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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20134C3421997-01-27027 January 1997 Special Rept:On 970110,improper Stack Monitor Calibr Occurred.Caused by Use of Flawed Procedure.Revised Q-2 Surveillance Data Sheet 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20148E8161988-03-15015 March 1988 Ro:On 880315,failure of Safety Channel 1 Circuit Occurred. Failed Component Replacement Has Restored Safety Channel 1 to Normal ML20209G7221987-04-13013 April 1987 Ro:On 870401,reactor Experienced Safety Channel 1 Trip. Caused by Operator Error.Rapid Recovery Restart Performed by Operator.Memorandum Issued Placing Restrictions on Automatic Operation & Limiting Removal of Regulating Blade ML20207J0321986-12-19019 December 1986 Ro:On 861211,actuation of Evacuation Alarm & Evacuation Alarm/Core Vent Sys Interlocks Occurred While Stack Count Rate Approx 300 Cps,In Potential Violation of Tech Specs. Cause Not Given.Vent Will Be Secured at 10 Cps During Drill ML20132B4241985-09-17017 September 1985 Ro:On 850904,one Control Blade Failed to Drop Fully Into Core on Demand from 64% Withdrawn Position.Probably Caused by Bearings Supporting Blade/Shaft Coupling or Magnesium Shroud housing-to-blade Clearance ML20132B4521985-09-0404 September 1985 Ro:On 850904,one Reactor Control Blade Failed to Drop on Demand from 64% Removed Position.Probably Caused by Binding in Clutch S-3 Possibly Due to Moisture or Other Effect Reducing Clearance 1997-01-27
[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
[Table view] |
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m NUCLEAR ENGINEERIND SCIENCES DEPARTMENT r Nuclear Reactor Facility University of Florida o ei.,
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iiu v e ='ue s 14, 1988 Temperature nonitoring Syst.es Failure Final (14 Day) Report Nuclear Regulatory Commission Suite 2900 101 Marietta Street, N.W.
Atlanta, GA 30323 Attention: Malcolm L. Ernst Acting Regional Administrator, Region II Re t University of Florida Training Reactor Facility License R-56, Docket No. 50-83 Gentiemen:
Pursuant to the reporting requirements of paragraph 6.6.2(3)(c) of the UFTR Technical Specifications, a description of a potential abnormal occurrence as '
defined in the UTTR Technical Specifications Chspter 1 is described in this 14-day report to include NRC nocification, occurrence sceaario, evaluation of coasequences, corrective action and current status. The potential promptly re-portable occurrence involved failure of the temperature monitoring syi. tem re-salting in an unscheduled shutdown.
NRC Notification h members of the Executive Committee of the Reactor Safety Review Subcommit-tee (RSRS) including the Director of the Facility (W.G. Vernetson) w.ere ap-prised of the details of this occurrence individually on November 4,1988 and individually concluded that it is a potential abnormal occurrence as defined in UFTR Technical Specifications, Chapter 1. The wembers recommended NRC noti-fication per Section 6.642 of the UFTR Tech Spessi. This notification was car-ried out by telephone to Mr. David Verre111 on Friday, November 4, 1988 with a following telecopy on November 7,1988 (next working day) as required (see At-tachment I).
The Executive Committee of the RSRS reviewed the full details of this occur-rence at a final meeting on November 8,1988. The Executive Committee also concurred wth management testart approval subject to NRC notification of the status of the corrective action and readiness to restart normal operations.
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f Nuclear Regulatory Commission yovember 14, 1988 Page Two Initial Event Scenario At 1108 on Fridty, Novembec 4,1988 with the reactor operating at 100 kw for an irradiation supporcing neutron activation analysis (with P.M. Whaley as Roactor 9perator), the temperature recLtder failed to indicate properly (i.e.,
stopped tracking). SRO P.M. Whaley noted that reactor power level indicators were functioning normally and, noting that no other abnormal indications existed, commenced an unschedaled shutdown. The reactor was shut down and se-cured without incidtst with all other systems responding properly. Following securing of the reactor and recorder, the temperature recorder readings for all monitored points failed to vaty shen the temperature recorder was manually activated. Manual manipulation of the indicator. print wheel was accomplished asich na resistance by the instrument. The print wheel remained at the indicat-ing point established by manipulation of the print wheel. .
