ML20148N608

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Operations Rept 40,Jan-Dec 1987
ML20148N608
Person / Time
Site: National Bureau of Standards Reactor
Issue date: 12/31/1987
From: Rozier Carter
NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8804070152
Download: ML20148N608 (11)
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NATIONAL BUREAU OF STANDARDS REACTOR Docket #50-184 Facility License No. TR-5 Operations Report

... #40 ---

January 1, 1987 - December 31, 1987 This report contains a su:nmary of activities connected with the operations of the NBSR. It is submitted in fulfillment of section 7.8(3) of the NBSR Technical Specifications and covers the period from January 1, 1987 to December 31, 1987.

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

March 28, 1988 ROBERT S. CARTER Chief, Reactor Radiation Division 8804070152$$

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TABLE OF CONTENTS 7.8(3)(a) Summary of Plant Operations 7.8(3)(b) Unscheduled Shutdowns 7.8(3)(c) Tabulation of Major Items of Plant Maintenance 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 CFR 50.59 7.8(3)(e) Summary of Radioactive Material Released and Results of Environmental Surveys Performed 7.8(3)(f) Summary of Significant Exposures Received by Facility Personnel and Visitors 2

7.8(3)(a) Summary of Plant Operations During the calendar year 1987, the reactor was critical for 3358.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the energy generated was 63,968 NWH. The following are highlights of significant operational activities during this period.

1. Spent Fuel Shipments Nine spent fuel shipments were made to the Department of Engineering for reprocessing.
2. Shim Arm Replacement The tour shim arm cadmium blades were replaced with new ones. The old ones lasted are than seven years. During the transfer of old blades, one of the hold down bolts were dropped into the vessel and was retrieved. The new shim arms utilize captive bolts. Following ,

assembly of the shim arm drives, shim No. 1 drive malfunctioned.

This was covered by a special report to the Region.

3. Ileat Exchanger Leaks Sixteen tubes in one of the main heat exchangers developed leaks and were plugged. This was covered by a special report to the Region.

l 4. Thermal Shield Cooling System Additional coils in the thermal shield cooling system developed Icaks and were isolated. A new method for sealing these leaks is being investigated, i

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7.8(3)(b) Unscheduled Shutdowns There were two (2) Scrams due to commercial power dips. In both cases the reactor was kept shutdown.

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

1. Replaced "cups" of ACV 7 air operator
2. Replaced thermal shield storage tank fill valve diaphragm
3. Changed experimental demin system filters
4. Installed top mechanical stop of regulating rod
5. Isolated several loops of thermal shield ring header that were leaking or suspected to be leaking
6. Repiced all "o" rings of RT-3 rabbit receiver
7. Regenerated demineralizer (5 times)
8. Changed storage pool IX pre and after filters (4 times)
9. Installed 3" make-up line to cooling tower basin from firemain
10. Replaced all pneumatic clamping cylinders of fuel cutting saw
11. Replaced thermal shield make-up isolation valve
12. Installed #2 retention tank pump for hot waste system
13. Replaced valve operator diaphragm for TSV 2
14. Replaced shaft sleeves, outer bearing, and mechanical seal of #2 secondary pump
15. Repiped filter of storage pool vacuum
16. Replaced seals and bearings of fuel transfer cannon
17. Plugged leaking tubes of experimental demin heat exchanger
18. Plant division conducted 5-year maintenance on all switchboards and transformer
19. Replaced CO2 purge fan drive belt 4
20. Replaced suction and discharge valve diaphragms of both experimental D 20 pumps
21. Plugged leaking tubes of main heat exchanger HE-1A
22. Replaced all conductivity cells in process room with new ones
23. Replaced storage pool IX resin and cleaned distribution screens 24 Replaced all four shim arms with new ones
25. Installed new sealing rings on all four shim arm shafts
26. Replaced air operator diaphragm of TSV 1
27. Replaced left battery bank on "B" emergency diesel generator
28. Replaced fuel lines on both emergency diesel generators
29. Replaced both pre and absolute filters in EF 4 ventilation unit
30. Replaced anthra-filt and acticar filters of station demineralizer
31. Replaced IX resin of station demineralizer
32. Changed valve diaphrages of SPV 4, 8, and 60
33. Changed resin in both thermal shield IX columns
34. Replaced cell w50 and #54 of station battery with new cells
35. Installed storage pool pump priming system
36. Replaced valve diaphragms of TSV-3 & 4
37. Replaced wear rings and seals of #1 storage pool pump
38. Replaced high voltage power supply on Reactor power channel NC 6.
39. Replaced alarm unit on Experimental Demin. Water Pressure PIC-1.
40. Calibrated Reactor Outlet Flow Recorder FR-1.

l 41, Replaced neutron detector on NC-6.

42. Replaced console panel meter on NC-6.
43. Replaced detecter on the Liquid Waste Monitor RM4 3.
44. Calibrated Storage Pool IX Flow FIA 14.
45. Replaced detector and source checked Area Monitor RM1 4 5
46. Replaced Input Unit Card 07 39 on NC 6 High Flux Scram.
47. Calibrated Reactor Vessel Level Channel LIA 40,
48. Replaced detector, checked calibration and source checked RM3 1.
49. Replaced digital eter for #1 Shim position Readout.
50. Calibrated Reactor Differential Temperature channels TIA 40A & B.
51. Replaced transmitter and manifold valve on Sec. Heat Exchanger HE lB.
52. Replaced Automatic Regulating Rod withdraw relay K50A.
53. Calibrated Recombiner internal & outlet Temp, channels TRA 10 &

TIA-11, 54 Replaced drive cable on the Radiation Recorder RR 1.

