ML20137F289

From kanterella
Revision as of 01:24, 18 June 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Operations Rept 49 for Jan-Dec 1996
ML20137F289
Person / Time
Site: National Bureau of Standards Reactor
Issue date: 12/31/1996
From: Rowe J
NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9704010048
Download: ML20137F289 (12)
v • d • e


Text

we UNITED STATES DEPARTMENT OF COMMERCE

, National Institute of Etendercle and Technology

. , Genter'om, Maryland 20099-0001

%,'* #/ (301) 975-6210 FAX (301) 975-9427 March 24, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 s

Subject:

Docket #50-184 Gentlemen:

Transmitted herewith is Operations Report No.49 for the NBSR. The report covers the period January 1, 1996 to December 31, 1996.

Sin rely, J. ic ael Rowe'~

lef, Reactor Radiation Division Enclosure cc: Project Scientist U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Project Manager Non-Power Reactor Directorate U.S. Nuclear Regulatory Commission Washington, DC 20555

/

9704010048 961231 PDR ADOCK 05000184 R PDR ,

51,HHillipt,II,M,Ep3R

4

  • N ATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR (NBSR)

Docket #50-184 i Facility License No. TR-5  ;

i Operations Report 1

--# 4 9-- l l

January 1,1996 - December 31,1996 l

4 l This report contains a summary of activities connected with the operations of the l NBSR. It is submitted in fulfillment of section 7.8(3) of the NBSR Technical Specifica-l tions and covers the period from January 1,1996 to December 31,1996.

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

Technical Specifications.

} March 24,1997 i s  ;

, J. Michael Rowe Chief, Reactor Radiation Division

, TABLE OF CONTENTS i 7.8(3)(a) Summary of Plant Operations 4

4 7.8(3)(b) Unscheduled Shutdowns 1

7.8(3)(c) Tabulation of Major items of Plant Maintenance ,

. 1 9 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 i 3

CFR 50.59 ,

l 7.8(3)(e) Summary of Radioactive Material Released and Results of Environmental Surveys Performed l l

i 7.8(3)(f) Summary of Significant Exposures Received by Facility Personnel and Visitors '

l J

1 1

I l

1996 Opeistions Report for NBSR (TR-5)

[ Docket #50-184]

Page 1

i l

. l

}

7.8(3)(a) Summary of Plant Operations I

}

1 During the period January 1,1996 through December 31,1996 the reactor was critical for 6104 hours0.0706 days <br />1.696 hours <br />0.0101 weeks <br />0.00232 months <br /> with energy output of 119,716 MWH. In general, reactor operation during 1996 l was smooth and uneventful. Two internally issued Unusual Occurrence Reports are summa- l rized below.

l

) Near the end of 1995 a sample of silicon wafers wrapped in aluminum foi!, sealed in

! quartz and contained in an aluminum can was being irradiated for a scheduled 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. The

sample was removed after about six hours because cf higher than expected reactivity worth
even though it was well below allowable limits. Subsequent inspection showed the following

l The outside aluminum container intact.

L The lead weight and quartz around it intact.

i The quartz around the sample was broken.

j

  • The sample and aluminum wrapping intact. l l There was no contamination or releases.

l} The quartz used for sample encapsulation was deiermined to be Vycor quartz instead of 1.

regular quartz. Steps have been taken to assure that only regular quartz is used in encapsu-j lation.

