IR 05000224/1985001
| ML20127D173 | |
| Person / Time | |
|---|---|
| Site: | Berkeley Research Reactor |
| Issue date: | 05/31/1985 |
| From: | Cillis M, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20127D127 | List: |
| References | |
| 50-224-85-01, 50-224-85-1, NUDOCS 8506240143 | |
| Download: ML20127D173 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION'
REGION V
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Report No.
50-224/85-01
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Docket No.
50-224 License No.
R-101
' Licensee:
University of California Department of Nuclear Engineering
Berkeley, California 94720
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Facility Name:
TRIGA' Mark III 1 Inspection at:
Etcheverry Hall, Berkeley, California Inspection conkyted:
- May 28, 1985 Inspector:
h 8f M. Cillis, Radi& tion Specialist Dite Signed
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4-Approveo By:
3ff/!T G. P. Yuhas,' Chief.
Dite Signed
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Facilities Radiological Protection Section Sununary:
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Inspection on May 28, 1985 (Report No. 50-224/85-01),
Areas Inspected: Special unannounced inspection of the ' actions taken-to correct the findings identified in' Region V Inspection Report 50-224/84-01 and Region V Memorandum entitled. Post Exit, Heeting of February 14', 1985" dated February 22, 1985. The early reexamination' included a. review of~the radiation protection program, reactor operations' program,rgeneral employee training, emergency preparedness program, transportation activities, procedures,
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Information Notice evaluations, surveys,. ' review and audit program,- and a tour of the facility. The inspection involved eight~ hours of_onsite time by one regionally based inspector.
Ofthe11areasinspected,"noviolationsordevIationswere Results:
j identified.
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DETAILS 1.
Persons Contacted ~
- Professor T.;H. Pigford,' Reactor Administrator
- Dr. T. Lim, Reactor Supervisor Professor R. M. Buxbaum, Chairman, Reactor Hazards Committee (RHC)
- M. Schoonover, Associate' Radiation Safety Officer M. Denton, Chief, Reactor Operator J. Harrell, Reactor Operator
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- P. G. Vernig, Reactor Health Physicist
- Denotes those individuals attending the exit interview.
2.
Followup on Previous Inspection Findings
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a.
General An early ' reexamination of the licensee's radiation protection and reactor operations program was conducted as previously requested by the Reactor Administrator during a post exit meeting that was held on February 14, 1985. The purpose of the February 14 meeting was to discuss the observations identified in Region V Inspection Report 50-224/84-01. The participants at the meeting and the items that were reviewed'are provided in Region V memorandum entitled " Post Exit Meeting of February 14, 1985," dated February 22, 1985. The
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February 14 meeting disclosed the following:
The licensee had initiated actior.s to resolve the findings identified in the inspection report.
- The Reactor Administrator specified additional actions that would be implemented to improve performance to a level that meets or exceeds the appropriate regulatory requirements.
The purpose for the early reexamination was to determine the status and adequacy of the licensee's corrective actions for improving perfo rmance.
b.
Scope The scope of the early reinspection included discussions with the licensee's staff and an examination of the following:
1)
Su rvey - records.
2)
-Personnel training records.
3)
Radioactive waste shipping records.
4)
Review and audit surveillance records.
5)
Reactor Operations Manual.
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Licensee evaluation reports related to Information Notices.
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Memorandum of Understanding with local emergency support agencies.
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The following procedures as documents:
Administrative Procedure 84-12 " Procedure Approval
Process" Audit of Reactor Operations - Administrative Fall, 1984
By-Laws - Reactor Hazards Committee of March 18, 1985.
- Calibration of Radiation Survey Instruments for Low Energy
Response Emergency Preparedness Plan Training Policy
General Employee Training Outline
Procedure RP-9, " Outgoing Radioactive Material Shipments"
Procedure RP-34-4, " Routine Swipe Program"
Procedure RP-34-5, " Routine Instrument Survey"
Procedure RP-34-7, " Calibration of Direct Reading Pocket
Ion Chambers used by Visitors" Procedure RP-34-8, " Air Particulate Vacuum Samplers"
Procedure RP-34-10, " Servicing Constant Air Monitors" c.
Results 1)
Closed Items
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(Closed) (50-224/84-01-01, 50-224/84-01-02, 50-224/84-01-03, 50-224/84-01-04, and 50-224/84-01-05). The inspection disclosed that management involvement and support was evident as it relates to improving the licensee's past performance at the Berkeley Research Reactor Facility and in resolving the findings identified in Inspection Report 50-224/84-01 and the Region V February 14, 1985 memorandum. The inspector observed the following improvements:
a)
Formal policies related to the preparation, review and approval of reactor operating procedures were established and implemented in'a manner that is consistent with Sections 6.2.d and 6.5 of the Technical Specifications.
The policies are provided in procedure No. 84-12,
" Procedure Approval Process."
b)
General employee and emergency preparedness training programs were formalized.
Improvements related to training outlines, attendance records, and in evaluating the effectiveness of training were established and are now being implemented.
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c)
The Reactor llazards Committee (RllC) Charter was revised for the purpose of improving the review and audit functions in a manner that is consistent with Sections 6.2 and 6.5 of the Technical Specifications.
d)
A formal process related to the evaluation of Information Notices for applicability to reactor activities was implemented.
e)
Procedures involving the transfer and shipment of radioactive material and waste were developed for the purpose of assuring compliance with 10 CFR Parts 20, Part 61, Part 71 and Department of Transportation (DOT)
requirements prescribed in 49 CFR Parts 0-199.
f)
Contamination survey forms were revised for the purpose of assuring that the results of-surveys are reported in units that are consistent with 10 CFR Part 20.401(b), " Records of surveys, radiation monitoring, and disposal" and 10 CFR 20.5, " Units of Radioactivity."
g)
Programs for verifying the calibration of Pocket Ionization Chambers (PICS) and for verifying the calibration of fixed air sampler flow measurement avices were established.
h)
Policies related to the performance of more representative contamination surveys of radioactive material shipments and radiation surveys that more clearly represent all phases of reactor operations, were established, i)
All procedures associated with the TRIGA Facility were incorporated into a Reactor Operations Manual. A copy 'of the manual is maintained at the reactor console and in the Reactor Supervisors office.
This matter is closed (84-01-01, 84-01-02, 84-01-03, 84-01-04, and 84-01-05).
No violations or deviations were identified.
2)
Open Items (Open,50-224/83-01-01) An evaluation related to the need for calibrating portable instruments for the determination of non penetrating dose rate measurements was in progress at the time of this inspection..This item will be examined during a subsequent inspection (83-01-01).
No violations or deviations were identifie r_
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3.
Exit Interview
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The inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on' May 28, 1985. The inspector summarized the scope and findings of the inspection. The licensee was informed that no apparent violations or deviations were
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identified.
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The inspector connended the licensee's staff for the manner and effort displayed in' resolving the findings identified in Inspection Report 50-224/84-01. The staff-committed to mai'ntain their performance at a level that meets or exceeds the regulatory requirements.
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