Apr 2.40E-8 696.92 0.57 9 Apr - 8 May 1. 21 E-8 719. 83 0.30 8 May - 6 June 1.51E-8 726.58 0.37 TOTAL 8870.50 5.05

b. The Constant Air Monitor in the PULSTAR Bay and the Particulate Monitor on the Bay exhaust did not evidence any activity whose half life was greater than 8 days.

2. The gaseous activity released during the above reporting period was A-41 in the amount of 5.05 Curies or an average of 1.68E-8' #Ci/ml for the hours indicated.

The MPC of A-41 in an unrestricted area is 4E-8 # Ci/ml.

Solid Waste from Reactor 3

1. Total volume of solid waste - 23 f t ,

2. _ Total Activity -

0.013028 curies

3. . Dates of shipments and dispositioni:

12 September 1979 Disposal by NECO 14 December 1979 Disposal by NECO 18 March 1980 Disposal by NECO ,

26 March 1980 Disposal by NECO l l

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6.7.5(g) P2rconn21 Radiatien Exposure Report (Raporting Period - 1 Juns 1979 -

31 May.1980)

Name Total Dose (rem)

Faculty and Staff Biddy, Jr., Oscar D. (04/02/80-05/31/80) 0. 0 Bilyj, Stephen J. 0.185 Bohannon, Jr. , James R. 0.107 Brackin, Thomas L. 0.114 Bray, Thomas C. 0.193 Cross, Robert D 0.123 Douglas, William G. 0.112 Elleman, Thomas S. (June 1979) 0.020

Eudy, Lucille P. (June and July 1979) 0.040 Cant, D. Michael 0.343 i Gardner, Robin P. 0.120 Kohl, Jerome 0.154 4

Lawrence, Craig P. 0. 21 7 Lewis, Luther E. 0.056 Miller, Carry D. 0.254 Murray, Raymond L. 0.292 Price, Leslie F 0.194 Rhiner, Glenda D. 0.027 Saxe , Raymond F. 0.059 Stam, Ephraim 0.078 Verghese, Kuruvilla 0.057 Weaver, Jack N. 0.036 Zumwalt, Lloyd R. 0.126 Radiation Protection Office Personnel Ball, Arthur C. 0. 0 Caruthers, L. Thomas 0.027 Corbett, E. Marcelle 0.053 Debman, Joshua 0. 0 Freeman, Ralph M. 0.044 Crady, Stanley M. 0.272 Howard, Suzanne M. 0.020 Mangum, Royelle 0. 0.136

' Morgan, W, William 0. 0 Custodians Dunn, Johnnie J. 0.017 Jones, Arthur 0.027 Sarders, Joseph 0. 01 6 Young, Charles 0.016

-Students 90 film badges were issued to Nuclear Engineering Department students during the reporting period. No significant radiation exposures were reported. The majority of the radiation exposures were in the' 'no measurable exposure' range.

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6.7.5L(g) Continued Summary of Radiation and Contamination Surveys Radiation surveys of the ' PULSTAR Bay performed on a monthly basis did not evidence any indication of an adverse trend.

Contamination surveys performed by the Radiation Proetection Office have not found any areas that were contaminated. Special Contamination Surverys performed following completion of RWP's did not disclose any contamination.

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ENVIR0tEZNTAL RADIATION SURVEILLANCE REPORT POR THE PERIOD OCTOBER 1,1979 TO }&RCH 31,1980 Radiation Protection Council L. T. Caruthers, Radiation Protection Officer D. W. Morgan, Associate Radiation Protection Officer North Carolina State University Raleigh, North Carolina

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1. INTRODUCTION '

Enviroanental radioactivity in the vicinity of North Carolina State University has remained at low levels throughout this reporting period. There have been no reported disturbances (such as atmospheric nuclear detonations or accidental releases from nuclear facilities) which would tend to cause noticeable increases in the radioactivity detected in envirorunantal samples, and no incresses have been detected.

2 AIR MONITORING No significant alpha or halogen activity was detected in air samples taken during the reporting period. Gross beta activity is reported in Table 2.2 and specific activities for gamma emitters are reported in Table 2.3.

3. MILK Strontium-90 activity is reported in Table 3.1. Iodine activity has remained below detection limits; this is also reported in Table 3.1.

