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Annual Rept for Jul 1986 - June 1987
	ML20237H385
Person / Time
Site:	North Carolina State University
Issue date:	06/30/1987
From:	Bray T, Geoffrey Miller; North Carolina State University, RALEIGH, NC
To:	; Office of Nuclear Reactor Regulation
References
	NUDOCS 8709030245
	Download: ML20237H385 (11)
	v • d • e

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PULSTAR ANNUAL REPORT TO UNITED STATES NUCLEAR REGULATORY COMMISSION for the Period of 1 July 1986 - 30 June 1987 Submitted by G. D. Miller, Associate Director NCSU NUCLEAR REACTOR PROGRAM Prepared by Thomas C. Bray PULSTAR Reactor Operations Manager References PULSTAR Technical Specifications Section 6.7.5 Docket No. 50-297 Department of Nuclear Engineering North Carolina State University Raleigh, North Carolina 27650 l

! August 28, 1987 l

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DEPARTMENT OF NUCLEAR ENGINEERING 4

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PULSTAR REACTOR ANNUAL REPORT For the Period: 1 July 1986 - 30 June 1987' The following report is. submitted in accordance with Section 6.7.5 of the PULSTAR Technical Specifications:

6.7.5.a Reactor Operating Experience i

'(1) The NCSU PULSTAR reactor has been utilized for the followings.

a. Teaching and Short Courses 63.86 hours9.953704e-4 days 0.0239 hours 1.421958e-4 weeks 3.2723e-5 months

b. Graduate Research 410.35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months

c. Faculty.Research 1215.51 hours5.902778e-4 days 0.0142 hours 8.43254e-5 weeks 1.94055e-5 months

d. Isotope Production. 2.80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months

e. Neutron Activation Analysis 2,514.85 hour9.837963e-4 days 0.0236 hours 1.405423e-4 weeks 3.23425e-5 months s-

f. NPP Reactor Operator Training 599.88 hours0.00102 days 0.0244 hours 1.455026e-4 weeks 3.3484e-5 months

g. PULSTAR Reactor. Operator. Training 13.22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months

h. Reactor Calibrations and Measurements 25.87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months

1. Reactor Health Physics Surveillance 2.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TOTAL 4,848.46 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-5 months Same reporting period'1984-85 4,125.42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months Reactor Facility Tours. 60.00 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.- Fast neutron flux-induced synergistic erosion effects on graphite first-wall plasma coating in fusion reactors. -

d. Thermal neutron depth profiling of Boron-implanted silicon.

e. Neutron diffusion length measurements in graphite.

f. . Target / detector distance and co111mation optimization in the Prompt Gamma facility utilizing Boron, Cadmium, Molybdenum, Sulfur and Titanium. !

g. kev Neutron Beam development,

h. Neutron Radiography.

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(2) Changes in Performance Characteristics and Operator Procedures Related to Reactor Safety:

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.

6.7.5.b Total Energy Output:

1365.275 Megawatt-hours 56.886 Megawatt-days

Pulse Operations:

0

Reactor was critical:

1642.433 hours0.00501 days 0.12 hours 7.159392e-4 weeks 1.647565e-4 months

Cumulative Total Energy Output since Initial Criticality:

12,592.566 Megawatt-hours 524.690 Megawatt-days 6.7. 5.c a Number of Emergency and Unscheduled Shutdowns >

1 Unscheduled shutdown - Radiation survey meter accidentally dropped in pool. Shutdown to recover survey meter

Number of Inadvertent Scrams:

23 Reasons: (1) Operator Error 17 (2) Low Flow Setpoint Drift 2 (3) Loss of Commercial Electrical Power 2 (4) Undetermined 2 Explanation of (1) above:

Nuclear Power Plant Reactor Operator Training and NRP staff Operations and Training.

Explanation of (2) above:

I Primary coolant flow rate trip switch activated at a conservative 490 gpm rather than the 475 gpm designated setpoint. Small

Indicated fluctuations of brief time duration are normal in the primary cooling system.

Explanation of (3) above:

Interruption of campus electrical power will result in an automatic reactor scram by virtue of RSS design.

6.7.5.de Major Maintenance Operations: .

i None during this reporting period.

6.7.5.e Changes in Facility, Procedures, Tests and Experiments:

Design Change 86-1, Cooling Water Temperature Recorder Modification to Eliminate Spurious Alarm.c.

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

1. Radioactivity Released During the Reporting Period.

(a) (b) (c) (d) (e)

Period No. of Total Total Vol. Diluent Tritium Quarter 1986 Batches pCl Liters Liters pCi ist 1 July-30 Sept. 8 56.92 2.72 E4 1.15 E4 61.29 2nd 1 Oct.-31 Dec. 4 31.82 1.36 E4 6.60 E4 36.72 1987 3rd- 1 Jan.-31 Mar. 6 35.1 2.03 E4 6.75 E4 64.148 q 4th 1 Apr.-30 June 6 16.66 2.04 E4 2.13 E4 114.24 (f) 140.5 pCi were released during this reporting period.

(g) 276.4 pCi were released during this reporting period.

2. Identification of Fission and Activation Products.

The gross alpha-beta-gamma activity of the batches in 1(a) above !

were less than 4 E-5 pC1/ml. An isotopic analysis of these batches indicated only background activity.

