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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML17265A7131999-07-22022 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 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 ML17264A9091997-06-0303 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 ML17264A8941997-05-0707 May 1997 Special Rept:On 970407,inoperable Fire Suppression Sprinkler Sys Hourly Tour Was Suspended Prematurely.Caused by Personnel Error.Action Rept Initiated & Fire Watch Personnel Were Advised That Operations Approval Is Required ML17264A8411997-03-24024 March 1997 Special Rept:On 970225,declared Sping Air Ejector Radiation Monitor R-15A Inoperable Due to Calibr Activities.Replaced Detector & Cable for Channel 9,tested Satisfactorily & Returned R-15A to Service ML17264A8281997-03-0303 March 1997 Special Rept:On 970202,Plant Process Computer Sys Received Alarms on All Points for Plant Vent Radiation Monitor R-14A. Skid Was Flushed & Desired Flow Rate Was Reestablished.Skid Was Taken OOS on 970210.Conducted Monitoring of R-14A ML17264A7481996-11-27027 November 1996 Special Rept:On 961015,identified Problem W/Automatic Release Actuation of Sys Deluge Valve & Sys Declared Inoperable.Compensatory Actions Will Remain in Effect Until All Four Suppression Sys Restored to Operable Status ML17264A3761996-02-21021 February 1996 Special Rept:On 960115,diesel Fire Pump & Controller Held & Declared Inoperable for Greater than Seven Days to Install Cummins NT855-F6 Fire Rated Diesel Driver & Ul Listed Firetrol FTA-1100 Micro Controller.Mod Completed on 960124 ML17264A2841995-12-0404 December 1995 Special Rept:On 951027,staff Discovered That Portion of Overall Basis for Approval of Exemption Was Not Being Met Due to Removal of Shield Wall.Inserted Kaowool within 6 Inch Gap Now Being Used as Temporary Seal ML17263A6991994-06-14014 June 1994 Close-out of Class Reduction Conditions:On 940610,motor Was Started & Sparks Were Noticed & Plant Was in Hot Shutdown ML17263A4291993-10-14014 October 1993 Special Rept:On 930930,operators Conservatively Declared Containment Isolation Valves Inoperable.Containment Recirculation Fans Replaced During 1993 Outage & Motor Coolers for Containment Recirculation Fans Replaced ML17263A3101993-07-0202 July 1993 Ro:On 930629,malfunction in Rod Control Sys Caused Minor Misalignment Between Control Rods in Group 1 & 2 of Bank D. Cause Under Investigation.Control Rods Will Be Maintained in Manual Control & Bank D Rods Will Be Exercised Daily 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.. ML17262A9721992-08-24024 August 1992 Special Rept:On 920813,D Containment Recirc Fan Cooler Declared Inoperable Due to Svc Water Leak in D Containment Recirc Fan Cooling Coils.Work Order Package 9201647 Developed to Perform Repair,Per Procedure EM-745 ML17262A9291992-07-16016 July 1992 Special Rept:On 920702,containment (CNMT) Sump a Actuation Received Due to Svc Water Leak Inside Containment. Alternatives to Redesign & Replacement of CNMT Recirculation Fan Cooling Coils Will Be Considered During 1994 Outage ML17262A8681992-05-20020 May 1992 Special Rept:On 920413,motor-driven Fire Pump Declared Inoperable,Disabling auto-start Logic for More than 7 Days. Domestic Water Supply cross-tied to Fire Water Sys.Pump Declared Operable on 920513 & cross-tie Removed 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 ML17262A6021991-09-17017 September 1991 Special Rept:On 910903,svc Water Leak Inside Containment Sump a Pump Identified.Abnormal Procedure AP-SW.1, Svc Water Leak, Entered.Work Order Package Prepared to Identify & Repair Svc Water Leak ML17262A4331991-04-0303 April 1991 Followup Rept of 910403 Event Re Removal of RHR Sys & Component Cooling Water Sys from Svc Due to Packing Leak from MOV-738B.Valve Manually Placed on Backseat & Leak Terminated ML17261B1471990-08-23023 August 1990 Special Rept:On 900717,fire Suppression Sys Inoperable for More than 7 Days W/Redundant Component.Replacement of Defective B Batteries Delayed Pending Receipt of Batteries for Both Banks.Limiting Condition Ended on 900724 ML17250B1821990-05-30030 May 1990 Special Rept:On 900430,RCS Pressure Transient Occurred Due to Excess Letdown Being Ineffective at Lower Pressures. Operating Procedures Revised to Alert Operators on Effective Methods of Pressure Control Under Conditions ML17261B0091990-03-16016 March 1990 Special Rept:On 900213,inoperable Fire Damper I-411-21-P Found.Caused by Improper Damper