ML20029E803
| ML20029E803 | |
| Person / Time | |
|---|---|
| Site: | 05000083 |
| Issue date: | 04/29/1994 |
| From: | Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Vernetson W FLORIDA, UNIV. OF, GAINESVILLE, FL |
| References | |
| NUDOCS 9405230003 | |
| Download: ML20029E803 (24) | |
Text
{{#Wiki_filter:y ORGAU?ECORD C0? aaa Docket No. 50-83 License No. R-56 University of Florida ATTN: Dr. W. G. Vernetson Director of Nuclear Facilities 202 Nuclear Sciences Center Gainesville, FL 32611 Gentlemen:
SUBJECT:
MEETING
SUMMARY
- UNIVERSITY OF FLORIDA RESEARCH REACTOR This letter refers to the management meeting conducted at your facility on the campus of the University of Florida in Gainesville, Florida on April 14, 1994.
The purpose of the meeting was to discuss the status of various aspects of the safety program at your facility and other items of mutual interest. A list of attendees, a meeting summary, and a copy of your handout are enclosed. In accordance with Section 2.790 of the NRC's Rules of Practice, Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room. Should you have any questions regarding this letter, we will be pleased to discuss them. Sincerely, i ORIGINAL stGNED BY ypgtt11PSTOHR J. Philip Stohr, Director Division of Radiation Safety and Safeguards .l l
Enclosures:
l. List of Attendees 2. Meeting Summary 3. Licensee's Handout cc w/encis: (See page 2) 9405230003 940429 PDR ADOCK 05000003 P PDR 1 i i _j t_-
~* .e. b 2 h }$94 . University of Florida 2 cc w/encls: Dr. J. S. Tulenko, Chairman Nuclear Engineering Sciences Department University of. Florida 202 Nuclear Sciences Center Gainesville, FL 32611 Dr. Ratib A. Karam, Director Neely Nuclear Research Center Georgia Institute of Technology i 900 Atlantic Drive, NW Atlanta, GA 30332 Mr. Pedro B. Perez Associate Director Nuclear Reactor Program North Carolina State University P. O. Box 7909 Raleigh, NC 27695-7909 Dr. R. U. Mulder, Director Reactor Facility University of Virginia Charlottesville, VA 22901 Lyle E. Jerrett, Acting Chief Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Boulevard Tallahassee, FL 32999 L bec w/encis: T. Michaels, NRR J. Caldwell,- NRR C. Bassett, RII Document Control Desk J g:\\drss\\rsps\\mmsum494.ufl RII:DRSS RII:DRSS RII:DRSS RII:DRSS BA "EtJvt 4817CC dtvv CBassett EMcAlpine 0 Collins BMallett 04/ R /94 04/ 2 1 /94 04/g/94 04/q/94
i ENCLOSURE 1 s List of Attendees University of Florida W. Bolch, Professor and Associate Chairman, Department of Environmental Engineering M. Ohanian, Professor and Associate Director, College of Engineering, and Chairman, Reactor Safety Review Subcommittee J. Tulenko, Chairman, Nuclear Engineering Sciences Department W. Vernetson, Director, University of Florida Training Rea: tor D. Munroe, Radiation Control Officer D. Simpkins, Manager, University of Florida Training Reactor Nuclear ReaulatorY Commission - Reaion II S. Ebneter, Regional Administrator B. Mallett, Deputy Director, Division of Radiation Safety and Safeguards (DRSS) C. Bassett, Project Inspector, Radiation Safety Projects Section (RSPS), Nuclear Materials Safety and Safeguards Branch (NMSS), DRSS Nuclear Reaulatory Commission - Office of Nuclear Reactor Reaulation (NRR) T. Michaels, Project Manager, Non-Power Reactor & Decommissioning Project Directorate, Division of Operating Reactor Support i i i + - ---m-- y 4 n y--
e ENCLOSURE 2 Meeting Summary ) On April 14, 1994, the Regional Administrator and staff held a management meeting with representatives from the University of Florida (UFL). T. Michaels from NRR in Headquarters also attended the meeting. The purpose of the meeting was to discuss the status of the licensee's non-power reactor safety program and the future of reactor operations at the facility. The licensee gave a presentation detailing:
- 1) the key characteristics of the facility, 2) the status of the facility and facility usage, 3) support for the reactor program, 4) the status of the operations program, 5) the status of the health physics program, 6) the status of the security program, and 7) the status of the emergency preparedness program at the facility.
