ML20064L210

NIST Reactor (Nbsr) Operations Rept 46 Jan-Dec 1993. W/

ML20064L210
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	12/31/1993
From:	Rowe J NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403240194
Download: ML20064L210 (8)

Text

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National institute of Standar-de and Technology

. Geschersburg, Maryland 20809-o001 f (301) 975-6210 g%,,,,,, , / FTS 879-6210 FAX (301) 921-9847 March 18, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Docket #50-184 Gentlemen:

Transmitted herewith is Operations Report No.46 for the NBSR. The report covers the period January 1, 1993 to December 31, 1993.

Si cerely,

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('j.MichaelRowe Chief, Reactor Radiation Division Enclosure cc: Project Scietist U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Project Manager Non-Power Reactor Directorate U.S. Nuclear Regulatory Commission Washington, DC 20555 V

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4 N ATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR (NBSR)

Docket #50-184 Facility License No. TR-5 Operations Report

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January 1,1993 - December 31,1993 This report contains a summary of activities connected with the operations of the NBSR. It is submitted in fulfillment oi section 7.8(3) of the NBSR Technical Specifica-tions and covers the period from January 1,1993 to December 31,1993. '

Section numbers in the report (such as 7.8(3)(a)) correspond to those used in the Technical Specifications.  ;

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March 18,1994 Z-J/blichael Rowe Chief, Reactor Radiation Division -

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TABLE OF CONTENTS i

l 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 7.8(3)(e) Summary of Radioactive Material Released and Results of Environmental Surveys Performed 7.8(3)(f) Summary of Significant Exposures Received by Facility Personnel and Visitors

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7.8(3)(a) Summary of Plant Operations  !

During 1993 reactor operations continued at reduced power level of 15MW since one of i the main heat exchangers was taken out of service. Form January 1,1993 through December 31,1993 the reactor was critical for 6664 hours0.0771 days <br />1.851 hours <br />0.011 weeks <br />0.00254 months <br /> and the energy generated was 98690 MWH.

The discovery of an uniatched element was the subject of a special report to the NRC dated September 22,1993. Since the report, additional checks were performed and further steps were taken. The detent in the grid under the unlatched position was examined with a borescope and it looked good, with no evidence of wear. The orientation of the latching bar on all elements was also checked. In three instances, even though the elmnent was latched, the bar was found not to be fully rotated. As a result, a special tool was developed that can only be rotated in the locking direction and will be used to confirm that the latching bar is in the proper orientation. The tool was tried during a shutdown with oxcellent results. This method will be used in future refueling since it provides the best assurance that the latching bar is in the detent of the grid.

An extended outage is scheduled for the middle nf 1994 in order to replace the main heat exchangers and to install a new liquid hydrogen cold source among other projects.

7.8(3)(b) Unscheduled Shutdowns

1. There were four (4) scrams due to a commercial power dip. The reactor returned to powe r.

2. The reactor was shutdown in order to shift Critical Power and Rod Drive Power from the T-9 to the T-10 system when the Static inverter failed. The reactor returned to power the next day after xenon decay.

3. The reactor was manually scramed because of apparent decreasing power on all channels. Investigation revealed that Shim Arm #1 had dropped a small amount. The output card for the #1 clutch current was replaced. The reactor returned to power the ,

next day after xenon decay. This was the subject of a specialinformation letter to the NRC dated April 9,1993.

4. The reactor was shutdown during a startup when oscillations were observed on all nuclear channels. Investigations subsequently reveled an uniatched element in the core. This event is discussed more fully in section (a) above.

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Page 3 7.8(3)(c) Tabulation of Major iterns of Plant Mhintenance

1. Replaced SCV 4 and SCV-48 (Cooling Tower make-up valves).

2. Installed new diaphragm in Secondary chemical addition pump.

3. Replaced 4 cells in the station battery.

4. Changed diaphragm in HEV 40 (Helium inlet to Rx vessel).

5. Adjusted #4 Shim arm clutch.

6. Changed diaphragm in DCV-1 (Exp Domin pressure controller).

7. Replaced spool piece downstream of DCV-1 due to pinhole leak.

8. Greased diaphragm shaft of Helium gas holder.

9. Replaced one strip heater in Helium sweep system.

10. Refurbished #1 & #4 Secondary pump motors (Redipped, baked, balanced, new bearings and motor leads).

11. Refurbishr.d #2 & #5 Secondary pump motors (Redipped, beked, balanced, new bearings and motor leads).

12. Replaced time delay in #2 Secondary pump motor controller.

13. Removed, disassembled, cleaned, lubricated, reassembled #2 Shim arm clutch mechanism and gapped clutch clearance to spec. Replaced position indicator pot.

