ML20059D145

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Pulstar Annual Rept to NRC for Jul 1989 - June 1990
ML20059D145
Person / Time
Site: North Carolina State University
Issue date: 06/30/1990
From: Bray T
North Carolina State University, RALEIGH, NC
To:
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ML20059D143 List:
References
NUDOCS 9009060108
Download: ML20059D145 (11)
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PULSTAR ANNUAL REPORT TO UNITED STATE NUCLEAR REGULATORY COhihilSSION for the i

Period 1 July 1989 30 June 1990 Submitted by f

G. D. hiiller, Associate Director NCSU NUCLEAR REACTOR PROGRAh!

Prepared by Thornas C. Bray PULSTAR Reactor Operations hianager

Reference:

PULSTAR Technical Specifications l Section 6.7.5 Docket No. 50 297 Department of Nuclear Engineering North Carolina State University Raleigh, North Carolina 27607

e August 31,1990 i

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4 DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT Por the Period: 1 July 1989 30 June 1990 The following report is submitted in accordance with Section 6.7.5 of the PULSTAR Technical Specifications:

6.7.5.a Reactor Operatine Experience:

(1) The NCSU PULSTAR Reactor has been utilized for the following:

a. Teaching and Short Courses 115.80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />
b. Graduate Research 19.55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />
c. Isotope Production 41.67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />
d. Neutron Activation Analysis 2088.52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br />
c. NPP Reactor Operator Training 287.02 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
f. PULSTAR Reactor Operator Training (PTO) 46.17- hours
g. Reactor Calibrations / Measurements & Surv. 23.43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />
h. Reactor Health Physics Surveillance 3.02 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> TOTAL 2625.18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> l Same reporting period 1988 1989 3347.19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> A cross section of experiments performed in the reactor relate to these areas: i
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. Thermal neutron depth profiling of Boron implanted silicon, i
e. Neutron diffusion length measurements in graphite,
f. Neutron Radiography,
g. Thermal neutron diffusion in oils l l

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(2)

Chanres in Perforrnance Charseteristics Related to Reneter Safety:

None (3) Results of Surveillance. Tests. and Inspections:

I The reactor surveillance program has revealed no significant nor knexpected trends in reactor systems performance during this report period.

6.7.5.b Tots 1 Enerry Outout:

990.597 Megawatt hours 41.275 Hegawatt days Pulse Operations:

0 Reactor was Critical:

1 1232.30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> Cumulative Total Enerry Outout since Initial Criticality:

15829.076 Megawatt hours 6$9.545 Megawatt days l

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6.7.5.c Number of roergenev and Unscheduled Shutdovns:

Unscheduled shutdowns 2 total (1) Response to building fire alarm (2) Pneumatic Shuttle could not be moved from irradiation position.

Inadvertent scrams 7 total (3) Operator error - - 7 Explanation of (1) above:

Operating Procedures require reactor shutdown by manual serem (followed by building evacuation) when fire alarm sounds. Fire was of chemical origin in a laboratory not related to the reactor facility.

Explanation of (2) above:

Pneumatic irindiation facility (" rabbit" or PN) shuttle had been sent to the PN irrad16 tion position in the south reflector peak adjt:ent to the reactor core far a 30 second exposure. Upon actuating the PN return switch, the raciochem station control panel blew a fuse for an undetermined reason and the rabbit could not be withdrawn from the core irradiation posit 3on. Rather than over expose the target the operator shutdovn the reactor by manual scram; the' correct action under the circumstances.

Explanation of (3) above:

Improper operation of the linear level power channel range switch by NPP I and NRP Operator trainees.

6.7.5d. Major Maintenance Operations:

Repaired pool liner w/ epoxy see': see NP 1 90 on file at facility, j

6.7.5e. Chanres in Facility. Procedures. Tests. and Experiments:

(1) Design Change 90 1, Replaecment instrumentation nower supplies for PUI. STAR Reactor contrni console The seven power supplies being replaced are original equipment in the reactor control and are of vacuum tube design. This change authorizes removal of the original power supplies and replacement with modern solid state technology supplies having identical electrical performance characteristics. Original electrical wiring and connections to other components in the affected power measuring channels !

will remain intact.

rut.staa etaette u.wat. erece 4 1 au '6e - so ams '90 4

Safety Evaluation: "runctional Design (Performance) of reactor nuclear instrumentation will not be changed.