L l While moving Shims with the reactor subcritical, it was discovered that Shim No.3 would

j. not drive. The reactor was shut down and upon scram, No.3 Shim scrammed normally with j no problems.
i. Checks indicated that contacts in the drive circuitry relay for Shim No.3 did not operate i properly. Wiring was moved to spare contacts and the Shim was tested and timed. Everything 4 funct!oned normally. The reactor was then restarted.  :

i 4

{- 7.8(3)(b) Unscheduled Shutdowns <

{ 1. There were (4) scrams due to commercial power interruptions. The reactor was returned to power within an hour.

l ,

j 2. There were (4) scrams due to commercial power interruptions and the reactor was not

returned to power because it was either late in the cycle or the cold source compressor 19 96 Operations Report for NBSR (TR-5)

! [ Docket #50-184]

L Page 2

_ _ _ _ . _ . _ . - , _ _ . _ _ _ _ _ _ _ - _ . . _ _ _ _ _ _ m. _ _

$ j

. . j j

'. had tripped off too and could not be restarted in time. Power was restored following

. Xenon decay or refueling. ,

j. 3. There was one scram due to commercial power interruption in which the reactor was not i immediately returned to power because of severe weather conditions in the area. Power l was restored the following day after Xenon decay, i 4. There was a scram due to the loss of the No.3 main D2O pump. Switched to a backup l - pump and returned to power.  ;

) 5. Shutdown the reactor to replace the NC-8 detector and returned to power after testing. )

i

6. There were several Rundown / Shutdowns because of Cold Source refrigerator trouble.

The reactor was returned to power after the problem was corrected. *

7.8(3)(c) Tabulation of Major items of Plant Maintenance )

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

1. Hydrostatically tested RT-2 rabbit tip to 100#.
2. Installed automatic valve on secondary inlet side of thermal shield heat exchanger

( SCV-560).

3. Replaced air operator diaphragm of SCV-3. ,

. 4. Replaced D2O portable pump for sample IX column.

5. Recirculated to clean D2O of experimental thimble G-4.

i 6. Adjusted shim height of BT-1 latch mechanism.

7. Replaced and tested personnel emergency door.
8. Disassembled, cleaned, reassembled and tested #2 shim arm drive ball-nut mecha-nism.
9. Adjusted #1 shim arm position indication.
10. Adjusted height of B-5, D-5,1-2, & E-2 fuel transfer arm pins that engage index plate.
11. Replaced #2 pump (pump end only) of N-16 detecting system.
12. Replaced #1 RD 3-4 / 3-5 blower.
13. Replaced Dp gauges and isolation valves of both 123 & 456 secondary strainers.
14. Replaced "O" rings in RT-1 & RT-3 rabbit receivers.
15. Replaced discharge pressure gauge of #4 secondary pump.
16. Replaced motor and aligned #3 main D2O pump.
17. Changed pre and after filters of spent fuel storage pool system.

19 96 Operations Report for NBSR (TR-5) ,

[ Docket #50-184]

Page 3 i

18. Replaced "O" rings on all ACV bellows valve flow restrictors.
19. Replaced manual SCV-550 (secondary auxiliary system bypass valve) with air operated valve.
20. Completed ECN-429 (NC-3 indication at cold source).
21. Replaced solenoid for cold source refrigerator turbine helium flow inlet valve.
22. Relocated both N-16 detectors and associated pumps and piping to new stand ( farther away from neutron guide). Also added additional shielding around both detector hous-  ;

ings to minimize background radiation levels.

23. Replaced filter of 100# air dryer.
24. Replaced air solenoid for COV-44,
25. Cleaned tritium detector and housing- and changed battery.
26. Removed process rcom to hot waste sump pump 1 A due to failure (new sump pumps  !

are on order).

27. Changed pre filters of spent fuel storage pool system.  ;
28. Replaced packing of 123 & 456 secondary strainers.
29. Replaced bearings and seals of #2 thermal shield pump pedestal bearing.
30. Installed additional support brackets to riser section of thermal shield supply and return i headers.
31. Overhauled #4 secondary main pump with new bearings, mechanical seats and shaft sleeves.
32. Replaced fill valve for ACV-1 emergency closure bottle.
33. Disassembled, cleanc4 lubricated and reassembled RT-4 rabbit receiver.
34. Installed actuator to DWV-19 allowing remote operation from console (ECN-409).
35. Replaced 4 cells of station battery.  !
36. Installed holdup collars on all fuel transfer arms (ECN-425).
37. Disassembled and removed old and commenced installation of new demineralized water station. j
38. Installed key switch to boral curtain control box.

l

39. Installed individual key switches to beam port and grazing tube control boxes '

(ECN-431).