The licensee also indicated that, with the addition of full-time Reactor Manager, the staffing level of the facility was adequate, that they were in full compliance with the regulations, and that the facility has a relatively high level of activity. The issues of the pending license renewal and the conversion to low enriched uranium (LEU) fuel were also discussed by those present. The NRC representatives indicated that the licensee appeared to have a competent and well trained staff and that their personnel were dedicated to operating the reactor in a manner consistent with the regulations. The strong points of the licensee's program were their practices of maintaining the doses to individuals low and maintaining the facility relatively contamination free, their maintenance of records, and their willingness to respond quickly to 1 safety issues. The NRC representatives stated that the continuing challenge for licensees who are currently performing well, as is UFL, is to maintain that high level of performance. The meeting proved to be very beneficial and, as a result, several issues were raised. These issues dealt with regulatory fees, discharges of effluents to the sanitary sewer, and a discussion of Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix I". l i I
ENCLOSURE 3 UNIVERSITY OF FLORIDA TRAINING REACTOR MANAGEMENT MEETING PRESENTATION for Nuclear Regulatory Commission Headquarters and Region II Representatives William G. Vernetson Director of Nuclear Facilities UNIVERSITY OF FLORIDA April 14,1994
PRESENTATION OUTLINE l 9 OVERVIEW OF PRESENTATION 9 KEY FACILITY CHARACTERISTICS 9 STATUS OF FACILITY AND USAGE i e SUPPORT FOR TliE REACTOR PROGRAM S STATUS OF OPERATIONS PROGRAM Operations Staff Training Reactor Instrumentation Improvements (Planned and Scheduled) e STATUS OF HEALTH PHYSICS PROGRAM Implemented Program and 10 CFR Part 20 Planned Reviews and Changes e STATUS OF SECURITY PROGRAM e STATUS OF EMERGENCY PREPAREDNESS PROGRAM
) ~ UNIVERSITY OF FLORIDA TRAINING REACTOR KEY CHARACTERISTICS e Rated Power 100 KWth a Fuel: MTR Plate - Type Metal Alloy 93% Enriched e Core Geometry: Two Slab Arrangement in Six Fuel Boxes i Four 11-Plate Fuel Bundles Per Fuel Box e Control: 4 Swinging Vane-type Cadmium Loaded Blades e Cooling Flow 40 GPM e Coolant Temperature Core inlet: 105 F Core Outlet: 120F e Pressure: 1 Atmosphere e Instrumentation: B-10 Proportional Chamber Fission Chamber Compensated lonization Chamber Uncompensated lonization i Chamber
Shield Tank Vertical Access Plugs Reinforced Concrete Shield (h i \\ M j / N l h ,nd./ Removable Concrete W Slifeld Diocks M isar. t D)A Removable Sliield l Di l M / [ Blocks (Thermal fi [IIby [ d E L E, *'# M"M Removable Shield Blocks I I : i
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/N k COOLANT ',s. OUTLET 04% 2 FUEL BUNDLES FUEL SUPPORT SH D OO x .3.x .e. v COOLANT INLET Figure 4-9. ISOMETRIC OF UFTR FUEL BOXES.
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RECENT UFTR FACILITY USAGE DATA 9 PRODUCTIVE USAGE TIME COMMITl\\ENT 25 + hours per week 10.25 hours critical per week (much variation) 5-10 EFPHs per week i 9 BROAD SPECTRUM OF USAGE Education (All Levels) Lab /Special Project Courses Lecture Segments for UF Courses Lectures / Exercises for Visiting Academic Units Training (Utility / College /Other) Research Projects (NAA, Color Centers, Defect Production...) Irradiation and Other Services Demonstrations and Tours
m-Energy Generation at the UFTR kW-Hours each Reporting Period 45000-- 40000-k35000-30000-25000-20000-15000-1@I lbl li l l i b k 10000-N9 NO N1 N2 N3 N4 N5 N6 N7 N8 N9 NO 81 N2 83 84 85 N6 N7 N8 89 NO N1 N2 Reporting Period Figure 1. eary En gge ra on Histo for the UFTR Rated at 100 kW (Reporting Year
OVERVIEW OF l REACTOR FACILITY USAGE 9 EDUCATION / TRAINING Secondary Schools Conunmiity Colleges Colleges / Universities 1 Utilities e RESEARCH Facility Life Extension HEU to LEU Conversion Plasma Kinetics NAA for Trace Element Identification NAA Methodology Special Detector Development Neutron Radiography Facility Development Dielectric Irradiation for Color Center Analysis e SERVICE (TYPICAL) Irradiated Boraflex Evaluation Generation of Radionuclides (e.g., Cu-64) Materials Irradiation e PUBLIC INFORMATION
The Rabbit System 4 9 Reactor Building tilall rr O: Vertical Access P!ugs ^0 Shield Tank Removable Concrete ^^ Shield Blocks ,r i To Reactor {-{- To Red f.. 7 ff $* Chem Lab ~.- l / Em // ~ ( r To ^ Prcssure 0: jig;;'j Control