Installation.Replacement Damper in Procurement Process & Will Be Installed by Jul 1990 ML17250A9041989-07-31031 July 1989 Ro:On 890729,control Room Received Annunciator Alarm, Indicating Failure of Microprocessor Rod Position Indication Sys & Disabling CRT & Plant Process Computer Sys.Unusual Event Declared & Terminated on 890730 ML17251A5481989-06-20020 June 1989 Ro:On 890619,safety Injection Pump Recirculation Valves B & C Discovered Locked Full Open at Approx 99% Power.Power Reduction Commenced to Comply W/Tech Spec.Testing & Throttling of Safety Injection Pumps B & C Accomplished ML17309A4151988-12-22022 December 1988 Followup Summary of Closeout of Ro:On 881222,onsite Medical Emergency Declared Due to Large Filter Falling on Contractor Workman Lower Leg.Injured Worker Found Not to Be Contaminated & Unusual Event Terminated ML17251A3691988-11-23023 November 1988 Special Rept:On 881018,turbine Driven Auxiliary Feedwater Pump Inoperable Per Procedure A-52.4.Existing Check Valve Leakage Indicated by Higher than Ambient Temp in Turbine Driven Auxiliary Feedwater Discharge Piping ML17251A3451988-11-0505 November 1988 Ro:On 881104,automatic Flow Alarm Received in Control Room on S-05.Caused by Inadvertent Operation of Control Station by Personnel Working in Area.No Fire Existed ML17251A2791988-09-22022 September 1988 Closeout Ro:On 880918,security Reported Smelling Smoke in Security Diesel Generator Room.Smoke Observed in Electrical Panel & All Power to Panel Terminated.Fire Brigade Captain Declared Fire Out ML17251A2621988-09-0909 September 1988 Ro:On 880908,info on Bomb Threat to Util Received from Wayne County Sheriff Ofc.Original Threat Received by Monroe County & Rochester Police Dept.Unusual Event Declared Per SC-100 & Offsite Notifications Made Per SC-601 ML17251A1761988-07-18018 July 1988 Ro:On 880716,electrical Fault Caused Five Main Breakers in Substation to Trip Open,Resulting in Loss of Approx one-half of Transmission Capability of Substation.Caused by Exploding Circuit Breaker.Offsite Power Restored ML17251A1691988-07-0707 July 1988 Special Rept:On 880516,turbine Driven Auxiliary Feedwater Sys Inoperable During Period from 880516-25.Valve V-3504B Operated W/Notable Resistance.Procedure A-52.4 Revised to Incorporate Check Valve ML17251A9871988-03-15015 March 1988 Ro:On 880314,radiation Process Monitor R-15 Alarmed, Indicating Possible Steam Generator Tube Leak.Leak Confirmed by Analysis of Steam Generator Blowdown & Air Injector Sys Grab Samples.Reactor Shut Down ML17251A9341988-02-10010 February 1988 Ro:On 880209,health Physics Technician Got Slightly Contaminated About Face & Head.Caused by Technician Falling Approx 15 Ft Inside Containment Vessel Loop Reactor Coolant Pump B Seal Area.Technician Taken to Hosp & Decontaminated ML17251A3671987-10-0505 October 1987 Special Rept:On 870630 & 0713,potential Problems W/Fire Doors Due to Several Small Door Skin Spot Weld Fractures Identified.Caused by Inability of Hydraulic Door Closer to Control Door Operation.Doors Repaired ML17261A4671987-04-21021 April 1987 Ro:On 870420,truck Bomb Threat Received.Armed Security Personnel Posted at Site Entrances.Security Threat Did Not Materialize & Plant Resumed Normal Operations ML20207R7521987-03-0909 March 1987 Ro:On 870207,MSIV Failed to Close During Plant Shutdown. Caused by Binding of Valve Disc on Partially Removed Valve Stop.Disc Stop Matl Removed & Valve Tested.Sketch of Valve & Stop Encl ML20207C8141986-12-22022 December 1986 Ro:On 861023 & 1128,RCS High Pressure Transient Occurred. Caused by Lifted Pressurizer PORV Due to Internal Event.More Specific Info Re Events Can Be Found in LERs 86-008 & 86-011 ML20215D6231986-12-11011 December 1986 Followup Ro:On 861128,operator Inadvertently Closed Main Steam Line Isolation Valves 3516 & 3517 Instead of Containment Vessel Depressurization Valves,Causing Pressurizer High Pressure Reactor Trip ML20204F9221986-07-29029 July 1986 Ro:On 860729,manual Reactor Trip Initiated When Large Quantity of Steam Found Rising Over Turbine Bay Area.Caused by Leak from Moisture Separator Reheater Drain Line 2A to High Pressure Feedwater Heater 5B.Drain Lines Repaired ML20138Q8751985-11-0707 November 1985 Followup Summary:On 851106,alarm & Deluge of Fire Sys S-05 Received in Control Room.Caused by Spurious Signal Spike on Second Alarm Module.Investigation on Failure Mode of Fire Sys Continuing.Cable Tunnel Dried Out ML20128L9181985-07-12012 July 1985 Ro:On 850701,containment Vessel Sump