ML20235L355

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Repts Progress to Date on Upgrading Procedures for Operations & Health Physics,Per Insp Rept 50-160/87-08.New & Revised Procedures Approved by NRC Listed as Stated
ML20235L355
Person / Time
Site: Neely Research Reactor
Issue date: 02/14/1989
From: Karam R
Neely Research Reactor, ATLANTA, GA
To: Verrelli D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8902270485
Download: ML20235L355 (4)
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g. g Georgia Institute of Technology g@....., . b NEELY NUCLEAR RESEARCH CENTER 900 ATLANTIC OAIVE ATLANTA GEORGIA 30332-0425

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February 14, 1989 Mr. David M. Verrelli, Chief Reactor Projects Branch No. 1 U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, N.W.

Atlanta, Georgia 30323 Dear Mr. Verrellit

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REFERENCE:

ENFORCEMENT CONFERENCE

SUMMARY

, March 14, 1988, NRC Inspection' Report # 50-160 87-08)

This letter reports progress made to date on upgrading procedures for both operations and Health Physics. The new and/or revised procedures that have been approved by Nuclear Safeguards Committee to date are:

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)
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 /Deta 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 8902270485 890214 PDR I

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Telex:: 542507 GTRIOCAATL Fax: 404 894 3120 (Verity 404 894-6951)

A Unit of the University System of Georgia An Equal Education and Employment Opportunity Institution

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Mr. David M. Verrelli' February 14,;1989 Page 2'

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 2 18 . Procedure 2005 Daily Reactor Shutdown Checklist
29. Procedure 2006 Weekly Reactor Shutdown Checklist
30. Procedure 2011 Operating Data Log-Field
31. Procedure 3107 Sample Handling
32. Procedure 3100 Experiment Approval Form
33. Procedure 3101 Definition of Experiment Categories
34. Procedure 3102 Quality Assurance for Experiments
35. Procedure 3109 Instructions for Experiment Approval
36. Procedure 3111 Sample Loading Into Vertical Experiment Ports
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 L__-_-_-_-

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l Mr. David M. Verrelli .

February 14, 1089 I Page 3

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 Picket j '

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 Responso to Fire at Neely Nuclear Research Center
57. Procedure 6050 Response to 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 Check-list (Rev. 5)
63. Procedure 2003 Daily Precritical Startup Check-list (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 Keithley Model 485 Picoammeter
67. Procedure 9010 Kanne Chamber Calibration (Rev. 3)

Our procedure review at NNRC is now complete. Those procedures listed above are the ones that have been either revised or drafted in response to our review. With these procedures in hand, it is felt that in general, these are adequate to ensure control of GTRR operations. We still have j several procedural areas we are addressing; completing  !

instrument calibration, completing bioassay, and completing l training. )

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. .' j Mr. David M. Verrelli i February 14, 1989

[ Page 4' As discussed with you by telephone on February 9, 1989, we shall finish addressing these issues by February 28, 1990. It is my understanding that this extension of time for procedure completion'is acceptable.

During the procedure review process, a new procedural format was adopted which we felt was more effective and provided better control. Adapting procedures to this new format is a slow process since the Nuclear Safeguards Committ7e' evaluates reformatted procedures as if they had undergone technical revision. Approval of reformatted procedures averages approximately 'five per month, and consequently, completion of procedure formatting will take some time.

Should you have any questions please let me know. Thank you for your help and cooperation.

Sincerely yours,

'h' R. A. Karam, Director Neely Nuclear Research Center RAK:dwa pc: Dr. A. P. Sheppard l

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