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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML17264A9091997-06-0303 June 1997 Special Rept:On 970503,declared Fire Barrier Component (Fire Door) Inoperable.Caused by Maint Activities That Unintentionally Blocked Open Fire Door F-30.Stopped Activities Approx 1 Hr Later & Closed Fire Door F-30 ML17262A9731992-08-24024 August 1992 Special Rept:On 920810,discovered That B Reactor Compartment Cooling Fan Cooling Coils Developed SW Leak. Work Order Package 9201643 Developed to Perform Tube Repair, Per Procedure EM-745, Repair of Containment Fan.... ML17262A6271991-10-24024 October 1991 Ro:On 911011,pin Hole Leak in 1/2-inch Copper Tubes Between 3-inch Carbon Steel Discharge Header & Cooling Coils on Fan Cooler B Discovered.Caused by Defect in Tubes.Work Request/ Trouble Rept Initiated.Reported Per NRC Bulletin 80-24 ML17250A3181980-06-0303 June 1980 RO 80-05:on 800603,during Performance of Procedure S-30.1, Breaker for A-loop Accumulator Discharge valve,MDV-865 Discovered in Closed Position.Cause Not Stated.Breaker Immediately Placed in Proper Position ML19249E1361974-02-0707 February 1974 RO 74-02:refueling Outage Required Eddy Current Testing of Steam Generator Tubes.Test Results to Date Indicate Wastage Problem to Be Localized & More Severe in Steam Generator a Hot Leg.No Primary or Secondary Leakage in Generators 1997-06-03
[Table view] Category:LER)
MONTHYEARML17264A9091997-06-0303 June 1997 Special Rept:On 970503,declared Fire Barrier Component (Fire Door) Inoperable.Caused by Maint Activities That Unintentionally Blocked Open Fire Door F-30.Stopped Activities Approx 1 Hr Later & Closed Fire Door F-30 ML17262A9731992-08-24024 August 1992 Special Rept:On 920810,discovered That B Reactor Compartment Cooling Fan Cooling Coils Developed SW Leak. Work Order Package 9201643 Developed to Perform Tube Repair, Per Procedure EM-745, Repair of Containment Fan.... ML17262A6271991-10-24024 October 1991 Ro:On 911011,pin Hole Leak in 1/2-inch Copper Tubes Between 3-inch Carbon Steel Discharge Header & Cooling Coils on Fan Cooler B Discovered.Caused by Defect in Tubes.Work Request/ Trouble Rept Initiated.Reported Per NRC Bulletin 80-24 ML17250A3181980-06-0303 June 1980 RO 80-05:on 800603,during Performance of Procedure S-30.1, Breaker for A-loop Accumulator Discharge valve,MDV-865 Discovered in Closed Position.Cause Not Stated.Breaker Immediately Placed in Proper Position ML19249E1361974-02-0707 February 1974 RO 74-02:refueling Outage Required Eddy Current Testing of Steam Generator Tubes.Test Results to Date Indicate Wastage Problem to Be Localized & More Severe in Steam Generator a Hot Leg.No Primary or Secondary Leakage in Generators 1997-06-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999 Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis ML17265A7621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With ML17265A7531999-09-23023 September 1999 Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped 05000244/LER-1999-011, :on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With1999-09-22022 September 1999
- on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With
ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr 05000244/LER-1999-004, :on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed1999-08-24024 August 1999
- on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7381999-08-16016 August 1999 SE Approving Licensee Requests for Relief 37,38,39,40 & 41 for Re Ginna Nuclear Power Plant for Third & Fourth 10-year Inservice Insp Interval ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With ML17265A7291999-07-29029 July 1999 Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent 05000244/LER-1999-007, :on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians1999-07-23023 July 1999
- on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7131999-07-22022 July 1999 Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521 05000244/LER-1998-003, :on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored1999-07-22022 July 1999
- on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7031999-07-19019 July 1999 LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp ML17265A7121999-07-19019 July 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 05000244/LER-1999-010, :on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With1999-07-15015 July 1999
- on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With