55. Replaced print coil & print head on the Radiation Recorder RR 1.
56. Replaced +10 VDC Nuclear power supply for maintenance.
57. Adjusted % Power Deviation Input Unit Card 07-30 to 104.
58. Replaced power tubes in main Radiation Area Monitor chassis.
59. Replaced three zener diodes on the anunciator panel AN4.

60 The following Technical Specification surveillance test were performed:

NC 8 Nuclear Power Range Channel LIA-3 Storage Tank Level FIA 15 Thermal Shield Cooling Water Flow Indicator BTUR 1 Reactor Thermal Power TIA 40A Reactor Delta Temperature Indicator RM1-1-10 Area Radiation Monitors NC-7 Nuclear Power Range Channel RM 3 4 Irradiated Air Monitor NC-4 Nuclear Intermediate Range Channel 6

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I I RM4 1 ' Stack Air Monitor 1 FRC 3 Reactor Outlet Plenus Flow

, FRC 4 Reactor Inlet Plenum Flow {

FCA 7 Thermal Column Flow Indicator Control RM4 4 N North Criticality Monitor RM4-4 S South criticality Monitor RM 3 5 Normal Air Monitor NC 3 Nuclear Intermediate Range Channel l 4

LRC 1 Reactor Level Recorder NC-9 Nuclear Interlock Trip Test  ;

! PC 3 Normal Exhaust Monitor  ;

PC 27 Process Room Fan Controller ,

SPC 150 Emergency Fan Controller ,

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! SPS 150 Emergency Standby Controller l SPS-151 Vacuum Breaker Controller [

1 NC 6 Nuclear Power Range Channel  ;

LIA 40 Reactor Level Indicator FIA 40 Reactor Outlet Flow Indicator l RM-3 1 N 16 Monitor l NC 1 Nuclear Source Range Channel

! NC 2 Nuclear Source Range Channel i

j RM 3 2 Fission Products Monitor i

TIA 40B Reactor Delta Temperature Indicator TRA-2 Reactor Outlet Temperature Recorder a

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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 CFR 50.59 D2 0 Cold Neutron Source Experiment A D2 0 cold neutron source was installed in the beam tube originally designed for it. The purpose of the source is to enhance the intensity of very low energy neutrons available for materials research using neutron methods. The source is self contained within its own shield.

Extensive analysis have shown that any creditable failure including potentieel release of stored energy will not affect the reactor.

Accordingly there are no unreviewed safety questions.

Relevant Engineering Changes are summarized below:

ECN-315 Install a Cryogenic Compressor alarm. This equipment has no effect on the operation of the reactor and therefore its failure would not involve an unreviewed safety question.

ECN 324 Modify makeup water system to the Cooling Tower. This system is a replacement for the previous system and operates on the same Cooling Tower level controller. Therefore, no unreviewed safety question exist.

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-l ECN-328 Install Cryogenic Bismuth Tip instrument panel for cryogenic flow and temperature. ,

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t This change incorporates an instrunentation panel for the  !

Bismuth tip. The instrumentation will monitor the cooling flows of the bismuth tip and associated equipment'and include trips, alarms and leak detectors. There will be a reactor scram or low flow connected to "Experiment Scram" channel.

With the exception of activating the "experiment scram", all j

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other safety functions remain the same and are unaffected by .

i this change. Therefore, there are no unreviewed safety l questions. Associated procedures have been prepared and i i

implemented.

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i~ ECN 330 Modify Cryogenic Shutter lift mechanism so that shutters A&

j and C could all be operated at the same time. l

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This modification involves no unreviewed safety question  !

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l since the shutters and latch mechanisms remain as originally j i

designed, i

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7.8(3)(e) Summary of Radioactive Material Released and Results of

Environmental Surveys Performed.

l The gaseous waste released was 1,154 curies of tritium (includes 796 curies via the cooling tower) and 727 curies of Argon 41, while 117.7 curies i

of tritium and 3 millicuries of other beta-gamma emitters were released into the sanitary sewer. l Environmental samples of the streams, vegetation, and/or soil, and air  !

showed no significant changes, j 1

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

1. None to visitors.
2. Dosimetry results for this reporting period indicated that no facility personnel received significant exposures.

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March 28, 1987  !

i U.'S. Nuclear Regulatory Commission i 1 Document Control Desk Washington, DC 20555 1 e

Subject:

Docket #50-184 l Gentlemen: l Transmitted herewith is Operations Report No. 40 for the pational Boread of ,

Standards Reactor. The report covers the period January 1,19n/ to December .

31,-1987.

Very truly yours, eckJ4. W Robert S. Carter Chief, Reactor Radiation Division Attachment ec: Director, Division of Reactor Licensing U. S. Nuclear Regulatory Commission 1 Washington, DC 20555 i

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