ML20215D623
ML20215D623 | |
Person / Time | |
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Site: | Ginna ![]() |
Issue date: | 12/11/1986 |
From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
To: | NRC OFFICE OF ADMINISTRATION (ADM) |
References | |
NUDOCS 8612160424 | |
Download: ML20215D623 (2) | |
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Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999
[Table view]Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30 Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER) MONTHYEARML20207R7521987-03-0909 March 1987
[Table view]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 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 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 05000244/LER-1982-003, RO 82-007/01T:on 820125,unit Experienced Event Described in LER 82-003 Leading to RCS Cooldown Rate Greater than 100 F/H.Further Info Will Be Submitted w/14-day Written Rept1982-02-24024 February 1982 RO 82-007/01T:on 820125,unit Experienced Event Described in LER 82-003 Leading to RCS Cooldown Rate Greater than 100 F/H.Further Info Will Be Submitted w/14-day Written Rept ML20084D9411977-07-15015 July 1977 Supplemental RO-77-010:four Addl Supports (SW-69,73,78 & 83) Found W/Stresses Under DBE Conditions in Excess of Allowable Values.Corrective Actions Underway ML20084D9381977-07-14014 July 1977 RO-77-010:on 770713,design Error Found in Redundant Svc Water Discharge Line Support.Overstress Condition Could Exist W/Line Not Yet Charged or in Svc.Line in Hold Condition ML20084B8551977-02-10010 February 1977 Supplemental RO 76-24:on 761008,leaks Found in 8-inch Schedule 10 Boric Acid Piping.Cause of Cracks Probably Due to Stress Corrosion Attack ML20084C1511976-12-21021 December 1976 Supplemental RO-76-21:on 760819,two Control Rods Dropped. Westinghouse Recommendations for Cause Later Determined Not to Be Actual Cause.New Recommendations to Be Carried Out During Next Refueling Outage ML20084C3151976-06-21021 June 1976 Supplemental RO 76-10:on 760228,excessive Leakage Observed from Valve Inside Purge Supply Control Valve.Results of Vendor Insp of Assembly Submitted ML20084C2901976-05-25025 May 1976 Supplemental RO-76-12:on 760331,during Testing,Excessive Leakage Found in Containment Personnel Airlock Handwheel Shaft Seal.Corrective Action Include Placing Seal on Packing Gland Nuts to Prevent Rotation W/Shaft ML20084A0971976-05-12012 May 1976 Supplemental RO 76-07 Re Train a Containment Isolation & Ventilation Isolation Failure to Latch.Fourteen Relays Checked for Clearance Between Electromagnet Pole Face & Raised Section of Armature ML20083R8881976-03-0909 March 1976 RO 76-11:on 760308,control Room Charcoal Filter Damper Discovered Improperly Positioned.Trouble Card Issued & Work Initiated to Correct Problem ML20084A0121976-02-23023 February 1976 RO 76-08:on 760227,39 Steam Generator Tubes Explosively Plugged in Steam Generator a & 2 in Steam Generator B.Tubes Exhibited Tube Wall Deterioration in Excess of 40% ML20084A1351976-02-0808 February 1976 RO 76-05:on 760208,excessive Leakage Observed Through Several Containment Penetrations.Cause Not Stated.Repairs to Valves Underway ML20084A9721974-11-0707 November 1974 Ro:On 741008,Westinghouse Informed Util That Safety Injection Sys Delivery Curve Employed for Steam Line Break Accident Analysis Inconsistent W/Analyses Used for Recent Loca.Util to Maintain Shutdown Margin of at Least 2.45% ML20084E2251974-06-0707 June 1974 Ro:On 740509,during Surveillence Procedure PT 16,little Flow Reduction Occurred Following Opening of Motor Driven Auxiliary Feedwater Pump a & B Discharge Valve.Cause Unapparent.Frequency of Surveillance Test Increased ML20084H0961974-02-25025 February 1974 RO: Overexposure of Individual to Radiation Occurred During First Quarter of 1974.Correction to Reporting Similar Occurrence Encl ML20084H0991974-02-20020 February 1974 RO: Individuals Overexposed to Radiation During First Quarter 1974.Investigation Underway ML20084E3341973-06-21021 June 1973 Ro:On 730523,thirty Minutes After Boric Acid Transfer Pumps Started Recirculation,Control Rods Noted as Stepping Out. Caused by Malfunction of Blend Sys Valve FCV-110B.Repair Instituted & Completed on 730524 ML20084E4361973-06-0808 June 1973 Ro:On 730529,during Performance of Monthly Surveillance Undervoltage & Underfrequency Protection,Device Armature of Knife Switches for Solenoid Coil Discovered Not Dropping to Assume Deenergized Condition.Caused by Scale Accumulation ML20084E3651973-06-0707 June 1973 Ro:On 730606,high Bistable Setting Approx 2.1% Higher than Specified Value Set Forth in Plant Procedure.Caused by Personnel Error in Transposing Desired Calculated Current Level from Work Sheet.Setting to Correspond W/Steam Flow ML20084E3541973-05-31031 May 1973 Ro:On 730502,Bank D Control Rod Sys Observed Stepping Out of Core.Caused by Loose Solder Joint in QM-401.Automatic Rod Control Immediately Switched to Manual W/No Indication of Any Change in Reactor Power.Averaging Unit Repaired ML20084E4561973-05-30030 