ML17265A7661999-06-30030 June 1999 1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With ML17265A7011999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Re Ginna Npp.With 05000244/LER-1999-001, :on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With1999-06-21021 June 1999
- on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With
ML17265A6831999-06-17017 June 1999 Safety Evaluation Re Response to Supplement 1 to GL 87-02 for Ginna Nuclear Power Plant on USI A-46 ML17265A6761999-06-16016 June 1999 Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis 05000244/LER-1999-009, :on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With1999-06-0202 June 1999
- on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With
ML17265A6681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 05000244/LER-1999-008, :on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With1999-05-27027 May 1999
- on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With
ML17265A6651999-05-27027 May 1999 Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001 05000244/LER-1999-006, :on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With1999-05-21021 May 1999
- on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With
ML17265A6591999-05-17017 May 1999 Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested 05000244/LER-1999-005, :on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With1999-05-13013 May 1999
- on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With
ML17265A6381999-05-0707 May 1999 Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG ML17265A6391999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With ML17265A6341999-04-23023 April 1999 Safety Evaluation Supporting Amend 74 to License DPR-18 ML17265A7251999-04-23023 April 1999 Rev 1 to Rept of Development of Rg&E Seismic Safe SD Equipment & Relay Review Lists for USI A-46 ML17265A6361999-04-23023 April 1999 Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001 ML17265A6301999-04-18018 April 1999 Rev 1 to Cycle 28 COLR for Re Ginna Npp ML17265A6251999-04-15015 April 1999 Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment ML17265A6551999-04-0909 April 1999 Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open ML17265A6221999-04-0808 April 1999 Safety Evaluation Approving Rg&E Proposed Alternative to Exam Requirement of ASME Code,Section Xi,For Circumferential Shell Welds of RPV for Third 10-year Insp Interval ML17265A6181999-04-0606 April 1999 Safety Evaluation Concluding Proposed Rev 26 to Rg&E QAP for Station Operation Incorporating Reductions in Stated Commitments Will Continue to Comply with QA Criteria of App B to 10CFR50 & Therefore,Acceptable ML17265A6241999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ginna Station.With ML17265A6291999-03-31031 March 1999 Rev 0 to Cycle 28 COLR for Re Ginna Npp 05000244/LER-1999-003, :on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With1999-03-31031 March 1999
- on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With
05000244/LER-1999-002, :on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With1999-03-29029 March 1999
- on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With
ML17265A5621999-03-0303 March 1999 Safety Evaluation Supporting Amend 73 to License DPR-18 ML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation ML17265A5581999-03-0101 March 1999 Rev 1 to Gnpp Internal Flooding Probabilistic Safety Assessment Final Rept ML17265A5961999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With ML17265A5541999-02-25025 February 1999 Safety Evaluation Approving Request to Apply leak-before- Break Status to Portions of Plant Residual Heat Removal Sys Piping ML17265A5341999-02-0404 February 1999 Safety Evaluation Granting Request Relief 36 from ASME Code Section XI Requirements for Plant Third 10-yr ISI Interval ML17265A5371999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr IR 05000244/19912011999-01-29029 January 1999 Safety Evaluation Accepting Licensee 920406 & 981104 Submittals Re Number of Pumps Required for Post LOCA Recirculation Phase Per Action Items Identified in Insp Rept 50-244/91-201 1999-09-30
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REGUL~RY INFORMATION DISTRISUTISYSTEM (RIDE)
ACCESSION NBR:8906280101 DOC.DATE: 89/06/20 NOTARIZED: NO DOCKET FACIL:50-244 'Rooert Emmet Ginna Nuclear Plant, Unit 1, Rocheste" G 05000244 AUTH.NAM AUTHOR AFFILZATZON SPECTOR,S.M. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Conr,rol Branch (Document Control Desk)
SUBJECT-: RO:on 890619,B & C sa etv injection pump recirculation valves discovered locked full open at approx 99% power.
