ML20082B042

NIST Reactor Operations Rept 47 for Jan-Dec 1994

ML20082B042
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	12/31/1994
From:	Rowe J NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9504040339
Download: ML20082B042 (11)

Text

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UNITED STATES DEPARTMENT OF COMMERCE National Instkute of Etonderde end Technology Gothersburg Maryland 20099-0001 (301) 975-6210 k

f FAX (301) 975-9427 r.. e March 28, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Docket #50-184 Gentlemen:

Transmitted herewith is Operations Report No.47 for the NBSR. The report covers the period January 1, 1994 to December 31, 1994.

Sincer ly, tw. cut <--

ichael Rowe Chief, Reactor Radiation Division Enclosure cc: Project Scientist U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Project Manager 4

Non-Power Reactor Directorate U.S. Nuclear Regulatory Commission Washington, DC 20555 f

A<1000q 9504040339 941231 jff.'I I PDR ADOCK 05000184 6

R PDR i

j

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

Docket #50-184 Fa cility License No. TH-5 Operations Report

..#47 January 1,1994-December 31,1994 This report contains a summary of activities connected with the operations of the NBSR. It is submitted in fuifillment of section 7.8(3) of the NBSR Technical Specifica-tions and covers the period from January 1,1994 to December 31,1994.

Section numbers in the report (such as 7.8(3)(a)) correspond to those used in the Technical Specifications, March 28,1995 6

. Michael Rowe Chief, Reactor Radiation Division

1 o

Page 1 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 L

7.8(3)(e)

Sommary of Radioactive Material Released and Results of Environmental Surveys Performed 7.8(3)(f)

Summary of Significant Exposures Received by Facility Personnel and Visitors t

1 19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

~

Page 2 7.8(3)(a). Summary of Plant Operations

)

During 1994, the reactor was operated for the first five months only. The reactor was critical for 2782 hours0.0322 days <br />0.773 hours <br />0.0046 weeks <br />0.00106 months <br /> with energy output of 41571 MWH. At the end of May 1994 the reactor was shut down in preparation for major upgrade of systems and facilities. Among these are upgrade of the cooling systems, replacement of the cold source, rebuilding of the top refueling plug and extensive maintenance and inspections. These programs are on-go and expected to be completed in the spring of 1995 at which time the reactor will be restarted. A summary of the programs is listed below.

1.

Cooling Systems The primary, secondary and auxiliary cooling systems were extensively upgraded. The two shell and tube type main heat exchangers were replaced with three plate type heat exchanger with the third one to serve as an installed spare. The purification and experime cooling system heat exchangers were also replaced. A new filtration system was added to the secondary system to provide cleaner water to the secondary side of the heat exch 2.

Cold Source The existing heavy water ice cold source installed in the cryogenic beam port is be replaced by a smaller, more effective liquid hydrogen source that will provide significa higher subthermal flux. The remaining three of seven guide tubes will also be complete 3.

Refueling System During maintenance and inspection of the refueling system transfer arms,it was noted that the boral plate underneath the top refueling plug had sagged and began to interfere wit the operation of the transfer arms. It was then decided to remove the top plug and rebuild th entire refueling mechanism.

Examination of the boral plate upon removal of the plug showed it to be in bad shap with swelling, corrosion and separation in several areas. The degradation was appar due to an electrochemical reaction between the aluminum and graphitar bearing on the transfer arm shafts where evidence of corrosion was also found at the bottom machined and a stainless steel sleeve shrunk fit onto it. All bearings were replaced and all pickup tools were refurbished with some parts replaced. A new helium seal system was i

==============================================

19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

F Page 3 installed atop of the transfer arms.

The boral plate was originally installed at the bottom of the refueling plug to reduce activation of the steel plate of the plug. The boral plate will not be replaced since 1

measurements indicated that radiation levels even without the boral would be manageable should future maintenance be required. The bottom of the plug is more than 10 ft. from the top of the core with heavy waterin between. However, approximately 20 aluminum and boral j

plates installed at the bottom of the transfer arms and shielding plugs were replaced with a borated aluminum alloy. This will further depress the flux at the bottom of the refueling plug.