40. Adjusted upper and lower micro switches on BT 2.
41. Installed new 110 volt electrical outlets for new demineralized water machine.
42. Installed new oxygen flow meter to helium sweep system recombiner. '

19 9 6 0pt: rations Report for NBSR (TR-5)

[ Docket #50-184]

Page 4

43. Replaced RT-1 D2O flow detector with new unit and verified low flow setpoints to both l

RT-1 and RT-2.

44. Continued work on reactor refueling training structure.

l

45. Continued modifications to future fuel transfer panel.

]

46. Continued treating leaking thermal shield tubes as necessary.
47. Performed regularly scheduled Tech specs and plant PM's.
48. Replaced detector for RM3-3 N-16 Channel.
49. Re-calibrated LIA-3 D2O Storage Tank Level Channel. l
50. Upgraded electronics for new FR-21 HE-1B D2O Flow Channel.
51. Repaired NC-3 Console indicator and recorder.
52. Re-calibrated TIA-8 Thermal Column Tank Outlet Temperature Channel.
53. Re-calibrated FIA-8A Cold Source D2O Flow. )
54. Re calibrated FRC-4 Inner Plenum Flow Channel.

1

55. Repaired LIA-2 Emergency Tank Level Channel.  ;

) 56. Corrected wiring problem with F1-22 and F1-23 Secondary Flow Channels for HE-1 A and i HE-18.

l 57. Repaired Main Control Panelindicator for RM3-2 Fission Product Monitor.

l 58. Re-zerced Main Control Panelindicator for NC-8 Power Channel.  !

59. Replaced Main Control Panelindicator for RM3-2 Fission Product Monitor. i
60. Replaced Main Control Panel indicator for TIA-40A Delta-T Channel. l
61. Repaired NC-5 Automatic Control Channel. j
62. Repaired NC-3 Log-N Channel. l l
63. Checked calibration of F1-30 Secondary Auxiliary Flow Channel. l
64. Replaced detector for RM3-1 N-16 Channel.  ;
65. Verified calibration of TR-1, TR-2 and TRC-3 Temperature Channels.

l

66. Re-soldered leads to Delta-T Recorder.  !
67. Verified calibration of Number 1 Shim Position Indication, i
68. Repaired BTUR Recorder Channel.
69. Installed upgraded firmware for new FR-21 and FR-22 D2O Flow Channels. {
70. Replaced detector for RM3-3 N-16 Channel.
71. Replaced failed LSI board in the Keithly Electrometerin the NC-5 Automatic Control 7

Channel.

4

72. Repaired paper cartridge in FR-1 Reactor Outlet Flow Channel.

========================================================2========= l 19 96 Operations Report for NBSR (TR-5)

[ Docket #50-184]

Page 5

73. Re-calibrated alarm set point for FIA-5 HE-2 D2O Flow Channel.

, 74. Verified calibration on TR-4 HE-1 A D2O Outlet Temperature Channel.  ;

75. Replaced temperature transmitter for TR-4 HE-1 A D2O Outlet Temperature Channel.  !
76. Re-calibrated alarm set point for LIA-7 Experimental Demineralized Storage Tank Level vhannel, j 1
77. Re-calibrated PC-3 Ventilation Pressure Regulation. I
78. Verified calibration on RM3-1 N-16 Channel.

! 79. Replaced the Main -10VDC Power Supply for Nuclear Instrumentation.