3. Disposition of Liquid Effluents Not Releasable to Sanitary Sewer System. t All batches of 1(a) above when diluted by campus water released to the sewer resulted in activity considerably less than 4 E-7 pCi/ml. ;

Therefore, all batches were released to the sanitary sewer system.

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Gaseous Waste (summarized on a monthly basis)

1. Radioactivity Discharged During the Reporting Period (in curies) for (a) Gases Total Time Period Hours C1, 1986 27 June- 4 Aug. 912.00 0.96 7 Aug - 3 Sept. 744.00 .83 4 Sept.- 1 Oct. 672.00 .66 2 Oct.- 31 Oct. 719.50 .59 ' ' ~ -

1 Nov. - 1 Dec. 744.00 .45 1986- 2 Dec. - 14 Jan. 1033.83 .74 1987 15 Jan. - 12 Feb. 698.00 .77 '

13 Feb.- 9 Mar. 599.34 .67 10 Mar. 6 Apr. 672.17 .62 '

7 Apr. - 6 May 719.00 .81 7 May - 5 June 743.58 .61 6 June - 6 July 743.75 .62 Totals 9001.17 8.33 (b) Particulate whose half-31fe is greater than eight (8) days.

Filters from the particulate monitoring channel were i analyzed upon removal each week. There was no particulate l activity ((b) above) indicated on any filter during this I reporting period.

2. Gases and Particulate Discharged During This Reporting Period.

Gases:

The yearly averaged concentration of Argon-41 released from the PULSTAR Reactor facility exhaust stack during this period was 2.7 E-8 pC1/ml .

The MPC in an unrestricted area for Argon-41 is 4 E-8 pCi/ml.

Particulate:

See Gaseous Waste 1(b) above.

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I Solid Waste from Reactor

1. Total volume of solid waste - 30 ft3 {

2. Total activity of solid waste - 0.31 mci

3. Dates of shipments and disposal: ,

i 29 July 1986 - Disposal by CNSI 19 Sept. 1986 - Disposal by CNSI l

'26 Sept. 1986 - Disposal by CNSI l

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6.7.5.g: Personnel Radiation Exposure Report (Reporting Period 07/01/86 - 06/30/87)

Faculty and Staff Total Exposure (rem)

Auciello, Orlando E. 0.020 Biddy, Oscar D. 0.010 ;

Bilyj , Stephen J. 0.050 '

Brackin, Thomas L. 0.010 Bray, Thomas C. 0.030 ;

Caves, John R. 0.020 j Cornetti, Richard 0.020 Davis, Glenda 0.010 Doster, J. Michael 0.020 Gardner, Robin P. 0.0 Gilligan, John 0.020

.Grady, Stanley M. 0.020 Hankins, Orlando H. 0.010 Kimberley, Michael M. 0.020 Kohl, Jerome 0.010 Lambert, Joseph P. 0.010 Mani, Kolam V. 0.010 Miller, Carry D. 0.020 Munn, R. Hugh 0.030 '

Murty, K. Linga 0.050 Rayno, Donald R. 0.060 Saxe, Raymond F. 0.030 Stam, Ephraim 0.010 Strickland, David D. 0.010 Turinsky, Paul J. 0.010 Verghese, Kuruvilla 0.030 Weaver, Jack N. 0.010 Wehring, Bernard 0.010 Wilshire, Frank W. 0.030 l Other - 31 film badges were issued to graduate students and temporary staff, 47 film badges were issued for student laboratories, 102 film badges were issued to participants in short courses, 433 film badges were issued to visitors.

No significant radiation exposures were reported; the majority of the l

radiation exposures were in the "no measurable exposure" range.

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6.7.5.h Summmary 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.

I 6.7.5.1: Description of Environmental Surveys Outside of the Facility, i l

(See Attachment A)

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ATTACHMENT A TO: Thomas C. Bray FROM NCSU Radiation Protection Office

SUBJECT:

Attachment A Portion of R-120 Annual Report DATE: August 26, 1987 Oue to equipment breakdowns and instrumentation problems, the Environmental Surveillance Report for this report period is not available for submission at this time. As soon as the report is completed, it will be mailed to you.

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Departnient of Ninicar Engineering Nuclear Hructor Progrant Ih4 79'9 7)P 2N6-71#9 (919) 73pa32 Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 DocketNo.50-297/

ANNUAL REPORTM

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 1986 through 30 June 1987.

Very truly yours,

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Garry 4. Miller l Associate Director )

TC8/t;DMiedt cc: All with attachment: l (1) USNRC Director of Regulatory Operations, Region II (2) Dr. John F. Roberts, Chairman Radiation Protection Council (3) Dr. Jimmie J. Wortman, Chairman Reactor Safeguards Advisory Committee (4) Mr. D. W. Morgan Radiation Protection Officer (5) Dr. L. K. Monteith, Dean School of Engineering (6) Dr. Paul J. Turinsky, Head Department of Nuclear Engineering kOY North Caroluna State University is a Land Grant Uniwrsity and a constituent institution of The University of North Carolina.

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ML20237H385

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SUBJECT:

Dear Sir:

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