IR 05000083/1998201
| ML20154E170 | |
| Person / Time | |
|---|---|
| Site: | 05000083 |
| Issue date: | 10/01/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154E165 | List: |
| References | |
| 50-083-98-201, 50-83-98-201, NUDOCS 9810080077 | |
| Download: ML20154E170 (7) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No:
50-83 License No:
- R-d56 Report No:
50-83/98-201 Licensee:
University of Florida
~ Facility:
University of Florida Test Reactor Location:
University of Florida, Gainesville, FL Dates:
September 810,' 1998
' Inspector:
Stephen W. Holmes, Radiation Specialist
- Approved by:
Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate
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9810000077 981001 PDR ADOCK 05000093 G
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EXECUTIVE SUMMARY This special, announced inspection consisted of the review of selected conditions and records since the last inspection, review of the respiratory protection program, and observations and discussions with licensee personnel of related operations. The inspection
'Nas Conducted in accordance with the guidance of NRC Inspection Manual.
Documentation and implementation of the University of Florida respi.atory protection program met regulatory requirements.
The University of rlorida Test Reactor was being maintained and operated as required by the license and applicable regulations.
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Renort Details Summarv of Plant Status'
During the inspection the reactor was shut down while the graphite surrounding the core was moved to gain access to the control blades, l. Operations
Conduct of Operations 01.3 Reactor Ooerations a.
Insoection Scoce (Insoection PIocedure 69001)
The inspector reviewed reactor logs, observed work briefings, dress-out activities, graphite block unstacking, and interviewed staff.
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b. Observations and Findinos Reactor operations were focused on unstacking of the graphite blocks enclosing the control blades. Briefings covered specific work to be performed, safety precautions, protective clothing, and control of operations. Work was done in a deliberate and controlled manner with appropriate communication between staff members. Changes to the planned tasks were made as needed based on operation requirements.
Testing of respirators for operability was done prior to each use as required by the University of Florida Training Reactor Respiratory Protection Program (UFTRRPP).
c. Conclusions Reactor operations conformed to licensee procedural requirements. No safety concerns were identified.
Quality Assurance in Operations a. Insoection Scoce (Insoection Procedure 69001)
The inspector reviewed Reactor Safety Review Subcommittee (RSRS) minutes and interviewed staff.
b. Observations and Findings The RSRS had reviewed and approved the UFTRRPP to include revision two.
Additionally they approved the policy statement on respirator usage.
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c. Conclusions The RSRS performed its review and approval of procedures and policy as required
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by Technical Specifications (TS) and licensee procedures.
l IV. Plant Support R1 Radiological Protection and Chemistry Controls
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R1.1 Radiation Protection Survevs a. Scone (Insoection Procedure 69001)
The inspector reviewed HP and reactor surveillances/ survey procedures, survey i
records, observed air sampling and contamination surveys, and interviewed staff.
b. Observations and Findinas l
Contamination and radiation area surveys were performed in and around the work area before, during, and after daily operations. Air samples were taken prior and during graphite block unstacking.
Samples were analyzed to identify the potential hazard, permit proper equipment i
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selection, and estimate exposures.
c. Conclusions Surveys were performed and documented as required by 10 CFR Part 20. TS and licensee requirements were met.
R1.4 Personnel Dosimetrv a. Scoce (Insoection Procedure 69001)
i The inspector reviewed dosimetry records, licensee procedures, observed j,
issuance of dosimetry, and interviewed staff.
i b. Observations and Findinas j
l Whule body and various extremity dosimetry were issued to staff prior to their
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performance of graphite block unstacking. Both thermoluminescent dosimetry I
and self reading dosimeters were used as appropriate. Doses were checked and recorded at the end of each work shift.
Doses recorded by the, self reading dosimeters were minimal, and corresponded well with expected exposures. Bioassays were to be performed as required by
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10 CFR 20.1703(a)(3)(ii) and in accordance with licensee procedures to evaluate intakes.
c. Conclusions Personnel monitoring procedures during graphite t, lock unstacking were acccptable and satisfied regulatory requirements.
R2 Status of RP&C Equipment a. Scone (Insoection Procedure 69001)
The inspector reviewed calibration, periodic checks, and certification records for the respirator fit testing unit and respirators used by the licensee, and interviewed HP and Environmental Health and Safety (EH&" staff.
i b. Observations and Findinas
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The facility used 3M 6000 series half-masks. Appropriate sized mask were issued to each individual along with a radioactive / particulate filter, both NIOSH/MSHA approved. The fit testing unit used by EH&S was calibrated by the manufacturer using NationalInstitute of Standards and Technology (NIST)
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traceable instruments, where applicable, and there own internal ones where NIST
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standards did not exist. The manufacturer's certificate was on file with EH&S.
c. Conclusions Respiratory protection equipment was being maintained and calibrated according to industry and equipment manufacturer standards. Calibration satisfied TS requirement =
R3 RP&C Procedures and Documentation a. Scooe (Insoection Procedure 69001)
The inspector reviewed UFTRRPP documentation, training records and interviewed EH&S staff.
b. Observations and Findinas The written UFTRRPP covered selection, fitting, issuance, maintenance, and testing of respirators, including testing for operability immediately prior to each use. It also encompassed supervision and training of personnel; monitoring, including air sampling and bioassay; and recordkeeping. The plan required that determination be made by a physician prior to initial use and thereafter at a-frequency determined by the physician, that the individual user is medically fit to use the respiratory protection equipmen.
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A policy statement had been issued by the Facility Director outlining the use of
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process or other engineering controls, instead of respirators; the routine, nonroutine, and emergency use; and the periods of use and relief from respirator use.
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c. Conclusions The written procedures and documentation of the UFTRRPP satisfied regulatory requirements.
R5 Staff Training and Qualification in RP&C
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a. Insoection Scone (Insoection Procedure)
The inspector reviewed reactor training records, EH&S training records, interviewed staff and observed use of respiratory protection during operations.
b. Observations and Findinas The university had a respiratory protection program of its own for which it provided training to the reactor staff. Vraining was also included in the reactor
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requalification program and additional training, specifically for the revised UFTRRPP, had recently been presented by EH&S.
Review of the training records, rosters, and class outlines by the inspector verified that training meeting the requirements of Section 20.1703 for a respiratory protection program had been given.
The inspector observations of respiratory protection during operations confirmed that the training had been sufficient for the staff to acquire the level of knowledge to use such equipment safely.
c. Conclusions Training for the UFTRRPP satisfied regulatory requirements.
V. Manaaement Meetinas X1 Exit Meeting Summary
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The inspector presented the inspection results to members of licensee management l
at the conclusion of the inspection on September 10,1998. The licensee acknowledged the findings presented.
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PARTIAL LIST OF PERSONS CONTACTED Licensee G. Mcdonald Reactor Trainee J. Power Acting Reactor Manager l
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M. Rusael Respirator Coordinator, EH&S
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R. Salazar Reactor Trainee J. Tulenko Chairman Nuclear and Radiological Engineering Department l
W. Vernetson Director of Nuclear Facilities J. Wolf Senior Reactor Operator INSPECTION PROCEDURE (IP) USED IP 69001: CLASS ll NON-POWER REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED Opened NONE Closed NONE PARTIAL LIST OF ANACHRONISMS USED EH&S Environmental. Health and Safety NIST NationalInstitute of Standards and Technology RSRS Reactor Safety Review Subecmmittee TS Technical Specifications UFTRRPP University of Florida Training Reactor Respiratory Protection Program i
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