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| | issue date = 05/30/1990 | | | issue date = 05/30/1990 |
| | title = 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 | | | title = 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 |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = MARTIN T T | | | addressee name = Martin T |
| | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000244 | | | docket = 05000244 |
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| =Text= | | =Text= |
| {{#Wiki_filter:ACCELERATED DIUTIONDEMONSATIONSYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9006110327 DOC.DATE: | | {{#Wiki_filter:ACCELERATED DI UTION DEMONS ATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| 90/05/30NOTARIZED: | | ACCESSION NBR:9006110327 DOC.DATE: 90/05/30 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear. Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp. |
| NOFACIL:50-244 RobertEmmetGinnaNuclear.Plant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.
| | RECIP.NAME RECIPIENT AFFILIATION MARTIN,T.T. Document Control Branch (Document Control Desk) |
| Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION MARTIN,T.T. | |
| DocumentControlBranch(Document ControlDesk)
| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Specialrept:on900430,use ofoverpressure protection systomitigateRCSpressuretransient.
| | Special rept:on 900430,use of overpressure protection sys to mitigate RCS pressure transient. |
| DISTRIBUTION CODE:IE22DCOPIESRECEIVED:LTR ENCL0SIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),ncidentRpt,etc.DOCKET05000244NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72). | | DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL 0 SIZE: |
| 05000244RECIPIENT IDCODE/NAME PD1-3LAJOHNSON,A INTERNAL:
| | TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc. |
| ACNWAEOD/DSP/TPABDEDRONRR/DET/EMEB9H3
| | NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR EN CL PD1-3 LA 1 PD1-3 PD 1 JOHNSON,A 1 INTERNAL: ACNW AEOD/DOA AEOD/DS P/TPAB AEOD/ROAB/DS P DEDRO NRR/DET/ECMB 9H NRR/DET/EMEB9H3 NRR/DLPQ/LHFB11 |
| ~NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7ENRR/DST/SRXB 8ERES/DSIR/EIB EXTERNAL: | | ~ |
| EG&GSTUART,V.A LPDRNSICMAYS,GNUDOCSFULLTXTCOPIESLTTRENCL11RECIPIENT IDCODE/NAME PD1-3PDAEOD/DOAAEOD/ROAB/DS PNRR/DET/ECMB 9HNRR/DLPQ/LHFB11 NRR/DOEA/OEABll NRR/DST/SELB 8DRBj~PLB8D1EG02RGN1FILE01LSTLOBBYWARDNRCPDRNSICMURPHY,G.A COPIESLTTREN1CLNOTETOALL"RIDS"RECIPIENTS: | | NRR/DLPQ/LPEB10 NRR/DOEA/OEABll NRR/DREP/PRPB11 NRR/DST/SELB 8D NRR/DST/SICB 7E RBj~ PLB8D1 NRR/DST/SRXB 8E EG 02 RES/DSIR/EIB RGN1 FILE 01 EXTERNAL: EG&G STUART,V.A L ST LOBBY WARD LPDR NRC PDR NSIC MAYS,G NSIC MURPHY,G.A NUDOCS FULL TXT NOTE TO ALL "RIDS" RECIPIENTS: |
| PLEASEHELPUSTOREDUCEWASTE!CONI'ACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
| | PLEASE HELP US TO REDUCE WASTE! CONI'ACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| LTTR34ENCL C~
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 34 ENCL |
| ROCHESTER GASANDELECTRICCORPORATION | | |
| ~e9EASTAVENUE,ROCHESTER, N.Y.I~6~9-000> | | C~ |
| /May30,1990Mr.ThomasT.Martin,RegionalAdministrator U.S.NuclearRegulatory Commission 475Allendale RoadKingofPrussia,PA19406 | | ROCHESTER GAS AND ELECTRIC CORPORATION ~ e9 EAST AVENUE, ROCHESTER, N.Y. I~6~9-000> |
| | / |
| | May 30, 1990 Mr. Thomas T. Martin, Regional Administrator U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 |
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| ==Subject:== | | ==Subject:== |
| Thirty(30)DaySpecialReportUseoftheOverpressure Protection SystemtoMitigateanRCSPressureTransient R.E.GinnaNuclearPowerPlantDocketNo.50-244 | | Thirty (30) Day Special Report Use of the Overpressure Protection System to Mitigate an RCS Pressure Transient R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
| | |
| | ==Dear Mr. Martin:== |
| | |
| | In accordance with Technical Specification 3.15.1.3, this thirty day special report on Use of the Overpressure Protection System to Mitigate an RCS Pressure Transient, is hereby submitted. |
| | On April 30, 1990, at 0810 EDST, the Reactor Coolant System (RCS) |
| | . was in a'olid condition with pressure and temperature at 325 psig and 340 F respe'ctively with the "B" Reactor Coolant Pump operating. Decay heat removal was via the steam generators with RHR still lined up to the RCS. The letdown pressure control valve, PCV-135, was in automatic controlling RCS pressure at 325 psig. Periodic test procedure PT-7 (Hydro Test of Reactor Coolant System) was in progress for the required RCS hydro subsequent to the annual refueling and maintenance outage. The reactor vessel overpressure protection system was in service as required until the RHR system is taken out of service and isolated from the RCS. |
| | Isolation of the RHR system was being performed when the over-pressure protection system activated at approximately 400 psig RCS pressure. The two pressurizer power operated relief valves (PORVs) operated as designed to mitigate the slow pressure transient and stabilized RCS pressure at approximately 360 psig. |
| | The pressurizer PORVs were open for approximately four seconds. |
| | 900gg i0 ~27 900~ |
| | F DR ADOCK 0.000244 ~+2.2. |
| | PDC Ii0 |
|
| |
|
| ==DearMr.Martin:==
| | The apparent causes of the event are as follows: |
| Inaccordance withTechnical Specification 3.15.1.3, thisthirtydayspecialreportonUseoftheOverpressure Protection SystemtoMitigateanRCSPressureTransient, isherebysubmitted.