Pump Actuation Interval Decreased Significantly from Normal.Caused by Svc Water Leak.Fan Cooler Inspected & Repaired ML20083P8141984-03-20020 March 1984 Ro:On 840307,during Drainage of RCS to Holdup Tanks,Rhr Containment Sump B Suction Valves MOV 851 a & B Opened Before Valve 850 a Closed,Causing Drainage of RCS Into Sump B ML20087P7331984-02-21021 February 1984 Ro:Providing Sequence Summary of Closeout or Class Reduction Condition for Unusual Event on 840219 Re out-of-svc Accumulators.Accumulators Returned to Svc & Declared Operable ML20087P9711984-01-27027 January 1984 Ro:On 831228,turbine Driven Auxiliary Feedwater Pump Steam Stop Valve Found in Tripped Position,Although Control Room Indication Indicated Valve Open.Caused by Contractor Stepping on Valve Trip Mechanism ML17255A4931983-10-0707 October 1983 Ro:On 831007,seismic Event Occurred in Upstate Area of Ny. Movement Not Noted by Control Room Operators.Unusual Event Declared & Earthquake Emergency Plan Initiated.Plant Tour Indicated No Damage ML20077N5901983-08-31031 August 1983 Ro:On 830303,diesel Fuel Oil for Fire Pump Found Below Viscosity Limit.Caused by Delays in Transporting Sample to Lab for Analysis.Procedures to Expedite Resampling & Analysis Being Reviewed ML20072N5891983-07-0808 July 1983 Ro:On 830609,during Safety Injection Functional Test,When Safety Injection Signal Initiated by Simulating High Containment Pressure,Charging Pump 1C Did Not Trip, Causing Operation of Reactor Overpressure Protection Sys ML20072U5941983-03-31031 March 1983 Ro:On 830331,health Physics Technician Fell 40 Ft to Floor of Reactor Cavity.Individual Removed from Area & Taken to Hosp to Be Treated for Serious Injuries & Decontaminated ML20028G2491983-01-26026 January 1983 RO 83-008/01:on 830125,emergency Diesel Generator Start Relay (R-1,R-2) Indicating Lights Found Off,Causing Loss of Permissive Start Relays.Caused by Personnel Error.Relays Reset.Memo Will Be Issued Describing Incident ML20083P1021983-01-21021 January 1983 RO 83-006/01:on 830120,alarm Received in Control Room Indicating Low Screenhouse Water Level of 20 Ft,Rendering Fire Suppression Water Sys Inoperable.Addl Info Will Be Presented in 14-day Written Rept 1999-07-22
[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 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
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 ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp 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 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 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 ML17265A6341999-04-23023 April 1999 Safety Evaluation Supporting Amend 74 to License DPR-18 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
ML17265A5941999-03-0808 March 1999 Safety Evaluation Accepting Request for Relief 34 from ASME Code Section XI Requirements for Plant Third 10-yr ISI Interval 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 1999-09-30
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ACCELERATED DISIBUTION DEMONSTRlON
'SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8803240270 DOC.DATE: 88/03/15 NOTARIZED: NO DOCKET g
FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION SNOW,B.A.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
RO:on 880314,radiation process monitor R-15, alarmed indicating possible steam generator tube leak.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:
,TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 S
RECIPIENT ID CODE/NAME PDl-3 LA STAHLE, C INTERNAL: ACRS MICHELSON AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS7E4 NRR/DEST/ESB 8D NRR/DEST/MEB9H3 NRR/DEST/PSB8D1 NRR/DEST/SGB 8D NRR/DLPQ/QAB10A NRR/DREP/RABlOA NRR/DRISJSIB9A1 02 RES/DE/EI B RGNl FILE 01 EXTERNAL: EGGG GROH,M H ST LOBBY WARD NRC PDR "NSIC MAYS,G COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD1-3 PD ACRS MOELLER AEOD/DSP/NAS AEOD/DSP/TPAB DEDRO NRR/DEST/CEB8H7 NRR/DEST/ICSB7A NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB10D NRR/DOEA/EAB11E NRR/DREP/RPB10A NRR/PMAS/ILRB12 RES TELFORD,J RES/DRPS DIR FORD BLDG HOY,A LPDR NSIC HARRIS,J COPIES LTTR ENCL 1
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 45 ENCL 44
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)
ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 1Cl.C>eel II ARCA CO>>C 1IC 546-27C<
March 15, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Sub) ect:
Follow-up Summary of Close-out of March. 14, 1988 Unusual Event R.E.
