ML20035B151
| ML20035B151 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 12/31/1992 |
| From: | Rowe J NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9303310239 | |
| Download: ML20035B151 (8) | |
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UNITED OTATED DEPARTMENT OF COMMERCE l I
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National Institute of Ctander de and Technology
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(301) 975-6210 FTS
-879-6210 FAX (301) 921-9847 l
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'l March 25, 1993 l
U.S. Nuclear Regulatory Commission j
Document Control Desk
't Washington, DC 20555
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Subject:
Docket #50-184 i
Gentlemen:
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Transmitted herewith is Operations Report No.45 for the NBSR. The
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report covers the period January 1, 1992 to December 31, 1992.
j Sin -rely, n a. R J. Michael Rowe Chief, Reactor. Radiation Division j
I Enclosure
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Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 i
l Project Manager Non-Power Reactor Directorate-U.S. Nuclear Regulatory Commission j
Washington, DC 20555 il l
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.N ATIDNAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR
- 3 (NBSR)
'l Docket #50-184 j
Facility License No. TR-5 l
l Operations Report
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.I January 1,1992-December 31,1992 j
i This report contains a summary of activities connected with the operations of the NBSR. It is submitted in fulfillment of section 7.8(3) of the NBSR Technical Specifica-l tions and covers the period from January 1,1992 to December 31,1992.
Section numbers in the report (such as 7.8(3)(a)) correspond to those used in the -
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Technical Specifications.
March
,1993
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w Efd'ichael Rowe Chief, Reactor Radiation Division
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Page 1 TABLE OF CONTENTS 7.8(3)(a)
Summary of Plant Operations 7.8(3)(b)
Unscheduled Shutdowns 7.8(3)(c)
Tabulation of Major items of Plant Maintenance 7.8(3)(d)
Tabulation of Major Changes in the Facility and Procedures, and the Test and Experiments, Carried Out Without Prior Approval by the NRC Pursuant to 10 CFR 50.59 l
7.8(3)(e)
Summary of Radioactive Material Released and Results of Environmental Surveys Performed i
7.8(3)(f)
Summary of Significant Exposures Received by Facility Personnel and Visitors 1
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19 92 Operations Report for NBSR (TR-5)
(Docket
- 50-184]
P 9* 2 7.8(3)(a)
Summ; f Plant Operations During the calendar year 1992, the reactor was critical for 6169 hours0.0714 days <br />1.714 hours <br />0.0102 weeks <br />0.00235 months <br /> and the energy generated was 92440 MWH. This year was one of the better operating years and essentially uneventful.
Maintenance, such as repair of the Thermal Shield cooling system described in past reports, continued. One of the two main heat exchangers continued to be kept out of service with the reactor operating with a single heat exchanger at 15 MW. Fabrication of new heat exchangers will be completed in about a year with installation currently scheduled during the following year.
7.8(3)(b)
Unscheduled Shutdowns i
1.
There were seven (7) scrams due to a commercial power dip. The reactor retumed to power.
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- 2. There was a scram due to loss 10 volt power supply while the Instrument Section was repairing the Auto Control circuit. The reactor was shutdown for instrument repairs and then returned to power.
- 3. The reactor was shutdown in order to recover a stuck rabbit. It was returned to power the next day after the rabbit was recovered.
4.
There was a scram due to the loss of the Static Inverter when a fuse blew after the failure of one of the two cooling fans. Repairs were made by replacing the fan and fuse and the reactor was returned to power.
- 5. The reactor was shutdown to replace the clutch output card for Shim No.3, checked for proper operation, and then returned to power.
7'.8(3)(c)
Tabulation of Major items of Plant Maintenance l
1.
Replaced diaphragm of PWV-9 (potable water to emergency cooling) 2.
Overhauled #2 Thermal Shield pump m
19 92 Operations Report for NBSR (TR-5)
[ Docket
- 50-184)
Page'3
- 3. Replaced discharge valve of RD 3-4,3-5 blower (ECN-342) 4.
Repaired air leak on SCV-3 (air diaphragm)
- 5. Replaced MOTOR bearings of #1, #2, & #3 Secondary pumps
- 6. Replaced time delay element in #1 Cooling Tower fan motor circuit
- 7. Changed pre and after filters of Storage pool, Thermal shield, and primary purification system three times.
- 8. Changed after filters of experimental demin system
- 9. Removed Battery cell #21,23,25, & 28 from Station battery bank and installed new cells at locations # 16,17,18,&19
- 10. Repaired 2 leaking valves in Bi-tip cooling system-(DWV-223 and lead /Bi-tip proportioning valve)
- 11. Outside contractor overhauled bu!! ding 235 Elevator Repaired CO leak for RT-3 rabbit tip above subpite room 12.
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- 13. Replaced faulty Fire detectors in the process room
- 14. Replaced control air valve (CAV) that supplies air to the guide tube isolation valves
- 16. Replaced universal joint between damper D-3 and air motor for EF-3
- 17. Replaced TSV-4 solenoid (#1 T.S. IX inlet)
- 18. Replaced caustic mixing tank on Demin water station
- 19. Regenerated IX column of Demin water station
- 20. Replaced oil sightglass on #1 Cooling Tower fan gearbox
- 21. Plugged 4 tubes in the Exp Demin heat exchanger I
Repaired D O leak in #2 Main D O pump by cutting small groove into shaft sleeve to 22.