Ongoing testing of the plug shows good performance and smooth operation.

4.

Maintenance and Inspections The planned reactor outage and the fact that the core was removed, the heavy water drained and the generally significantly lower radiation levels provided an opportunity for extensive maintenance and inspections that otherwise could not be easily done. The removal of the top plug allowed for careful borescope inspection of the reactor vessel and the grid.

Everything appeared in. good condition. The detents at the bottom of top grid showed no sign of wear and appeared intact.

Items of significant maintenance included replacement of the shim arm blades, replacement of most valve diaphragms, overhaul of the diesel generators, the air systems, and the cooling tower, refurbishing of the confinement building, installation of custom i

shielding for IXs and filters and maintenance of the thermal shield cooling system. During this period too, Improvement and upgrade of portions of reactor instrumentation was undertaken and a significant amount of low level waste was packaged and shipped.

i in planning and executing the above activities, the main focus was on keeping exposures and releases as low as reasonably achievable. As many potential sources of o

exposure such as filters, resins and identified components were removed prior to any l

significant work. As a result, exposures were held well below those of similar but lesser outages in the past.

i I

............................................=..=...=...======..=.

19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

Page 4 7.8(3)(b)

, Unscheduled Shutdowns

1. There were three (3) scrams due to a commercial power dip. The reactor returned to power.

2. There was one (1) scram due to a commercial power dip after which the reactor stayed down because it was at tne end of a fuel cycle.

3. There was a scram caused by the loss of a 10-volt Nuclear Instrument Power Supply during maintenance in the area. The power supply was put back into service and the reactor was returned to power.

4. There was a scram caused by a spike on a 10-volt Nuclear instrument Power Supply while attempting to reset a failed standby unit. The original power supply was put back into service and the reactor was returned to power.

7.8(3)(c)

Tabulation of Major items of Plant Maintenance 1.

Replaced #1 N 16 pump with new pump head - motor was not replaced.

2. Located and repaired three DC grounds in emergency lights circut.

3. Changed primary purification system after filters 4.

Regenerated demin station IX column several times.

5. Changed air cylinders on fuel cutting saw.

6. Replaced #4 shim position indication module.

7. Cut 36 spent fuel elements for rad waste shipment of aluminum pieces.

8. Changed storage pool pre-filters.

9.

Removed spent resin from both thermal shield IX columns.

10. Removed drive mechanisms from #1 & #2 shim arms.

11. Changed primary purification system pre & after filters.

12. Removed drive mechanisms from #3 & #4 shim arms.

l

13. Pumped spent resin from #3 & #4 IX to High Integrity Container (H.I.C.).

14. Pumped spent thermal shield resin to H.I.C. for transport

15. Loaded all spent filters from fluid systems into H.I.C.

16. Disassembled primary and secondary piping for systems modifications.

17. Replaced shim arms.

18. Old HE 2 (primary purification system HX) removed from process room.

19. Old HE-7 (exp demin system HX) removed from pra ess room.

-----------------------------------------.....==---------===

19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

Page 5

20. Inspected and removed reactor inlet strainer basket.

21. In'spected and removed reactor outlet strainer basket.

22. Old HE-6 (thermal shield system HX) removed from process room.

23. Old HE-1B (primary system HX) removed from process room.

24. Old HE-1 A (primary system HX) removed from process room.

25. Old #4 sump pumps removed from process room.

26. Removed old and installed new chiiled water cooling lines to the helium condensor.

27. Replaced seal cups on ACV 2 operating cylinder.

28. New HE-7 (exp demin system HX) installed.

29. New HE-2 (primary purification system HX) installed.

30. Replaced air soleniod for DWV-40 (emergency tank inlet).

31. Removed sightglasses from the thermal shield storage tank and exp demin storage tank.

32. Cleaned cooling tower basin.

33. Completed installation of decontamination machine.

Replaced casing drain valves of both D O shutdown pumps with stainless steel ball 34.

