ML20202D300

Operations Rept 38,1985

ML20202D300
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	12/31/1985
From:	Rozier Carter NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8604110529
Download: ML20202D300 (10)

Text

1 NATIONAL BUREAU OF STANDARDS REACIOR Docket #50-184 Facility License No. TR-5 Operations Report

1. 38 January 1, 1985 - Decerber 31, 1985 This report contains a summary of activities connected with the operations of the NBSR.

It is submitted in fulfillent of section 7.8(3) of the NBSR Technical Specifications and covers the period from January 1,1985 to December 31, 1985.

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

March 20, 1986 RMJW -

m>BsRr S. c-R Chief, Reactor Radiation Division 8604110529 DR 851231 ADOCK 05000184 PDR l

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TABIE OF CONTEtfrS 7.8(3)(a) Surmnry of Plant Operations 7.8(3)(b) Unscheduled Shutdowns 7.8(3)(c) Tabulation of flajor Items of Plant Maintenance 7.8(3)(d) Tabulation of flajor 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) Sunnry of Radioactive !!aterial Released and Results of Environmental Surveys Performed 7.8(3)(f) Summry of Significant Exposures Received by Facility Personnel and Visitors 4

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'7.8(3)(a) Summary of Plant Operations ~

During the calendar year 1985, the reactor was critical for 5246 hours0.0607 days <br />1.457 hours <br />0.00867 weeks <br />0.002 months <br /> and the energy generated was 101,979 21AI.

On April 3, 1985 the reactor achieved its new power level of 20 FM.

This followed programmed step. increases in reactor power. A baseline was established at the old power of 10 tH, followed, over a period of time, by increases to 12.5111,15 IH,17.5 IM and finally to 20141. The approach to 20' FM was. uneventful. All parameters, nuclear, process and radiation were as predicted and essentially double the baseline data obtained at 10 iM.

Only 3 primary main pumps were needed to produce the desired flow of about 8900 gpm, leaving the fourth pump as a. spare. The' flow is about 50%

more than that at 10 fM. A 4 F increase in primary delta T brought it to about 14 F. Since April 1985, the reactor was operated routinely at. 20 PM .

in the same manner as in previous years at 10 PM.

7.8(3)(b) Unscheduled Shutdawns There were five (5) Scrams due to-commercial power dips during storms

on 5-21-85, 5-28-85, e-5-85, 7-12-85, . and 26-85. In four of the five

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cases the reactor was returned to power at once. In the - fif th case it happened at the end of a cycle and the: reactor stayed down for refueling.  !

l On 6-17-85 the reactor Scrammed on low flow while the operator was shifting No. 4 main cooling pump from Hand to Auto. The reactor was. j l

returned to power at once. l 7.8(3)(c) Tabulation of 11ajor Items of Plant liaintenance

1. Repaired leak on 150# air receiver.

2. Cleaned air operator on DWV-6.

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3. Cleaned air regulator on SCV-1, 2, and 3.

4. Repaired backup door seal regulator.

5. Cleaned out channels and repaired facings at elevator door seals.

6. Installed upper and lower strong-backs for elevator sliding door.

7. Repaired building ceiling leaks.

8. Repaired locks on B-2 door to confinement building.

9. Installed safety rails above stairwells.

10. Installed grating above HE-1A & B.

11. Repaired demineralized water piping leak in room B-153 and on B-2.

12. Changed demineralized water filters.

13. Plugged 4 leaking tubes in HE-4..

14. Replaced time delay relays TD-1, 2, & 3 in the Inverter / Diverter.

15. Cleaned breaker on Diesel B.

16. Replaced 2 cells in station battery.

17. Changed overload relays in DP-1,2,3,&4 and replaced time delay relay in #3 controller.

18. Replaced time delay relay in DP-5.

19. Replaced breakers in Aux. pumps 1 & 2.

20. Replaced control relays and undervoltage relays in A-5/B-6 Breakers 1,2,3, & 4.

21. Cleaned contacts on DP-1.

22. Replaced boral plates on lower shutter of BT-9.

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23. Replaced 2 strip heaters on helium sweep system.

24. Replaced diaphragas on IEV-40, 41, 30, 31, & 32.

25. Replaced diaphragm on IRV-5.- l

26. Replace pump B and repaired suction line on pump A of sump #3 in purp house. Also repaired level sensor.

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27. Cleaned drive on Shim Arm #4.

28. . Installed return punp on sampling system.

29. Installed flow switch on tritium monitor.

30. Changed D 2 O in G-2 experimental tube.

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31. Installed leak detection system on Shim Arm #2.

32. Cleaned Shim Arm #1 clutch.

33. Replaced pedestal bearing in DP-2.

34. Replaced LIA-40.

35. Replaced inpoller gaskets on DP-1 & 3.

j 36.. Changed pre & after filters on primary IX colunns. .,

37. Replaced "O" rings in RT-3, 4, & l.

38. Replaced IN light on RF-4.

! 39. Inspected and cleaned RbN-13.

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40. Replaced bearing on G-6 transfer arm.

t 41. Installed new lower section on dropout tool.

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42. Replaced SCV-5.

l 43. Replaced Cooling Tower makeup valves.

44. Installed auxiliary makeup line to Cooling Tower.

i j 45. Replaced coupling on Seconchry Punp #4. ,

i 46. Installed a priming system on storage pool punps.

47. Installed new hoses and piping on pool vacuum.

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48. Changed pool system pre and after filters twice.

49. Installed pressure indicators on the upper ring header of the thermal-shield cooling system.

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50. Replaced bonnet on TSV-1. 'l 4

51. Repaired air solenoid on TSV-2. .  ;

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52. Replaced seal on T.S. pump #2.