| | o Excess letdown, which is normally used to control RCS pressure by varying charging flow with excess letdown flow during the performance of the RCS hydro, was ineffective at the lower pressures so the Control Room Operators were using normal letdown to supplement excess letdown for RCS pressure control. Also, with the RHR system still open to the RCS, some letdown was still being accomplished through its letdown path. |
| OnApril30,1990,at0810EDST,theReactorCoolantSystem(RCS).wasina'olidcondition withpressureandtemperature at325psigand340Frespe'ctively withthe"B"ReactorCoolantPumpoperating.
| | 0" During the above evolution, RCS pressure was being controlled by the letdown pressure control valve, PCV-135, from the letdown orifices and RHR system. Excess letdown was in service, but ineffective in controlling RCS pressure. When the RHR system was isolated from the RCS, letdown from the RHR path was terminated and all normal letdown now to PCV-135 was through ,letdown orifices. With PCV-135 set in automatic, letdown pressure was being controlled at approxi-mately 325 psig. With charging flow at a minimum, RCS pressure slowly increased to the overpressure protection actuation setpoint due to an approximate 80 psig system differential between letdown and the operating coolant pump discharge pressure, before Control Room Operators could intervene manually to control it. |
| Decayheatremovalwasviathesteamgenerators withRHRstilllineduptotheRCS.Theletdownpressurecontrolvalve,PCV-135,wasinautomatic controlling RCSpressureat325psig.Periodictestprocedure PT-7(HydroTestofReactorCoolantSystem)wasinprogressfortherequiredRCShydrosubsequent totheannualrefueling andmaintenance outage.Thereactorvesseloverpressure protection systemwasinserviceasrequireduntiltheRHRsystemistakenoutofserviceandisolatedfromtheRCS.Isolation oftheRHRsystemwasbeingperformed whentheover-pressureprotection systemactivated atapproximately 400psigRCSpressure.
| | Immediate corrective action was taken to ensure that the pres-surizer PORVs opened to mitigate the RCS pressure transient and then closed. Subsequently, the Control Room Operators placed PCV-135 in manual and adjusted approximately 340 psig. |
| Thetwopressurizer poweroperatedreliefvalves(PORVs)operatedasdesignedtomitigatetheslowpressuretransient andstabilized RCSpressureatapproximately 360psig.Thepressurizer PORVswereopenforapproximately fourseconds.900ggi0~27900~FDRADOCK0.000244PDC~+2.2.Ii0 Theapparentcausesoftheeventareasfollows:oExcessletdown,whichisnormallyusedtocontrolRCSpressurebyvaryingchargingflowwithexcessletdownflowduringtheperformance oftheRCShydro,wasineffective atthelowerpressures sotheControlRoomOperators wereusingnormalletdowntosupplement excessletdownforRCSpressurecontrol.Also,withtheRHRsystemstillopentotheRCS,someletdownwasstillbeingaccomplished throughitsletdownpath.0"Duringtheaboveevolution, RCSpressurewasbeingcontrolled bytheletdownpressurecontrolvalve,PCV-135,fromtheletdownorificesandRHRsystem.Excessletdownwasinservice,butineffective incontrolling RCSpressure.
| | it to control RCS pressure at Corrective action to prevent recurrence will be as follows: |
| WhentheRHRsystemwasisolatedfromtheRCS,letdownfromtheRHRpathwasterminated andallnormalletdownnowtoPCV-135wasthrough,letdownorifices.