2 valves.

35. Re-piped IX #1 & #2 back into the primary purification system.

36. Replaced the following 0.5" diaphragm valves with stainless steel ball valves:

DWV-179,180,182, & 183.

37. Replaced open indication limit switch on DWV-8 ( #1 D 0 S/D pump ).

2

38. Installed backwash pump in secondary system.

39. Painted process room ceiling, walls, & floor.

40. Replaced the following 0.5" diaphragm valves with stainless steel ball valves:

DWV-124,125, 311, & 312.

41. Removed sightglass from the emergency D O tank.

2

42. Replaced the following 0.5" diaphragm valves with riWniess steel ball valves:

DCV-50 & 51.

43. Completed cooling tower bolt replacement-carbon steel bolts replaced with stainless steel bolts.

44. Moved 2 automatic strainers, backwash assist pump and bag filter to secondary pumproom and continued with piping installation.

45. Replaced FTV-18 diaphragm valve with a stainless steel ball valve.

46. Placed new HE-1 A, HE-18, & HE-1C in process room.

47. Stacked lead bricks onto shielding stand of HE-2.

...=....--.......................

---

...=======================

1994 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184)

Page G

48. Replaced TSV-18 & 19 diaphragm valves with brass ball valves.

49. Rbplaced DCV-3 ( demin water to refueling ) operator with a manual bonnet and handwheel.

50. Removed reactor Upper Outer Plug (UOP) Static weight = 36,000 lbs.

51. Stacked lead around #1 & #2 thermal shield IX columns.

52. Changed storage pool system pre & after filters.

53. Replaced secondary pump suction, discharge, & discharge check valves with new ones.

54. Removed B-2 level 10# air compressor from system.

55. Mounted and aligned both exp D O pumps next to HE-2.

2

56. Replaced bearings and seals of #2, #3, & #4 shim arm shafts (#1 shim arm has temporary seal until new D O is loaded into the reactor).

2

57. Installed and connected #4 sump pumps.

58. Fabricated and installed new weather station.

59. Tested both emergency diesel generators under load (150 KW ).

60. Installed and lowered new cryostat shutters D, E, & G. Shutter F installed but remains raised and pinned with cryostat inserted.

61. Removed refueling plug and placed on stand

62. Motorized confinement-building truck roll-up door.

63. Refurbished truck door sealing surfaces and sill plate.

64. Stacked lead shielding around #1 & #2 D 0 IX columns.

2

65. Completed removal of the boral plate from the underside of refueling plug.

66. Completed drain line and filtering system for FTV-3.

67. Altered FTV-1 drain valve so ' can be operated from outside of the subpile room.

68. Changed all valve diaphragrr.s.c he thermal shield system.

69. Changed all valve diaphragms of the exp demin system.

70. Installed manual butterfly valves upstream of cooling tower bypass valves.

71. Replaced horizontal shaft oil seal on #1 cooling tower fan gearbox.

72. Replaced the following 0.5" diaphragm valves with stainless steel ball valves:

SPV-6,7,10,11,18,19,20,24,25,51, & 52.