. 4. SURFACE WATER Specific activities for surface water samples are reported in Table 4.1. All specific activities are consistently low with the exception of Potassium-40 which is a naturally occurring radionuclide which is widespread in the environment. Its presence in surface water is thus dependent upon the con-centration of dissolved and suspended solids in water and is therefore subject to a large variation.

5. SOIL

, Gross alpha end beta and specific genmaa smitter activities are reported for the various soil samples in Table 5.1.

6 VEGETATION Specific activities for corn, soy beans, and pine needles are reported in Table 6.1.

7. REACTOR UASTE TANK AND SEWAGE Gross alpha and beta activities for samples taken from the PULSTAR Reactor waste tanks are reported in Table 7.1. Specific activities for samples of Raleigh sewage water are also reported here.

8. THERH0 LUMINESCENT D06IMETERS (TLDs)

TLD average weekly exposure readings for area and reactor monitors are reported in Table 8.2.

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Table 2.1 Air Particle Sampling Stations I

Designation Distance Elevation Direction _

Broughton Southwest 410 ft. - 55 ft.

David Clark Lab (DCL) West Library Northwest- 529 ft. + 36 ft.

Riddick. Southeast 325 ft. - 46 ft. ,

Withers Northeast 270 ft. _ 19 ft. !

j Direction - Direction from Reactor Stack Distance Distance from Reactor Stack

Elevation - Elevation with respect to top of Reactor Stach l Table 2.2 Airborne Gross Beta Activity (fCi/M3*1o)

Date Broughton DCL Library Riddick Withers 1979 l i

i 10/1-10/5 9.0

3.8 32.9

5.0 43.5

5.5 40.1 5.7 31.4

5.0 !

10/8-10/12 33.6 4.9 45.6

5.6 26.0

4.8 40.7

5.8 28.5

4.9 !

