ML20235W857

Annual Rept for 1988

ML20235W857
Person / Time
Site:	Neely Research Reactor
Issue date:	02/21/1989
From:	Karam R Neely Research Reactor, ATLANTA, GA
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
0RA-881231, RA-881231, NUDOCS 8903130219
Download: ML20235W857 (12)

Text

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q Georgia Institute of Technology s

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NEELY NUCLEAR RESEARCH CENTER h, 4 900 ATLANTI ga a"

ATLANTA, GEORGIA f

February 21, 1989 U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW Atlanta, Georgia 30303 References Docket 50-160; License R-97 Gentlemen:

Pursuant to Section 6.7a of the Technical Specifications for the Georgia Tech Research Reactor (License R-97),

the following annual report is submitted.

The reporting period is January 1, 1988 through December 31, 1988 (calendar year 1988).

The designation of the sections below follow the title and order of Section 6.7a of our Technical Specifications.

1.

Operations Summary

a. Chances in Facility Desian There was minor change requiring relay substitution in the power level trip amplifiers circuit.

Three relays failed.

These relays are no longer manufactured.

Similar relays manufactured by another company were found.

Approval for the substitution was given by the Nuclear Safeguard Committee on the basis that said substitution will not increase the consequences of an accident, or the malfunction of equipment important to safety, or reduce margin of safety.

b. Performance Characteristics During the reporting period the reactor was operated at power levels up to 1000 kw(t) using a 17-element core.

Fuel performance has continued to be satisfactory with no known problems.

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P PDC A Unit of the Unwersity System of Georgia An Equal Education and Employment Opportunny institution

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-USNRC February 21, 1989 Page 2 c.-Chanaes la Operatina Procedures The list of new and or revised procedures which-were approved by.the Nuclear Safeguards Committee follows:

1.

Procedure 9302, Protective Clothing Requirements-2.

Procedure 9304, Routine Facility Radiation Surveys 3.

Procedure 9306,: Preparation and Maintenance of RWP's 4.

Procedure 9308, Airborne Radioactivity Surveys 5.

Procedure 9310, Posting of Radiological Control Areas-and Materials 6.

Procedure 9010, Kanne Chamber Calibration (Rev. 2) l 7.

Procedure 9012, Operation and Calibration of Gas Monitor.

8.

Procedure 9013, Calibration and Testing of Moving Air.

Particulate Monitor 9.

