ML20030D355

Pulstar Annual Rept to NRC Jul 1980-June 1981

ML20030D355
Person / Time
Site:	North Carolina State University
Issue date:	08/27/1981
From:	Bray T, Cockrell R North Carolina State University, RALEIGH, NC
To:
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ML20030D354	List: ML20030D353 ML20030D355
References
NUDOCS 8109010232
Download: ML20030D355 (10)

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PULSTAR ANNUAL REPORT TO UNITED STATES NUCLEAR REGULATORY COMMISSION for the Period of 1 July 1980 - 30 June 1981 j

Submitted by R.G. Cockrell, Director i

NCSU NUCLEAR REACTOR PROGRAM i

Prepared by Thomas C. Bray PULSTAR Reactor Operations Manager i

Reference:

PULSTAR Technical Specifications Section 6.7.5 Docket No. 50-297 Departinent of Nuclear Engineering North Carolina State University i

Raleigh, North Carolina 27650 I

l i

August 27, 1981 l

8109010232 810827

^

gDRADOCK 05000297 PDR

,m DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT For the Period: 1 July 1980 - 30 June 1981 The following report is submitted in accordance with Section 6.7.5 of the PULSTAR Technical Specifications:

6.7.5.(a)

Reactor Ooerating Exnerience (1) The NC?U PULSTAR reactor has been utilized for the following:

a.

Teaching and Short Courses 95.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> b.

Graduate Research 37.96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> c.

Isotope Pmduction 125.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> d.

Neutron Activation Analysis 1365.40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> e.

Neutron Radiography 91.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> f.

NPP Reactor Operator Training.

736.74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> g.

PULSTAR Reactor Operator Training 31.10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> h.

Reactor Calibrations and Measurements 25.60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> 1.

Reactor Health Physics Surveillance 2.17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />

j. Tours and Visitors 65.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> k.

Faculty Research 65.10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> TOU *.

2640.56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> Same reporting period 1979-19Ei 3075.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br /> A cross section of experiments performed relate to these areas:

a.

Radial and axial neutron flux mapping in fuel assembly cooling channels.

b.

Ball Milling and related flow / tracer studies, c.

K-42 and Ma-24 pmduction for medical research.

d.

Reactor Noise Measumments using a water-driven cadmitra ribbon as fuel vibraticn sirrulator.

e.

Reactor Core delta-T measurerrants under forted and free convection flow.

f.

Neutron Activation analysis of fly ash, animal tissue, sediments, rain / river water, msins, graphite, coal, milk, textile fibers, etc.

g.

Neutron Radiography of electrical connectors, capacitors, B C 4

absorber rods, hydmgenous sealants, RTD construction materials.

h.

Control rod reactivity measurement by pmmpt drop method. -- -

(2) Design Changes Accomplished:

No. 80-1 Extend reactor building evacuation.alann notifi-cation to relocated Health Physics Office and Laboratory.

1 j

No. 80-2 De-activate Low Shutdown Margin alann during i

mactor shutdown sequence.

i i

i No. 80-3 Change source of mactor building H & V Damper Contml Air.

4 (3) Changes in Perfonnance Characteristics and Operator Procedures related to Reactor Safety:

1 a.

Change to existing Startup Channel Calibration pmcedures l

(P.C. 5-80) necessitated by replacement of-:aw voltage

(+ 20 volts d.c.) power supply in mactor startup channel.

b.

Change to existing Special Pmcedum 3.1, Removal, Insoec-tion and Installation of Contml Rods and Control Rod Drive Mechanism incorporates contml rod position indicator scale modification made earlier. Also made minor woni changes j

]

and clarification.

1 (4) Results of Seveillance Tests and Inspections:

The reactor surveillance program has mvealed no significant nor unexpected trends in reactor systems perfonnance during the past year, i

{

6.7.5.(b): Total Energy Outnut:

939.67 Megawatt-hours 39.15 Megawatt-days

Pulse Ooerations:

O 4

Reactor was critical:

i 1211.94 hours0.00109 days <br />0.0261 hours <br />1.554233e-4 weeks <br />3.5767e-5 months <br />

Total Cumulative Energy Outout since Initial Criticality 5682.60 Megawatt-nours 236.78 Megawatt-days j

i I

C.7.5.(c): Number of Energency and Unschedaied Shutdowns O

l.

NtInber of Inadvertent Scrams 26 Rease (1) Operator ermr 23 (2) Low Primary Flow setpoint drift 1

(3) Safety Flapper position switch 2

Explanation of (1) above:

Nuclear Power Plant Reactor Operator Training (19) NRP staff opera-tors (4).

Explanation of (2) above:

Primary coolant flow rate trip switch activated at a conservative 490 gpm rather than the 475 gpm designated setpoint. Small indi-cated fluctuations of brief time duration are nonnal in 'he primary ecoling system.