80. Repaired insulation between detector cabling and building ground for NC-6 Nuclear Channel.
81. Repaired local indicator for RM3-5 Normal Air Radiation Channel.
82. Repaired FIA-16 Thermal Shield IX Flow Channel.  !
83. Repaired loose wire on NC-3 Log-N Channel.
84. Repaired local indicator for RM3-5 Normal Air Radiation Channel.
85. Corrected RM3-1 N-16 Channel alarm problem.
86. Repaired insulation between detector cabling and building ground for NC-6 Nuclear Channel.
87. Replaced UIC detector for NC-8 Nuclear Channel.
88. Replaced UIC detector for NC-6 Nuclear Channel.
89. Repaired LIA-2 Emergency Tank Level Channel. I
90. Replaced recorder for new Sk Waste Tank Level Channel.
91. Verified calibration of RM3-2 Fission Product Monitor Channel.
92. Replaced print head on RR-3 Tritium Recorder. I
93. Re-calibrated LIA-3 D2O Storage Tank Level Channel.
94. Replaced the Main -10VDC Power Supply for Nuclear Instrumentation.
95. Repaired problem with Nuclear Instrumentation Pulse Checker.
96. Replaced failed annunciator card for Thermal Shield Conductivity Channel.
97. Repaired local indicator for RM3-5 Normal Air Radiation Channel.
98. Re-routed detector cable for RM3-3 N-16 Channel. I
99. Verified proper operation of Thermal Shield and Thermal Column Run-downs.

100. Repaired noisy Reactor Delta-T recorder.

101. Cleaned cooling fan filters on Annunciator Equipment Rack.

102. Replaced NC-3 Period Amplifier and re-calibrated channel.

19 9 6 Operations Report for NBSR (TR-5)

[ Docket #50-184]

Page 6

l 103. Replaced failed alarm unit for FIA-8A Cold Source D2O Flow Channel.

104. Repaired Fire Alarm Bell Switch on main console.

105. Repaired Number 3 Shim Arm control circuit.

106. Replaced indicator lamp on RM1-4 Area Radiation Monitor.

, 107. Verified calibration of FR-1 and FIA-40 Flow Channels.

, 108. Replaced differential pressure transmitter on LIA-3 D2O Storage Tank Level Channel.

109. Repaired TIA-15 Storage Pool Temperature Channel.

j 110. Repaired RR-1 Radiation Recorder.

111. Repaired LRC-1 Level Recorder.

l

, 112. Re-calibrated FRC-3 Outer Plenum Glow Channel.

113. The following instrument calibration surveillance tests were performed:

Channel Title BTUR-1 Reactor Thermal Power Recorder FRC-3 Outer Plenum Flow Recorder 1

' \

FRC-4 inner Plenum Flow Recorder l FIA-16 l Thermal Shield IX Flow Indicator 1 FIA-17 Secondary Auxiliary Cooling Flow Indicator FIA-40 Reactor Outlet Flow Indicator Alarm LRC-1 Reactor Vessel Level Recorder LIA-3 D2O Storage Tank Level l 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 i NC-7 Nuclear Power Channel NC-7 NC-8 Nuclear Power Channel NC-8 NC-9 Nuclear Safety System 3

PC-3 Normal Exhaust System Pressure Controller

! PC-27 Process room Pressure Controller SPC-150 Emergency Fan Controller SPS-150 Emergency Standby Fan Controller I

i l

......................................u........................... l i 9 9 6 Operations Report for NBSR (TR-5)

[ Docket #50-184]

Page 7

_ _ _ . _ . _ _ _ . _ _ . _ ~ _ _ _ _ _ _ _ - . _ _ . . - . _

. i

. t l . SPS-151 Vacuum Breaker Controller l' . . RM .1-1 Area Monitor- First Floor North Wall f RM 1-2 Area Monitor - First Floor East Wall RM 1-3 }

Area Monitor- First Floor South Wall j

. . RM 1-4 Area Monitor- First Floor West Wall  !

