ML19343C450

Operations Rept 30 for Jul-Dec 1980.

ML19343C450
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	03/20/1981
From:	Rozier Carter NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:
Shared Package
ML19343C446	List: ML19343C445 ML19343C450
References
NUDOCS 8103240233
Download: ML19343C450 (6)

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National Bureau of Standards Reactor Docket #50-184

' Facility License No. TR-5 OPERATIONS REPORT-

- - - #30 - - -

July,'1980 December, 1980

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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 7.8d of.the NBSR; Technical Specifications ~and covers the period.from July 1,

' $1980, to December'31, 1980.-

JSection numbers in this report (such as, ~ 7.8d(l)) correspond to those

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. used 'in the . Technical Specificat ions.

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3. March 20, 1981.-

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ROBERT.-S.. CARTER-Chief,i Reactor Ra'iationd Division.

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TABLE OF CONTENTS

7.8d(l)- Summary of Plant Operations >

7.8d(2) Unscheduled Shutdowns 7.8d(3)~ Tabulation of Major Items of Plant Maintenance-

- Tabulation of Major Changes-in the Facility and Procedures,

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. 7. 8d(4)

. and the . Test and Experiments, Carried Out Without Trior Approval

.by the U.-S. AEC (10 CFR 50.59)

. 7.8d(5) Summary of Radioactive Material Released and Results of Environ- t mental-Surveys Performed 7.8d(6) SummaryLof Significant Exposures Received by Facility Personnel

. and' Visitors 1  !,

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l 7.8d(1) Summary of Plant Operations I During the period Jdly 1, 1980, through December 31, 1980,

, the reactor was critical for 2976.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and the energy generated i

j was 29150.2 MWH.

7.8d(2) Unscheduled Shutdowns October 5: Two reactor scrams because of commercial electrical power interruptions.

Returned to power promptly.

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

.l.' Replaced D 0 prefilter elements.

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2. c. hanged'diaphrams on suction and discharge valves of both Thermal 4

Shield pumps.

3. ~ Changed diaphrams on Thermal Shield _IX' drain valves.

4. Installed'new door seal of B-2 elevator door. Also installed lower seal dogs. -

I l' 5. Repaired index plate pins for transfer arms B-5, L-5, E-2, I-2, D-3, -3, D-5, and'J-5.

6. Changed Experimental Demin. IX resin.

7.- ' Replaced TSV-1 0-rings.

8. ' Changed diaphram on-Thermal Shield Heat Exchanger inlet valve.

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.9.~ l Changed Storage Pool IX after filters.

10. -- -Removed strainers from #1, 2, and 3 Secondary pump in preparation

for new piping.

11. Repaired #6 Secondary pump suction valve.

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- 12. Moved Secondary pumps to new bedplate locations.

13. Changed both Thermal Shield IX resins.

i 14. Changed diaphram on TSV-17.

15. Replaced door seal regulator CAV-20.

16. Replaced mechanical seal. shaft sleeve, and impeller gasket on

-#3 D 0 pump.

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17. Removed broken springs from check valve on #3 D 20 pump discharge.

l 18. Repair d'#1 Shim Arm shock.

~ 19. Installed pressure guages on Secondary pump headers.

20. Installed stainless steel ball valves on all Secondary drains, vents and guages.

. 21. Replaced #4 Secondary pump coupling and realigned pump / motor.

22. Changed 0-rings in RT-3 rabbit receiver and replaced section of flight 11ne between receiver and switch.

23. Removed, disassembled and repaired all-fuel transfer pickup tools"except E-2, I-2, B-5 and L-5.

j- . -24. Changed Storage Pool'prefilters.

25. Repaired Area Radiation Monitor Main Power Supply.

26. Replaced R/I-Amplifier on CO2 gas holder.

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27. Repaired intermittant grounding of annunciator panel- AN2.

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28. Replaced seven GM Tubes on the N16 monitor during this six-month period. _

29. -Replaced USE/ TRIP selector-switch on NC-3-Period Amplifier.

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30. Instrument Procedures Performed.

FIA-40 Reactor' Outlet flow LRC-1 Reactor Level Recorder LIA-40 Reactor Level Indicator NC-1 Low Count Rate Range Intermediate Range (Log N)

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NC-3

- NC-6 Power Level Range PC-3 ,

-Normal Exhaust System Press. Contr.

PC-27 Process Room Pressure Control SPC-150 Emergency Fan Control SPS-151 Vacuum Breaker Control.

RM-3-5 . Building Exhaust Radiation Monitor 7.8d(4) -Tabulation of Major Changes;in the Facility and Procedures, and the. Test and Experiments, Carried Out Without Prior Approval 1by the U. S. AEC -(10 CFR 50.59)

Constructed replacement Cooling Tower and rearranged.

- piping'*and pumpsfin the Secondary System for use in connection with the new tower.

This modernization of the Secondary System involves

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' . component replacement and associated piping changes. The new.

-Cooling Tower conforms to'the Specifications of the Cooling-

. Tower Institute.and toLthe. applicable standards of ASTM.

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Piping conforms tofapplicable. ANSI Standards and all piping-materials certified to: applicable ASTM Standards. The concrete 1 basin complies'with the State of Maryland requirementstfor

-highways,_ bridges'and; structures. : Electrical' equipment and f

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! connections were specified to conform to applicable NEMA Standards'and Federal Specifications.

, This Secondary System modernization program will improve 3 both performance and reliability. All of the functions of the old system, and more, will.be performed by the new system.

Even though the Secondary System is not directly connected to any safetyffunction, it is= concluded'that there is no reduction

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. in any safety margin'and no unreviewed iety questions.

1, - Secondary System procedures were revised accordingly to reflect the new system.

NOTE: Even though some of the work associated with this

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.c change carries into the next reporting period, it

< is' included here for completeness.

i- 7.8d(5)L Summary of Radioactive Material Released and Results of i

. Environmental Surveys' Performed.

Two hundred ninety-five-(295) curies of tritium and 226.

curies'of Argon-41?were. released-as gaseous vaste,'while 226 millicuries'of= tritium and 491 microcuries'of other S-y emitters were released into the sanitary sewer. ,

'C  ? Environmental samples -of the streams, wells, vegetation l< and/or soil,' and air showed no significant changes.

- 7. 8d'(6) - ' Summary of Significant Exposures Re.ceived Ly Facility Personnel

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.and Visitors. ,

, L 1'. No significant exposures were received by any visitors.

. 2.. (No:significant Exposures.were-received by facility-1 personnel for.this. period.-

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