ML20063J461
| ML20063J461 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 08/27/1982 |
| From: | Bray T North Carolina State University, RALEIGH, NC |
| To: | |
| Shared Package | |
| ML20063J446 | List: |
| References | |
| NUDOCS 8209020413 | |
| Download: ML20063J461 (9) | |
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s PULSTAR ANNUAL REPORT TO UNITED STATES NUCLEAR REGULATORY COMMISSION for the Period of 1 July 1981 - 30 June 1982 Submitted by R. G. Cockrell, 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 27650 August 27, 1982 8209020413 820826 PDR ADOCK 05000297 R PDR
DEPARTMENT OF flVCLEAR 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 Operating Experience (1) The NCSU PULSTAR reactor has been utilized for the following:
- a. Teaching and Short Courses 105.98 hours0.00113 days <br />0.0272 hours <br />1.62037e-4 weeks <br />3.7289e-5 months <br />
- b. Graduate Research 10.26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />
- c. Faculty Research 19.21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />
- d. Isotope Production 40.45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />
- e. Neutron Activation Analysis 1762.37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />
- f. Neutron Radiography 11.32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> 9 NPP Reactor Operator Training 1230.37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> D. PULSTAR Reactor Operator Training 55.61 hours7.060185e-4 days <br />0.0169 hours <br />1.008598e-4 weeks <br />2.32105e-5 months <br />
- i. Reactor Calibrations and Measurements 29.43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />
- j. Reactor Health Physics Surveillance 7.80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />
- k. Tours and Visitors
- 2.42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> TOTAL 3275.22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> Same reporting period 1980-81 2640.56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br />
- Reactor Facility tours not utilizing the reactor. 92.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> A cross section of experiments performed in the reactor relate to these areas:
- a. Axial neutron flux mapping in graphite thermal column.
- b. Ball Milling and related flow tracer studies.
l c. F-18, Ts-42 and Na-24 production for medical research.
- d. Reactor Noise Measurements using a water-driven cadmium ribbon as fuel vibration simulator.
- e. Neutron Activation Analysis of fly ash, animal tissue, sediments, rain / river water, resins, coal, graphite, milk, textile fibers, etc.
- f. Neutron Radiography of electrical connectors, capacitors, 8 C absorber rods, hydrogenous sealants, RTD construction 4
j materials.
i
( (2) Design Changes Accomplished:
i No. 81-1 Replace existing reactor coolant temperature measuring
! system with improved equipment.
t
(3) Changes in Performance Characteristics and Operator Procedures related to Reactor Safety:
None (4) Results of Surveillance Tests and Inspections:
The reactor surveillance program has revealed no significant nor unexpected trends in reactor-systems performance during this reporting period.
6.7.5.(b): Total Energy Output:
1022.21 Megawatt-hours ~
42.15 Megawatt-hours
- Pulse Operations:
0
- Reactor was critical:
1438.18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />
- Cumulative Total Energy Output since Initial Criticality 5704.81 Megawatt-hours 279.37 Megawatt-hours 6.7.5.(c): Number of Emergency and Unscheduled shutdowns 0
- Number of Inadvertent Scrams:
55 Reasons: (1) Operator error 51 (2) Low Primary Flow setpoint drift 1 (3) Loss of commercial power 3 Explanation of (1) above:
l Nuclear Power Plant Reactor Operator Training (48) and NRP staff opera-tors (3).
Explanation of (2) above:
Primary coolant flow rate trip switch activated at a conservative 490 gpm rather than the 475 gpm designated setpoint. Small indicated fluctuations of brief duration are normal in the primary cooling system.
- Explanation of (3) above:
Commercial or campus electrical power interruptions result normally in l
i reactor shutdown. Procedural response to this occurrence requires starting the auxiliary generator and monitoring the reactor power decrease until the control rod magnets are fully down.
6.7.5.(d): Major Maintenance 0perations:
None during this reporting period.
6.7.5.(e): Changes in the Facility, Procedures, Tests and Experiments:
Design Change 81-1 "PULSTAR Reactor Cooling System Tempera-ture Measurement Channel Replacement with Improved, Similar Equipment" was accomplished to improve system accuracy.
The original temperature measuring channel incorporated sensors ( RTD's) with fixed thermal-electrical character-istics, not capable of individual sensor calibration.
Heretofore, when a sensor aged out of specified accuracy, replacement was necessary and expensive. The replace-ment temperature measuring system features RTD's with individual current transmitters that enable each RTD output to be calibrated independently. Total system accuracy is improved and RTD replacement due to normal use aging has been eliminated.
Safety Evaulation: " The primary and secondary cooling system temperature measuring channel is part of the Reactor Safety System ( RSS); therefore, this change is a safety-related issue. System accuracy of the replacement equipment is superior to that currently installed and was selected because of excellent performance history in many NPP faci-lities."
r 6.7.5(f): Radioactive Effluents Liquid Wastes (summarized by quarter)
- 1. Radioactivity Released During the Reporting Period Quarter Period No. of Total Total Vol. Diluent Tritium 1981 Batches pCi Liters Liters Ci ist 1 July-30 Sept. 8 18.72 2.56E4 3.14E4 141.74 2nd i Oct.-31 Dec. 10 41.15 3.19E4 8.10E4 887.46 1982 3rd 1 Jan.-31 Mar. 6 24.41 1.97E4 4.22E4 200.46 4th 1 Apr.-30 June 8 7.97 2.62E4 3.56E4 201.59 (f) 92.25 uCi of activity were released during the reporting period.
(g) 1.43 Ci of tritium were released during the reporting period.
- 2. Identification of Fission and Activation Products.