73. Changed storage pool pre-filters.

74. Stacked lead shielding around primary purification system pre and after filter housings.

75. Changed valve diaphragms of the storage pool system,

76. Outside contractor replaced confinement building elevator doors and associated hardware.

1 i

---

..,--------------.........................--=--===...=-===

19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

Page 7

77. Valve diaphragm replacement continues in the HEV & DWV systems.

78. C'ontinued treating leaking thermal shield tubes as.necessary.

79. Repaired Uquid Waste System 1K/5K recorder.

7

80. Repaired CIA-3 Experimental Demineralizer conductivity channel.

81. Replaced broken Flow Meter on MCP for EHF-5 & -6.

82. Replaced GM Tube for RD 3-1 (N-16 channel).

83. Replaced detector for RD 1-1 (Area Radiation Monitor).

84. Recalibrated FRC-3 (Outer Plenum Flow channel).

85. Repaired NG-6 Indicator circuit.

86. Repaired alarm relay on Area Radiation Monitor system.

87. Repaired NC-8 MCP meter.

68. Repaired D2O Storage Tank Level channel.

89. The following instrument calibration surveillance tests were performed:

Channel Title BTUR-1 Reactor Thermal Power Recorder FCA-7 Thermal Column Flow Indicator Control FIA-14 Storage Pool IX Flow Indicator FRC-3 Outer Plenum Flow Recorder LCA-19 Storage Pool Pump Pit Level Control LIA-13 1000 Gallon Retention Tank Level Indicator LIA-40 Reactor Vessel Level Indicato NC-1 Source Range Channel #1 NC-2 Source Range Channel #2 NC-4 Nuclear Power Channel NC-4 NC-7 Nuclear Power Channel NC-7 RM 1-1 Aree. Monitor RM 1-10 Area Monitor RM 1-15 C001 Rabbit Lab Radiation Area Monitor RM 1-2 Area Monitor RM 1-3 Area Monitor RM 1-4 Area Monitor RM 1-5 Area Monitor RM 1-6 Area Monitor RM 1-7 Area Monitor

............................................==.....====...........

19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184)

Page 8 RM 1-8 Area Monitor lim 1-9 Area Monitor RM 3-1 Secondary Coolant High Radiation Alarm RM 3-4 Irradiated Air High Activity Alarm RM 4-2 Emergency Ventilation Stack Monitor RM 4-3 Liquid Waste Monitor l

TIA-11 Recombiner Internal Temperature Recorder TIA-31 Experimental Demineralized Water HE Outlet Temperature Indicator TIA-40A Reactor Outlet Inlet Temperature Differential indicator Channel-A i

TIA-40B Reactor Outlet-Inlet Temperature Differential Indicator Channel-B TRA-2 Reactor Outlet Temperature Recorder 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.

1.

Finished replacing the Control Room annunciator panels for modernization.

2.

Modifications to instrumentation associated with Liquid Waste System.

3.

Installation of NC-3/-4 Intermediate Range Period Recorder.This recorder was added in order to maintain a record of reactor period. It has no effect on other instrumentation or any safety function.

4.

Removal of existing instrumentation and scrams associated with the old Bismuth Tip Cold Source and installation of new instrumentation and rundowns associated with the new Hydrogen cold Source.

5.

Replaced Neutron Guide inclication on MCP with annunciation on panel AN-1.

6.

Relocated level transmitters for Reactor Vessel Level Recorder Channel LRC-1 and Indicator Channel LIA-40 from C-100 to the Process Room.

7.

Replaced Honeywell Model 33400 monitor switches with Action Pak Model AP1090 electronic switches.

8. Removed Republic Flow Instrumentation F1-101,-102, and -103.

9. Replaced Honeywell Automatic and Manual Valve Controllers with new LFE Model

[

2010 Controllers.

10. Replacement of remaining Honeywell Model 29211 transmitters with Leeds and Northrup Model 2610 and 2620 transmitters.

....................................==...........=================

1994 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

f:

Page 9 s

- All of these changes involved replacement of equipment with equal or superior ehulpment and do not involve unreviewed safety questions.

7.8(3)(e)

Summary of Radioactive Material Released and Results of Environmental Surveys Performed.

The gaseous waste released was 637 curies of tritium,469 curies of Argon-41 and 0.16 curies of Br-82. There were 2.7 curies of tritium and 0.8 millicuries of other beta-gamma emitters released into the sanitary sewer. Environmental samples of the streams, vegetation, and/or soil, and air showed no significant changes.

7.8(3)(f)

Summary of Significant Exposures Received by Facility Personnel and Visitors.

