ML20151U354

Corrected Operations Rept 40,1987

ML20151U354
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	12/31/1987
From:	Rozier Carter NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:
Shared Package
ML20151U350	List: ML20151U346 ML20151U354
References
NUDOCS 8805020035
Download: ML20151U354 (10)

Text

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!MTIONAL BURENJ OF STANDEDS REACTOR Docket #50-184 Facility License No. TR-5 Operations Report

-- #40 ->

f January 1,1987 - December 31, 1987 This report contants a summry 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 fron Jarnary 1,1987 to December 31, 1987.

Sectior. numbers in the report (such as 7.8(3)(a)) correspond to tlose used in the Tedinical Specifications.

March 28, 1988 ROBERT S. CARTER Chief, Reactor Radiation Division 8805020035 880421 PDR ADOCK 05000184 R DCD

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- '. o TABLE OF GJtEEtES 7.8(3)(a) Summry of Plant Operaticns 7.8(3)(b) Unscheduled Shutdcuns 7.8(3)(c) Tabulation of Major Items of Plant bhintenance 7.8( 3) (d ) Tabulation of Major Changes in the Facility and Procedures, and the Test and Experimnts, Carried Out Withcut Prior Approval by the NRC Pursuant to 10 CFR 50.59 7.8(3)(e) Summry of Radioactive thterial Released and Results of Environmntal Surveys Performd 7.8(3)(f) Summry of Significant Exposures Received by Facility Personnel and Visitors 1

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7.8(3)(a) Summry of Plant Operations During the calendar year 1987, the reactor was critical for 3358.4 huurs and the energy generated was 63,968 fMI. The follcuing are highlights of significant cperational activities during this period.

1. Spent Fuel Shipmnts Nine spent fuel shipmnts were mde to the Departmnt of Energy for re-processing.

2. Shim Arm Replacemnt The fcur shim arm cadmium blades were replaced with new ones. The old ones lasted' nore than seven years. During the transfer of old blades, one of the hold-down bolts was 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 mlfunctioned.

This was covered by a special reprt to the Region.

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

4. Therml Shield Cooling System Additional coils in the thermi shield cooling system develq>ed leaks and were isolated. A new mthod for sealing these leaks is being investigated.

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7.8(3)(b) Unsdieduled Shutdmns There were two (2) Scrams due to ccranurcial pwer dips. In both cases the reactor was kept shutdown.

7.8(3)(c) Tabulation of !!ajor Item of Plant !!aintenance

1. Replaced "cups" of ACV 7 air cperator

2. Replaced thermi shield storage tank fill valve diaphragm

3. Changed experinental demin. system filters

4. Installed tcp nochanical stop on regulating rod

5. Isolated several loops of thermi shield ring header that were leaking or suspected to be leaking

6. Replaced all "o" rings on RT-3 rabbit receiver

7. Regenerated demineralizer (5 tires)

8. Changed storage pool IX pre and af ter filters (4 tines)

9. Installed 3" mke-up line to cooling tower basin from fire min

10. Replaced all pneumtic clanping cylinders of fuel cutting saw

11. Replaced thermi shield mke-up isolation valve

12. Installed #2 retention tank punp for hot waste system

13. Replaced valve operator diaphragm for TSV-2

14. Replaced shaf t sleeves, outer bearing, and nuchanical seal c2 #2 secondary puq)

15. Re-piped filter of storage pool vacuum

16. Inplaced seals and bearings of fuel transfer cannon

17. I lugged leaking tubes of experinental demin. heat exdianger

18. Plt.nt division conducted 5-year minter ance on all switchbmrds and transformer

19. Replaced (D2 purge fan drive twalt 4

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20. Replacel suction aM discharge valve diaphragms of both experimental D O 2

pumps

21. Plugged leaking tubes of nuin heat-exdianger HE-1A

22. Replaced all conductivity cells in process room with new ones

23. Replaced storage pool IX resin aM cleaned distribution screens

24. Replaced all four shim arms with new aTes

25. Installed new sealing rings on all four shin arm shaf ta

26. Replaced air operator diaphragm of TSV-1

27. Replaced lef t battery bank on "B" emrgency diesel generator

28. Replaced fuel lines on bath emrgency diesel generators

29. Replaced both pre aM absolute f11ters in EF-4 ventilation unit

30. Peplaced anthra-filt and acticar filters of station demineralizer

31. Replaced IX resin of station demineralizer

32. Changed valve diaphragms of SPV 4, 8, and 60

33. Changed resin in both therml shield IX colutns

34. Replaced cell #50 aM #54 of station battery with new cells

35. Installed storage pool purp priming system

36. Replaced valve dial tiragms of TSV-3 & 4

37. Replaced wear rings and seals of #1 storage pool pu m

38. Replaced high voltage pwer supply on Reactor power channel NC-6.

39. Replaced alarm unit on Experimncal Demin. Water Pressure PIC-1.

40. Calibrated Reactor Outlet Flow Recorder FR-1.

41. Replaced neutron detector on NC-6.

42. Rephced ccnsole panel mter on NC-6.

43. Replaced detecter on the Liquid Waste Monitor P2M-3. ,

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44. Calibrated Storage Pool IX Flow FIA-14.

