ML20217H448

Operations Rept 50 for Jan-Dec 1997

ML20217H448
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	12/31/1997
From:	Rowe J NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9804030349
Download: ML20217H448 (9)

Text

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UNITED STATES DEPARTMENT OP COMMERCE

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National Institute of Standerde and Technology Geithersburg, Maryland 20899 0001

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(301) 975-6210

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FAX (301) 975-9427 March 25, 1998 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Docket #50-184 Gentlemen:

Transmitted herewith is Operations Report No.50 for the NBSR. The report covers the. period January 1, 1997 to December 31, 1997.

Since

. Michael Rowe Director, NIST. Center for Neutron Research Enclosure 1

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cc: Project. Scientist U.S. Nuclear Regulatory Commission g

Region 1 475 Allendale Road King of Prussia, PA 19406 i

Project Manager

-Non-Power Reactor Directorate U.S. Nuclear Regulatory Commission Washington, DC 20555

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9804030349 971231

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PDR ADOCK 05000184 R

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N ATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR (NBSR)

Docket #50-184 Facility License No. TR-5 l

Operations Report l

-- #50 -

1 January 1,1997 - December 31,1997 1

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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-tions and covers the period from January 1,1997 to December 31,1997.

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

March 18,1998 Au^'

J. Michael Rowe Director, NIST Center for Neutron Research i

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i 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 7.8(3)(e)

Summary of Radioactive Material Released and Results of Environmental Surveys Performed

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7.8(3)(f)

Summary of Significant Exposures Received by Facility Personnel and Visitors l

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1997 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184)

Page 1

7.8(3)(s)

Summcry of Pl:nt Operations During the period January 1,1997 through December 31,1997 the reactor was critical for 5978 hours0.0692 days <br />1.661 hours <br />0.00988 weeks <br />0.00227 months <br /> with energy output of 119,008 MWH. In general, reactor operation during this I

period was uneventful. Heavy utilization of reactor research facilities continues.

7.8(3)(b) - Unscheduled Shutdowns

1. There were (3) scrams due to commercial power interruptions. The reactor was retumed j.

to power within an hour.

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2. There was one shutdown due to commercial power interruptions and the reactor was not retumed to power because it was either late in the cycle and could not be restarted i

in time. Power was restored two days later after Xenon decay.

3.' There was a MajorScram due to an upscale failure of the Stack Monitor RD 4-1. The -

monitor was put out of service and power was restored the following day. The monitor l

was retumed to service repair and recalibration.

4. There was an unscheduled Manual Scram caused when a worker installing conduit on the experimental level (C-100) bumped a box on the west wall that contained a Manual Scram button. Vibration caused the button to trip and the reactor scramed.The reactor was not retumed to power because it was at the end of the cycle. Everyone has been wamed to exercise caution when working in the area of one of these buttons.

7.8(3)(c)

Tabulation of Major items of Plant Maintenance 1

Note: Several of these items are covered by an Engineering Change Notice (ECN).

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11. Cleaned and relubricated both drive bearings and ball n' t assembly of #2 Shim arm u

drive mechanism

_2.

Replaced solenoid plunger assembly of #2 Thermal Shield IX inlet valve (TSV-3) l

3. Replaced Secondary system blocide addition solenoid valve

4. Replaced flex coupling sleeves on all Main coolant pumps

5. Reworked air supply line to Thermal Column flow control valve (DWV-28) so operation i

of other local valves will not affect thermal column flow

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6. High voltage breaker testing and preventative maintenance was done.

1997 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

Page 2

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7. Compint:d installation of cnd placed into service the new Demineralized water machine l