1. None to visitors.

2. None to facility personnel.

0 MER E M alt ES WER M M M E E W W EE EM E WE M M E R 33 M E M E = E = M EM E M E: 2 32 E M EE === MM E R E = EE EEEEE = ===M 19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

1

w UNITED STATES DEPARTMENT OF COMMERCE National Institute of Etonderde enct Technology Gertterinburg. Mand 2o0000001

', t j

(301) 975-6210

/

FAX (301) 975-9427 March 28, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Docket #50-184 Gentlemen:

Transmitted herewith is Operations Report No.47 for the NB5R. The report covers the period January 1, 1994 to December 31, 1994.

Sincer ly, I

kH-

.ichael Rowe Chief, 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 i

(

_ )

lf

+

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

Docket #50-184 Facility License No. TR-5 Operations Report

--# 47--

January 1,1994 - December 31,1994 This report contains a summary of activities connected with the operations of the NBSR. It is submitted in fulfillment of section 7.8(3) of the NBSR Technical Specifica-tions and covers the period frorn January 1,1994 to December 31,1994.

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

March 28,1995

. Michael Rowe Chief, Reactor Radiation Division 1

i l

^.

1.'

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 t:y 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 1994 Operations Report for NBSR (TR-5)

(Docket

1. 50-184]

Page 2 7.8(3)(a)

Summary of Plant Operations During 1994, the reactor was operated for the first five months only. The reactor was critical for 2782 hours0.0322 days <br />0.773 hours <br />0.0046 weeks <br />0.00106 months <br /> with energy output of 41571 MWH. At the end of May 1994 the reactor was shut down in preparation for major upgrade of systems and facilities. Among these are upgrade of the cooling systems, replacement of the cold source, rebui! ding of the top refueling plug and extensive maintenance and inspections. These programs are on going and expected to be completed in the spring of 1995 at which time the reactor will be restarted. A summary of the programs is listed below.

1.

Cooling Systems The primary, secondary and auxiliary cooling systems were extensively upgraded. The two shell and tube type main heat exchangers were replaced with three plate type heat exchanger with the third one to serve as an installed spare. The purification and experimental cooling system heat exchangers were also replaced. A new filtration system was addeo to the secondary system to provide cleaner water to the secondary side of the heat exchangers.

2.

Cold Source The existing heavy water ice cold source instajied in the cryogenic beam port is being replaced by a smaller, more effective liquid hydrogen source that will provide significantly higher subthermal flux. The remaining three of seven guide tubes will also be completed.

3.

Refueling System During maintenance and inspection of the refueling system transfer arms, it was noted that the boral plate underneath the top refueling plug had sagged and began to interfere with the operation of the transfer arms. It was then decided to remove the top plug and rebuild the entire refueling mechanism.

Examination of the boral plate upon removal of the plug showed it to be in bad shape with swelling, corrosion and separation in several areas. The degradation was apparently due to an electrochemical reaction between the aluminum and graphitar bearing on the transfer arm shafts where evidence of corrosion was also found at the bottom. This area was machined and a stainless steel sleeve shrunk fit onto it. All bearings were replaced and all pickup tools were refurbished with some parts replaced. A new helium seal system was

.................. -........ - = = = = = = = = = = = = = = =.... = = = =.. - = =. - =.

19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

Page 3 installed atop of the transfer arms.

The boral plate was originally installed at the bottom of the refueling plug to reduce activation of the steel plate of the plug. The boral plate will not be replaced since measurements indicated that radiation levels even without the boral would be manageable should future maintenance be required. The bottom of the plug is more than 10 ft. from the top of the core with heavy water in between. However, approximately 20 aluminum and boral plates installed at the bottom of the transfer arms and shielding plugs were replaced with a borated aluminum alloy. This will further depress the flux at the bottom of the refueling plug.

Ongoing testing of the plug shows good performance and smooth operation.

4.

