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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20207C0881998-12-31031 December 1998 Rev 11 to Uftr SAR, Consisting of Change Page 12-20 ML20217M6581998-03-27027 March 1998 Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from Heu to LEU Fuel ML20101L3491996-03-27027 March 1996 Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from HEU to LEU Fuel ML20094S4071992-04-30030 April 1992 Rev 7 to SAR Section 5.2 Re Secondary Cooling sys,9.2.3 Re Demineralized Water Makeup sys,9.2.4 Re Purification Sys & 9.2.5 Re Potable & Sanitary Water Sys ML20091C0451992-03-26026 March 1992 Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Univ of Florida Training Reactor Conversion from HEU to LEU Fuel ML20070T4061991-03-27027 March 1991 Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Univ of Florida Test Reactor Conversion from High Enriched U to Low Enriched U ML20205H5591987-03-26026 March 1987 Proposal to Meet NRC Requirements for Conversion from High Enriched U to Low Enriched U Fuel ML20003A5121981-01-31031 January 1981 SAR for Univ of Fl Training Reactor. 1998-03-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20207C0881998-12-31031 December 1998 Rev 11 to Uftr SAR, Consisting of Change Page 12-20 ML20217M6581998-03-27027 March 1998 Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from Heu to LEU Fuel ML20203C4551997-12-0303 December 1997 Safety Evaluation Supporting Amend 22 to License R-56 ML20216A8791997-08-31031 August 1997 Univ of Fl Training Reactor Annual Progress Rept for 960901-970813 ML20148G3561997-05-29029 May 1997 Univ of Fl Training Reactor Operator Requalification & Recertification Training Program Plan,Jul 1997-June 1999 ML20134C3421997-01-27027 January 1997 Special Rept:On 970110,improper Stack Monitor Calibr Occurred.Caused by Use of Flawed Procedure.Revised Q-2 Surveillance Data Sheet ML20137C1481996-12-31031 December 1996 195-96 Annual Progress Rept, Replacing Pages IV-6,IV-11 & IV-12 ML20128N4671996-10-10010 October 1996 Safety Evaluation Supporting Amend 21 to License R-56 ML20135D0081996-08-31031 August 1996 Univ of Fl Training Reactor Annual Progress Rept for 950901-960831 ML20116J5791996-08-0909 August 1996 Annual Progress Rept of Univ of Florida Training Reactor 940901-950831 ML20116D9851996-07-24024 July 1996 14 Day Rept:On 960710,non-conservative Setting for Safety Channel 2 High Voltage Sensing Circuit Occurred.Caused by Failures in Safety Channel 2 High Sensing Circuit.Performed Successful Check of Sensing Circuit Loss of Voltage Setting ML20116D9921996-07-12012 July 1996 Ro:On 960711,Safety Channel 2 High Voltage Sensing Circuit Failed.Allowed Reactor to Sit Over Weekend & Planned to Restart ML20107L7481996-04-25025 April 1996 Ro:On 960404,failures in Safety Channel 2 High Voltage Sensing Circuits Resulted in Safety 2 Trip.Stated Resistors Replaced & Safety Channel 2 High Voltage Power Supply Temporarily Replaced W/Exact Duplicate on 960412 ML20107L7601996-04-0505 April 1996 Ro:On 960404,spurious Safety Channel 2 Loss of High Voltage Trip Occurred.Caused by Previously Undetected Matl Failure. Repairs Should Be Completed by 960410 & Restart Approved Subject to Successful post-repair Checks ML20101L3491996-03-27027 March 1996 Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from HEU to LEU Fuel ML20086D1041995-06-30030 June 1995 Ro:On 950609,failure of Primary Coolant Return Line Flow Sensor to Initiate Trip Occurred.Flow Sensors Checked After Debris Removal & as of 950626 Problem Considered Resolved ML20091L2891995-06-12012 June 1995 Ro:On 950609,primary Coolant Flow Line Return Sensor Failed. Caused by Debris in Line.Line Repaired ML20082D0221995-04-0303 April 1995 Ro:On 950309-13,leakage of Coolant HX Occurred After Primary Coolant Resistivity Increase Noted.Primary & Secondary Flow Secured & Shell Side of HX Drained.No Leakage Collected.Hx Returned to Primary Sys & Placed in Operation ML20115B5881994-08-31031 August 1994 Annual Progress Rept of Univ of Fl Training Reactor for Sept 1993 - Aug 1994 ML20072P7141993-08-31031 August 1993 Annual Progress Rept of Univ of Fl Training Reactor for Sept 1992 - Aug 1993 ML20044G8351993-05-28028 May 1993 Revised, Operator Requalification & Recertification Training Program Plan of Univ of Florida Training Reactor, Jul 1993 Through June 1995. ML20069D0971992-08-31031 August 1992 Annual Progress Rept of Univ of Fl Training Reactor for Period 900901-910831 ML20099H7641992-08-10010 August 1992 Ro:On 920727,temp Recorder Point 2 Noted to Be Reading Downscale,Indicating Failure in Circuit Monitoring Water Temp at Exit of South Ctr Fuel Box 2.Caused by Blockage in Fuel