ML20063P180

Operations Rept 33,Jan-June 1982

ML20063P180
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	09/30/1982
From:	Rozier Carter NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:
Shared Package
ML20063P177	List: ML20063P176 ML20063P180
References
NUDOCS 8210130163
Download: ML20063P180 (5)

Text

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

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OPERATIONS REPORT

- - - #33 - - -

l l Janu.ry, 1982 - June, 1982 l This report contains a surmary of activities connected with the i operations of the NBSR. It is submitted in fulfillment of section 7.8d i

j of the NBSR Technical Specifications and covers ' the period from January 1, 1982 to June 30, 1982.

L Section numbers in this report (such an, 7.8d(1)) correspond to those used in the Technical Specifications.

September 30, 1982 h Gf& ' k u%  %

L ROBERT S. CARTER Chief, Reactor Radiation Division

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7.8d (l) Sununary of Plant Operations

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7.8d('2) I - Unscheduled Shutdowns -!

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7.8d (3) Tabulation-of Major Items of Plant Maintenance

.7. 8d (4) Tabulation of Major Changes in the Facility'and Procedures,.

and the Test and Experiments',-Carried Out Without Prior Approval

'by: the U. S. AEC (10 CFR 50.59) 7.8d (5) Sununary of Radioactive Material Released and Results of Environ-mental Surveys Performed 7.8d(6) Summary of Significant Exposures Received by Facility Personnel and Visitors i

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-7. 8d (l) Summary of Plant' Operations

• During the period January 1, 1982 through June 30, 1982, the reactor was critical for 3691 hours0.0427 days <br />1.025 hours <br />0.0061 weeks <br />0.0014 months <br /> and the energy generated was 36203 MWH. All reactor operations were routine and uneventful.

A program for modernization of the Reactor Console was initiated and is continuing.

.7. 8d (2) Unscheduled shutdowns There were no' unscheduled shutdowns during this reporting period.

7.8d(3) Tabulation of Major Items of Plant Maintenance

1. Adjusted vibration cutout switch on #2 C.T. fan.

2. . Replaced compressed air regulator in the Emergency Control Station.

3.- Replaced pump head, backing ring and check valves in the Secondary acid pump.

4. Repaired rubber boot on EF-3 ventilation ducting.

5. Replaced belt on #1 Shim Arm position indicator.

6. Cleaned breaker contacts on #1 D 0 Pump.

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7. Installed deck plates over C.T. valve pit.

8. Replaced photo cell circuit board in RT-4 Rabbit System.

9. Installed new impeller, wear rings, bearings and seals in #1 Secondary Pump.

10. Changed prefilters and I.X. resin in the Thermal Shield 6y tem.

11. Replaced TSV-28.

12. Replaced RT-5 circuit board.

13. Cleaned and lubricated the Reg Rod drive.

14. Replaced #3 D O Pump motor.

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. '15.' Replaced EF-3 pulley.

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. .. yl6. Replaced gaskets on flow orfice {FIA-16) in'the Thermal Shield System.

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w , 19.) Replaced EF-2 pulley belts.

20'.i, Replaced NC-6;.71and'8 Power meter.;

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21. ' Replaced NC--8 detector. , .;-

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22. Replaced ~1 N,6 monitor ratemeter. l

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23. Cleaned and repaired read-out. pots on CO and He Gas Holders.-

2 24 7 Replaced RD 3-5 ratemeter.

25. Replaced selsyn drive unit.on #2 Shim Arm drive.

26. Replaced NC-8 Rundown card.

27. Replaced amplifier in TRC-2 transmitter.

28. Replaced LRC-1 monitor switch.

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29. Replaced cards #18 and 19 'in Ann. #1 panel, f

30. Replaced amplifier in FRC-4 transmitter. -

31. Engineering Changes during this period: '

t ECN-260 Installed Reactor level alarm and tritium alarm with signal-

.to Guard Office when building is unoccupied. l t

'ECN-261 Installed a REACTOR'ON light at the Thermal' Column. j ECN-262 Installed a level alarm in the Liquid Waste System.

ECN-266 Replaced D 2 O Storage Tank level transmitter with new type.

.ECN-269 Replaced the following console recorders with new type recorders.

D O Conductivity 2

Helium and CO 2

Recombiner temperature Outer Plenum flow

' Inner Plenum flow Reactor level'

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-32.' Instrument Procedures performed:

FRC-3 Outer Plenum Flow FRC-4 Inner Plenum Flow NC-1 ~ Low Count Rate NC-2 Low Count Rate-

'NC-4 -Intermediate Range

- NC-8 Power level RM1-1 thru 10 Area Monito{g RM3-1 Secondary N Monitor RM3-4 ' Irradiated Air Monitor.

RM3-5 Building _ Exhaust Monitor RM4-1 Stack Air Monitor TIA-40A Reactor AT TIA-40B Reactor AT 8d (4) Tabulation of Major Changes in the Facility and Procedures, and the Test and Experiments, Carried Out Without Prior Approval by the U. S. AEC (10 CFR 50.59).

None this reporting period.

7.8d (5) Summary of Radioactive Material Released and Results of Environmental Surveys Performed.

Three hundred forty-eight (348) curies of tritium and 264 curies of Argon-41 were released as gaseous waste, while 43 millicuries of tritium and 190 microcuries of other 8-y emitters were released into the sanitary sewer.

Environmental samples of the streams, wells, vegetation and/or soil, and air showed no significant changes.

7.8d(6) Summary of Significant' Exposures Received by Facility Personnel and Visitors.

1. No significant exposures were received by any visitor.

2. One facility personnel received a significant exposure of 1.05 REM during this period.

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