|
|
| (3 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 04/03/1991 | | | issue date = 04/03/1991 |
| | title = 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 | | | title = 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 |
| | author name = SPECTOR S M | | | author name = Spector S |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = | | | addressee name = |
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9104090259 DOC.DATE: | | {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| 91/04/03NOTARIZED: | | ACCESSION NBR:9104090259 DOC.DATE: 91/04/03 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION SPECTOR,S.M. Rochester Gas & Electric Corp. |
| NODOCKETFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION SPECTOR,S.M.
| | RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Followupreptof910403eventreremovalofRHRsys&component coolingwatersysfromsvcduetopackingleakfromMOV-738B.Valve manuallyplacedonbackseat&leak-terminated.
| | Followup rept of 910403 event re removal of RHR sys & |
| DISTRIB'STION CODE:IE22DCOPIESRECEIVED:LTR 4ENCLLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.DNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72). | | component cooling water sys from svc due to packing leak from MOV-738B.Valve manually placed on backseat & leak D terminated. |
| 05000244ARECIPIENT IDCODE/NAME PD1-3LAJOHNSON,A INTERNAL:
| | DISTRIB'STION CODE: IE22D COPIES RECEIVED:LTR ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), 4Incident Rpt, etc. |
| ACNWAEOD/DSP/TPABNRR/DET/ECMB 9HNRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8DNPLB8D1REGFIL02FILE01EXTERNAL:
| | L SIZE: |
| EG&GBRYCE,J.H NRCPDRNSICMURPHY,G.A COPIESLTTRENCL1111221111111111111111331111RECIPIENT IDCODE/NAME PD1-3PDAEOD/DOAAEOD/ROAB/DSP NRR/DET/EMEB 7ENRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7ENRR/DST/SRXB 8ERES/DSIR/EIB LSTLOBBYWARDNSICMAYS,GNUDOCSFULL'TXTCOPIESLTTRENCL11112211112,2111111111DDRDNOTETOALL"RIDS"RECIPIENTS:
| | NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 A |
| ADDPLEASEHELPUSTOREDUCEiVASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMP1-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
| | RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 1 PD1-3 PD 1 1 D JOHNSON,A 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D 1 |
| LTTR31ENCL31 nfpa+
| | 1 1 |
| <<'l~i~i7i7'fi/I2!7 | | 1 1 |
| /Pgt"'"""IROCHESTER GASANDELECTRICii<<<<t+g~<<~%~AQ.104K,j~,!STATICrCORPORATION
| | 1 NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E 2, |
| ~89EASTAVENUE,ROCHESTER, N.Y.14649.0001 | | 1 1 |
| 'CLEP<0<<<<f,A<<<<KAcooE7lc5462700April3,1991U.S.NuclearRegulatory Commission DocumentControlDeskWashington, DC20555 | | 2 1 |
| | 1 N PLB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG FIL 02 1 1 RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST LOBBY WARD 1 NRC PDR 1 1 NSIC MAYS,G 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL'TXT 1 R D |
| | A D |
| | D NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 |
| | |
| | n f pa+ |
| | |
| | i <<<<t+ |
| | /Pgt "'"""I i |
| | <<'l~i~i7i7'fi/I2!7 g ~ << ~% ~ A Q |
| | . 104K, STATIC j~,! |
| | r ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001 |
| | ' C L E P < 0 <<<< f, A<<<<KA cooE 7lc 546 2700 April 3, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Follow-up SummaryOfClose-Out OfApril3,1991UnusualEvent.R.E.GinnaNuclearPowerPlantDocketNo.50-244Inaccordance withNUREG0654,FEMA-REP-1, Rev.1reporting requirements whichrequiresawrittensummaryof"close-out orclassreduction conditions", | | Follow-up Summary Of Close-Out Of April 3, 1991 Unusual Event. |
| theattachedclose-out summaryfor'theApril3,1991UnusualEventisherebysubmitted.
| | R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with NUREG 0654, FEMA-REP-1, Rev. 1 reporting requirements which requires a written summary of "close-out or class reduction conditions", the attached close-out summary for |
| Thiseventhasinnowayaffectedthepublic'shealthandsafety.Verytrulyyours,xc'tanley
| | 'the April 3, 1991 Unusual Event is hereby submitted. |
| .SpectorPlantManagerU.S.NuclearRegulatory Commission RegionI475Allendale Road.KingofPrussia,PA19406GinnaUSNRCSeniorResident, Inspector RichardBeldueRobertC.Mecredy9104090259 910403PDRADOCK05000244F'DR ATTACHMENT FORCLOSE-OUT OFAPRIL31991UNUSUALEVENTOnApril2,1991at2335ESTthereactorwasintherefueling modewithrefueling inprogress.
