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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045H4921993-07-13013 July 1993 Special Rept:On 930603,vibration & Loose Parts Monitoring Sys Experienced Series of Invalid Alarms Attributed to Excessive Background Noise.Caused by Failure to Implement Temporary Setpoints.Alarm Levels Will Be Set ML20012C7161990-03-14014 March 1990 Special Rept:On 900202,inoperable Loose Parts Detection Sys Instrumentation Noted.Caused by Failing Accelerometer or Breakdown of Nonsafety Signal Cable.Sys Still Meets Intent of Reg Guide 1.133 by Maintaining Two Operable Channels ML20006A4971990-01-19019 January 1990 Special Rept:On 891222,valid Failure of Div 1 Diesel Generator Occurred During Div 1 Diesel Generator Start. Caused by Degraged Lubricant on Latch Mechanism Pivot Point Due to Aging.Work Order Initiated to Svc Breaker 1993-07-13
[Table view] Category:LER)
MONTHYEARML20045H4921993-07-13013 July 1993 Special Rept:On 930603,vibration & Loose Parts Monitoring Sys Experienced Series of Invalid Alarms Attributed to Excessive Background Noise.Caused by Failure to Implement Temporary Setpoints.Alarm Levels Will Be Set ML20012C7161990-03-14014 March 1990 Special Rept:On 900202,inoperable Loose Parts Detection Sys Instrumentation Noted.Caused by Failing Accelerometer or Breakdown of Nonsafety Signal Cable.Sys Still Meets Intent of Reg Guide 1.133 by Maintaining Two Operable Channels ML20006A4971990-01-19019 January 1990 Special Rept:On 891222,valid Failure of Div 1 Diesel Generator Occurred During Div 1 Diesel Generator Start. Caused by Degraged Lubricant on Latch Mechanism Pivot Point Due to Aging.Work Order Initiated to Svc Breaker 1993-07-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant1999-08-0909 August 1999 SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
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, ' o ,o THE CLEVELAND ELECTRIC ILLUMINATING COMPANY P.O. BOX 97 E PERRY, OHIO 44001 S TELEPHONE (216) 266 3737 3 ADDREBS10 CENTER ROAD FROM CLEVELAND: 4741260 3 TELEX; 241699 ANSWERBACK: CEIPRYO Al Kaplan Serving The Best location in the Nation PERRY NUCLEAR POWER PLANT vet estram i NUCLE AR GROLW p<
January 19, 1990 PY-CEI/NRR-1120L l
Document Control Desk U.S. Neclear Regulatory Commission Washington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 '
Special Report -
Valid Test Failure ,
Division 1 Diesel Generator
Dear Sir:
Attached is a Special Report concerning a valid test failure of the Unit 1 Division 1 Diesel Generator. This report satisfies the conditions of i Technical Specifications 4.8.1.1.2 and 6.9.2.
Please feel free to contact me if you have any further questions.
Very truly yours, i .
A. Kaplan Vice President Nuclear Group AK/nje Attachment cc T. Colburn P. Hiland L. Hiller (Office of Resource Management)
USNRC Region III, Regional Administrator 9001290034 900119 PDR ADOCK 05000440 s PDC
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l c o Attachment PY-CEI/NRR-1120L Page 1 of 2 t
SPBCIAL REPORT Unit 1 Division 1 Diesel Generator Valid Failure On December 22, 1989, a valid failure of the Division 1 Diesel Generator occurred while performing the Division 1 Diesel Generator Start and Load Surveillance Test. This is a valid test and failure in accordance with Regulatory Guide, R.G. 1.108 C.2.e.5. This is the third valid failure in 73 total valid tests to occur on the Unit 1 Division 1 Diesel Generator and the first failure in the last twenty valid tests.
On December 22, 1989, a valid failure of the Division 1 Standby Diesel Generator occurred while performing the Start and Load surveillance test as part of Technical Specification Action statement required due to the Division 3 Diesel Generator being declared inoperable. The engine start was normal with the acceleration and stability times for voltage and speed within specification. At 14.5 seconds after the Division 1 engine start, the generator voltage vas lost and the governor shifted to mechanical control, accelerating to the rated mechanical setpoint of 477 RPM. Voltage decay was normal for loss of excitation; however, no field reflash was exhibited. All indications on the Engine Control Panel vere normal and no alarms were received either remotely in the Control Room or locally in the Diesel Generator Room. All engine operating parameters were normal. The engine was stopped at 1415 for troubleshooting without further incident.
The troubleshooting investigation identified no deficiencies with the field breaker K1 closing coil or the field flash relay K2 coil. The generator voltage sensing relay K3 contacts closed as expected; however, at no time was the field reflashed after the loss of voltage. Because the 200 RPM relay R11 vas sealed-in, a reflash of the field should have occurred by the time generator voltage decayed to zero, provided that the field breaker K1 was closed. Troubleshooting, however, indicated that the field breaker K1 had spuriously opened.
Normally, reset of field breaker K1 is caused by operation of shutdown relay RS. Had the shutdown relay RS operated, the engine vould have been tripped.
The continued operation of the engine confirmed the field breaker K1 trip to be spurious. Maintenance replaced the defective field breaker K1 (Basler part number 9-1183-01-001) with a new component. The new K1 contactor was procured, inspected, cleaned and tested prior to installation. Two successful maintenance runs vere performed to verify proper latching on field breaker K1 prior to performance of the surveillance test for operability.
The Division 1 Diesel Generator was declared operable on December 23, 1989 at 2125.
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L Attcchment PY-CEI/NRR-1120L Page 2 of 2 Failure analysis of the original contactor on the defective field breaker l K1 revealed that the lubricant on the latch mechanism pivot point had degraded due to aging. Spring tension was unable to overcome the frictional resistance to properly extend the latching mechanism. It was concluded that the latch mechanism did not fully latch behind the trip mechanism allowing the contactor to unlatch due to normal tension and vibration. The valid test failure was considered to be an equipment malfunction attributed to insufficient maintenance and lubrication of the latching mechanism. The K1 contactor had been previously inspected during the first refueling outage (March, 1969) havever, the latch mechanism was not specified as an item requiring inspection or service.
The Division 1 Diesel Generator failed to maintain specified generator voltage and was declared inoperable on December 22, 1989 at 1400. The Division 1 Diesel Generator was subsequently declared operable on December 23, 1989 at 2125. The total out-of-service time for the Division 1 Diesel Generator was 1 day, 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, and 25 minutes.
Satisfactory operation of the trip latch mechanism on the Division 2 Diesel Generator field breaker K1 was verified on December 23, 1989. Additional corrective actions included the initiation of a work order to service the Division 2 Diesel Generator field breaker K1. This work vill be performed in the next quarterly outage currently scheduled for February 12-16, 1990.
Periodic Maintenance Instruction (PMI-088, Rev. 0), " Diesel Panel Maintenance" vill incorporate specific inspection and service requirements for both Division 1 and 2 field breakers Kl. The procedural change vill be completed by March 15, 1990.
The Division 1 Dicsel Generator Surveillance Test interval vill remain at once every 31 days in accordance with Perry Technical Specification Table 4.8.1.1.2-1.
NJC/ CODED /3085 I
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