10/15-10/19 28.6 4.7 35.8

5.2 28.7

5.0 36.6

5.7 48.0 5.8 i 10/22 10/26 37.5

4.9 49.2

5.5 41.4

5.2 43.6

5.7 48.0 5.5 10/29-11/2 44.8

5.4 40.4

5.4 31.9

5.1 57.1 t 6.6 30.3

5.0 ,

i 11/5-11/9 45.7 5.4 61.4 6.2 48.6 i 5.7 70.6 7.1 52.0

5.9 11/12-11/16 31.1

4.8 36.3

5.2 54.4

6.1 40.4

5.9 51.7

5.9 t 11/19-11/23 60.4

6.1 67.4

6.5 50.5

6.3 68.8

7.0 50.6

5.8 11/26-11/30 37.5 i 4.9 27.2 4.6 38.0

5.1 35.7

5.4 31.7 4.8 12/3-12/7 30.1

4.8 53.4

5.9 48.3

5.8 41.6

5.9 36.9

5.3

) 12/10-12/14 31.8

4.8 51.1

5.8 40.9

5.5 38.1

5.7 33.0

5.1 l 12/17-12/21 28.6

4.6 41.2

5.3 30.3

4.9 26.9

5.1 38.8

5.2 2

12/24-12/28 40.3

5.0 32.9

4.8 36.4

5.0 45.1

5.8 31.1 t 4.8 1980 1/1-1/4 28.6

4.9 31.4 i 5.2 27.1

5.1 34.3

5.8 21.1

4.8 3 1/7-1/11 54.2 5.7 43.0

5.4 62.6

6.3 63.5

6.7 46.2

5.6 1/14-1/10 30.1

4.7 23.1

4.5 24.7

4.7 15.5

4.7 20.0

4.4 1/21 1/25 31.1

4.6 32.7

4.8 28.7

4.7 25.8

4.9 36.7

5.0 1/28-2/1 25.6

4.3 52.4

5.7 41.1

5.2 41.3

5.6 49.3

5.6 1 2/4-2/8 5.7 i 3.4 26.7

4.5 26.5

4.5 62.9

6.5 43.3

5.3 2/11-2/15 48.2

5.7 52.1

6.0 42.2

5.7 Not Operational 34.0

5.4 2/13-2/22 23.1

5.2 23.1

4.7 27.1

4.9 48.6

6.2 37.7

5.3 2/25-2/29 25.1 4.7 43.0

5.6 41.1 5.6 35.1 t 5.8 32.2

5.2 3/3-3/7 30.1

4.8 25.7

4.8 19.9

4.7 41.6

5.9 33.8

5.2 3/10-3/14 38.0

5.1 37.6

5.2 38.8

5.3 30.2 i 5.4 23.7

4.7 3/17-3/21 28.1 a 4.8 20.2

4.6- 16.7 i 4.6 44.8

6.1 30.6

5.1 3/24-3/28 19.4

4.3 27.5 i 4.8 15.9

4.4 26.9

5.2 29.5

4.9 2

Table 2.3 Airborne Particulate Specific Activity ( y emitters)

Campus Average fCi/M

1 c)

Date Ce 141g , 103 106 95 Ru Ru Zr Nb Cs 1979 10/1-10/5 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 1.50 * .82 10/8-10/12 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 < 0.1 10/15-10/19 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 1.57 * .95 10/22-10/26 < 5.0. , < 1.0 < 4.5 < 5.0 < 1.0 < 0.5 0.71 * .90 10/29-11/2 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.89 * .84 11/5-11/9 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 4.35 *1103 11/12-11/16 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.56 * .85 11/19-11/23 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.19 *1.22 11/26-11/30 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.95 .82 12/3-12/7 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 2.32 a .63 12/10-12/14 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 1.77 * .59 12/17-12/21 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.43 i .79 12/24-12/28 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.62 * .67 1980 12/31-1/4 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.46 * .88 1/7-1/11 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 1.95 * .86 1/14-1/18 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.57 .69 1/21-1/25 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.80 .85 1/28-2/1 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.86 * ,70 2/4-2/8 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.22 .79 2/11-2/15 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.86 .77 2/18-2/22 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.56 * .75 2/25-2/29 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.3 < 0.1 3/3-3/7 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.57 * .81 3/10-3/14 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.64 1.15 3/17-3/21 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 1.89 .70 3/24-3/28 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 0.62 i .67 Table 3.1 Milk Specific Activity (pCi/1 i 1 o )

Date 131

_'_ S._r_ I 10-79 2.84 .47 < 2.0 11-79 3.54 .61 < 2.0 12-79 4.78 * .64 < 2.0 k-80 5.59 i .59 < 2.0 2-80 2.46 * .45 < 2.0 3-80 3.95 .49 < 2.0

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Table 4.1 Eurface Water Specific Activity (rCi/1 1o)

Date Location

Cs K Sr Gross Alpha Gross Beta 10 79 CN < 0.1 8.74

43.41 .31 * .03 .48 * .10 6.23 * .49 0FF 0.35 * .84 < 2.0 .25 * .02 .16 .06 5.13 * .44 11-79 ON 0.32 i .92 4.50

39.41 .15 * .02 .10 * .05 3.86 * .37 0FF < 0.1 < 2.0 .19 * .02 08 * .05 3.98 * .38 12-79 ON < 0.1 < 2.0 20 * .02 .30 * .09 4.78 .42 4.20 * .40 1

0FF < .01 < 2.0 .17 * .02 .15 * .07 1 80 ON 0.61 * .80 < 2.0 .37 * .03 .68 * .12 5.43 * .44 0FF 1.55 * .84 < 2.0 .25 * .02 .41 * .09 4.63 .40

' 2 80 ON 1.41 * .83 < 2.0 .19 * .02 .25 * .07 3.32 * .34 OFF 0.79 .82 < 2.0 .22 * .02 .15 * .06 2.99 * .33 3-80 ON 1.06 * .80 < 2.0 .28 * .02 .49 * .10 4.08 * .39 CFF 0.52 * .79 33.72

41.96 .15 * .02 .25 * .07 4.19 .39

0N . Denotes Rocky Branch Creek as it Enters NCSU Campus OFF . Denotes Rocky Branch Creek as it Leaves NCSU Campus Table 5.1 Soil Specific Activity (pci/gm

1 o )

228 226 137 40 Location

Gross or Gross G Th _

Ra_. C.s_ . . _ _ K_. _ _.