Maintenance and Inspections The planned reactor outage and the fact that the core was removed, the heavy water drained and the generally sign.ficantly lower radiation levels provided an opportunity for extensive maintenance and inspections that otherwise could not be easily done. The removal of the top plug allowed for careful borescope inspection of the reactor vessel and the grid.

Everything appeared in good condition. The detents at the bottom of top grid showed no sign of wear and appeared intact.

Items of significant maintenance included replacement of the shim arm blades, replacement of most valve diaphragms, overhaul of the diesel generators, the air systems, and the cooling tower, refurbishing of the confinement building, installation of custom shielding for IXs and filters and maintenance of the thermal shield cooling system. During this

]

period too, improvement and upgrade of portions of reactor instrumentation was undertaken i

and a significant amount of low level waste was packaged and shipped, in planning and executing the above activities, the main focus was on keeping exposures and releases as low as reasonably achievable. As many potential sources of i

exposure such as filters, resins and identified components were removed prior to any significant work. As a result, exposures were held well below those of similar but lesser outages in the past.

...........................=.....= =..=.....==..====.===..======

19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

E c

Page 4 7.8(3)(b),Unsche ed Shutdowns

1. There were three (3) scrams due to a commercial power dip. The reactor returned to power.

2. There was one (1) scram due to a commercial power dip after which the reactor stayed down because it was at the end of a fuel cycle.

3.

There was a scram caused by the loss of a 10-volt Nuclear Instrument Power Supply during maintenance in the area. The power supply was put back into service and the reactor was returned to power.

4.

There was a scram caused by a spike on a 10-volt Nuclear instrument Power Supply while attempting to reset a failed standby unit. The original power supply was put back into service and the reactor was returned to power.

7.8(3)(c)

Tabulation of Major items of Plant Maintenance 1.

Replaced #1 N-16 pump with new pump head - motor was not replaced.

2. Located and repaired three DC grounds in emergency lights circut.

3.

Changed primary purification system after filters 4.

Regenerated demin station IX column several times.

5. Changed air cylinders on fuel cutting saw.

6.

Replaced #4 shim position indication module.

7.

Cut 36 spent fuel elements for rad waste shipment of aluminum pieces.

8.

Changed storage pool pre-filters.

9.

Removed spent resin from both thermal shield IX columns.

10. Removed drive mechanisms from #1 & #2 shim arms.

11. Changed primary purification system pre & after filters.

12. Removed drive mechanisms from #3 & #4 shim arms.

13. Pumped spent resin from #3 & #4 IX to High Integrity Container (H.I.C.).

14. Pumped spent thermal shield resin to H.I.C. ior transport

15. Loaded all spent filters from fluid systems into H.I.C.

16. Disassembleo primary and secondary piping for systems modifications.

17. Replaced shim arms.

18. Old HE 2 (primary purification system HX) removed from process room.

19. Old HE-7 (exp demin system HX) removed from process room.

19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

,~

l L

Page 5 l

1

20. I,nspected and removed reactor inlet strainer basket.

21. Inspected and removed reactor outlet strainer basket.

(

22. Old HE-6 (thermal shield system HX) removed from process room.

23. Old HE-1B (primary system HX) removed from process room.

)

24. Old HE-1 A (primary system HX) removed from process room.

25. Old #4 sump pumps removed from process room.

26. Removed old and installed new chilled water cooling lines to the helium condensor.

27. Replaced seal cups on ACV-2 operating cylinder.

28. New HE-7 (exp demin system HX) installed.

29. New HE-2 (primary purification system HX) installed.

30. Replaced air soleniod for DWV 40 (emergency tank intet).

31. Removed sightglasses from the thermal shield storage tank and exp demin storage tank.

32. Cleaned cooling tower basin.

33. Completed installation of decontamination machine.

Replaced casing drain valves of both D O shutdown pumps with stainless steel ball 34.

2 valves.

35. Re-piped IX #1 & #2 back into the primary purification system.

l

36. Replaced the following 0.5" diaphragm valves with stainless steel ball valves:

DWV-179,180,182, & 183.

