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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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, .- OCT 03 '97 02 0TM PAD SCittfGR CCf41CR P.2/2 PENNSTATE - - -
Remon science and r.ngenes Cemer ($lal 665 6s51 Ceners of ragineenris The Fenmyiv.na sim Universo i October 3,1997 aiem ie u.cie., ne. w suiiding Unnemty Puk h 16602 2MI U.S. Nuclear Regulatory Commission Document Cont 01 Desk
- Washington, DC 20555 Re: Reportable Occunence: V!olation of Tech Spec 3.2.6 License No. R 2, Docket No 50 005
Dear Sir or Madame:
his letter confirms my telephone call of this moming,3 October 1997, to Marvin Mendonca regarding an operational event at the Penn State Ilreareale Reactor Durmg that callit was determined that the event was a repostable occunence. On 29 September 1997 it was observed that the Transient Rod (TR) exhibited a sluggish response to a freedom of motion scrarn check conducted during luct movements. The reactor was immediately removed from operation and the TR scram time was measured. It was between one and two seconds; this is greater than the one second requirement of Tech Spec (TS) 3.2.6. Inspection, cleaning, and lubncation of the TR mechanism was performed and subsequent testmg indicated acceptable scram times. The reactor was then retumed to operation. On 2 October 1997 it was decided to perform a further inspection, cleaning and lubrication. Following that maintenance the scram tirnes were further improved. A weekly surveillance testing of the TR scram performance has been initiated to provide monitoring and trending so as to determine what further corrective action may be appropnate. Contact is also being made with the reactor vendor to collect more information. The cause for the sluggish response appears to be an o ring seal at the bottom of the air cylinder for the TR.
At all times the Safety, Shim, and Regulating rods were operable meeting the TS 3.2.1 requirement for a minimum of three operable conti01 rods. Analysis was performed to assure the requd rements of TS 3.1.3 regarding shutdown margin were also met even if the TR had failed to scram. The shutdown margin was assured for both actual operating rod positions as well as for having the most reacuve rod fully withdrawn. Note that at no time has the TR failed to scram. Also, prior to the observations of 29 Septembcr 1997 there were no indications of TR 7toblems. The TR scram time had been measned in June as part of the periodic surveillance and tie scrsm time was acceptable.
This letter is being faxed today,3 October 1997, to Marvin Mendonca and Thomas Dragoun. A 14 day written report, as required by TS 6.6.2, will be submitted.
Sincerely,
!d 0,9MM bM-. e C. Frederick Sears Director, RSEC M' g CFS/pjs 4052.97 T. Dragoun, NRC, Region I pc:
M. Mendonca, NRC, Headquarters hhNhhl*))
E. Klevans O_ McMurtry R. Erickson coll!gMh$ leering An ret opmung UnNenHy 9710060153 971003 PDR ADOCK 05000005
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