Replacement power supplies will be adjusted to provide same electrical potentials as present vacuum tube. type equipment."

(2) Procedure Changes (a) Twenty nine (29) llealth Physics Procedures wert reviewed and approved by the Radiation Protection Council. Some of these procedures are revisions and some are new methodology. All subject procedures are noted on the index sheet attached to this report.

(b)

  • 5.sion 5 to the PULSTAR Operations Manual was made e, improve some reactor system descriptions; dccument minor procodural changes; remove typographical and figure errots; and standardize operations manual format.

(c) PC 50 89 was a change to the Technical Specifications that increased membership on the Reactor Safeguards Advisory Group from three (3) to five (5) individuals and extended appointment term from three (3) years to five (5) years.

(d) NP 1 90 documented the procedural steps to accomplish permanent repair to the reactor primary pool liner leak. First described in our 1987 1988 Annual Report (Paragraph 6.7.5.d), the leak repair culminated almost two years of rigorous leak causal analyses and ,

proposed repair techniques.

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1 i

0 BEALTH PHYSICS PROCEDURES INDEX 1

.MCL .BEM 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)

--* 13 0 Physical Examinations & Bloassey Requirements for SCBA Users

---* 10 1 2 inventory and 1.ocation of Special Nuclear Material

10 2 2 Special Nuclear Mate 1al (SNM) Accountability

--* 10 3 2 Radiation Work Permit

--+ 10-5 2 Transfer and Shipment of Radioactive Material

--+ 20 1 2 Servicing Continuous Filter 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 Valves

--* 20-6 2 PULSTAR Deep Pool Water Samples

--* 20 7 2 Water Sample Preparation for Neutron Activation Analysis

20-8 2 Water Sample Preparation for Gross Beta / Gamma Counting  ;

---* 20 4 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

* 20 12 2 Changing Continuous Air Monitors (CAM) Filters .

---* 20 13 2 Calibration of Eberline Continuous Air Monitor (CAM) l

---> 20 14 2 Radiation and Contamination Surveys of PULSTAR Bay l  : 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 Drift and Response Checks for Direct Read Out Dosimeters 20 18 0 Decontamination 20 19 0 Lower Limit of Detection (LLD) and Minimum Detectable Concentration (MDC)

--* 20-20 0 Sample Analysis Using The Nuclear Services Gamma Spectroscopy System

---* 20 21 1 Radiochemical Determination of Tritium in Waste Water, Urine and other Biological Samples 1 --* 20-22 0 GM Detector Sensitivity to Argon-41 (Channel #5) ,

1 30 1 2 Access to Restricted Areas 30 2 0 Radiation Safety Training

40 1 3 Utilization of Reactor Irradiation Facilities

---+ 40-2 0 Encapsulation

-- -

  • 50-1 0 Pressure Testing Sump Discharge Line i

lasved by the NRP Admin. office May 16,1990 nie C.\MANINDX\HP

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, PtfLSTAt ELAe7t-t AsamAL ttstet 3 1 MfLV '89 + 30 amt '90 6.7.5(F) Radiosetive Effluents:

Liould Vaste (summarized by quarters) ,

1. Radioactivity released during the reporting period.

(a) (b) (c) (d) (e) no. of total tot. vol. Diluent Tritium Ounrter Period batches uCi . 2n ltrs 1tra uCi 1st 1 Jul 30 Sep 89 6 68.93 2.04 E4 1.52 E5 64.69 2nd 1 Oct 31 Dec 89 6 23.34 2.05 E4 3.78 E4 20.28 3rd 1 Jan 31 Mar 90 6 34.65 2.05 E4 6.61 E4 14.84 4th 1 Apr 30 Jun 90 6 511.50 2.05 E4 1.25 E6 481.39-(f) 581.20 pCi were released during this reporting period.

(g) 638.42 pCi were released during this reporting period.