37. Replaced open indication limit switch on DWV-8 ( #1 D O S/D pump ).

2

38. Installed backwash pump in secondary system.

39. Painted process room ceiling, walls, & floor.

l

40. Replaced the following 0.5" diaphragm valves with stainless steel ball valves:

l DWV-124,125, 311, & 312.

41. Removed sightglass from the emergency D O tank.

2

42. Replaced the following 0.5" diaphragm valves with stainless steel ball valves:

DCV-50 & 51.

43. Completed cooling tower bolt replacement-carbon steel bolts replaced with stainless steel bolts.

44. Moved 2 automatic strainers, backwash assist pump and bag filter to secondary pumproom and continued with piping installation.

45. Replaced FTV-18 diaphragm valve with a stainless steel ball valve.

46. Placed new HE-1 A, HE-1B, & HE-1C in process room.

47. Stacked lead bricks onto shielding stand of HE-2.

.......--.............-----,......--== ---=======================

1994 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

l

Page 5

48., Replaced TSV-18 & 19 diaphragm valves with brass ball valves.

49. Replaced DCV-3 ( demin water to refueling ) operator with a manual bonnet and handwheel.

50. Removed reactor Upper Outer Plug (UOP) Static weight = 36,000 lbs.

51. Stacked lead around #1 & #2 thermal snield IX columns.

52. Changed storage pool system pre & after filters.

53. Replaced secondary pump suction, discharge, & discharge check valves with new ones.

54 Removed B-2 level 10# air compressor from system.

55. Mounted and aligned both exp D O pumps next to HE-2.

2

56. Replaced bearings and seals of #2, #3, & #4 shim arm shafts (#1 shim arm has temporary seal until new D O is loaded into the reactor).

2

57. Installed and connected #4 sump pumps.

58. Fabricated and installed new weather station.

59. Tested both emergency diesel generators under load (150 KW ).

60. Installed and lowered new cryostat shutters D, E, & G. Shutter F installed but remcins raised and pinned with cryostat inserted.

61. Removed refueling plug and placed on stand

62. Motorized confinement-building truck roll-up door.

63. Refurbished truck door sealing surfaces and sill plate.

64 Stacked lead shielding around #1 & #2 D 0 IX columns.

2

65. Completed removal of the boral plate from the underside of refueling plug.

66. Completed drain line and filtering system for FTV-3.

67. Altered FTV-1 drain valve so it can be operated from outside of the subpile room.

68. Changed all valve diaphragms of the thermal shield system.

69. Changed all valve diaphragms of the exp demin system.

70. Installed manual butterfly valves upstream of cooling tower bypass valves.

71. Replaced horizontal shaft oil seal on #1 cooling tower fan gearbox.

72. Replaced the following 0.5" diaphragm valves with stainless steel ball valves:

SPV-6,7,10,11,18,19,20,24,25,51, & 52.

i l

73. Changed storage pool pre filters.

74. Stacked lead shielding around primary purification system pre and after filter housings.

75. Changed valve diaphragms of the storage pool system.

76. Outside contractor replaced confinement building elevator doors and associated hardware.

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1994 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