| | Continued evaluation of the events initiating the RCS pressure transient. |
| WithPCV-135setinautomatic, letdownpressurewasbeingcontrolled atapproxi-mately325psig.Withchargingflowataminimum,RCSpressureslowlyincreased totheoverpressure protection actuation setpointduetoanapproximate 80psigsystemdifferential betweenletdownandtheoperating coolantpumpdischarge
| | Checkout of the proper operation of the excess letdown system during these conditions. |
| : pressure, beforeControlRoomOperators couldintervene manuallytocontrolit.Immediate corrective actionwastakentoensurethatthepres-surizerPORVsopenedtomitigatetheRCSpressuretransient andthenclosed.Subsequently, theControlRoomOperators placedPCV-135inmanualandadjustedittocontrolRCSpressureatapproximately 340psig.Corrective actiontopreventrecurrence willbeasfollows:Continued evaluation oftheeventsinitiating theRCSpressuretransient.
| | Revision of operating procedures to alert operators on effective methods of pressure control under these conditions. |
| Checkoutoftheproperoperation oftheexcessletdownsystemduringtheseconditions.
| | Ve truly yours, Robert C. M cre Division Manager Nuclear Production RCM/eeh xc: U.S. Nuclear Regulatory Commission (Original) |
| Revisionofoperating procedures toalertoperators oneffective methodsofpressurecontrolundertheseconditions.
| | Document Control Desk Washington, DC 20555 Ginna USNRC Senior Resident Inspector}} |
| Vetrulyyours,RobertC.McreDivisionManagerNuclearProduction RCM/eehxc:U.S.NuclearRegulatory Commission (Original)
| |
| DocumentControlDeskWashington, DC20555GinnaUSNRCSeniorResidentInspector}}
| |
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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
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
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
ML20050B1261982-03-24024 March 1982
RO 82-010/01T:on 820323,local Radiation Emergency Declared, Including Confirmation of 24-h Notification Re Evacuation of Fire Watches from Inoperable Zone S-015.Caused by Increase in Airborne Activity Associated W/Mod in B Steam Generator
ML20041F9301982-03-0303 March 1982
Ro:On 820125,event Described in LER 82-003 Resulted in Calculated Temp Difference Across Tube Sheet of B Steam Generator of Approx 280 F.Addl Info Will Be Submitted W/ 14-day Written Rept
ML20040H4191982-02-0404 February 1982
RO 82-006:on 820203,RCS Inadvertently Diluted During Performance of T-7P,filling & Purge of Steam Generator B. Caused by Only One End of Leaky Steam Generator Tube Plugged,Due to Procedural Inadequacy.End Plugged
ML17258A4521982-01-13013 January 1982
Ro:During Routine Surveillance,Two Pinhole Leaks Were Discovered in Suction Line from Containment Sump B to a RHR Pumps.Revision to Tech Spec 3.3.1.2 Will Be Proposed to Permit Inoperability of One ECCS Subsystem for Up to 72-h
ML17258B0761981-05-15015 May 1981
RO 81-009:on 810515,during Refueling & Maint Outage,Eddy Current Examinations Revealed Abnormal Degradation of Steam Generator B Inlet Tubes.Crevice Indication Tubes Will Be Sleeved.Hot Leg Tubes Will Be Removed
ML17258B0661981-05-0101 May 1981
Ro:On 810501,fire Announced on Operating Floor of Containment Vessel.Caused by Spark from Work on Seismic Support Entering Storage Box Igniting Webbing.Open Flame Welding & Grinding Permits Cancelled During Investigation
ML17250A4151980-07-14014 July 1980
RO 80-06:on 800714,chemical Analysis Indicated Boric Acid Storage Tanks Out of Spec for Vol & % Weight of Boric Acid. Caused by Inadvertent Dilution of Concentration Determining Chemical Reagents.Tanks Restored to Required Specs
ML17250A3961980-07-11011 July 1980
RO 80-06:on 800711,chemical Analysis Indicated Boric Acid Storage Tanks Below Tech Specs for Vol & Percent Weight Boric Acid.Cause Not Stated.Orderly Power Reduction & Batching Operations Begun to Restore Tanks to Specs
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
ML17250A3381980-06-0303 June 1980
RO 80-05:on 800603,during Performance of Safety Injection Valve Position Verification Procedure,Discovered Breaker for A-loop Accumulator Discharge Valve MOV-865 Was in Closed Position.Breaker Placed in Proper Position,
ML17250A3041980-05-0707 May 1980
RO 80-04:during Performance of post-mod Installation Testing Both Power Operated Relief Valves Determined Inoperable & RCS Vent Established.Caused by Two Switches Which Supply Dc Power in Off Position
ML17249A8471980-04-14014 April 1980
RO 80-003:eddy Current Exams Conducted to Detect Potential Tube Defects.Based on Results,Pulling Initiated to Remove Tube W/Abnormal Absolute Signal
ML17249A3621979-12-11011 December 1979
RO 79-023:on 791207,liquid Penetrant Examination of safe- End of 4-inch Relief Nozzle Adjacent to Nozzle to safe-end Weld Revealed 6-inch Long Indication.Further Analysis Required to Determine Cause
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 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
[Table view] |
Text
ACCELERATED DI UTION DEMONS ATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9006110327 DOC.DATE: 90/05/30 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear. Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION MARTIN,T.T. Document Control Branch (Document Control Desk)
SUBJECT:
Special rept:on 900430,use of overpressure protection sys to mitigate RCS pressure transient.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL 0 SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc.