Ginna Nuclear Power Plant Docket No. 50-244 In accordance with NUREG 0654 reporting requirements which requires a written summary of "close-out or class reduction conditions," the attached close-out summary for the March 14, 1988 Unusual Event is hereby submitted.
This event has in no way affected the public's health and safety.
Very truly yours, Bruce A. Snow Superintendent of Nuclear Production Attachment XCA U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Resident Inspector SS03240270 SS0315 PDR ADOCK 05000244
'CD pgss 773< I~
Attachment to Close-out of March 1
1988 Unusual Event R E.
Gonna Nuclear Power Plant Docket No. 50-244 On March 14, 1988 at approximately 1409 EST Radiation Process Monitor R-15 (Condenser Air Ejector) alarmed indicating a possible primary to secondary Steam Generator Tube Leak.
At this time radiation process monitor R-19 (Steam Generator Blowdown) was out of service for maintenance so confirming indication from this monitor could not be obtained.
At approximately 1500 EST R-19 (Steam Generator Blowdown) monitor was returned to service thus adding additional monitoring of the Steam Generator Tube Leak.
At 1515 EST air ejector and Steam Generator Blowdown grab samples were taken and analyzed confirming a primary to secondary Steam Generator Tube Leak of approximately 60 cc/min (i.e.
.016 gpm) and that the tube leak was in the "B" Steam Generator; At 1600 EST a meeting was held between the Plant Superintendent and department managers to plan for a forced outage to investigate and repair the "B" Steam Generator Tube Leak.
At approximately 1830 EST a "B" Steam Generator sample iodine calculation indicated that the primary to secondary leak rate was approximately 0.11 gallons per minute although air ejector calculations still indicated 0.016 gpm.
Based on the above leakage determination, at 1845 EST the Plant Superintendent ordered the plant shutdown to investigate and repair the leak.
Also at this time the Technical Specification limit of no more than.1 gpm tube leakage in one steam generator when averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was addressed and it was decided since the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average was not exceeded, to wait for a more accurate leak rate calculation from a Steam Generator Blowdown sample.
At 2116 EST the Turbine Generator was taken off the line.
At '2117 EST the "B" Steam Generator was isolated from the secondary steam system to limit releases to the environment and to limit contamination of the secondary system.
At 2127 the reactor was shutdown with all control rods inserted and plant cooldown commenced.
At 2130 EST a "B" Steam Generator Blowdown sample calculation indicated the primary to secondary tube leak was greater than
.1 gpm (i.e.
approximately
.14 gpm).
At this time the Operations Shift Supervisor declared an Unusual Event in accordance with SC-100, "Ginna Station Event Evaluation and Classification,"
EAL:
Reactor Coolant Leakage; Steam Generator Tube Leakage
>.1 gpm as identified by sampling.
All offsite notifications were made per SC-601, "Unusual Event Notifications."
At 0159 EST March 15, 1988 the plant reached less than 350 F
reactor coolant temperature.
This completed the Technical Specification action statement for a Steam Generator Tube Leak of
.1 gpm.
The action statement states to be in hot shutdown within six hours and at an RCS temperature of less than 350 F
within the following six hours.
Pith the RCS temperature less than'50 F and all Technical Specification action statements met, the Operations Shift Super-visor, with approval of the Superintendent
- Ginna Station, declared the Unusual Event terminated at 0213 EST in accordance with SC-110, "Ginna Station Event Evaluation For Reducing The Classification."
At 0346 EST the Residual Heat Removal system was placed in service and cooldown to cold shutdown continued.
At 0700 EST the plant entered the cold shutdown mode of operation.
An estimated release to the environment was calculated assuming a
0.14 gpm tube leak during the entire event.
Total noble gas release calculated was.062 curies or approximately 0.00154 of the Technical Specification limit.