Procedure 9015, Cooling-Water Gamma Monitor

10. Procedure 9016, Calibration and Testing of Filter Bank Monitor

11. Procedure 9017, Stack Grab Sample Analysis

12. Procedure 9018, Charcoal Cartridge Analysis

13. Procedure 9038, Bioassay Program

14. Procedure 9040,. Liquid Waste Tank Analysis

15. Procedure 9054, Calibration of the Low Beta II.

Alpha / Beta Counting System

16. Procedure 9055, Operation of the' Low Beta II Alpha / Beta Counting System

17. Procedure 9056, Calibration and Operation of the Ludlum 2000 Scaler

18. Procedure 9150, Operation and Calibration _of Area Radiation Monitors

19. Procedure 9151, Calibration and Operation of the Tri

-Carb 2000 Series Liquid Scintillation Counter

20. Procedure 9154, Operation and Calibration of the Gamma Analysis System for Effluent Monitoring

21. Procedure 9250, Facilities Contamination Surveys

22. Procedure 9280, Personnel Monitoring

23. Procedure 0010, How to Modify Procedures

24. Procedure 2001, Two Operator Operation

25. Procedure 2002, Weekly Pre-Startup Checklist

26. Procedure 2003, Daily Pre-Startup Checklist

27. Procedure 2004, Shift Supervisor Startup Approval

28. Procedure 2005, Daily Reactor Shutdown Checklist

29. Procedure 2006, Weekly Reactor Shutdown Checklist

30. Procedure 2011, Operating Data Log-Field

31. Procedure 3100, Experiment Approval Form

32. Procedure 3101, Definition of Experiment Categories

33. Procedure 3102, Quality Assurance for Experiments

34. Procedure 3107, Sample Handling j

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USNRC j

February 21, 1989 Page 3

35. Procedure 3109, Instructions for Experiment Approval

36. Procedure 3111, Sample Loading Into Vertical Experiment Ports 1'

37. Procedure 3113, Sample Removal from Vertical Experiment Ports

38. Procedure 3800, Liquid Waste Disposal

39. Procedure 0100, Preparation of Procedures

40. Procedure 4950, Tagging Equipment Out of Service

41. Procedure 6010, General Rules and Guidelines for Handling Emergencies

42. Procedure 7200, Primary Coolant Sampling for Radionuclides Analysis

43. Procedure 7221, Maintenance of Containment Building Doors

44. Procedure 7222, Verification of Light Water Addition to Emergency Core Cooling System

45. Procedure 7420, Channel Check, Test or Calibration for Safety Related Instruments

46. Procedure 9155, Determination of Count Times Based on a Priori Lower Limit of Detection (LLD)

47. Procedure 9041, Storage Pool Water Sampling and Analysis

48. Procedure 9057, Calibration Procedure for Eberline Model E-120 GM Survey Meter

49. Procedure 9059, "As Found" Calibration Check

50. Procedure 9060, Calibration Procedure for Bicron Model RSO-5 Survey Meter

51. Procedure 9061, Testing Procedure for Pocket Ionization Chambers (PICS)

52. Procedure 9016, Calibration and Testing of Filter Bank Monitor

53. Procedure 9058, Calibration Procedures for Eberline Model RM-14 Rate Meter

54. Procedure 6020, Response to Heavy Water Leakage in Containment Building

55. Procedure 6030, Response to Irradiated Fuel Element Becoming Unshielded

56. Procedure 6040, Response to Fire at Neely Nuclear Research Center

57. Procedure 6050, Response Zinc Bromide Leak in Hot Cell Window

58. Procedure 6060, Response to Pool Water Draining with Co-60 Sources on Bottom

59. Procedure 6070, Response to Loss of Integrity of Co-60 Sources

60. Procedure 6090, Personnel Monitoring After Building Evacuation in Emergency Situations

61. Procedure 6100, Emergency Notification

62. Procedure 2002, Weekly Precritical Startup Checklist (Rev. 5)

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63. Procedure 2003, Daily Precritical Startup Checklist (Rev. 5)

64. Procedure 7211, Emergency Cooling System Fuel Element Flow Verification (Rev. 1)-

65. Procedure 7900, Calibration Requirements for Test and Measurement Instruments

66. Procedure 7910, Calibration Test for Keithly Model 485 Picoammeter

67. Procedure 9010, Kanne Chamber Calibration (Rev. 3) d.

Results of Surveillance Tests and Inspections The surveillance tests and-inspections of the facility required by the Technical Specifications were performed.

Documentation of each of the tests and inspections are-available at the site for review.

e.

Chances, Tests and Experiments Acoroved by USGRC There were no

changes, tests or experiments that required the approval of the USNRC pursuant to 10 CFR 50.59 (a).

f.

Chances in Plant Staff and Committee Membershio Dr.'R.A. Karam, Director, Nuclear Research Center Dr. Robert N. Macdonald, Associate Director Dr. Betty Revsin, Manager, Office of Radiation Safety Mr. L. Dean McDowell, Reactor Supervisor Mr. William Downs, Senior Reactor Operator Mr. Mitch Mercer, Electronics Specialist Mr. David Cox, a Trainee for Reactor Operator Mr. Jerry Taylor, Senior Radioisotope Lab Specialist Mr. Richard Barrow, Research Scientist I Ms. Daphne Aycock, Administrative Secretary Ms. Judy Rodgers, Administrative Secretary Mr. Dixon Parker, Trainee for Reactor Operator The current membership of the Nuclear Safeguards Committee is:

1.

Dr. Bernd Kahn, Chairman Discipline:

Radiation Protection, Environmental Radioactivity 2.

Dr. James Mahaffey, Vice Chairman Discipline:

Instrumentation and

Control, Nuclear Engineering, Reactor Operation

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I, USNRC February 21, 1989 Page 5 3.

.Dr. Prateen V.

Desai, Secretary.

Disciplines Thermal Hydraulics, Mechanical Systems 4.

Mr.-Emsley Cobb, member Disciplines Reactor Operation and

-Reactor Safety 5.

Dr. Said I. Abdel Khalik, member

' Discipline:

Nuclear

' Engineering; Transient Phenomena 6.

Dr. Billy R. Livesay, member Disciplines Material' Science, Physics 7.

Dr. Henry Neumann, member Discipline Chemistry, Radiochemistry 8.

Mr. G. Les Petherick, member Discipline Environmental Safety (Toxic Substances) 9.

Mr. Jack Vickery, member Disciplines Security 10.

Dr. Kent Barefield, member Disciplines Organometallic Chemistry 11.

Dr. James N. Gordon, member Discipline Medicine 12.

Dr. Patton H. McGinley, member Disciplines Medical Health Physics, Radiological Safety 2.