Page 7

77. Valve diaphragm replacement continues in the HEV & DWV systems.

78. Continued treating leaking thermal shield tubes as necessary.

79. Repaired Liquid Waste System 1K/5K recorder.

80. Repaired CIA-3 Experimental Demineralizer conductivity channel.

81. Replaced broken Flow Meter on MCP for EHF-5 & -6.

82. Replaced GM Tube for RD 3-1 (N-16 channel).

83. Replaced detector for RD 1-1 (Area Radiation Monitor).

84. Recalibrated FRC-3 (Outer Plenum Flow channel).

85. Repaired NG-6 Indicator circuit.

86. Repaired alarm relay on Area Radiation Monitor system.

87. Repaired NC-8 MCP meter.

88. Repaired D20 Storage Tank Level channel.

89. The following instrument calibration surveillance tests were performed:

Channel Title BTUR-1 Reactor Thermal Power Recorder FCA-7 Thermal Column Flow Indicator Control FIA-14 Storage Pool IX Flow Indicator FRC-3 Outer Plenum Flow Recorder LCA-19 Storage Pool Pump Pit Levei Control LIA-13 1000 Gallon Retention Tank Level Indicator LIA-40 Reactor Vessel Level Indicato NC-1 Source Range Channel #1 NC-2 Source Range Channel #2 NC-4 Nuclear Power Channel NC-4 NC-7 Nuclear Power Channel NC-7 RM 1-1 Area Monitor RM 1-10 Area Monitor RM 1-15 C001 Rabbit Lab Radiation Area Monitor RM 1-2 Area Monitor RM 1-3 Area Monitor RM 1-4 Area Monitor RM 1-5 Area Monitor RM 1-6 Area Monitor RM 1-7 Area Monitor i

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1994 Operations Report for NBSR (TR-5)

[ Docket

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Page 8 RM 1-8 Area Monitor

~ RM 1-9 Area Monitor RM 3-1 Secondary Coolant High Radiation Alarm RM 3-4 Irradiated Air High Activity Alarm RM 4-2 Emergency Ventilation Stack Monitor RM 4-3 Liquid Waste Monitor TIA-11 RecombinerInternalTemperature Recorder TIA-31 Experimental Demineralized Water HE Outlet Temperature Indicator TIA-40A Reactor Outlet Inlet Temperature Differential Indicator Channel-A TIA-408 Reactor Outlet-Inlet Temperature Differential Indicator Channel-B TRA-2 Reactor Outlet Temperature Recorder 7.8(3)(d)

Tabulation of Major Changes in the Facility and Procedures, and the Test and Experiments, Cairled Out Without Prior Approval by the NRC pursuant to ~iO CFR 50.59.

1.

Finished replacing the Control Room annunciator panels for modernization.

2. Modifications to instrumentation associated with Liquid Waste System.

3.

Installation of NC-3/-4 Intermediate Range Period Recorder.This recorder was added in order to maintain a record of reactor period. It has no effect on otherinstrumentation or any safety function.

4.

Removal of existing instrumentation and scrams associated with the old Bismuth Tip Cold Source and installation of new instrumentation and rundowns associated with the new Hydrogen cold Source.

5. Replaced Neutron Guide Indication on MCP with annunciation on panel AN-1.

6.

Relocated level transmitters for Reactor Vessel Level Recorder Channel LRC-1 and Indicator Channel LIA-40 from C-100 to the Process Room.

7. Replaced Honeywell Model 33400 monitor switches with Action Pak Model AP1090 electronic switches.

8. Removed Republic Flow Instrumentation F1-101,-102, and -103.

9.

Replaceo Honeywell Automatic and Manual Valve Controllers with new LFE Model 2010 Controllers.

10. Replacement of remaining Honeywell Model 29211 transmitters with Leeds and Northrup Model 2610 and 2620 transmitters.

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19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

J'6 p

lAll of these changes involved replacement of equipment with equal or superior equipment and do not involve unreviewed safety questions.

7.8(3)(e)

Summary of Radioactive Material Released and Recults of Environmental Surveys Performed.

The gaseous waste released was 637 curies of tritium,469 curies of Argon-41 and 0.1E curies of Br-82. There were 2.7 curies of tritium and 0.8 millicuries of other beta-gamma emitters released into the sanitary sewer. Environmental samples of the streams, i

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

7.8(3)(f)

Summary of Significant Exposures Received by Facility Personnel and Visitors.

1. None to visitors.

2. None to facility personnel.

a mm mm m m m m m m m m m m mmm m m m m mm = mm m m m=mn = = man ans m=m a n= m=ma= mu m= ====m u mmma 19 94 Operations Report for NBSR (TR-5)

[ Docket

1. 50-184]

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