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53. Repaired TSV-586.

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54. '. Replaced T.S. IX conductivity cells.-

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55. -Repaired leak _in T.S. heat exchanger end bell with a different i,

gasket.

j 56. Replaced washers on all upper ring header valves.

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57. Replaced digital. indicator on Shim Arm #2.

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, 58. Cleared water out of Fission Products detector housing.

59. Replaced gain pot'entiometer in the Reg Rod DIAT Controller.

l '60 . Replaced GI! tube in RI13-2 Fission Products 11onitor. Corrected j tube failures by placing dropping resistor nearer detector.

l- 61. Partial test and operational ~ test of RM4-1 Stack Monitor.

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l 62. . Replaced G1 tube in RM3-1 N-16 fionitor.

63. Replaced PSX relay in the emergency fan controller SPC-150.

j. 64. Replaced anplifier in FR-1 Reactor Outlet Flow channel, performed 1

l- calibration check.

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65. Cleaned NC-6 test switch and verified NC-6 trip points.

66. Installed ? (1/2 anpere) fuses in Reg Rod motor control circuit. . '

I i' 67. Replaced anplifier and calibrated FR-3 Outer Plenum Flow.

68. Replaced acplifiers on FR-3 and FR-4, Outer and' Inner Plenum Flow 1

channels. Performed calibration and' scram response tests. l

69. Technical Specificatio Test ,

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] Ri-3-5 Norma 1 Air Monitor-l TIA-40A Reactor Delta Tenperature Indicator j PC-3 Nornni Exhaust Monitor t ,

i PC-27 Process Room Fan Controller SPC-150 Emergency Fan Controller l

j .SPS-151~ Vacuum Breaker Controller c

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SPS-150 Emergency Standby Controller R4-3-5 Nornal Air Monitor R1-3-4 Irradiated Air Monitor R4-3-1 N-16 11onitor NC-1 Nuclear Source Range Channel NC-2 Nuclear Source Range Channel NC-4 Nuclear Intermediate Range Channel NC-6 Nuclear Power Range Channel NC-8 Nuclear Power Range Channel BTUR-1 Reactor Thermal Power FR-3 Reactor Outlet Plenum Flow LIA-40 Reactor level Indicator FR-4 Reactor Inner Plenum Flow l RI-4-1 Stack Air Monitor NC-7 Nuclear Power Range Channel ,

R11-1-10 Area Radiation 11onitors .

NC-3 Nuclear Intermediate Range Channel LRC-1 Reactor level Recorder NC-6 Nuclear Power Range Channel  !

NC-9 Nuclear Interlock Trip Test  !

l FIC-3 Reactor Outlet Flow TRA-2 Reactor Outlet Temperature Recorder TIA-40B Reactor Delta Temperature Indicator j l

R1-3-2 Fission Products Monitor LIA-40 Reactor level Indicator FIA-40 Reactor Outlet Flow Indicator Ri-3-1 N-16 11onitor 7

7.8(3)(d) Tabulation of liajor 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 Relevant Engineering Changes are summarized below.

EW-288 RFI protection for temperature transmitters.

This involved the fabrication of a metal cabinet to contain the plant temperature transmitters in order for them to be protected from RF when 2-way radios might be used in their vacinity.

i EW-305 Renoval of unnecessary and unused valves in primary system.

This involved the renoval of such valves as the Storage tank drain, strainer vent valve and helium to IX column valve.

These valves are not involved in reactor operation and therefore pose no unreviewed safety question their renoval.

ECN-310 Installation of a flow switch in the tritium monitor system.

The purpose of this installation is to alert the Control Room operator of any condition that results in a low flow of sample air to the tritium detector. It has no effect on the operation of the reactor and therefore it's failure would not involve an unreviewed safety question.

EW-311 Install additional ball plungers in the fuel element head mounting block.

The purpose of this installation is to install two additional ball plungers, to the two already in the design, in the fuel 8

element mounting head in such a way as to engage a groove in the shaft of the fuel element lifting head so that it can not easily rotate once the latching bar has engaged beneath upper.

grid. This is a minor change for inprovemnt and will not change the function of the fuel element head. All other functions and operations of the head remain the same.

Changes to procedures:

Comprehensive Emergency Procedures were prepared and instituted to implement the new NRC approved Emergency-Plan.

7.8(3)(e) Surmary of Radioactive flaterial Released and Results of Environmental Surveys Performed.

The gaseous waste released was 234 curies of tritium and 852 curies of Argon-41, while 14.38 curies of tritium and 0.002 curies of other beta-ganmu emitters were released into the sanitary sewer.

Environmntal sanples of the streams, wells, vegetation, and/or soil, l and air showed no significant changes.

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7.8(3)(f) Summary of Significant Exposures Received by Facility Personnel j i

i and Visitors

1. None to visitors.

2. Dosimetry results for this reporting period indicated that 6 j l

operators received from 1.367 to 2.236 Rem. I l

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UNITED {~TATZ3 DEPAZTM ~.NT OF COMMERCE I National Bureau of Standards i k %# / Gaithersburg, Maryland 20899 l l

March 20, 1986 U. S. Nuclear Regulatory Commission Regional Administrator, Region 1 631 Park Avenue King of Prussia, PA 19406 J

Subject:

Docket #50-184 Gentlemen:

Transmitted herewith is Operations Report No. 38 for the National Bureau of

, Standards Reactor. The report covers the period January 1, 1985 to December 31, 1985.

Very truly yours, l 1

( - A Robert S. Carter j Chief, Reactor Radiation Division i

Attachment cc: Director, Division of Reactor Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555 l

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