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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20041F1251982-03-0505 March 1982 Ro:On 820303,instrumentation Components That Monitor Primary Coolant Flow & Core Outlet Temp Would Not Provide Scram for Power Failure.Cause Not Given.Components Reworked to Provide Scram ML19290B6931979-12-0303 December 1979 Ro:On 791121,decrease in Negative Differential Pressure Discovered Between Inside & Outside of Nuclear Science Ctr Bldg.Caused by Loose Fitting Gasket on Truck Door.Gasket Adjusted.Maint Schedule Will Be Implemented ML19290B6841979-11-28028 November 1979 Ro:On 791127,pH of Secondary Water Sample Exceeded Tech Spec Limit.Caused by Failure to Initiate Automatic Blowdown of Secondary Water Sample.Importance of Procedure Stressed to Operators 1982-03-05
[Table view] Category:LER)
MONTHYEARML20041F1251982-03-0505 March 1982 Ro:On 820303,instrumentation Components That Monitor Primary Coolant Flow & Core Outlet Temp Would Not Provide Scram for Power Failure.Cause Not Given.Components Reworked to Provide Scram ML19290B6931979-12-0303 December 1979 Ro:On 791121,decrease in Negative Differential Pressure Discovered Between Inside & Outside of Nuclear Science Ctr Bldg.Caused by Loose Fitting Gasket on Truck Door.Gasket Adjusted.Maint Schedule Will Be Implemented ML19290B6841979-11-28028 November 1979 Ro:On 791127,pH of Secondary Water Sample Exceeded Tech Spec Limit.Caused by Failure to Initiate Automatic Blowdown of Secondary Water Sample.Importance of Procedure Stressed to Operators 1982-03-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211G9371999-08-16016 August 1999 Ri Nuclear Science Center Annual Rept for Period 980701 Through 990630,providing Reactor Operating Statistics,Info Re Inadvertent Reactor Shutdowns or Scrams,Maint Operations Performed & Changes in Facility ML20199E8351997-11-12012 November 1997 Safety Evaluation Supporting Amend 25 to License R-95 ML20217E2991997-09-23023 September 1997 Safety Evaluation Supporting Amend 24 to License R-95 ML20141H6191997-07-23023 July 1997 Annual Rept for Jul 1996 - June 1997,consisting of Reactor Oeprating Statistics,Inadvertent Reactor Shutdowns or Scrams & Maint Operations Performed During Reporting Period ML20236T9201997-07-17017 July 1997 Annual Rept for Jul 1997 - Jun 1998,consisting of Reactor Operating Statistics,Inadvertent Reactor Shutdowns or Scrams & Maint Operations Performed During Reporting Period ML20140H7401997-06-17017 June 1997 Safety Evaluation Supporting Amend 23 to License R-95 ML20132E2541996-12-18018 December 1996 Safety Evaluation Supporting Amend 22 to License R-95 ML20086T3731995-07-27027 July 1995 First Annual Rept Required by Rev 1 to Ts,Providing Monthly Summary for Period 940701-950630,per TS 6.8.4.a,including Info on One Emergency Shutdown,Maint Operations & Descriptions of 10CFR50.59 Evaluations ML20063K7951994-02-16016 February 1994 Preliminary Rept on Ri Nuclear Ctr Conversion from HEU to LEU Fuel ML20126F4511992-12-31031 December 1992 Rev 1 to SAR for Low Enriched Fuel Conversion of Ri Nuclear Science Ctr Research Reactor ML20099A6221992-07-23023 July 1992 Rev 1 to SAR for Low Enriched Fuel of Rhode Island Nuclear Science Ctr Research Reactor ML20086D2141991-11-30030 November 1991 SAR for Low Enriched Fuel Conversion of Rhode Island Nuclear Science Ctr Research Reactor ML20247P1971989-07-25025 July 1989 Ro:On 890725,fuel Element 141 Had Estimated U-235 Burnup to 18.9 G.Operator Instructed That in Addition to Quarterly Calculations Required by Tech Specs,Operator Will Make Projections to Insure That No Element Will Reach Limit ML20205K6381988-10-20020 October 1988 Safety Evaluation Supporting Amend 16 to License R-95 ML20154J4221988-05-12012 May 1988 Ro:On 880512,standby Power Sys Generator Failed.Repeated Starting & Stopping of Generator Performed W/O Difficulty. Generator Ran for Approx 2 H W/O Difficulty & W/Normal Characteristics ML20196H6351988-03-0808 March 1988 Headquarters Daily Rept for 880308 ML20245C9751987-10-27027 October 1987 Safety Evaluation Supporting Amend 15 to License R-95 ML20128D3141985-05-10010 May 1985 Safety Evaluation Supporting Amend 14 to License R-95 ML20093M9151984-09-27027 September 1984 Ro:On 840927,generator Stopped & Would Not Restart.Stiff Wire Attached to Coil Snapped Off Due to Vibration.Wire Replaced W/Soft Wire & Sys Operated Normally ML20094S5891984-08-10010 August 1984 Ro:On 840810,telephone Lines Between Narragansett,Ri & Providence,Ri Failed,Preventing Transmission of Signals from Burglar Alarm & Supervisory