DISTRlBUTZON CODE: E22D COPIES RECEIVED:LTR t ENCL t SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER)-, Incident Rpt, etc.
fi NOTES:License Exp date 'n accordance ~rith 10CFR2,2.109(9/19/72). 05000244 I5 RECIPIENT COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL ZD CODE/NAME LTTR ENCL
.PD1-3 LA 1 1 PD1-3 PD 1 JOHNSON,A .1 1 INTERNAL: ACRS MZCHELSON 1 1 ACRS MOELLER 2 ACRS WYLIE 1 1 AEOD/DOA 1 AEOD/DSP/TPAB 1 AEOD/ROAB/DSP 2 DEDRO 1 1 ZRM/DCTS/DAB 1 NRR/DEST/ADE 8H 1 1 NRR/DEST/ADS 7E 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 NRR/DEST/ICSB 7 1 NRR/DEST/MEB 9H 1 NRR/DEST/MTB 9H 1 NRR/DEST/PSB 8D 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 NRR/DLPQ/HFB 10 NRR/DOEA/EAB NUDOCS-ABS RAC ll 1 1
1 NRR/DLPQ/PEB NR REP RPB BEG F~~r 10
'0 02 1
2 1
RES/DSIR/EZB 1 1 RES/DSR/PRAB 1 RGNl "ILE 01 1 1 R
EXTERNAL: EG&G WZLLIAMSFS 4 4 FORD BLDG HOY,A L ST LOBBY HARD 1 1 LPDR I NRC PDR 1 1 NSZC MS YS G NSIC MURPHY,G.A 1 D h
NOZE K) ALL 'KIDS" RZCIPIENIS:
PLEASE HELP US 'IO REDUCE RESTE.'DNI'ACr 'IHE DOCUMERI'ONIROL DESK, RXN Pl-37 (EXT. 20079) To EIJKQRTE VXK NAME PRES DIPHGBVPIGN LISTS FOR DOCQQZZS KXJ DOHFT NEEDt TOTAL NUMBER OF COPIES REQUZR=D: LTTR 43 NCL 42
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ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TE'+ Obf iici conc "~ < 5 "G.2 700 June 20, 1989 U.S. Nuclear'egulatory Commission Document Control Desk Washington, DC 20555
Subject:
Follow-up Summary of Close-out of June 19, 1989 Unusual Event R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with NUREG 0654, FEMA-Rep-l, Rev. 1 reporting requirements which requires a written summary of "close-out. or class reduction conditions", the attached close-. out summary for the June 19, 1989 Unusual Event is hereby submitted.
C This event has in no'ay affected the public's health and safety.
Very truly yours, Stanl y M. Spector Plant Manager Ginna Station xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Resident Inspector R. C. Mecredy D. W. Burke CyPgr20 aeoszsoioi ADOCV
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PDR egu S
Attachment to Close-out of June 19 1989 Unusual Event On June 19, 1989 at approximately 1440 EDST with the reactor at approximately 99% power, it was discovered that the "B" and "C" safety injection pump recirculation valves- were locked full open rather than throttled to 50 gpm as required. The "B" and "C" safety injection pumps were immediately declared inoperable and a power reduction was commenced to comply with the plant Technical Specification.
At approximately 1515 EDST, the operations shift supervisor declared an Unusual Event in accordance with SC-100, "Ginna Station Event Evaluation and Classification>>, EAL: Loss of Engineered Safety Features; Exceeding a Limiting Condition for.
operations on a safety system requiring a plant shutdown. Tech Spec Section 3.3 Emergency Core Cooling System. All offsite notifications were made per SC-601, "Unusual Event Notifications".
At approximately 1615 EDST; subsequent to the satisfactory testing and throttling of the "B" and "C" safety injection pumps recirculation valves to 50 gpm, the "B" and "C" safety injection pumps were declared operable and the load reduction stopped..
With the "B" and "C" safety injection pumps declared operable and the load reduction stopped, the operations shift supervisor, with approval and concurrence from the Plant Manager Ginna Station, the Superintendent Ginna Production, the assistant operations supervisor, PORC and the duty engineer, declared the Unusual Event terminated't 1626 EDST, June 19, 1989 in accordance with SC-110, "Ginna Station Event Evaluation for Reducing the Classification".
All offsite notifications were made of the Unusual Event termina-tion and the plant was subsequently returned to approximately full power.