ML19343C450

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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:
References
NUDOCS 8103240233
Download: ML19343C450 (6)


Text

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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.-

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

~. used 'in the. Technical Specificat ions.

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March 20, 1981.-

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1-ROBERT.-S.. CARTER-Reactor Ra'iation 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-

. 7. 8d(4)

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

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. 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

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Replaced D 0 prefilter elements.

2 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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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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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.

2 17.

Removed broken springs from check valve on #3 D 0 pump discharge.

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18.

Repair d'#1 Shim Arm shock.

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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.

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-24.

Changed Storage Pool'prefilters.

25.

Repaired Area Radiation Monitor Main Power Supply.

26.

Replaced R/I-Amplifier on CO gas holder.

2 I-27.

Repaired intermittant grounding of annunciator panel-AN2.

.s, 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

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NC-3 Intermediate Range (Log N)

- 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-

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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 both performance and reliability.

All of the functions of the 3

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

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

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- 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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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.

? Environmental samples -of the streams, wells, vegetation

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and/or soil,' and air showed no significant changes.

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

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.and Visitors.

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No significant exposures were received by any visitors.

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

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