Sys.Cause Unknown.Line Restored ML20090H2681984-07-0909 July 1984 Ro:On 840705,motor Starter Timer in Cleanup Sys Air Blower Failed During Electrical Storm.Timer Believed Struck by Lightning.Replacement Timer Installed & Reactor Returned to Power on 840709 ML20090E3771984-06-28028 June 1984 Ro:On 840628,during Normal Operation,Standby Power Sys Shut Off & Would Not Restart.Caused by Wire Pulled Loose from Connection on Solenoid Valve.Connection Repaired & Generator Started Normally ML20084C2981984-04-17017 April 1984 Ro:On 840416,failure Occurred on Long Distance Telephone Lines Which Carry Burglar Alarm & Police Call Signals from Science Ctr to Rhode Island Electric Protective Co. Phone Lines Restored ML20083Q0121984-03-0101 March 1984 Ro:On 840229,long Distance Telephone Lines Transmitting Burglar Alarm,Power Failure,Fire & High Radiation Failed. Caused by Flooding of Phone Company Cables During Rain Storm.Message Relay Line Established ML20078B8051983-09-0808 September 1983 Ro:On 830907,hood Exhaust Blower Stopped.Caused by Shorted Electrical Feed Wire.Repairs Initiated ML20071G8001983-05-17017 May 1983 Ro:On 830516,seepage of Approx 160 cm3/h in Reactor Pool Water Discovered from Area Below Thermal Column Case.Leak Will Be Isolated to Determine Cause.Tech Specs Do Not Specify Pool Leak Rate ML20071H6921983-05-17017 May 1983 Ro:On 830516,seepage of Reactor Pool Water Discovered Below Thermal Column Case.Investigation Revealed Seepage from Horizontal Const Joint in Concrete Biological Shield. Procedures Initiated to Isolate Leak ML20072H5771983-03-10010 March 1983 Annual Rept of Changes,Tests & Experiments for Fy Ending 820630 ML20054C2551982-04-16016 April 1982 Ro:On 820416,during Startup of Reactor,Period Circuits of Wide Range Log N Channel Failed So as to Provide No Period Info to Operator or Scram Circuits,Resulting in Shutdown of Reactor ML20041F1251982-03-0505 March 1982 Ro:On 820303,instrumentation Components That Monitor Primary Coolant Flow & Core Outlet Temp Would Not Provide Scram for Power Failure.Cause Not Given.Components Reworked to Provide Scram ML20041E1991982-01-31031 January 1982 Operating Statistics,Jul 1980-June 1981. ML19290B6931979-12-0303 December 1979 Ro:On 791121,decrease in Negative Differential Pressure Discovered Between Inside & Outside of Nuclear Science Ctr Bldg.Caused by Loose Fitting Gasket on Truck Door.Gasket Adjusted.Maint Schedule Will Be Implemented ML19290B6841979-11-28028 November 1979 Ro:On 791127,pH of Secondary Water Sample Exceeded Tech Spec Limit.Caused by Failure to Initiate Automatic Blowdown of Secondary Water Sample.Importance of Procedure Stressed to Operators ML19276H0531979-02-28028 February 1979 Ri Atomic Energy Commission Nuclear Science Ctr Operating Statistics for Jul 1977-June 1978 ML19269D5381978-02-16016 February 1978 LER 78-004/03L-0 on 780109:main Steam Line Low Pressure Switches Found to Actuate at Approx 35 Psig Below Tech Spec Requirements.Caused by Limited Setpoint Drift.Existing Surveillance Program Considered Adequate 1999-08-16
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j STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Ferry Road ,,g l
Narragansett, R. I. 02882 -
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March 5, 1982 ,
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Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission IEECEfVED 9 Region 1 b 631 Park Avenue 2 MARI'57982=0 hl' King of Prussia, Pa. 19406
- a License R-95 /f Docket 50-193 %
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Gentlemen:
On March 3, 1982, during maintenance of the reactor system, we learned that components in the process instrumentation, which monitor primary coolant flow and primary coolant core outlet temperature, would not provide a scram for power failure. After approval of our Reactor Utilization Committee (safety review com-mittee), the components were reworked so that in addition to pro-viding a scram for loss of flow and high temperature, they would cause a scram for power loss to individual components.
At no time during the almost 18 years of operating history has a power failure occurred which did not shut down the reactor. In addition, at no time did process control instrumentation compo-nents fail without causing a shutdown of the reactor.
This situation was discussed by telephone with R. Starostecki, R.
Gallo and E. Greenman of NRC, Region 1 on March 3, 1982.
Very truly yours, s v:rt&M A. Francis DiMeglio Director AFD:ag cc: RUC RIAEC 8203160212 820305 }h $1 &
PDR ADOCK 05000193 S PDR