Power Generation For the period January 1, 1988 through December 31,

1988, the total power generation of the reactor was 4.02 megawatt hours.

The reactor was operated for a total of 8.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

There was no operation at power levels higher than 1 MW.

3.

Shutdowns During the reporting period there was no unscheduled shutdown of the reactor.

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USNRC February 21, 1989 Page 6 4.

Unscheduled Maintenance on Safety-Related Systems and Components:

a.

1/22/88 Filter Bank..

Pressure drop across filter high.

Replaced pre-roughing filters.

Functional test showed that performance was normal.

b.

1/27/88 Area Radiation Monitor (ARM).

J00( #7 was not working.

Replaced operational amp in detector.

Calibrated and returned to service.

6 c.

4/5/88 Gas monitor pump.

The pump was not functioning properly.

Replaced with a spare pump.

Functional test showed that performance was normal.

d.

4/8/88 Stack fan.

Breaker tripping on overload.

Replaced bearings on both ends in fan motor.

Functional test.

showed that performances was normal.

e.

4/5/88 Bismuth secondary flowmeter.

Float was not moving freely.

Disassembled components and cleaned thoroughly.

After reassembling functional test showed that performance was normal.

f.

4/5/88 Beam port H-4 light water cooling system Resin Bed Depleted.

Replaced resin bed.

Functional test showed that system was normal.

g.

4/12/88 Charcoal Filter Pump.

Pump was not working.

Replace pump with a

spare.

Functional test showed that pump was normal.

h.

4/13/88 Kanne Recorder.

Response to signal not smooth.

Replaced two gears and one shaft to a third gear.

Functional test showed that recorder was working properly.

1.

5/3/88 Moving Air particulate (MAP-1).

Monitor Filter paper not advancing.

Replaces worn out gear.

Functional test showed that system was returned to normal.

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'USNRC February 21, 1989 Pago;71 1.

-5/3/88 Moving Air particulate.(MAP-1).

Monitor Filter paper not advancing.:

Replaces worn out gear.

Functional test-showed that system was returned to normal.

j.

4/20/88 MAP-1.

Preamp not working.

Replaced

. preamp and power supply.

Calibrated.and-returned to service.

k.

6/30/88 Filter Bank.

Pressure drop 'across' filter was high.

Replaced roughing filters.

Functional test showed that performance was normal.

1.

7/5/88

.MD-2A pump.

Seal was leaking.

Replaced mechanical seal.--Functional test showed' that pump is normal and.not leaking.

m.

7/22/88 Shield system ROTAMETER sight glass.:

Glass broken.

Replaced sight _ glass.

n.

8/17/88 Do not enter light.

Light did not flash.

Light was repaired.

o.

10/27/88 Charcoal filter pump.

Pump not working.

Replaced pump, p.

11/18/88 Sola transformer.

Shorted ~ capacitor.

Replaced transformer.

q.

11/17/88

'LogN #1 and

1. 2.

Adjusted high voltage on #2 and replaced power supply on- #1.

Functional

. tests,.

showed that performance was normal.

r.

11/28/88 Cooling water gamma monitor.

No response to source check.

Replaced detector.

Functional test and calibration showed that performance was normal.

s.

12/1/88 Caution entry alarm.

Burnt transformer.

Replaced transformer' and conducted functional test.

All was normal.

t.

12/5/88 Filter Bank Monitor.

Source check was reading high.

Recalibrates lower and upper level discriminatory.

Functional test showed that performance was normal.

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-USNRC February 21, 1989 Page 8 u.

12/12/88 Area monitor recorder.

Pen was stuck.

Replaced idler gear 'in drive motor.

Functional test showed that performance was normal.

v.

12/19/88 Picoammeter

1. 2.

Instrument-~was not working.

Replaced detector.

Functional test showed the performance was normal.

5.

During the. reporting period there was one approved experiment using the Georgia Tech Research Reactor.

The experiment was evaluated prior to its approval with regard to Section 3.4 of our Technical' Specifications.

6.

RADIOACTIVE EFFLUENT RELEASES a.

Technical Specification 6.7(6)(a).

Gaseous Effluents

- Summation Of All Releases Via Stack, i.e.,

ground level release 1.

FISSION AND ACTIVATION GASES Tritium Released (gaseous)

None' measurable I

Argon-41 released:

Total Avg Release

% Tech Release Rate (pCi/cc)

Spec (C1) ist Qtr 2.35 2.1 x 10- '

4.0%

2nd Otr 0.00 3rd Qtr 0.00 4th Qtr 0.00 Maximum instantaneous release rate = 4.4 x 10-'pCi/cc 2.