RM 1-5 Area Monitor - Second Floor Celling 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

' l RM 1-9 Area Monitor - Process Room West Wall j RM 1-10 Area Monitor - Control Room l l RM 1-15 C001 Rabbit Lab Radiation Area Monitor  ;

RM 3-1 Secondary Cooling N-16 Radiation Monitor l RM 3-2 Helium Sweep Gas Radiation Monitor

! RM 3-3 Secondary Cooling N-16 Radiation Monitor i RM 3-4 Irradiated Air High Activity Radiation Monitor RM 3-5 Building Exhaust High Activity Radiation Monitor j RM 4-1 Stack Gas High Activity Radiation Monitor l RM 4-2 Emergency Ventilation Stack Radiation Monitor

[ RM 4-4 MAA Gamma Radiation Monitor

' BT-4FACS BT-4 FACS Spectrometer Radiation Monitors j TRA-2 Reactor Outlet Temperature Recorder i

TR-4 D2O HE-1 A Outlet Temperature Recorder I

TIA-15 . Storage Pool Water Temperature Indicator & Alarm j TIA-40A Reactor Outlet-Inlet Temperature Differential Indicator & Alarm - Channel A

! TIA-40B Reactor Outlet-Inlet Temperature Differentiai Indicator & Alarm - Channel B I

7.8(3)(d) Tabulation of Major Changes in the Facility and Procedures, and i the Test and Experiments, Carried Out Without Prior Approval by l the NRC pursuant to 10 CFR 50.59.  !

There were no significant changes to procedures during 1996. j

\

19 96 Operations Report for NBSR (TR-5)

[ Docket #50-184]

Page 8

.The f'ollowing facility changes were completed this year;

.ECN-421 A new drive system was installed at Beam Tube 8 that improved the beam shut-ter operation and beam status read-out. This installation was due to the installation of a new residual stress measurement facility and associated shielding at the beam port. The new shutter mechanism is similar to the mounting of the replaced drive system with the elimination of a potential safety hazard. The mechanism and its mounting involve no unteviewed safety questions.

ECN-428 The Passive Inft . red Detector and the No Entry Sign at the Thermal Column were interfaced with the Boral Curtain Hoist Control. Whenever the Boral Curtain is in the down position, a relay activates a key switch circuit at the Thermal Column that powers the Passive Infrared Detector and the No Enter Sign. This modification eliminates nuisance in-trusion alarms at the Thermal Column that occur when the Boral Curtain is in the full down position. This modification does not create an unreviewed safety issue.

ECN-429 Installation of an Action Pak electro-optic isolator in the Intermediate Range Nuclear Channel No. 3 provides indication of reactor power from shutdown to 20 MW to the controller for the Liquid Hydrogen Cold Source. This modification does not create an unre-viewed safety issue.

ECN-431 Installed unique captive key switches for the Beam Ports / Grazing Tubes and the Boral Curtain control circuits to provide more uniformity and enhance control of the neutron beams. The unique key for each facility will allow tagging individual keys when specific con-trol of that facility is required. This change will not prevent the lowering / closing of the shutters and will provide better control of each facility with individual key controls. This change does not involve an unreviewed safety question.

7.8(3)(e) Summary of Radioactive Material Released and Results of Environmental Surveys Performed.

The gaseous waste released was 203 curies of tritium,914 curies of Argon-41,0.065 curies of Cl-38, and 0.05 curies of Br-82. There were 0.275 curies of tritium and 60 mi-crocuries of other beta-gamma emitters released into the sanitary sewer.

Environmental samples of the streams, vegetation, and/or soil, and air showed no signif- i l

19 9 6 Operations Report for NBSR (TR-5)

[ Docket #50-184]

Page 9

l

~ ~

. ' icant changes. ,

l j

7.8(3)(f) Summary of Significant Exposures Received by Facility Personnel i and Visitors.

1. None to visitors. ,

J

2. Dosimetry results for this reporting period indicated that no facility personnel received significant exposures. ,

I l

3 19 9 6 Operations Report for NBSR (TR-5)

[ Docket #50-184]

j Page 10

Retrieved from "https://kanterella.com/w/index.php?title=ML20137F289&oldid=2834215"