North 1.35 * .25 8.30 * .95 0.79 * .37 1.20 * .30 2.90 * .27 < 0.4 South 0.94 * .20 6.79 * .85 0.39 .31 0.51 * .25 1.20 * .19 < 0.4 East 3.26 * .44 30.54 2.11 1.64 * .47 1.61 * .38 4.09 a .36 74.68 14.10 West 3.59 * .57 20.81 *2.10 1.56 * .35 0.95 * .28 8.85 * .52 16.07

10.05 OBG 4.5' 2.43 .53 7.24 el.79 2.18 i .53 1.27 * .41 < 0.1 < 0.4 NBG 4.5' 3.83 i .66 28.74 *2.71 3.19 * .57 1.07 * .44 < 0.1 47.42

15.80 4

U 4.5' O.03 * .20 7.99 * .95 1.01 * .29 0.99 * .23 < 0.1 < 0.4

Location is designated by direction froct Reactor - Burial Ground Samples are in near proximity to fence (outside).

OBG denotes Old Burial Ground NDG denotes New Burial Ground 4.5' denotes Depth of Sample. Others are Surface Samples.

l 4

Table 6.1 Vegetation Specific Activity (pCi/gm i 1 o )

40g Sample Gross Alph,a Cross Beta Cs Corn .01 * .00 5.75 * .31 0.66 * .04 1.46 * .76 Soy Beans .06 * .02 21.30

1.13 13.13 * .67 53.85

3.43 S. Pino .06 * .02 3.83 * .23 2.93 * .15 6.90 * .99 Rx Pine .01 * .01 2.69 .16 0.62 * .04 6.62 + 1.07 Table 7.1 Reactor Uaste Tank and Setrage Specific Activity (pCi/1

1 o )

Sample cross Alpha Groso Beta O, g

WT #1 11/79 < 0.5 192.1 11.2 '.

WT #3 11/79 < 0.5 297.3

16.3 WT #1 12/79 < 0.5 1110.2

55.5 int #2 12/79 < 0.5 6390.4

320.6 WT #2 2/80 < 0.5 409.6

22.6 WT #3 2/80 < 0.5 279.1 a 16.3 WT #2 3/80 < 0.5 144.7

10.1 WT #3 3/80 < 0.5 122.3

9.1 11/79 Sewage 0.00 * .07 11.39 .91 29 * .39 01/8') Sewage 0.07 * .00 10.04 * .84 .75 * .41 03/0] Sewage 0.13 * .09 16,75

1.18 .29 * .39

~~ , ~

Table 8.1 Thermolumineccent Dosimeter (TLD) Locations Desinnation g,kocation Broughton I410 f t, southwest of and 55 f t. below top of Reactor Stack DCL Roof of David Clark Laboratories Library 629 ft. northwest of and 36 ft. above top of Resctor Stack Riddick 325 f t. southeast of and 46 f t, belou top of Reactor Stach Withers 270 ft. northeast of and 19 ft belou top of Reactor Stack Control Room 214 David Clark Labs R-3 Entrance to NCSUR-3 Reactor Bay from Control Room PULSTAR PULSTAR Reactor Bay, West Wall Equipment Room PULStar Equipment Room East of PULStar Bay Control Room PULStar Control Room Pool Over PULSTAR Reactor Pool Stack Top of PULSTAR Reactor Stack

. Table 8,2 Thermolumincocent Dosimeter Readings (Average mR/wk based on Co.60 Standard)