14. Replaced FTV-3 shut indicator.

15. Replaced diaphragm in DCV-52 1 G. Reiurbished #3 & #6 Secondary pump motors (Redipped, baked, balanced, new

bearings and mott r leads).

17. Replaced Storage pool after filters.

18. Replaced relay in BT-9 shutter controller.

i9. Overhauled Wilden Pump M-4 (air operated to pump storage pool water over weir to pump pit).

20. Replaced air pilot sensor from Cooling Tower deluge system to make-up valve SCV-4.  ;

21. Replaced AC filter capacitors in Static inverter.

22. Repaired leak in #3 Main D20 pump by cutting small grove into shaft sleeve to t accommodate rubber "O" ring. '

23. Installed new AC input breaker for 200 amp battery charger.

24. Changed storage pool IX pre-filters

25. Replaced diaphragms of valves DCV- 40 & 46 (filter isolation valves of Experimental Domin system).

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Page 4 26 Replaced flexible coupling of #2 Storage Pool pump.

27. Replaced "O" ring on DWV-3 position indicating shaft to ep air leak. Lubricated stem and adjusted open/close limit switches.

28. Replaced pre & after filters of storege poolIX.

29. Replaced bonnet and diaphragm of storage pool IX outlet valve SPV-49.

30. Replaced (:>per bearing of D-5 fuel element transfer arrn.

31. Replaced de ' <alve of storage pool after filter.

32. Replaced 2 w..; t,f station battery.

33. Continued treating leaking Thermal Shield tubes as necessary.

34. Performed regularly scheduled Tech Specs and plant PM's.

35. Replaced Magnetic Amplifier on NC-6 Input Card.

36. Repaired ground on BTUR Recorder servo motor.

37. Replaced radiation alarm unit on BT 4.

38. Replaced GM tube on RD 3-1.

39. Replaced Thermal-Shield Tank Level indicator.  :

40. Replaced Criticality Monitors.

41. Replaced batteries for Tritium Monitor.

42. Replaced RD 1-1.

43. Repaired FRC-1.

44. Replaced Ganged Potentiometers on NC-6, -7, and -8.

45. Replaced AN-1, -2, -3, and -5 Annunciators.

46. Replaced FIA-5 flow 1". mitter.

47. Replaced plungers in 1G . solation Valve solenoids.

48. The following instrument calibration surveillance tests were performed:

Channel T!tle FRC-3 Reactor Inner Plenum Flow FRC-4 Reactor Outer Plenum Flow FIA-5 D2O to Purification HE-2 Flow Indicator FCA-7 Thermal Column Flow Indicator Control l FIA-14 Storage Flow 1.X. Flow indicator l FIA-40 Reactor Flow '

LIA-3 D2O Serage Tank Level LRC-1 Reactor Vessel Level ,

LCA-19 Storage Pool Pump Pit Level Control )

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Page 5 NC-1 Nuclear Source Range Start Up NC-2 Nuclear Source Range Start Up NC-3 Reactor Intermediate Power Range NC-4 Reactor Intermediate Power Range NC-5A Unear Power Range and Regulating Rod Controller NC-6 Nuclear Power Range NC-7 Nuclear Power Range NC-8 Nuclear Power Range NC-9 Nuclear Safety System PC-3 Normal Air Exhaust Pressure Controller PC-27 Process Room Air Exhaust Pressure Controller RM 1 1-10 Reactor Building Area Monitors

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RM 1-15 C001 Rabbit Lab Radiation Area Monitor RM 3-1 Secondary Cooling N-16 Monitor RM 3-2 Fission Product Monitor RM 3-3 Secondary Cooling N-16 Monitor RM 3-4 Irradiated Air Monitor RM 3-5 Building Exhaust High Activity Alarm RM 4-1 Stack Monitors RM 4-2 Emergency Ventilation Stack Monitor RM 4-3 Liquid Waste Monitor RM 4-4N Criticality Monitor RM 4-4S Criticality Monitor SPC-150 Emergency Fan Controller l SPS-150 Emergency Standby Fan Controller l SPS-151 Vacuum Breaker Controller  :

TRA-2 Reactor Outlet Temperature TIA-12 Cooling Tower Temperature Indicator TIA-40A Reactor Delta-T TIA-40B Reactor Delta-T l

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Page 6 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.

1. Started replacing the Control Room annunciator panels for modernization.

2. Replaced the Inverter / Diverter with a 20KVA UPS system.  ;

Both of these changes involved replacement of equipment with equal or superior l equipment. l l

l 7.8(3)(e) Summary of Radioactive Material Released and Results of l Environmental Surveys Performed.

The gaseous waste released was 425 curies of tritium and 879 curies of Argon-41.

There were 1.5 curies of tritium and 0.2 millicuries of other beta-gamma emitters released into the sanitary sewer. Environmental samples of the streams. vegetation, and/or soll, 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.

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