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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
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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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PEMSTATE 2L q na.ia 4. shirn3 Semor Vase h. sident f.w Rwmii ue renn#ama sue t:mscrsny 207 Old Mam and Dean of the Oraduate ihoW l'msersity Park, PA 1MU2-1$03 July 26,1994 US Nuclear Regulatory Commission Document Control Rcx>m Washington, DC 20555 Re: Report of Incident at the Penn State Breazeale Reactor License Number R-2, Docket Number 50-05 On the morning of July 21,1994, the reactor was being checked out following a power outage caused by an electrical stomi the previous evening. As part of the checkout procedure, the transient control rod was scram tested. Technical Specification 3.2.6 requires as a limiting condition for operation that rods scram in less than one second. The transient rod did not fully insert and thereby failed the test. Technical Specification 1.1.33.b defines operation in violation of a limiting condition for operation a reponable occurrence which must be reported in accordance with Specification 6.6.2.a.(3). While it is not clear that a degraded condition existed during operation it is being reported for information purposes.
Immediately following the failure to fully scram the transient rod was inspected. It was found that a bolt on the control rod drive had hooked on a nearby wire which prevented full travel. The wire was re-routed and properly secured. Subsequent testing venfied proper operat'on of the control rod. The control rods had been successfully scram tested on June 26,1994. Maintenance since that time, some as late as the day prior to the incident, had the potential to move the wire in question. IIad the condition persisted during operation, the wire would very likely have been pulled during normal transient rod motion, suggesting that the condition did not exist for an extended thne.
In addition to correcting the situation, staff personnel have been briefed on the incident, the patential consequences, the root cause, and the need for care in routing wires to prevent recurrence.
Sincerely yours, David A. Shirley Senior Vice President for Research and Dean of the Graduate School pc: Region 1 Administrator US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 DAS/ld14085.94 [
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