Area Monitors

10 11 79 12 79 01 80 - 02-80 03-80 Broughton L 2.0 2.3 1.0 2.7 1.3 1.7 Broughton C 1.9 1.7 1.7 1.4 1.8 2.6 DCL L 1.5 1.9 0.5 2.0 0.7 1.5 DCL C 1.1 1.9 1.1 0.9 1.5 1.7 Library L 2.3 2.0 0.6 3.4 1.5 1.9 Library C 1.7 1.7 1.7 1.9 2.1 1.7 Riddick L 2.5 2.5 1.2 0.9 1.3 1.9 Riddich C 2.1 2.1 2.1 2.4 2.2 2.5 Uithers L 1.6 1.5 1.1 1.4 1.0 1.5 Withers C 1.6 1.5 1.4 1.4 1.7 1.5 Control L 1.3 1.9 0.7 2.8 4.3 1.6 Control C 1.5 0.8 1.6 1.4 1.5 1.5 Reactor Monitors R-3 L 2.4 3.5 2.6 5.0 1.8 3.4 R-3 C 3.1 3.1 2.9 2.7 3.1 4.7 PULSTAR L 46.7 24.7 21.0 60.2 15.9 36.4 PULSTAR C 6.0 6.0 5.9 5.4 5.5 7.0 Equipment Room L 25.4 15.9 14.9 26.5 11.7 20.9 Equipment Room C 24.9 32.2 22.1 23.8 35.3 29.3 Control Room L 8.7 5.0 9.0 3.4 3.6 Control Room C 3.4 2.5 7.4 3.5 3.8 Pool L 46.6 30.2 14.6 40.5 17.1 31.2 Pool C 36.3 29.8 29.6 32.8 40.8 35.3 Stack L 2.8 2.2 0.6 3.0 1.2 1.9 Stack C 1.4 1.2 1.4 1.3 2.0 1.4

L . Denotes Locally Evaluated LiF Dosimeters C - Denotes CaSO 4

Dy Dosimeters Contracted to Toledyne Isotopec for Analysis 6-

ENVIRONMENTAL RADIATION SURVEILLANCE REPORT FOR THE PERIOD APRIL 1, 1979 TO SEPTEMBER 30, 1.979 Arthur C. Ball, Environmental Health Physicist i Joshus Debnam, Environmental Chemist Radiation Protection Council L. T. Caruthers, Radiation Protection Officer D. W. Morgan, Associate Radiation Protection Officer North Carolina State University Raleigh, North Carolina 27607

5

1. INTRODUCTION Enviroissental radioactivity in the vicinity of North Carolina State i University has remained at low levels throughout the current reporting period. There have been no reported disturbances (such as atmospheric nuclear detonations or accidental releer cd from nuclear facilities) which

. would tend to cause noticeable increase.s in the radioactivity detected in environmental samples, and no increases have been detected.

2. AIR MONITORING

~

Alpha and halogen activities in air stmples have remained below detection limits for this reporting period. Groos beta and specific gamma activities are reported in Tables 2.2 and 2.3 reopectively.

3. MILK Strontium-90 activity is reported in Table 3.1. Iodine activity has remained below detection limits, and this is also reported in Table 3.1.

4. SURFACE WATER

' Specific activities for surface water samples are reported in Table 4.1 All activities are consistently low with the exception of Potassium-40 which

, is a naturally occurring widespread radionucli N , Its presence in surface water is thus dependent upon the concentration of dissolved and suspended solids in the water and therefore is subject to a large variation.

5. SOIL Specific activities for soil samples are reported in Table 5.1, No abnormal readings were observed.

6. VEGETATION 4 Two pine needle samples were taken during this repo?: ting period.

Specific activities for gross alpha and beta, Cesium-137 and Potassium-40 are reported in Table 6.1

7. REACTOR WASTE TANKS AND SEUAGE Gross alpha and beta activities for samples taken from the PULSTAR Reactor waste tanks are reported in Table 7.1. Specific activities for samples of Raleigh sewago water are also reported here.

8. THERM 0 LUMINESCENT DOSINETERS (TLDs)

TLD average weekly exposure readings for area and reactor monitors are reported in Table 0.1. Recults of contracted TLD readings for the month of July have not been returned and are precumnbly lost. The large discrepancies between local and contracted readings for the dooimetero on the West Wall of the reactor boy (PLLCr!.R) are unexplained. This location is such that these dosimotera shculd huvu bcen czposed to open bear 2 tube radiation, thus the higher (local) ror. dings are ciore readily acceptable.

3'Y

_ _ u_

Table 2.1 Air Particle Samplin8 Locations Designation Direction Distance Elevation Broughton Southwest 410 ft. - 55 ft.

David Clark Lab (DCL) West Library Northwest 629 ft. + 36 ft.

Riddick Southeast 325 ft. 46 ft.

Withers Northeast 270 ft. - 19 ft.