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR EN CL PD1-3 LA 1 PD1-3 PD 1 JOHNSON,A 1 INTERNAL: ACNW AEOD/DOA AEOD/DS P/TPAB AEOD/ROAB/DS P DEDRO NRR/DET/ECMB 9H NRR/DET/EMEB9H3 NRR/DLPQ/LHFB11
~
NRR/DLPQ/LPEB10 NRR/DOEA/OEABll NRR/DREP/PRPB11 NRR/DST/SELB 8D NRR/DST/SICB 7E RBj~ PLB8D1 NRR/DST/SRXB 8E EG 02 RES/DSIR/EIB RGN1 FILE 01 EXTERNAL: EG&G STUART,V.A L ST LOBBY WARD LPDR NRC PDR NSIC MAYS,G NSIC MURPHY,G.A NUDOCS FULL TXT NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONI'ACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 34 ENCL
C~
ROCHESTER GAS AND ELECTRIC CORPORATION ~ e9 EAST AVENUE, ROCHESTER, N.Y. I~6~9-000>
/
May 30, 1990 Mr. Thomas T. Martin, Regional Administrator U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Subject:
Thirty (30) Day Special Report Use of the Overpressure Protection System to Mitigate an RCS Pressure Transient R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Martin:
In accordance with Technical Specification 3.15.1.3, this thirty day special report on Use of the Overpressure Protection System to Mitigate an RCS Pressure Transient, is hereby submitted.
On April 30, 1990, at 0810 EDST, the Reactor Coolant System (RCS)
. was in a'olid condition with pressure and temperature at 325 psig and 340 F respe'ctively with the "B" Reactor Coolant Pump operating. Decay heat removal was via the steam generators with RHR still lined up to the RCS. The letdown pressure control valve, PCV-135, was in automatic controlling RCS pressure at 325 psig. Periodic test procedure PT-7 (Hydro Test of Reactor Coolant System) was in progress for the required RCS hydro subsequent to the annual refueling and maintenance outage. The reactor vessel overpressure protection system was in service as required until the RHR system is taken out of service and isolated from the RCS.
Isolation of the RHR system was being performed when the over-pressure protection system activated at approximately 400 psig RCS pressure. The two pressurizer power operated relief valves (PORVs) operated as designed to mitigate the slow pressure transient and stabilized RCS pressure at approximately 360 psig.
The pressurizer PORVs were open for approximately four seconds.
900gg i0 ~27 900~
F DR ADOCK 0.000244 ~+2.2.
PDC Ii0
The apparent causes of the event are as follows:
o Excess letdown, which is normally used to control RCS pressure by varying charging flow with excess letdown flow during the performance of the RCS hydro, was ineffective at the lower pressures so the Control Room Operators were using normal letdown to supplement excess letdown for RCS pressure control. Also, with the RHR system still open to the RCS, some letdown was still being accomplished through its letdown path.
0" During the above evolution, RCS pressure was being controlled by the letdown pressure control valve, PCV-135, from the letdown orifices and RHR system. Excess letdown was in service, but ineffective in controlling RCS pressure. When the RHR system was isolated from the RCS, letdown from the RHR path was terminated and all normal letdown now to PCV-135 was through ,letdown orifices. With PCV-135 set in automatic, letdown pressure was being controlled at approxi-mately 325 psig. With charging flow at a minimum, RCS pressure slowly increased to the overpressure protection actuation setpoint due to an approximate 80 psig system differential between letdown and the operating coolant pump discharge pressure, before Control Room Operators could intervene manually to control it.
Immediate corrective action was taken to ensure that the pres-surizer PORVs opened to mitigate the RCS pressure transient and then closed. Subsequently, the Control Room Operators placed PCV-135 in manual and adjusted approximately 340 psig.
it to control RCS pressure at Corrective action to prevent recurrence will be as follows:
Continued evaluation of the events initiating the RCS pressure transient.
Checkout of the proper operation of the excess letdown system during these conditions.
Revision of operating procedures to alert operators on effective methods of pressure control under these conditions.
Ve truly yours, Robert C. M cre Division Manager Nuclear Production RCM/eeh xc: U.S. Nuclear Regulatory Commission (Original)
Document Control Desk Washington, DC 20555 Ginna USNRC Senior Resident Inspector
