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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
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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
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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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l STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS
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Rhode Island Atomic Energy Commission NUCLEAR SCIENCE CENTER South Ferry Road Narragansett, R. I. 02882 Decec er 3, 1979 U. S. Nuclear Regulatory Cc::missicn Office of Inspection & Enforcerent 631 Park Ave.
King of ?"ussia, Pa. 19hC6 Gentleren- N r.se R-95 Dccket 50-193 Tne technical specifications, Secticn K.3.b. (2) (a) and (b), pages 24 and 25 require that the building cleanup system te tested weekly and that the negative differential pressure between the inside and cutside of the building be at least 0.5 inches of water.
On Thursday, Noved er 29, 1972, during the weekly test of the s'/ stem, .
the differential pressum was measured at 0.4 inches of water. Du-ing the test en Noved er 21, 1979, the differential pressure was measund as 0.6 inches of water. ?.ese reasurerents a"e made bercre sta-tup cf the mactor.
It was determined that the cause of the decrease in the differential pressure was a lecse fitting portien of the gasket en the truck dcor.
After adjusting tne gasket, the differential pmssure increased to 0.8 inches differential pressure.
To I:dnimite the chance of a recurrance, a schedule & procedures for the inspection and maintenance of the gaskets en all buildire pene-trates will be develcped and ir:pleranted.
21s matter was discussed with Harmcn Kester by phcne On Noveder 29, 1979 Very truly ycurs, f'.,
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A. Jrancis DiMeglio Director Q
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