2. Identification of Fission and Activation Products.

The gross alpha beta *Eamma activity of the batches in (a) above were less than 4 x IO'S pCi/ml. An isotopic analysis of these batches indicated only background ,

activity,

3. Disposition of liquid effluents not releasable to Sanitary Sever System. All batches of 1(a) above when diluted by campus water resulted in activity considerably less than 4 x 10'? pCi/ml. Therefore all batches were released to the sanitary sever system.

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e tutstat DLACTC) ANifDAs RsPC'.T 6 ass .es - n aus 's,e Caseous Vaste (summarized monthly)

1. Radioactivity discharged during the reporting period (in Curies) for:
a. Cases Total Time ItaI Period In Hours Curles 1989 04 Jul - 1 Aug 704.42 0.17 02 Aug 31 Aug 736.17 0.23 01 Sep 01 Oct 767.30 0.37 02 Oct 31 Oct 744.50 0.63 01 Nov 30 Nov 744.75 0.43 01 Dec 31 Dec 768.25 0.50 1990 01 Jan 31 Jan 718.25 0.25 01 Feb 01 Mar 720.00 0.73 02 Mar 30 Mar 680.75 0.32 01 Apr 30 Apr 703.75 0.50 01 May 20 May 706.25 0.60 30 May 28 Jun 712.20 Q 41 8706.59 5.21 (b) Particulates whose half life is gr' eater than (8) days.

Filters from the particulate monitoring channel were analyzed upon removal and again the following week. There was no particulate activity ((b) abovt.) indicated on any filter during this reporting period.

2, Oases and particulates discharged during this reporting period.

Cases:

The yearly average concentration of Argonl released from the PULSTAR reactor facility exhaust stack during this period was 1.7 x 104 pCi/ml.

Particulates:

See gaseous vaste 1(b) above, r

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2 m y iso - so m e oo SOLID VASTE FROM REACTOR j

.i a 1. total volwee' of solid waste 38 ft' d

' 2, total activity of solid waste - 0.13312 sci

3. Dates of shipments and. disposal:

11 Aug 1989 CNSI .

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19 Apr 1989: CNSI- ti 12.Apr.1989 ' CNSI' ,  ;

6 Jun 1990 CNSI F

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6.7.5.G: P;rtonnel Radiation Exposure Report (Reporting Period 07/01/89 06/30/00)

Facultv and Staff Total Exooture fremi f

BIDDY, Oscar D. 0.010  :

BILYJ, Stephen J. 0.060 BRACKIN, Thomas L. 0.0 BRAY, Thomas C. 0.020 BULLEN, Daniel B. 0.0 CAVES, John R. 0.020 DAVIS, Glenda 0.010

. DOSTER, J. Michael 0.010 ELLEMAN, Thomas S. 0.010 , ,

GARDNER, Robin P. 0.010 GILLIGAN, John 0.010 GRADY, Stanley M. 0.080 HANKINS, Orlando H. 0.0 JOHNSON, Jr., Charles M. 0.0 -

KOHL, Jerome 0.0 LAMBERT, Joseph P. F. 0.010 LODGE, Phillip S 0.030 MANI,Kolam V. 0.020 MILLER, Garry D. 0.020 MUNN, R. Hugh 0.040 MURTY, K. L. 0.030 RAYNO, DONALD R. 0.020 STAM,E. 0.030 STRICKLAND, David D. 0.020 TITTLE, Charles . 0.0 ,

TURINSKY, PaulJ. 0.110 VERGHESE, Kuruvilla 0.010 WEAVER, Jack N. 0.010 WILSHIRE, Frank W. 0.030

OTHER
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l Approx. 25 film badges were issued monthly to graduate students and temporary staff; Approx.130 film badges were issued for short courses; Approx. 380 film badges were issued for visitors.

No significant radiation exposures were reporled; the majority of these radiation exposures were

- in the 'no measurable exposure" range.

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6. 7. 5.h J.uama ry of Radiation and Contamination Surveys Within the Facility i

_ . . l Neither the-radiation nor the contamination surveys indicated.any I trend or shift-of omta'from past experience / surveys.  !

6.7.5.1 -Descrietion of Environmental survevs outside of the racility .

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