45. Replaced detector and source dTecked Area Monitor R'il-4.

46. Replaced Input Unit Card 07-39 on NC-6 High Flux Scram.

47. Calibrated Reactor Vessel Level Channel LIA-40.

48. Replaced detector, cnecked calibration and scurce checked Rt13-1.

49. Replaced digital meter for #1 Shim position readout.

50. Calibrated Reactor Differential Terrperature channels TIA-40A & B.

51. Replaced transmitter and mnifold valve on Sec. Heat Exdianger HE-1B.

52. Replaced Autom tic Regulating Rod withdras relay K50A.

53. Calibrated Recotr.biner internal & outlet Tenp. diannels TRS-10 &

TIA-ll.

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 pmer supply for mintenance.

57. Adjusted % Pmer Deviation Ingit Unit Card 07-30 to 10%.

58. Replaced pmer tubes in min Radiation Area lionitor diassis.

59. Replaced three zener diodes on the anurciator panel AN4.

60 The follming Technical Specification surveillance test were performd:

IC-8 Nuclear Pm er Range Channel LIA-3 Storage Tank Level FIA-15 Therm 1 Shield Cooling Water Flm Irrlicator BTUR-1 Reactor Nrml Pmer TIA-40A Reactor Delta Temperature Irrlicator l

Rt11-1-10 Area Radiacion tionitors NC-7 Nuclear Pmer Range Channel l Ril-3-4 Irradiated Air tionitor

! NC-4 Nuclear Intermdlate Range Channel l

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Ril-1 Stack Air Monitor FRC-3 Reactor Outer Plenum Flw FRC-4 Reactor Innar Pierum Flow FCA-7 'Iherml Colum Flw Irxiicator Control RM4-4 N North Criticality Monitor R41-4 S South Criticality Monitor l

Rb1-3-5 Normal Air Mmitor NC-3 Nuclear Intermediate Range Channel LRC-1 Rmetor Level Recorder l NC-9 Nuclear Int < lock Trip Test PC-3 Noren1 Exhaust Monitor PC-27 Process Room Fan Controller SPC-150 Energency Fan Controller SPS-150 Emergency Starribf Controller SPS-151 Vacuum Breaker Controller NC-6 Nuclear Pmer Range Channel LIA-40 Re ctor Level Indicator FI A-40 Reactor Outlet Fim Indicator Ict-3-1 N-16 flanitor NC-1 Nuclear Soarce Range Channel NC-2 Nuclear Source Range Channel R i-3-2 Fission Products Monitor TIA-40B Rmctor Delta Temperature Indicator TRA-2 Reactor Outlet Terperature Recorder 7

7.8( 3) (d) Tabulation of !!ajor Changes in the Facility and Procedures, and the Test and Experinents, Carried out Witlnit Prior Approval by the imC pursuant to 10 CFR 50.59 D2 0 Cold Neutron Source Experirent:

A D 0 cold neutron source was installed in the beam tube originally 2

designed for it. The purpose of the source is to enhance the intensity of very low energy neutrcns available for caterials research using neutron nethods. The source is self contained within its own shield.

Extensive analysis have'shown that any credible failure including potential release of stored energy will not affect the reactor.

Accordingly there are no un-reviewed safety questicos.

Relevant Engineering Changes are summrized belcw:

ECJ-315 Install a Cryogenic Cocpressor alarm. This equipnent has no effect on the operation of the reactor and therefore its failure wcula not involve an un-reviewed safety question.

EC1-324 I:odify mkeup water system to the Cooling Tcwer. This system is a replacenent for the previous system and operates on the l

sam Cooling Tcwer level controller. Therefore, no i

! un-reviewed safety question exist.

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• "i D21-328 ' Install Ctyogenic Bismth Tip instrumnt panel for cryory?nic fim and temperature.

This change incorporates an instrutentation panel for the Biscuth tip. 'Ihe instrumntation will nonitor the cooling flms of the bistuth tip and associated equipcent and ,

includes trips, alarms, and .'eak detectors. There will be a reactor scram on lw ficw connected to the "Experinent Scram" channel. With the exception of activating the "exp3rinunt scram", all other safety functions renuin the sane and are unaffected by this change. Therefore, there are no un-reviewed safety questions. Associated procedures have been prepared and icplemnted.

Bli-330 tblified Cryogenic Shutter lif t mdianism so that shutters A&B and C could all be operated at the same time.

This rodification involves n.) un-reviewed safety question since the shutters and latch cuchanisms retain as originally designed.

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7.8(3)(e) Surmary of Radioactive Ibterial Released arrl Results of Environnental Surveys Perforned.

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 of tritium and 3 millicuries of other beta-ganma emitters were rele.ased into the sanitary sewer.

Environnental sarples of the streans, vegetation, arrl/or soil, arri air showed no significant changes.

7.8(3)(f) Sunrary of Significant Exposures Received by Facility Personnel airl Visitors

1. None to visitors.

2. Dositetry results for this reporting period irxlicated that no facility personnel received significant exposures.

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