ML19343C450
| 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.
Chief,i d
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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
.l.'
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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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.
2 17.
Removed broken springs from check valve on #3 D 0 pump discharge.
2 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.
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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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