I Direction - Direction from Reactor Stack 2

Distance . Distance from Reactor Stack Elevation - Elevation with respect to top of Reactor Stach Table 2.2 Airborne Cross Beta Activity (fCi/M

1 a)

Date Broughton _DCL, Library Riddick Withers 1979 4/2-4/6 62.5

5.7 75.0 i 6.3 39.9

4.6 20.0 i 3.8 27.6

4.1 4/9-4/13 33.1 i 4.5 38.6

4.7 41.2

4.8 41.2 i 4.8 38.2

4.7 4/16-4/20 36.0

4.4 54.8 i 5.3 41.2

4.6 49.1

5.0 11.0

3.3 4/23-4/27 47.0

5.0 47.6

5.0 42.1

4.8 43.8

4.8 13.2

3.5 4/30-5/4 46,0 5.0 62.1

5.8 48.9

5.2 52.2

5.3 59.0

5.6 5/7-5/11 31.4 4.4 37.1 4.6 20.6 4.0 24.6 4.1 22.4 4.0 5/14-5/18 33.0

4.4 49.3

5.2 90.0

7.1 45.8

5.0 45.0

5.0 5/21-5/25 35.3

4.5 46.3

5.0 52.4

5.3 43.4

5.0 37.1

4.6 5/28-6/1 45.4 i 5.0 40.6

4.8 44.3

5.0 47.8

5.1 31.8

4 4 6/4-6/8,$

34.2

4.3 31.8

4.2 38.6

4.5 41.4

4.6 43.4

4.8 6/11-6/1 50.0 t 5.0 43.4 4.7 54.2

5.2 51.1

5.1 36.8

4.4 6/18-6/22 33.0

4.8 47.4

5.2 33.8

4.6 40.8

5.0 35.7

4.7 6/25-6/29 38.8

4.8 38.6

4.8 44.3

5.0 31.1

4.4 38.8

4.8 7/2-7/6 28.5 4.4 40.4

4.9 38.8

4.0 31.1

4.5 28.5

4.4 7/9 7/13 41.7

4.9 36.0

4.6 32.9

4.5 36.2 i 4.6 32.4

4.5 7/16-7/20 49.1

5.1 34.2 i 4.5 48.2

5.1 24.8 4.1 34.2

4.5 7/23-7/27 27.4

4.2 15.4

3.7 24.3

4.1 13.4

3.6 74.1

6.3 7/30-8/3 47.1

5.2 44.7

5.1 55.0

5.6 55.0

5.6 55.0

5.6 8/6-8/10 27.8 4.2 51.3 5.3 50.4 5.2 46.7 o 5.1 46.5 5.1 8/13-8/17 48.5

5.0 39.2

4.5 24.3 4.0 34.0

4.4 31.0

8/20-8/24 42.1

5.0 33.6

4.6 39.5

4.8 29.8

4.4 38.6 *4.8 4.2 8/27-8/31 16.7

4.0 23.2

4.2 22.4

4.2 17.1

4.0 24.3

4.2 9/3-9/7 20.2

4.0 21.0 4.0 Ifi.6

3.C 22.8 4.0 21.0

4.0 9/10-9/14 33.1

4.4 30.7 + 4J 27.0*4126.1*4.1 21 J

3. 9 9/17-9/21 -

36.0

4.8 - - -

9/24-9/28 24.8 A 4.1 41.7 4.8 20.0 + 3 9 40.8 t 4 8 2!i.6

4.1 2-

Table 2.3 Airborne Particulate Specific Activity (Y amittero)

(Compue Average fCi/M3

1 c) 1I ce 106Ru 95 '$

Date 1979 144Ce ,{03Ru Zr Nb 6.6

2.3 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 4/2-4/6 < 5.0 < 1.0 < 0.5 4/9-4/13 < 5.0 < 1.0 < 0.5 13.6

2.4 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 4

4/16-4/20 < 1.0 < 0.5

~4/23-4/27 18.3

4.0 < 1.0 < 0.5 < 5.0 4/30-5/4 16.5

2.5 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 5/7-5/11 9.5

2.7 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 12.8

1.8 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 ,

5/14-5/18 < 5.0 < 1.0 < 0.5 5/21-5/25 10.3

2.4 < 1.0 < 0.5 8.9

2.4 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 5/28-6/1 < 1.0 < 0.5 !