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accommodate rubber O" ring
- 23. Replaced shaft seal of #1 Thermal Shield p' imp
- 24. Cleaned leads, reconnected, and checked resistance of #1 D O Storage tank pump 2
- 25. Completed certification test of new Static inverter
- 26. Replaced diaphragm of WTV-97 (Storage Pool manual fill valve)
- 27. Replaced time delay relay in #2 Main D O pump motor controller 2
- 28. Disassembled, cleaned, and assembled HCSC (helium compressor secondary cooling) heat exchanger
- 29. Changed resin in both the Thermal Shield and Storage Pool IX columns
- 30. Continued treating leaking Thermal Shield tubes as necessary 19 9 2 Operations Report for NBSR (TR-5) i
[ Docket
- 50-184]
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- 31. Performed regularly scheduled Tech Specs and plant PM's
- 32. Replaced period rod stop card on NC-3.
- 33. Repaired annunciator AN-1.
- 34. Repaired HV supply on Area Monitors.
- 35. Replaced GM tube on Liquid Waste Monitor.
- 36. Repaired power supply in Reg Rod Controller.
- 37. Replaced NC-4 Scram card (# 07-28).
- 38. Replaced NC-3 Log-N Amplifier card.
- 39. Repaired BTUR Recorder.
- 40. Replaced servo motor on Area Radiation Recorder RR-1.
- 41. Replaced Outer Plenum Flow Recorder FRC-3.
- 42. Replaced digital readout module for #2 Shim Position indicator.
- 43. Replaced take-up motor on Wind Direction recorder at Emergency Control Station.
- 44. Replaced amplifier card on delta-T recorder.
- 45. Replaced servo motor on BTUR recorder.
- 46. Repaired Mag Amp on NC-6 input unit card (07-31).
- 47. Corrected servo motor ground wiring in BTUR recorder.
- 48. The following instrument calibration surveillance tests were performed:
Channel Title NC-2 Nuclear Source Range Start Up NC-1 Nuclear Source Range Start Up BTUR Reactor Thermal Power RM4-3 Liquid Waste Monitor RM3-4 Irradiated Air Monitor SS-K103 Relay Scram Safety System BT-4A&B BT4 Area Monitor NC-4 Reactor Intermediate Power Range NC-7 Nuclear Power Range NC-8 Nuclear Power Range FCA-7 Thermal Column Flow indicator Control RM1-1 -10 Reactor Building Area Monitors NC-3 Reactor Intermediate Power Range (partial)
RM4-1 Stack Monitor FRC-3 Rcactor inner Plenum Flow 19 92 Operations Report for NBSR (TR-5)
[ Docket
- 50-184)
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Page 5 FRC-4 Reactor Outer Plenum Flow FIA-15 Thermal Shield Flow RM4-4N Criticality Monitor RM4-4S Criticality Monitor TIA-17 Thermal Shield HE Secondary Outlet Temperature Indicator PC-27 Process Room Air Exhaust Pressure Controller PC-3 Normal Air Exhaust Pressure Controller SPC-150 Emergency Fan Controller SPS-150 Emergency Standby Fan Controller SPS-151 Vacuum Breaker Controller LRC-1 Reactor Vessel Level NC-3 Reactor Intermediate Power Range TI-22 Thermal Shield Storage Tank Inlet Temperature Indicator PIC-11 Building Leak Check PressNacuum Controller TIA-40A Reactor Delta-T TIA-40B Reactor Delta-T RD3-5 Building Exhaust High Activity Alarm NC-5A Linear Power Range and Regulating Rod Controller NC-6 Nuclear Power Range NC-9 Nuclear Safety System TRA-2 Reactor Outlet Temperature RM1-15 C001 Rabbit Lab Radiation Area Monitor FIA-40 Reactor Flow RM3-1 Secondary Cooling N-16 Monitor RM3-2 Fission Product Monitor RM3-3 Secondary Cooling N-16 Monitor 7.8(3)(d)
Tabulation of Major Changes in the Facility and Procedures, and the Test and Experiments, Carried Out Without Prior Approval by the NRC pursuant to 10 CFR 50.59.
I There were none this reporting period.
19 92 Operations Report for NBSR (TR-5)
[ Docket
- 50-184)
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7.8(3)(e)
Summary of Radioactive Material Released and Results of
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Environmental Surveys Performed.
The gaseous waste released was 351 curies of tritium and 665 curies of Argon-41.
There were 1.5 curies of tritium and 0.4 millicuries of other beta-gamma emitters released into the sanitary sewer. Environmental samples of the streams, vegetation, and/or soil, and air showed no significant changes.
7.8(3)(f)
Summary of Significant Exposures Received by Facility Personnel and Visitors.
1.
None to visitors.
2.
Dosimetry results for this reporting period indicated that no facility personnel received significant exposures.
19 9 2 Operations Report for NBSR (TR-5)
[ Docket
- 50-184)