8. Regenerated IX column of Demin water machine 30 times l

9. Replaced RD 3-4 / 3-5 blower suction and discharge valves and solenoids

10. Completed ECN-402 on #1 Main coolant pump- (installed "O" ring between shaft sleeve and shaft to stop leakage)

11. Overhauled #1 Main coolant pump-new shaft sleeve, mechanical seal, Teflon gaskets, and suction casing gasket l

12. Replaced Secondary blowdown solenoid valve (SCV-6)

13. Installed new hot waste sump pumps in process room sump #1

14. Installed new proximity detectors on refueling conveyor

15. Replaced primary purification system pre and after filters

16. Installed primary system discharge header piping support beam next to #1 main coolant Pump

17. Changed pre and after filters of the Thermal shield purification system

18. Changed after filters of the Experimental Demin purification system

19. Replaced 4 cells in the station battery

20. Replaced mechanical seal and casing "O" ring of #1 Secondary Aux booster pump

21. Changed porostone filter in Plant air system

22. Cleaned and unclogged Cooling Tower flow diffuser nozzles

23. Changed pre-filters three times and after-filters twice of the Spent Fuel storage pool purification system

24. Completed ECN-438 (helium supply for neutron guide inpile glass)

25. Replaced fcur way valve on DWV-4 air operator

26. Replaced "O" ring in DWV-5 position indicator stem

27. Replaced resin of #1 Thermal shield IX column

28. Replaced rollers of refueling conveyor

29. Replaced Reg Rod drive "A" with drive "B"

30. Replaced air cylinders on spent fuel cutting saw 3.

Replaced mechanical seal and casing "O" ring of #2 Secondary Aux pump

32. Electrical system-Inverter / charger replaced with new UPS

33. Replaced Reg Rod drive "B" with drive "A"

34. Cooling Tower fans-replaced gaskets of gearbox oil sight glasses

35. Replaced Reg Rod drive "A" with drive "B" l

19 97 Operations Report for NBSR (TR-5)

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36. Install:d n:;w rabbit rec:iv;rs for RT-1 & 4

37. Replaced Reg Rod drive "B" with drive "A"

38. Replaced air pilot valve on Cooling Tower make-up valve

39. Removed old refueling panel and installed new updated panel

40. Replaced BT-4 operating cylinder with new one

41. Replaced valve diaphragm of DWV-23 l

42. Installed air connection at BT-1,4, and 9 shutter control boxes

43. Replaced radiator and thermostat on "A" Emergency Diesel Generator

44. Completed assembly of the refueling training structure

45. Continued treating leaking thermal shield tubes as necessary

46. Corrected operation of TRC-3 Valve Controller.

47. Checked calibration of FIA-12, F1-22 and F1-23.

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48. Corrected NC-8 noise problem.

49. Cleaned the contacts in Flux Recorder Channel Selector Switch.

50. Repaired C-001 No.1 Hood local radiation alarm.

51. Cleaned contacts on Major Scram Relays K-114.

52. Reset FR-20 and FR-21 Flow Channels.

53. Replaced Tritium Recorder.

54. Repaired Emergency Exhaust Flow Channel.

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55. Corrected problem with Area Radiation Monitor reset push-button,

56. Replaced C-001 Hood Radiation alarm unit.

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57. Repaired wiring to Acknowledge push button for AN-3/-5.

58. Cleaned pen and adjusted its height on Tritium Recorder.

59. Repaired CRA-1-2B Primary IX Outlet Conductivity Channel.

60. Repaired CIA-7 Thermal Shield IX Conductivity Channel.

61. Replaced close push-button for NGIV-6 in Guide Hall.

62. Repaired Radiation Recorder RR-1.

63. Corrected problem with Wind Speed and Direction Recorder.

64. Replaced FIA-12 flow transmitter.

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65. Corrected failure of the Scram Reset push-button to reset Scram Relays.

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66. Replaced card 07-37 in the Nuclear instrumentation System.

67. Replaced electronics in FIA-8A flow transmitter.

68. Replaced digital indicator for Shim Arm No. 2.

1997 Operations Report for NBSR (TR-5)

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1. 50-184]

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69. R2-ctlibrat d HE-2 D2O Inl:t Temperature Channel TI-7.

70. Replaced annunciator card AN3-19.

71. Repaired No.1 Hold Up Tank Recorder.

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72. Repaired Control Room Area Monitor RM1-10.

73. Repaired Flux Recorder chart drive.

74. Replaced detector cable between Main Control Panel and RM1-9 in Process Room.

75.. Repaired Flux Recorder pen slide bar.

76. Replaced FIA-8A flow transmitter.

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77. Repaired LogN recorder.

78. Repaired level recorder for No.1 Hold Up tank.

79. Replaced Flux Recorder pen servo motor and pointer.

80. Vented common sensing lines for FIA-8A & -8B Flow Channels.

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81. Re-calibrated FRC-3 flow transmitter.

82. Replaced defective LED for NGIV control power.

83. Replaced failed coil on DSR-1 relay.

84. Corrected problem with Reg Rod coarse indication.

85. Re-calibrated RM4-2.

86. Replaced A/D card in Keithley'616 Electrometer for NC-5.

87. Repaired and Re-calibrated RM4-1.

88. Replaced defective butt-splice for NGIV control power.

89. Replaced fuses in Emergency Exhaust Flow Channel.

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90. Re-aligned limit switch cams in B Reg Rod Drive unit.