Box.Planned Maint Underway.Event Not Reportable ML20094S4071992-04-30030 April 1992 Rev 7 to SAR Section 5.2 Re Secondary Cooling sys,9.2.3 Re Demineralized Water Makeup sys,9.2.4 Re Purification Sys & 9.2.5 Re Potable & Sanitary Water Sys ML20091C0451992-03-26026 March 1992 Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Univ of Florida Training Reactor Conversion from HEU to LEU Fuel ML20087A0521991-12-29029 December 1991 Rev 1 to Operator Requalification & Recertification Training Program Plan of Univ of Florida Training Reactor, Jul 1991 Through June 1993 ML20086H8081991-12-0303 December 1991 Final Ro:On 911119,safety Channel 2 Meter Flickered & Dropped Out Hard Downscale (Pegged).Caused by Intermitten Fault in Fine Adjust Potentiometer of Circuit. Poteniometer Replaced & Amplifier Card Reseated ML20086G2631991-11-27027 November 1991 Ro:Unscheduled Reactor Trip Occurred While Measuring Temp Coefficient of Reactivity.Caused by Secondary Cooling Water Dropping Below 8 Gpm Min Required by Limiting Safety Sys Setting.Cooling Water Logic Placed in City Water Mode ML20086H8151991-11-20020 November 1991 Ro:On 911120,unscheduled Shutdown Conducted Due to Failure of Safety Channel 2 Circuit on 911119.Possibly Caused by Problem in Safety Channel 2 Meter Circuit.Permission to Restart Not Yet Sought ML20086G2681991-11-19019 November 1991 Ro:Reactor Tripped on Loss of Secondary Cooling Flow on City Water & Gate Valve on City Water Flow Partially Closed to Allow Operation at Higher Temp.All Safety & Control Sys Functioned Properly.Detailed Rept Will Be Submitted ML20085H4911991-10-16016 October 1991 Ro:On 911003,failure to Perform Required Surveillance of Limiting Safety Sys Setting of Loss of Secondary Coolant Pump Power Discovered.Trip Check on Loss of Pump Power Incorporated Into Q-1 Quarterly Scram Checks ML20085H5071991-10-0303 October 1991 Ro:Possibility That Tests for Operability on Loss of Secondary Coolant Well Pump Power May Not Meet Tech Spec Surveillance Requirement 3.2.2(2) Discovered.Minutes of 911007 Executive Committee Meeting Encl ML20105B3751991-08-31031 August 1991 Annual Progress Rept of Univ of Florida Training Reactor, Sept 1990 - Aug 1991 ML20070T4061991-03-27027 March 1991 Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Univ of Florida Test Reactor Conversion from High Enriched U to Low Enriched U ML20058F4281990-10-29029 October 1990 Ro:On 901002,three Reactor Startups Occurred W/O Performing Daily Checkout or Control Blade Interlock Checks Following Previous Shutdown ML20058F3481990-10-25025 October 1990 Ro:On 901025,three Reactor Startups Performed W/O Daily Checkout Being Performed within Required Time Interval,Per SOP SOP-A.2, Reactor Startup ML20072S3761990-08-31031 August 1990 Annual Progress Rept of Univ of Florida Training Reactor, for Sept 1989 - Aug 1990 ML20248F1081989-09-29029 September 1989 Ro:On 890915 & 18,reactor Trips Occurred When Safety Channel 1 High Voltage Power Supply Dropped to 90% or Less of Rated Voltage.Caused by Instabilities in 15-volt Dc Power Supply. Trip Relays Replaced & Bistable Adjusted ML20006D5491989-08-31031 August 1989 Annual Progress Rept of Univ of Florida Training Reactor, Sept 1988 - Aug 1989. W/900207 Ltr ML20244A7401989-03-31031 March 1989 Ro:On 890317,reactor Trip W/High Primary Coolant Temp Indication Occurred.Caused by Failure of Specific Temp Recorder Sys Due to Dust/Corrosion Buildup on Slide Wire Causing Excessive Resistance.Buildup Cleaned Off ML20244D5981989-03-31031 March 1989 Final Rept Re Higher than Expected High Streaming Radiation Levels Present at Vertical Ports During Full Power Operation.Caused by Inadequate Survey of Rabbit Shield on 870120.Extra Shielding Installed on Rabbit Sys Shield ML20235W6951989-02-21021 February 1989 Ro:On 890221,potential Failure to Rept Significant Change in Level 1 Administration Existed,Per Tech Spec 6.6.3. Evaluation Determined No Significant Administration Oversi Oversights Involved ML20206J7841988-11-14014 November 1988 Ro:On 881104,unscheduled Reactor Shutdown Occurred Due to Failure of Temp Recorder to Indicate Properly.Caused by Failure of Microswitch.Microswitch & Vacuum Tube Replaced & Calibr Check Performed ML20196C0821988-08-31031 August 1988 Annual Progress Rept of Univ of Florida Training Reactor, Sept 1987 - Aug 1988 ML20196A3661988-06-23023 June 1988 Ro:On 880610,control Blade Safety 2 Clutch Indicating Lamp Burned Out.Burned Out Clutch Current Indicating Bulb Replaced to Include Necessary Control Blade Drive & Drop Time Checks ML20150B6821988-06-23023 June 1988 Ro:On 880610,clutch Current Indication Lamp for Control Blade safety-2 Burned Out at Full Power,Dropping Control Blade from 