Evaluation of Consoquences Rasetor staff and administration including Director W.G. Vernetson concluded there was no compromise to reactor safety from this event, nor was there as/ ;
impact on personnel radiation doses. This event is considered to be potential- "
ly a reportable occurrence since the temperature recorder would potentially i fail to register the high temperature required to initiate a high primary l coolant system temperature trip. However, all other control and safety systems responded properly.
Based on evaluations of this event, restart was recommended following replace-mont of the degraded microswitch that disables the motor during switching L transients, recalibration of the temperature recorder and completion of a ;
valid weekly sad daily p*eoperational checkout on the affected portions of the reactor system. !
Corrective Action i
i Immediate corrective action consisted of securit.g the reactor and putting it [
on administrative shutdown until the problem could be isolated and corrected. :
L
- Preliminary investigation indicated a loss of power to drive the servo motor.
- Manual manipulatio7 of the indicator met no resistance and the indicator post-tion did not return to normal. These aymptoms indicated the problem to be in one of three (3) areast the amplifier, the drive control circuit, or the con- l stant voltage unit. The amplifier and drive motor were checked to be func- l tional in an out-of-circuit test and t!.e constant voltage unit was measured to !
be operating properly in place. :
, r In-circuit measurements of the servo drive motor, however, indicated one set !
of windings had low resistance. Following the removal (for physical examina-tion) and replacement of the microswiten that disables the motor during ;
switching transients, system operation was returned to normal. Checks indi-cated the servo drive motor had proper resistance values. All symptoms were ,
duplicated by installing axternal resistance in parallel (simulating contact l resistance) with the microswitch indicating the microswitch as the probable (
cause of the failure. j l
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Nuclear Regulatory Commission Novembe r 14, 1988 Page Theat Prior to returning to normal operations, the microuitch was replaced along with a vacuum tube which had a marginally acceptable gain when tested and a calibration check was performed on the temperature mnitoring system. Finally, '
a valid weekly and daily preoperational check on the affected portions of the reactor systems were completed. A one hour power operation exercising thJ ten-perature monitor over most of its normal range was the first critical opera-tion af ter return to operations based upon RSRS approval and NRC notification to Mr. Robert Carroll on 9 Novembet 1988. After this test operation was suc-cessful on November 9, the reactor was approved for return to full normal op-
- erations including running experiments and other normal operational activi-ties.
Current Status All operators have been made cognizant of this problem. Sinct tastart on No-vember 9, 1988, there has been no recurrence of the temperature recorder failure.
I Sincerely, William G. Vernetson Director of Nuclear Facilities I
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Reactor Scfety Review Subcommittee t
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NUCLEAR ENGINEERIN3 SCIENCES DEPARTMENT Nuclear Reactor Facility University of Florida ,
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- ce.vae,nesw. autt Novsmber 7, 1988 Nuclear Regulatory Commission, Region 11 101 Marietta Street, N.W.
Suite 2900 Atlanta , CA 30323
- Atteation: Malcolm L. Ernst Acting Regions 1 Administrator, Region 11 Re: University of Florida Training Reactoe Facility License: F.-56, Docket No. 50-83 - -
This letter is in followup to our telephone esil of 4 November 1988 notifying Mr. Dave Verre111 of a failure of the temperature record to track proparly and requiring an unscheduled shutdown.
Preliminary contact with the Reactor Safety Review Subcormittee supported conclusion that this event constitutes a potentially reportable occurrence per Technical Specifications 6.6.2(3)(c) and so the NRC .ts hereby notified per Sect.on 6.6.2 of the UFIR Technical Specifications.
The probable cause has now been isolated and the event and subse-quent planned recovery will be revirsed by the Resctor Safety Re-view Subcommittee within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for permission to re-start with c followup report to follow.
h 4 William G. 'Vernetson Tlf, h Dap '
Director of Nuclear Facilities WGV/ps cc Reactor Safety Review Subcommittee P.M. Whaley
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