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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20198Q6041997-11-0505 November 1997
Ro:On 971024,one Kw Interlock Did Not Meet Definition of Operable Intended Function,Contrary to TS 3.2.4.Caused by Lack of Detail & Precision in Some of Maint & Surveillance Procedures.Interlock Setpoints Adjusted
ML20058P4911993-10-19019 October 1993
Ro:On 931012,discovered That Design Feature in TS Incorrect W/Respect to Min Free Vol in Reactor Bay.Reactor Secured Until Discussion Held W/Nrc.Ts Change W/Sar Revs Will Be Requested
ML20117A6341992-11-25025 November 1992
Ro:On 921005,inadvertent Partial Withdrawal of One Control Rod Occurred When Operator Changed Control Sys Parameters W/ All Rods Fully Inserted.Caused by Inadequate Procedural Controls.Procedural Controls Re Software Tuning Implemented
ML20067B3241991-01-30030 January 1991
Ro:On 910122,reactor Operator Stepped Out of Reactor Control Room to Provide Experimeters W/Access to Reactor Bay. Training Procedure Explaining Event Being Circulated to All Licensed Reactor Operators
ML20203N9021986-04-28028 April 1986
Ro:On 860418,during Experiment to Check Operation of New Instrumented Fuel Element,Temp Scram Sys Could Not Have Performed Intended Safety Function.Caused by Std Operating Procedure SOP-2 Not Being Followed.Procedure Emphasized
ML20117J4991985-05-0707 May 1985
Ro:On 850503,during Annual Fuel insp,12 Weight % Triga Fuel Element in Ring B of Core Found Swollen & Unable to Be Removed from Grid.Integrity of Fuel Element Intact.Element to Be Stored & No Longer Used at Facility
1997-11-05
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20198Q6041997-11-0505 November 1997
Ro:On 971024,one Kw Interlock Did Not Meet Definition of Operable Intended Function,Contrary to TS 3.2.4.Caused by Lack of Detail & Precision in Some of Maint & Surveillance Procedures.Interlock Setpoints Adjusted
ML20058P4911993-10-19019 October 1993
Ro:On 931012,discovered That Design Feature in TS Incorrect W/Respect to Min Free Vol in Reactor Bay.Reactor Secured Until Discussion Held W/Nrc.Ts Change W/Sar Revs Will Be Requested
ML20117A6341992-11-25025 November 1992
Ro:On 921005,inadvertent Partial Withdrawal of One Control Rod Occurred When Operator Changed Control Sys Parameters W/ All Rods Fully Inserted.Caused by Inadequate Procedural Controls.Procedural Controls Re Software Tuning Implemented
ML20067B3241991-01-30030 January 1991
Ro:On 910122,reactor Operator Stepped Out of Reactor Control Room to Provide Experimeters W/Access to Reactor Bay. Training Procedure Explaining Event Being Circulated to All Licensed Reactor Operators
ML19327A8171989-10-11011 October 1989
Ro:On 891005,failure to Perform Reactor Checkout Prior to Operations Results in Reactor Failing to Fulfill Surveillance Requirements in Facility Tech Specs Sections 4.2.3.a,4.2.3.c,4.2.4.a,4.3.3 & 4.6.1
ML20236J7551987-06-30030 June 1987
Thirty-Second Annual Progress Rept,Penn State Breazeale Reactor,Jul 1986 - June 1987
ML20203N9021986-04-28028 April 1986
Ro:On 860418,during Experiment to Check Operation of New Instrumented Fuel Element,Temp Scram Sys Could Not Have Performed Intended Safety Function.Caused by Std Operating Procedure SOP-2 Not Being Followed.Procedure Emphasized
ML20117J4991985-05-0707 May 1985
Ro:On 850503,during Annual Fuel insp,12 Weight % Triga Fuel Element in Ring B of Core Found Swollen & Unable to Be Removed from Grid.Integrity of Fuel Element Intact.Element to Be Stored & No Longer Used at Facility
1997-11-05
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. 1 PENNSTATE '%f%s.
r College of Engineering Breazeale Nuclear Reactor Building j Radiation Science and Engineenog Center The Pennsylvania State University l University Park. PA 16802-2301 May 2,1997 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Re: Reportable Occurrence: Tech Spec Violation l License R-2, Docket No.50-005 l
Dear Sir or Madame:
As per the requirements of sections 6.5.2 and 6.6.2 of the Technical Specifications for the Pennsylvania State University Breazeale Reactor, this letter is to infami the NRC of a reportable occurrence on May 1,1997.
On May 1,1997 dtring the conduct of SOP-2, Reactor Checkout, step M-6 which collects PSBR water data was not completed. This was discovered on May 2,1997 during the conduct of SOP-2. Tech Spec 4.3.3, Pool Water Conductivity, requires pool water conductivity to be measured and recorded daily when the reactor is to be operated. During that day, the reactor was operated. Information exists which demonstrates the coolant conductivity limits of Tech Spec 3.3.5 were met at all times.
It is unknown whether the missed surveillance was due to negligence or mistake. There is no evidence it was intentional. The licensed operators responsible were not available on May 2, 1997 for interviews. This will be done on their return to work. AP-4, Identification, Evaluation and Documentation of Safety System Failures, Abnormal Events, and Operational Events was completed to the extent feasible at this time; it was ascertained conductivity was and had been within spec; and reactor startup was authorized by the SRO with review and approval of the Manager of Operation and Training, and the Acting Director.
A further report with investigation results, root cause, and corrective actions will be provided to the NRC by May 16,1997.
Sincerely, /
b,krab @
Dr. C. Fredrick Sears Director -f
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