i 6/4-6/8 < 5.0 < 1.0 < 0.5 < 5.0 6/11-6/15 10.9

1.1 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5

< 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 6/18-6/22 < 1.0 < 0.5 6/25-6/29 10.5

2.6 < 1.0 < 0.5 < 5.0 6.8

2.2 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 7/2-7/6 < 5.0 < 1.0 < 0.5 7/9-7/13 12.6

3.0 < 1.0 < 0.5

< 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 7/16-7/20 < 1.0 < 0.5 7/23-7/27 < 5.0 < 1.0 < 0.5 < 5.0 7/30-8/3 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 8/6-8/10 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 g0.5

< 5.0 < 1.0 < 0.5 < 5.0 < 1.0 0.5

, 8/13-8/17 < 1.0 < 0.5 8/20-8/24 - < 5.0 < 1.0 < 0.5 < 5.0 l

< 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5

8/27-8/31 < 1.0 < 0.5 9/3-9/7 < 5,0 < 1.0 < 0.5 < 5.0

< 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 i 9/10-9/14 < 1.0 < 0.5 l 9/17-9/21 < 5.0 < 1.0 < 0.5 < 5.0

< 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 9/24-9/28 1 Table 3.1 Milk Specific Activity (pci/1

1 o)

Date 903 , ,{

3.29

0.43 < 2.0 4/79 2.37

0.37 < 2.0 5/79 1.79

0.45 < 2.0

6/79 2.3320.35' < 2.0 7/79 2.11

0.40 < 2.0 8/79 4.97 f 0.62. < 2.0 9/79 i

4

. - - . , _ - . . . ,___m . -, . . _ . . _. _ . , _ , . . . . - . . - .

Table 4.1 Surface Water Specific Actifity (pCi/1 i i c)

Date Location

Cs K Sr Gross Alpha Gross Beta 0.39 i 0.75 < 2.0 April ON 0.11

0.22 0.33

0.08 3.35

0.35 OFF < 0.1 < 2.0 0.16 0.02 0.35 2 0.08 3.31 0~. 35 May ON 0.45

0.72 17.74

33.58 0.16

0.02 0.18

0.07 3.26

0.34 OFF 0.40

0.74 12.01

33.67 0.20

0.02 0.18

0.07 3.70 0.36 June ON < 0.1 10.10 44.01 0.20

0.02 0.63 i 0.11 5.51

0.45 0FF < 0.1 < 2.0 0.27 0.02 0.23

0.07 3.67

0.36 July ON < 0.1 < 2.0 0.14 0.020.6120.11 3.71

0.38 0FF < 0.1 7.92 37.82 0.21 0.02 0.25

0.07 4.14 0.39 Aug ON < 0.1 7.64

34.05 0.22

0.02 0.41

0.09 3.76

0.38 0FF 0.38

0.80 23.61 i 34.11 0.13 i 0.02 0.08 0.05 4.01

0.39 Sept ON 0.64 2 0.78 < 2.0 0.17

0.02 0.25

0.07 3.51

0.37 0FF 0.48

G.77 < 2.0 0.21 i 0.02 0.16

0.06 3.31

0.36

ON Denotes Rocky Branch Creek as it Enters NCSU Campus OFF Denotes Rocky Eranch Creek as it Leaves NCSU Campus

... ___________i _________________________

Table 5.1 Soil Specific Activity (pCi/gm 1 c)

Location

Gross or . Gross S Th Ra Cs K North 2.94do.50 12.17*1.47 < 0.1 1.74do.25 3.02do.26 18.62*9.09 South 1.90*0.32 10.30il.04 < 0.1 0.87do.25 4.27*0.31 27.37i8.90 East 4.64 0.57 35.93*2.42 1.55 0.56 2.83dO.51 1.81*0.33 81.86il2.76 West 2.20 0.34 20.12*1.50 1.53i0.46 1.70*0.36 1.28dO.27 29.60 13.18 OBG 4.5' O.56i0.17 8.06*0.96 < 0.1 < 0.1 0.09 0.29 < 0.1 NBG 4.5' 3.47do.44 21.92*1.66 2.52d0.57 1.84do.44 < 0.1 24.56*15.89 W 4.5' 1.15*0.22 12.49il.10 < 0.1 1.06*0.24 0.01*0.00 31.33i9.08

Location Denotes Direction from Reactor Burial Ground Samples are in near proximity to fence NEG Denotes New Burial Ground 03G Denotes Old Burial Ground

4.5' Denotes Depth of Sample. Others are at surface.