May 1973 Ro:On 730529,upon Opening Knife for Solenoid Coil of Primary Undervoltage Device 273/IIA,device Armature Discovered Not Dropping Down to Assume Deenergized Condition.Caused by Scale Accumulation on Device.Investigation Continuing ML20084E6161972-12-28028 December 1972 RO:720831 & 0901 Unplanned Release of Radioactive Passes Occurred During Removal of Spent Resins from Spent Resin Tanks.Cause Not Stated.Written Procedure for Handling Resin Revised & Precaution Included Re Vent Header Pressure ML20084E9641972-06-30030 June 1972 Ro:On 720623,w/reactor at 5% Thermal Power,Control Board Received Alarms of Rod Bottom Rod Stop & Rod Control Urgent Failure Rod Stop.Caused by Water from Swagelok Fitting on Tubing Dropping on Rod Control Cabinets.Fitting Repaired ML20084E9731972-05-31031 May 1972 Ro:On 720503,upon Entering Steam Generator & Starting Grit Blasting Equipment,Workman Discovered Face Mask Not Functioning & Exited Area.Caused by Failure to Tighten Threaded Connection of Air Hose to Mask.Exams Performed ML20084E4681972-04-28028 April 1972 Ro:On 720420,while Plant Being Cooled Down in Preparation for Refueling,Release Rate of Airborne I-131 from Plant Vent Exceeded Tech Spec Limits.Cause Unknown.Charcoal Filters from Plant Vent Iodine Monitor Being Replaced ML20084E6591972-03-30030 March 1972 Ro:On 720320,while Reactor in Hot Shutdown,Msivs Tested for Closure & MSIV-1B Valve Found Closed Only Half Way.Cause Unknown.Valve Mfg Contacted for Recommendations to Prevent Recurrence ML20084F0801972-02-0707 February 1972 Ro:On 720131,while Conducting Monthly Surveillance Test, Underfrequency Relay on 4160-kV Bus 11B Failed to Transmit Signal to Logic Racks.Caused by Faulty Capacitor.Spare Relay Installed & Tested Satisfactorily ML20084F1211971-12-14014 December 1971 Ro:On 711205,safety Injection Pump Motor C Tripped Automatically When Nearly Up to Speed.Caused by Motor Tripping Out on Starting Current Due to Leakage in Time Delay Dashpot.Replacement Overcurrent Device Installed ML20084E5671971-07-0909 July 1971 Ro:On 710630,MSIV Failed to Close on Signal.Solenoid Operators on MSIV 1A Removed & Inspected and All Parts ML20084E6101971-06-11011 June 1971 Ro:Between 710601-05,calculations Indicated Gaseous Effluent Release Limits Exceeded.Caused by Gasket Leak on Vol Control Tank Pressure Control Regulator Valve PCV141.Continuous Recording Iodine Monitor Installed on Stack Vent ML20084E6371971-04-29029 April 1971 Ro:On 710422,during Diesel Generator Load & Safeguard Sequence Test,Valves 826 A,B,C & D Failed to Open.Caused by Momentary Loss of Voltage on 480-volt Safeguard Busses.Power Supply Transfer Recommended ML20084E8361970-12-21021 December 1970 Ro:During 700930-1015 Shutdown,Broken Stud Found on One Support for Primary Sys Component.W/O Stated Encl ML20084E8561970-10-14014 October 1970 Ro:On 701004,core Deluge Valve 852B Malfunctioned.Caused by Seizure of Stem Nut to Valve Stem.New Stem Nut Installed ML20084E5501970-07-15015 July 1970 Ro:On 700706,boron Dilution Performed W/Reactor Critical & No Reactor Coolant Pump on RHR Pump in Operation.Orders Issued That Maint Work Performed Only W/Authorized Procedures Available ML20084E7211970-05-22022 May 1970 Ro:On 700514,during Reactor Cooldown Procedure,Msiv 1B Failed to Close.Caused by Malfunction of Valve Mechanism. Packing Gland Loosened ML20084E7821970-03-13013 March 1970 Ro:On 700306,during Surveillance Test,Excessive Air Leakage Around Lower Handwheel Shafts That Penetrate to Outside Handwheels Noted.Ring of Packing to Lower Handwheel Shaft Added ML20084E7771970-02-27027 February 1970 Ro:On 700130,motor Operated Svc Water Valves 4013,4300 & 4028 on Emergency Suction Line to Auxiliary Feedwater Pumps Reported to Operate Improperly.Caused by Operating Personnel Misunderstanding ML20084E4161970-01-19019 January 1970 RO:700108,during Draining Required to Permit Replacement of Coolant Temp detectors,in-core Thermocouple Reading Indicated Temp Exceeded Tech Spec Limit.Caused by Failure to Monitor Temp by Alternate Means 1987-03-09 Category:TEXT-SAFETY REPORT MONTHYEARML17265A7601999-10-0505 October 1999
[Table view]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 991008 Ltr 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 ML17265A7541999-09-22022 September 1999 LER 99-011-00: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 990922 Ltr ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr ML17265A7431999-08-24024 August 1999 LER 99-004-01: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 ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr 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 ML17265A7181999-07-23023 July 1999 LER 99-007-01: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 ML17265A7081999-07-22022 July 1999 LER 98-003-02: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 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 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 990719 Ltr ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp. ML17265A7021999-07-15015 July 1999 LER 