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FINANCIAL SUPPORT FOR T11E REACTOR. PROGRAM l 9 UNIVERSITY SUPPORT Relatively Static Use of Electronics Engineer (infrequent) Support from Radiation Control Office i 9 EXTERNAL SUPPORT Reactor Sharing Program University Reactor Instrumentation Program (canceled as of 8/94) HEU-to-LEU Conversion Grant Research Support Service Work
OTHER SUPPORT FOR THE REACTOR PROGRAM S INTEGRATED COMPONENT OF NE AND NES CURRICULUM Assures Visibility Good Public Relations Generally Well Accepted 9 UTILIZATION BY MANY DEPARTMENTS Environmental Engineering Sciences Chemistry Materials Science and Engineering Anthropology i l Pharmacology 1 STUDENT PROJECTS ASSURE CONTINUING FACILITY IMPROVEMENTS / VISIBILITY l l 1
STATUS OF OPERATIONS PROGRAM l STAFFING ADEQUATE FOR CURRENT PROGRAMS Four SROs/One RO Expect Loss of RO Soon OPERATIONS STAFF REQUALIFICATION AND RECERTIFICATION PROGRAM Revised Program In 1993 (Approved) Development of Question / Answer Banks Annual Operations Test Annual Walkthrough Oral Examination Additional Practical Training Continued Improvement of Training Materials O REACTOR INSTRUMENTATION Sources of Recent Outage Time / Unavailability Blade Position Indicating System Temperature Monitoring System Blade Control System Five Trips Since 1990 (11/91, 12/91, 5/92, 3/93, 8/93) Twelve Unscheduled Shutdowns Since Mid-1991 (11/91, 7/92, 7/93 (3), 8/93, 12/93 (3), 1/94 (3)) Some Instrumentation Failures
RECENT FIVE YEAR INSTRUMENTATION IMPROVEMENTS l l 9 IMPLEMENTED Two Pen Recorder Survey Meters Ion Chamber (RO-2A) GM Meter (ASP-1) Neutron Rem Meter (ESP-2) Bicron MicroR Meter Xetex Telescan High Dose Rate Instrument Electronic Maintenance Kit Dual Channel High Speed Chart Recorder Fiber Optics Extendable Boroscope 9 IN PROCESS (FUNDED) Air Particulate Detector (AMS ) d Digital Control BPI System (4 Channels) Area Radiation Monitoring System (3 Channels) Multipoint Temperature Recorder Thermocouple Pseplacement (Partially Implemented) IN RESERVE NI Channel Replacement 9 PLANNED (FUNDED) Telescoping High Dose Rate Survey Instrument Multipoint Temperature Recorder Thermocouple System Replacement S PLANNED (UNFUNDED) Stack Effluent Monitoring System l l l l
OTHER IMPROVEMENTS IMPLEMENTED FACILITY REFURBISHMENT Painting Equipment Pit Painting Cell Walls Painting NAA Laboratory Areas Housekeeping / Painting Hot Cave Air Handler Replacements NAA SUPPORT EQUIPl\\ENT HPGe Detector Systems (2) Automatic Sample Changer Electronic Balance Moisture Analyzer Freeze Dryer OMNIGAM Software l J
STATUS OF HEALTH PHYSICS PROGRAM S ROUTINE PROGIMM Minimal Dose Commitment Low Contamination Levels 9 NON ROUTINE PROGRAM Fuel Inspection Core Area Maintenance l e IMPLEMENTATION OF NEW 10 CFR PART 20 ALA.RA Program 1 Revised Radiation Protection Program RWP Procedure Changes i i 9 PLANNED REVIEWS AND CHANGES j Ongoing Updates l Respirator Program Development i I
g 1 i-STATUS OF SECURITY PROGRAM S GOOD SECURITY SYSTEM RELitBILITY Low Alarm Frequency Good UPD Support / Training / Response Good Staff Support / Training 9 OCCASIONAL ENTRY IN LOG OF SAFEGUARD EVENTS 9 ANNUAL REVIEW OF PROGRAM Occasional Minor Problems No. Major Problems < -J
= j.; STATUS OF EMERGENCY PREPAREDNESS PROGRAM 9-QUARTERLY DRILLS S LARGE ANNUAL DRILL 9 EMERGENCY EQUIPl\\ENT TRAINING G CALL LIST UPDATES e INTERACTIONS WITH STATE EMERGENCY PREPAREDNESS OFFICE 9 ANNUAL REVIEW OF El\\ERGENCY PLAN Removing Revised Emergency Procedures from Emergency Plan Removing Agreement-Letters from Emergency Plan-Updating Various Tables of Support Equipment Updating Hospital Plan for Handling. Radiation Emergencies
{ 6
SUMMARY
STATUS REPORT e FACILITY NEEDS UPGRADE / MODERNIZATION. 9 USAGE REMAINS AT HIGH LEVELS e MANAGEl\\ENT/ STAFF ANTICIPATE NEEDS Limited By Support Successful Overall 9 . DOE IS A KEY SUPPORT SOURCE Reactor Sharing - Reactor Instrumentation IEU/ LEU Conversion TRTR Newsletter 9 FACILITY IS A REGIONAL ASSET 9 MANY IMPROVEMENTS IMPLEMENTED a 9 MORE IMPROVEMENTS ARE PLANNED 9 . OPTIMISTIC OUTLOOK- .J
u ,. ~.. -.--- .. -.~- -. } + n :. \\ CURRENT STATUS OF R-56 LICENSEE 9 FULL TIME REACTOR MANAGER 9 FULL COMPLIANCE Working on Respirator Program S RECEPTIVE TO REGULATORY REQUESTS. i e RELATIVELY HIGH LEVEL OF ACTIVITY 9 FIVE LICENSED OPERATORS (4 SROs,1 RO) 4 1 .}}