Explanation of (3) above:

Flapper closure handle operates a flappt a position signal switch in addition to physically closing the flapper valve. The flapper closing sequence is ' flapper closure, ti switch actuation'. Because this operating sequence requires a rather forceibl pull on the flapper han-die to operate the switch pmperly, occasionally an operator will not exert sufficient force to close both flapper and switch. The flapper valve has not been observed open when the position switen was indica-ting closed.

6.7.5.(d): Major Maintenance Ooerations None during this reporting period.

6.7.5.(e): Changes in the Facility, Proceuan>s, Tests and Exoeriments:

(1) Design Change 80-1 " Addition of two (2) buzzers in pcuu-llel...th Reactor Building Evacuation Homs" was accom-plished to prcvide inmediate notice to the Reactor Health Physicist in case of building evacuation. Prior to this change, the primary method of notification was by tele-phone, and should the telephone be in use at the time of building evacuation onset, the only recourm for notifi-cation was to dispatch a mnner to the relocated llealth Physicist's office and/or laboratory.

Safety evaltation.

"The evacuation horn installation allows connection of additional sounding devices. Connect-ing two (2) buzzers in parallel with the existing reactor building evacuation horn bus is therefore in keeping with the as-built signalling p_an and does not constitute an unreviewed change.

(2, Design Change 80-2 " Modification to deactivate the low Shutdown Margin Alarm during reactor shutdown sequence" pmvents meaningless actuation of the LSDM alann. During.

startup and operation, the mactor operator must maintal 1 a specified SDM by insuring that the mactor power level is less than four (4) watts until the control rods reach a setpoint in tems of outwart travel. However, during routine shutdowns the indicated reactor power (with nomi-nal power history) exceeds four watts even though the contml rods are iblly seated (and hence below the set-point mentioned above).

Safety evaluation based on stipulation of RPC mview concluded tN change could be made, provided that at least bimonthly the operability of the LSDM alam be verified and recorded.

(3) Design Change 80-3 " Change Source of Reactor Building Main H & V Damper Control Air" was made to pmvent recurring loss of H & V damper control air supplied from a compmssor subject to frozen air linc 3 during the winter months. The physical change resulted in utilizing an air compressor in-side the reactor building not subject to seasonal malfune-tions.

Safety eva'uation was not mqaimd because change did not impact oper ating mactor safety.

(4) Procedure Change 5-80 was a revision to PS 1-Ol:S1, "Startup Channel Calibration" and was required by replacement of the LVPS in the startup channel electronics. Specifically, the replacement power supply +_ 20 volt adjustments differed fmm the fomer LVPS and the mlated calibration procedure was changed to meet the manufacturer's instructions.

'Ihe safety evaluation is contained in DC 79-11, reported last ye w.

(5) Procedum Change 1-81 was Revision #2 to SP 3.1, " Removal, Inspection, and Installation of Control Rods and Control Rod Drive Mechanisms". Control rod position scale modifications accomplished earlier resulted in the necessity of making ad hoc changes in numerical rerdout of contml rod positions when performing SP 3.1.

This procedure change revised the nurrerical descriptions in SP 3.1 of control rud positions to agree with the reactor console scale indicators. Some minor word changes in procedural steps were also made.

A safety evaluation was not appropriate to this procedure change because the mvision did it impact operating mactor safety.

(6) Experiment Request 81-1 was approved to allow installation a reactor noise simulator device in the NCSU PULSTAR reactor com. 'Ihis particular experiment, untried heretofore, con-sisted of an empty fuel box containing a water driven, vi-brating cadmium ribbon designed to produce smM1 core reactivity changes on the order one could expect %m fbel vibration.

_4_

6.7.5.(e)(6) continued:

The safety evaluation sunmary "'Jhe combined effect of very low operating power and rather sizeable experi-ment mactivity value will produce trutine core dynamics and, themfom, assure administrative mactor operating limitations will be observed and no IfD will be approached."

i 6.7.5.(f): Radioactive Effluents Liquid Wastes (stImnrized by qtnrter) 1.

Radioactivity Released During the Reporting PericKi (a)

(bi (c)

(d)

(e)

Quarter Period No. of Totcl Total Vol. Diluent Trititra 1980 Batches pCi Liters Liters pCi 1 Ju y-30 Sept.

12 88.07 3.89E4 1.08E7 55.30 l

lst 2nd 1 Oct..; Dec.

6 79.75 1.90E4 6.46E6 145.56 1981 3rxl 1 Jan.-31 Mar.

6 4.76 1.93E4 6.46E6 50.56 4th 1 April-30 June 10 45.28 3.15E4 8.61E6 61.31 (f) 217.86 pCi of activity were mleased during reporting period.

(g) 312.73 pC1 of trititIn wem released during mporting period.

2.

Identification of Fission and Activatici Products.

The concentration of each batch of 1.a above was less than 4E-5 pCi/ml. Therrfore, an isotopic analysis was not mquired.

3.

Disposition of Liquid Effluents not Releasable to the Sanitary Sewer System.