56% Withdrawn to Fully Inserted Position.Clutch Replaced & Lamp Replacement Frequency Increased ML20195H8791988-06-0909 June 1988 Final Ro:On 880409,recurrence of Safety Channel 1 Circuit to Provide Proper Power Indication Occurred After Return to Normal Operations on 880401 Following Previous Failures on 880315 & 16.Caution Memo Issued to Operators ML20151W8931988-04-27027 April 1988 Safety Evaluation Supporting Amend 17 to License R-56 ML20151W3711988-04-25025 April 1988 Ro:On 880321,0401 & 09,safety Channel 1 Failed to Bottom Meter Stop.Cause Not Yet Identified.New Program Developed to Isolate & Correct Cause of Failure ML20151B3681988-03-28028 March 1988 Reportable Occurrence:On 880314,safety Channel 1 Circuit Failed to Provide Proper Power Indication for Several Seconds on Two Occasions.Caused by Capacitor Failure. Capacitor Replaced W/Substitute of Different Mfg 1998-03-27
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The strip chart recorder is a Gutton Rustrak D.C. Recorder. This D'arsonval meter instrument records signals from the RS-2 log count rate meter for permanent record. All three radiatior.
, monitoring systems are calibrated quarterly with the assistance of the Radiation Control Office.
In the event of a loss of power, all radiation monitors operate on installed battery packs (rated l to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) to insure their availability at all times.
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l 12.3.4.2 The Stack Monitoring System. The Stack Monitor System, consisting of a GM detector, a l l log rate meter and a strip chart recorder, is equivalent to the area monitoring system. In addition to
{
l these, it may also include a log rate meter with an alarm setting capability for different operating
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L power levels, with the information obtained from the RS-2 log count rate meter. The GM detector is '
l located on the downstream side of the absolute filter, before dilution takes place. !
i 12.3.4.3 Air Monitoring System. An Air Particulate Detector (APD) is designed to detect airborne ;
particulate activity. The APD is equipped with a flow indicator (LPM), a strip chart recorder and _ ;
! audible as well as visual alarm settings. The monitor is a compact airborne particulate counter which l may be used in an occupational environment or in confined spaces. The air is drawn through a filter ,
paper by a constant volume pump; the activity is detected by the counter near the filter and recorded on the strip chart recorder. An alarm is activated whenever a high activity level is detected.
123.4.4 Radiation Monitoring. Operators and other personnel working in the reactor wear film, TLD, Luxel or other individual personnel monitoring badges at all times. Ifindicated by the type of work, a direct-reading pocket dosimcer, or other dosimeter is worn as specified by the D-Series of the UFTR Standard Operating Procedures which address radiation protection and control. l l Various portable survey meters are also available to be used whenever it is deemed necessary and/or required by the SOPS.
Surveys performed on a weekly basis include swipe surveys, air and water samples, and beta-gamma radiation field surveys. Surface contamination in the room is determined by means of portable
. instruments and smear tests. Particular attention is given to the equipment pit, experimental areas and u the irradiated fuel storage pits during each survey. Periodic surveys by health physics personnel are performed to check for leakage around beam plugs and through the stacked-block reactor shield; periodic air samples are also taken and analyzed providing a check on the proper functioning of the continuous air monitoring (CAM) system. The coolant is checked by evaporating a sample to dryness and counting with a gas flow proportional or equivalent counter.
As indicated previously, there is an ongoing program by the Radiation Control Office and the UFTR facility staff to monitor radiation levels outside the UFTR building in the nearby vicinity.
Monitoring is performed by placing radiation recording devices at seven (7) or more locations outside l the UFTR building. Typicallocations for such devices are marked on the sketch of the UFTR building and immediate vicinity presented in Figure 12-9c These film badges, TLDs or other monitoring devices are collected by the UFTR staff or Radiation Control personnel and evaluated
, monthly at a NVLAP-certified processor.
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12-20 REV 9,8/95 l 9903090355'990219 REV 11,12/98 DR ADOCK 0 3.
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