91. Corrected problem with noise on NC-5 Recorder Channel.

92. Corrected problem with Retention Tank level channel.

93. Replaced detector for NC-5 Channel and troubleshot grounding problem.

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94. The following instrument calibration surveillance tests were performed:

I Channel Title BTUR-1 Reactor Thermal Power Recorder-CRA1-2A Primary D2O IX Inlet Conductivity Recorder CRA1-2B Primary D2O IX Out'et Conductivity Recorder FRC-3 Outer Plenum Flow Recorder FRC Inner Plenum Flow Recorder FIA-12 Secondary Cooling Water Flow Indicator 1997 Operations Report for NBSR (TR-5)

(Docket

1. 50-184]

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FIA-15 Th;rm I Shl:Id Coolint Flow indicator FIA-40 Reactor Outlet Flow Indicator Alarm LRC-1 Reactor Vessel Level Reeorder LIA-3 D2O Storage Tank Level LCA-19 Storage Pool Pump Pit Level Control LIA-40 Reactor Vessel Level Indicator NC-3 Intermediate Channel NC-3 NC-4 Intermediate Channel NC-4 NC-5 Nuclear Power Channel NC-7 NC-6 Nuclear Power Channel NC-6 NC-7 Nuclear Power Channel NC-7 NC-8 Nuclear Power Channel NC-8 NC-9 Nuclear Safety System PC-3 Normal Exhaust System Pressure Controller PC-27 Process room Pressure Controller SPC-150 Emergency Fan Controller SPS-150 Emergency Standby Fan Controller SPS 151 Vacuum Breaker Controller RM 1-1 Area Monitor-First Floor North Wall l

RM 1-2 Area Monitor-First Floor East Wall RM 1-3 Area Monitor - First Floor South Wall RM 1-4 Area Monitor - First Floor West Wall RM 1-5 Area Monitor - Second Floor Ceiling RM 1-6 Area Monitor - Second Floor West Wall RM 1-7 Area Monitor - Fuel Storage Pool Area RM 1-8 Area Monitor-Process Room East Wall RM 1-9 Area Monitor-Process Room West Wall RM 1-10 Area Monitor - Control Room RM 1-15 C001 Rabbit Lab Radiation Area Monitor RM 3-1 Secondary Cooling N-16 Radiation Monitor RM 3-2 Helium Sweep Gas Radiation Monitor l

RM 3-3 Secondary Cooling N-16 Radiation Monitor RM 3-4 Irradiated Air High Activity Radiation Monitor f

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l 19 9 7 Operations Report for NBSR (TR-5)

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RM 3-5 Building Exhaust High Activity Radiation Monitor RM 4-1 Stack Gas High Activity Radiation Monitor RM42 Emergency Ventilation Stack Radiation Monitor RM 4-4 MAA Gamma Radiation Monitor BT-4FACS BT-4 FACS Spectrometer Radiation Monitors TRA-2 Reactor Outlet Temperature Recorder l

TI-7 D2O HE-2 Inlet Temperature Indicator TIA-10 Recombiner Outlet Temperature Recorder TIA-11 Recombiner Intemal Temperature Recorder TIA-40A Reactor Outlet-Inlet Temperature Differential Indicator & Alarm - Channel A TIA-40B Reactor Outlet-Inlet Temperature Differential Indica tor & Alarm - Channel B 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.

There were no significant changes to procedures or test and experiments during this period.

The following facility changes were completed this year, all of which are considered minor; 4

ECN 402 The installation of an o-ring between the shaft sleeve and shaft of #1 main D 0 2

cooling pump to stop water seepage. The pump continues to function as designed. There are no unreviewed safety questions.

ECN 432 Installation of an ultraviolet disinfecting unit in the spent fuel storage pool cooling system to increase the cleanliness of the pool does not increase the chances of a

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pool leak. Minor documentation changes were made and there is no affect, direct or indirect, upon the reactor. There are no unreviewed safety questions.

ECN 433 Relocation of experimental chilled water lines to accommodate the BT-5 i

experiment involved no unreviewed safety questions, as this system has minimal interaction with auxiliary reactor systems and no affect upon the operation of the reactor.

ECN 434 Replacement of a D O pump discharge pipe support did not change the design 2

function of the pipe support and affected no other equipment. There are no unreviewed J

safety questions.

ECN 438 The installation of a helium supply valve to provide a convenient source of 19 9 7 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184)

Page 7

r purge g:s for n:utron guid)inpib girss replaced a bank of helium bottles used for that j

purpose. The small volume of helium drawn from the reactor helium supply has no affect upon the design function of the reactor helium sweep system. Minor documentation changes I

were made and there are no unreviewed safety questions.

ECN 439 Relocation of the regulating rod drive motor power fuses for easier access. This J

had no affect upon reactor safety systems, and involved no unreviewed safety questions.

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7.8(3)(e)

Summary of Radioactive Material Released and Results of l

Environmental Surveys Performed.

The gaseous waste released was 202 curies of tritium,938 curies of Argon-41,0.123 curies of Cl-38, and 0.041 curies of Br-82. There were 1.02 curies of tritium and 164 i

microcuries 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.

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1997 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184) l Page 8 l