%e activity concentration of each batch of 1.a above met the requimments of 10CFR20, Appendix B, Note 2d, and were mleased to the sanitary sewer system. Diluent was used as necessary.

g.

Gaseous Waste (stImnrized on a monthly basis) 1.

Radioactivity Discharged Nring the Reporting Period (in curles) for:

(w Gases Total Period Ci g

1980 6 June - 7 July 736,87 0.56 7 July - 6 Aug.

744.13 0.34 6 Aug. - 4 Sept.

702.02 0.72 4 Sept. - 3 Oct.

698.58 0.52 3 Oct. - 3 Nov.

735.20 0.64 3 Nov. - 2 Dec.

703.72 0.50 2 Dec. - 2 Jan.

712.75 0.31 1981 2 Jan. - 2 Feb.

773.25 0.60 2 Feb. - 2 Mamh 714.60 0.40 4 March - 6 April 791.65 0.49 6 April - 16 May 960.42 0.64 16 May - 17 June 768.05 0.41 9041.22 6.13.

(b) Particulates, with half lives greater than cic;bt (8) 00ys.

Particulates whose half life is gmater than (8) days were 1 t found on any filter removed from the Particulate Manitor during this reporting period.

2.

Gases and Particulates Discharged During 'DTis Reporting Period.

Gases:

Argon-41 was discharged during this reporting period in the total activity of 6.13 curies for a.: average concentration of 2.00 E-8 pCi/ml.

The MPC for A-41 is 4E-8pC1/ml in an unmstricted area.

Parciculates:

See 1.b above.

Solid Wastes from Reactor 1.

Total volume of solid s:aste - 62 ft.

2.

Tr'

. ictivity of solla vaste - 0.008195 curies of shipments and disposition:

2C August 1980 DiJposal by IIECO 7 October 1980 Disposal by IECO 1 December 1980 Disposal by IECO 4 February 1981 Disposal by fiECO 17 ".arth 3 981 Disposal by TECO 26 May 1981 Disposal by IJECO G.7.5.(g) Personnel Radiation Exposure Report (Reporting Period -

1 June 1980 - 31 May 1981).

IJame Total Dose

("*

Faculty and Staff Biddy, Jr., Oscar D.

D.0 Bilyj, Stephen J.

O.105 Brackin, Thomas L.

0.0 Bray, Thomas C.

0.058 Caccamo, David P. (Start 01/13/81) 0.0 Cockrell, Robert G. (Start 08/18/80) 0.0 Cross, Robert D.

0.0 Douglas, William G.

0.027 Gardner, Robin P.

0.040 Grady, Stanley M.

0.019 Holland, Lao (Start 08/25/80) 0.020 Kohl, Jerrme 0.027 Lawrence, Craig 0.0 Lewis, Luther E.

O.C I'.unn, Hugh (Start 08/08/80) 0.0 Prico, Leslie F. (TerTainated 11/30/80) 0.055 Phiner, Glenda 0.0.

6.7.5.(g) continued Faculty and Staff Total Dose Saxe, 'aymond F.

0.061 Stam, Shrairr 0.0 Turinski, Paul J. (Start 07/01/80) 0.0 Ver;pese, Kumvilla 0.0 Weaver, Jack N.

0.0 Ztamit, Lloyd 0.0 F adiation Protection Office Personnel Anderson, Tamry L. (Start 02/10/81) 0.0 Ball, Arthur C. (Terminated 07/01/80) 0.0 Camthers, L. Thorras 0.0 Corbett, E. Marcelle 0.0 Debnam, Joshua 0.0 Freeman, Ralph M.

0.0 Ihrris, Ralton (Start 09/11/80) 0.0 House, Andy (Start 06/01/81) 0.0 Howard, Suzanne M. (Terminated 12/31/80) 0.0 Mangum, Royelle O.

0.056 Morgan, D. William 0.012 Custodians Dunn, Johnnie J.

0.0 Jones, Arthur (Teminated 11/30/80) 0.0 Lucas, Calvin (Start 02/05/81) 0.0 Sanders, Joseph O.0 Young, Charles 0.0 Students - 66 film badges wem issued to Nuclear Engineering Department students during the reporting period. No signifi-cant radiation exposams were reported. The majority of the radiation exposures wem in the 'no measurable exposure' range Visitors and Short Courses - 561 film badges were issued to vistors and participants in short courses during t'1 reporting period. No significant radiction exposures were reported.

The majority of the radiation exposures were in the 'no mea-surable expos".:' range.

Strmrv of Radiation and Contamination Surveys l

l Radiation surveys of +bc PULSTAR Bay did not dimlose any trend that would be indicative of incmasing radiation levels.

l l

Contamination surveys were negative this past year. Care-l l

fbl clean-up and survey irrmediately after finishing any work task in the PULSTAR Bay precludes a routine survey frm find-ing contamination. - -

s h.

Description of Environmental Surveys Outside of Facility.

Due to manpower problems in the Radiological Protection Office, the envirurmental reports will be subnitted later. The raw data has been collected and partially analyzed.

9_

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