99-010-00: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 990715 Ltr 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 991020 Ltr ML17265A7011999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr ML17265A6851999-06-21021 June 1999 LER 99-001-01: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 990621 Ltr 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 ML17265A6661999-06-0202 June 1999 LER 99-009-00: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 990602 Ltr ML17265A6681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr 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 ML17309A6541999-05-27027 May 1999 LER 99-008-00: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 990527 Ltr ML17265A6631999-05-24024 May 1999 LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved ML17265A6601999-05-21021 May 1999 LER 99-006-00: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 990521 Ltr 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 ML17265A6441999-05-13013 May 1999 LER 99-005-00: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 990513 Ltr ML17265A6431999-05-12012 May 1999 LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed 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 990510 Ltr 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 ML17265A6291999-03-31031 March 1999 Rev 0 to Cycle 28 COLR for Re Ginna Npp. ML17265A6241999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr ML17265A6141999-03-31031 March 1999 LER 99-003-00: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 990331 Ltr ML17265A6131999-03-29029 March 1999 LER 99-002-00: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 990329 Ltr ML17265A6061999-03-24024 March 1999 LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp ML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation. ML17265A5961999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr ML17265A5371999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr ML17265A5951998-12-31031 December 1998 Rg&E 1998 Annual Rept. ML17265A5001998-12-21021 December 1998 Rev 26 to QA Program for Station Operation. ML17265A4951998-12-21021 December 1998 LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr ML17265A4931998-12-17017 December 1998 LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery ML17265A4761998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr ML17265A4691998-11-25025 November 1998 LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR ML17265A4531998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr ML17265A4271998-10-0505 October 1998 LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr ML17265A4291998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr 1999-09-30 |
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- ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE, ROCHESTER, N.Y. 14645'0001 ;
ROGER W. MOBER z7/c"'cEEm =mucrm .. . co[c$.Y4e.2 7oo December 11, 1986 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Follow-up Summary of Unusual Event at R.E. Ginna Nuclear Power Plant on November 28, 1986 Docket No. 50-244 In accordance with the NUREG-0654 reporting requirements, which require a written summary of close out or class reduction condi-tions, the following is submitted for the Unusual Event declared at R.E. Ginna Nuclear Power Plant on November 28, 1986:
l On November 28, 1986 at 1116 hours0.0129 days <br />0.31 hours <br />0.00185 weeks <br />4.24638e-4 months <br /> with the reactor at 100%
l power, the reactor Containment Vessel (CV) was being depressur-ized per Operating Procedure 0-11 (Control of Containment Depressurization Valves While Reactor is Critical) . At this time, with CV depressurization complete, the Licensed Control Operator proceeded to close the 2 CV depressurization valves (AOV-7970 AND AOV-7971) but inadvertently closed the Main Steamline Isolation Valves (MSIV) 3516 and 3517 which were just below the CV depressurization valves on the Main control Board. This caused a pressurizer high pressure reactor trip at 2377 psig within approximately 5 seconds.
At 1127 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.288235e-4 months <br />, the Shift Supervisor declared an Unusual Event in accordance with the SC-100 "Ginna Station Event Evaluation and Classification" for reactor coolant pressure greater than 2335 psig.
Following the automatic reactor trip the pressurizer pressure returned to normal and the plant was stabilized in hot shutdown with no compromise to plant safety or the health and welfare of the general public.
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ROCHESTER GAS AND ELECTRIC CORP. SHEET NO. 2 DATE December 11, 1986 TO U.S. Nuclear Regulatory Concission With Superintendent - Support Services and plant staff approval, the Shift Supervisor declared the Unusual Event terminated at 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br />, in accordance with SC-llo "Ginna Station Event i Evaluation For Reducing the Classification".
V truly yours, af & Kober Roger W.
xc: U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 L