Table 6.1~ Vegetation Specifis Activity (pCi/gm

1 a )

40g Gross D Cs t Sample Gross a Rx Pine 0.05

0.01 2.26

0.14 .055 * .031 8.92

1.79 0.04

0.01 2.27 0.14 .097 * .038 12.01

2.04 S. Pine Table 7.1 11asco Tank and Sewage Specific Activity (pCi/1

1 o )

Gross D 903 ,

Sample Gross a IR #1 June < 0.5 26.0

13.0 tit #2 June < 0.5 146.9

18.6 IIT #3 June < 0.5 20.2

12.7 IU #1 Aug < 0.5 123.5

17.2 UT #3 Aug < 0.5 122.3

17.1 in #1 Sept < 0.5 82.8

14.8

!!T #2 Sept < 0.5 103.6

15.9 May Sewage < 0.1 13.76

1.11 0.51

0.42

- June Sewage < 0.1 11.24 1.01 0.54

0.43

!Ang Seunge < 0.1 13,8%

1.11 0.64

0.28 i

l l

I l

i l l

Table 8.1 Thermoluminescent Dosimeter (TLD) Locations Designation Location Broughton 410 ft. southwest of and 55 ft. below top of Reactor Stack DCL Roof of David Clark Laboratories Library 629 ft. northwest of and 36 ft. above top of Reactor Stack Riddick 325 ft. southeast of and 46 ft. below top of Reactor Stack Withers 270 f t. northeast of and 19 ft. below top of Reactor Stack Control Room 214 David Clark Laboratories R-3 Entrance to NCSUR-3 Reactor Bay from Control Room PULSTAR PULSTAR Reactor Bay, West Wall Equipment Room PULSTAR Equipment Room East of PULSTAR Bay Control Room PULSTAR Control Room Pool Over PULSTAR Reactor Pool Stack Top of FELSTAR Reactor Stack Table 8.2 Thermoluminescent Dosimeter Readings (Average mR/wk based on Co-60 Standard) 27 d 29 d Area Monitors

4/79 5/79 6/79 7/79 8/79 9/79 Broughton L 2.5 3.8 3.8 5.2 2.9 3.5 Broughton C 1.8 . 2.4 1.8 1.9 1.7 DCL L 1.8 3.0 3.0 3.8 2.0 2.8 DCL C 1.4 1.4 1.0 1.6 1.0 Library L 2.5 3.8 3.8 6.2 3.4 3.6 Library C 1.8 2.0 2.1 2.1 2.2 Riddick L 2.6 3.4 3.4 6.0 3.3 3.7 !

Riddick C 1.9 2.3 2.1 2.1 2.2 l Withers L 2.2 3.4 3.4 4.8 3.1 3.3 l Withers C 1.6 1.7 2.3 1.6 1.6 Control L 2.4 2.6 2.6 5.4 1.7 1.4 Control C 1.2 1.8 1.5 1.5 1.5 Reactor Monitors R-3 L 4.5 5.0 5.0 43.5 2.9 7.2 R-3 C 2.8 3.4 2.7 3.0 2.8 ,

PULSTAR L 54.6 56.4 56.4 128.2 23.8 50.6 PULSIAR C 8.4 8.5 5.8 4.8 4.9 Equipment Room L 20.5 21.2 21.2 55.7' 22.9 31.0 Equipment Room C 18.3 31.0 20.8 18.7 22.3 Control Room L 7.1 8.0 8.0 17.6 6.4 9.4 Control Room C 3.2 3.9 8.1 3.3 6.3 Pool L 37.4 37.2 37.2 94.2 35.4 46.2 Pool C 27.8 40.4 24.1 24.8 34.0 -

Stack L 2.7 3.7 3.7 2.2 2.9 2.8 ;

Stack C 1.2 1.8 1.7 1.6 1.7 ,

t

L Denotes Locally Evaluated LiF Dosimeters C Denotes CaSO 4 :Dy Dosimeters Contracted to Teledyne Isotopes for analysis I

a i

i

ML19344E607

Text

Reference:

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