The concentration of each batch of 1.a above was less than 4E-5 uCf/ml.
Therefore, an analysis was not required. However,several batches were analyzed with only background data indicated in the sample spectrum.
- 3. Disposition of Liquid Effluents not Releasable to the Sanitary Sewer System.
The concentration of activity in each batch of 1.a above, considering the campus dilution water as necessary, was equal to or less then 4E-7pCi/ml (10CFR20, Appendix B, Note 2d) and, therefore, each batch was released to the sanitary sewer system.
- g. Gaseous Waste (sumnarized on a monthly basis)
, 1. Radioactivity Discharged During the Reporting Period (in curies) for:
(a) Gases
! Total l Time Period Hours Ci 1981 17 Jun -16 Jul. 709.37 .56 16 Jul.-14 Aug. 689.37 .71 14 Aug.-21 Sept. 905.12 .85 21 Sept.-20 Oct. 699.52 .45 l 20 Oct.- 19 Nov. 723.70 1.02 l 19 Nov.-18 Dec. 703.37 .99 l
I 18 Dec.-18 Jan. 735.75 .12 1982 18 Jan.-16 Feb. 701.50 .94
! 16 Feb.-17 Mar. 697.83 .87 17 Mar.-16 Apr. 712.42 1.10 16 Apr.-14 May 700.45 1.16 14 May-14 June 735.80 1.19 8714.20 9.96 (b) Particulates with half lives greater then eight (8) days.
Particulates whose half life is greater than eight (3) days
- were not found on any filter removed from the Particulate Monitor during the reporting period.
- 2. Gases and Particulates Discharged During this Reporting Period.
Gases:
Argon-41 was discharged to the atmosphere through our exhaust stack. The total activity was 9.96 curies for an average (yearly) con-centration of 6.73 E-8 pCi/m1, Our exhaust stack is 100 feet high.
The MPC for A-41 is 4E-8 pCi/ml in an unrestricted area.
Particulates:
See 1.b above.
Solid Wastes from Reactor
- 1. Total volume of solid waste - 309.1 ft 3
- 2. Total activity of solid waste - o.73657 curies
- 3. Dates of shipments and disposition:
4 August 1981 Disposal by US Ecology i 14 August 1981 Disposal by US Ecology
, 16 September 1981 Disposal by US Ecology 15 December 1981 Disposal by US Ecology 27 January 1982 Disposal by US Ecology 8 March 1982 Disposal by US Ecology 17 May 1982 Disposal by US Ecology 20 July 1982 Disposal by US Ecology i
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1 8
t 6.7.5(g) Personnel Radiation Exposure Report (Reporting Period - 1 June 1981 -
31 May 1987.5 ,
Name Total Exposure (rem)
Faculty and Staff Biddy, Jr., Oscar D. 0.0 Bilyj, Stephen J. 0.090 Brackin, Thomas L. 0.040 Bray, Thomas C. 0.070 1 Caccamo, David P. 0.020 Cockrell, Robert G. 0.020 Cross, Robert D. 0.0 Douglas, William G. 0.020 Gardner, Robin P. 0.020 Grady, Stanley M. 0.050 Kohl, Jerome 0.040 Lawrence, Craig 0.030 Lewis, Luther E. 0.020 Munn, Hugh 0.0 Davis, Glenda 0.030 Saxe, Raymond F. 0.090 Stam, Ephraim 0.0 i Turinsky, Paul 0.010 Verghese, K 0.0 l 0.0 Weaver, Jack i
Radiation Protection Office Personnel Anderson, Tommy L. 0.0 Caruthers, L. Thomas 0.020 Corbett, Marcelle 0.0 Debnam, Joshua 0.0 Freeman, Ralph M. (Terminated 02/28/82) 0.0 l Harris, Ralton 0.0 House, Andrew 0.0 l Mangum, Royelle 0. 0.0 I Morgan, D. William 0.0 Custodians
! Dunn, Johnnie J. 0.0 l Lucas, Calvin 0.0 Saunders, Dorothy 0.0 0.0 l Young, Charles j Other 46 film badges were issued to graduate students and temporary staff, 49 film badges were issued for student laboratories, 203 film badges were issued to participants in short courses, and 632 film badges i were issued to visitors. No significant radiation exposures were reported. The majority of the radiation exposures were in the "no measureable exposure" cange.
l
i Summary of Radiation and Contamination Surveys Radiation surveys of the PULSTAR Bay did not indicate any trend of increasing radiation levels. The-Neutron Radiography Unit was disassembled and the beam tube reconfigured in the normal manner. This change reduced the radiation levels in this area.
Contamination surveys during the reporting period were negative. Prompt and cars . clean-up after accomplishing schedule tasks precludes routine surveys from finding contamination.
- h. Description of Environmental Surveys Outside of the Facility.
(See Attachment 1)
. : Attachment 1 f,g North Carolina State University -
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- P.O. Ilox 5344, Raleigh, NC 27 by>-334; /W G1
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Tel. phone bn9 ;r-aw 30 August 1982 ,y on,d cL,L tabs 6
Mr. Thomas C. Bray Reactor Operations Manager 2126 Burlington NC State Campus We have experienced several major equipment failures in our environ-mental surveillance laboratory over the last several months. This has -
caused a delay in our preparation of the Environmental Surveillance Report for this period.
I understand that you plan to submit the PULSTAR Annual Report to the Nuclear Regulatory Commission by 30 August 1982. Please note in the report that the environmental radiation surveillance data will follow later in the next 10 - 14 days.
Thank you for your assistance and indulgence in this regard.
T
-(!$u c) C-D. W. Fbrgan sociate Radiation Pr ction Officer