IODINES RELEASED None measurable Lower Limit of Detection < 5.0 x 10-

• pci/cc f

3.

PARTICULATE RELEASED None measurable Lower Limit of Detection < 6.25 X 10-'pCi/cc

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50 USNRC February. 21,~1989=

Page 9 1

b.-

. Technical Specification 6.7(6)(b).

Liquid Effluents

-Summation of All Reactors 1.

FISSION AND ACTIVATION PRODUCTS l-j' Cobalt-60 was the only activation product released via

'the liquid pathway, no fission products were released.

Total-Avg Release

% Tech Est. Total L

Release Rate (pCi/cc)

Spec Error (%)

(Ci) ist Qtr 0.000109

5. 5 x 10~ ' ' '

< 1%

N/A 2nd Qtr 0.000070 3.5 x 10'**

< 1%

N/A 3rd Qtr 0.000095 4. 8 x 10- * '

< 1%

N/A 4th Qtr 0.000003

1. 5 x 10* * '

< 1%

N/A TOTAL 0.000277.

Maximum concentration released 1.7 x 10-**pCi/cc

• These values include 2 x 10' dilution factor.

2.

TRITIUM Total Avg Release

% Tech Release Rate (pCi/cc)

Spec (Ci) ist Qtr 0.0058

2. 9 x 10- * * *

< 1%

'2nd Qtr 0.0081 4.1 x 10~**

< 1%

3rd Qtr 0.0098 4.9 x 10-**

< 1%

4th Qtr 0.0011

5. 5 x 10' * *

< 1%

TOTAL 0.2480

• These values include 2 x 10' dilution factor.

3.

DISSOLVED & ENTRAINED GASES None released 4.

GROSS ALPHA RADIOACTIVITY None released Lower Limit of Detection < l.3 x 10pci/cc 5.

VOLUME OF WATER RELEASED (PRIOR TO DILUTION) (Liters) i 1st Qtr - 1.00 x 10' 2nd Qtr - 8.85 x 10*

3rd Qtr - 1.59 x 10' 4th Qtr - 4.42 x 10'

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.USNRC Februaryf 21,'1989

Page 10 6.-

. VOLUME OF DILUTION WATER USED DURING~. PERIOD (Liters)-

lat:Qtrl-2.0~x 10' 2nd Qtr - 2.0 x 10' 3rd - Qtr - 2. 0 x 10' 4th'Qtr - 2.0 x 10' ENVIRONMENTAL MONITORING TECHNICAL SPECIFICATION 6.7(6)

The environmental parameter. monitored for GTRR a and b operation is that of direct radiation'from the facility and from gaseous. effluent-via a system of 30 film badges around the perimeter. fence-(see. Figure 1, Environmental Monitoring Station).

c-

-1 During 1988, the reactor was operational for a single day on January 12, 1988.

Therefore, ~only the exposure measured on.the January, 1988 film badge would represent exposure;due to.

GTRR operations.

The film badge has a minimal sensitivity level of 10 mrem.

Of the 30 film badge stations, none showed activity-above background 'due to reactor operations.

Station 9 did show activity above' local background; however, the January 1988, 50-mrem exposure measured at this station was due to radiation from sealed sources used for calibrating health physics instruments stored in'a nearby building.

Similar' values were observed at Station 9 during the remainder of the months of the year, i.e.,

when the reactor was not operational confirming that the dose of.

this station was non-reactor related.

d-Highest: lowest and annual average levels of radiation for sampling point with the highest average due to reactor operations and location of that point with respect to the site (excludes Station 9).

All station film badges indicated background levels of exposure including the film badge housed in the reactor-stack.

Reactor Operation -

January 12, 1989 Average - < 10 mrem Highest - < 10 mrem Lowest. - < 10 mrem e - Maximum cumulative radiation dose which could have been laceived by an. individual continuously present in an unrestricted area during reactor operation from:

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,j USNRC February _21, 1989.

Page'll 1.

~ direct. radiation and' gaseous effluent:

< 10 mrem / year 2.

liquid effluent

<1% 10 CFR 20 limits 8.

Occupational Personnal Radiation Exposure a.

Summary of occupation exposure greater than 500 mrem

- None b.

Summary of exposure for persons under 18 of age greater than 50 mrem None Should there be any questions concerning this report,.please let us know.

Sincerely yours, 0*

X R.A. Karam, Director Neely Nuclear Research Center RAK gef cc

'Dr. A.P Sheppard Members Safeguard Committee

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