| | This event has in no way affected the public's health and safety. |
| TheReactorCoolantSystem(RCS)temperature andpressurewereapproximately 60Fand0psigrespectively.
| | Very truly yours, xc'tanley U.S. Nuclear Regulatory Commission Region I Plant Manager Spector 475 Allendale Road |
| Maintenance personnel wereintheprocessofrepacking motoroperatedvalve(MOV)-738B (CCWInletMOVtoRHRHXB)whichtheybelievedtobeisolated, butwasnot.AtthistimetheControlRoomwasnotifiedofapackingleakfromMOV-738B.Subsequent investigation ofplantpipingandinstrument drawingsrevealedthattheleakwasnon-isolatable. | | .King of Prussia, PA 19406 Ginna USNRC Senior Resident, Inspector Richard Beldue Robert C. Mecredy 9104090259 910403 PDR ADOCK 05000244 F'DR |
| AnattemptwasmadetoopenMOV-738Belectrically toplacethevalveonthebackseatandstopthepackingleak.Thisattemptcausedtheleakratetoincreasetoapproximately 25gallonsperminuteandMov-738Bwasclosedelectrically.
| | |
| Atapproximately 2341EST,April2,1991aplantannouncement wasmadetoinformpersonnel oftheComponent CoolingWater(CCW)spillintheAuxiliary BuildingMezzanine Level.Atapproximately 0003EST,April3,1991,refueling operations wereterminated andtheResidualHeatRemoval(RHR)systemandCCWsystemwereremovedfromservicetomanually.placeMOV-738Bonthebackseattostopthepackingleak.Alsoatapproximately 0003EST,April3,1991,theOperations ShiftSupervisor declaredanUnusualEventinaccordance withEPIP1-0,"GinnaStationEventEvaluation andClassification",
| | ATTACHMENT FOR CLOSE-OUT OF APRIL 3 1991 UNUSUAL EVENT On April 2, 1991 at 2335 EST the reactor was in the refueling mode with refueling in progress. The Reactor Coolant System (RCS) temperature and pressure were approximately 60 F and 0 psig respectively. Maintenance personnel were in the process of repacking motor operated valve (MOV)-738B (CCW Inlet MOV to RHR HX B) which they believed to be isolated, but was not. At this time the Control Room was notified of a packing leak from MOV-738B. Subsequent investigation of plant piping and instrument drawings revealed that the leak was non-isolatable. An attempt was made to open MOV-738B electrically to place the valve on the backseat and stop the packing leak. This attempt caused the leak rate to increase to approximately 25 gallons per minute and Mov-738B was closed electrically. |
| EAL:ColdShutdownActivities; Potential LossofCoreCoolingDueToInability ToMaintainResidualHeatRemovalSystemWhileInColdShutdown. | | At approximately 2341 EST, April 2, 1991 a plant announcement was made to inform personnel of the Component Cooling Water (CCW) spill in the Auxiliary Building Mezzanine Level. |
| Theseactivities mayincludelossofcoolingtotheRHRsystemsuchasaCCWorservicewatersystems.Alloff-sitenotifications weremadeperEPIP1-5(Notifications).
| | At approximately 0003 EST, April 3, 1991, refueling operations were terminated and the Residual Heat Removal (RHR) system and CCW system were removed from service to manually .place MOV-738B on the back seat to stop the packing leak. |
| GinnaTechnical Specifications specifically allowfortheremovalofbothRHRpumpsforuptoone(1)hourprovidedcoreoutlettemperature ismaintained atleast10Fbelowsaturation andnooperations arepermitted thatwouldcausedilution'f thereactorcoolantsystemboronconcentration.
| | Also at approximately 0003 EST, April 3, 1991, the Operations Shift Supervisor declared an Unusual Event in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification", |
| Itisnotedthatalthoughcompliance totheGinnaTechnical Specifications wasbeingmaintained, theOperations ShiftSupervisor conservatively declaredtheUnusualEvent.Thisconservative approachactivated theresponseteamtoprovidesupportshouldconditions furtherdegrade.TheRHRsystemwasthenrunfortwominuteseveryfiveminutesduringthe.isolation ofCCW.
| | EAL: Cold Shutdown Activities; Potential Loss of Core Cooling Due To Inability To Maintain Residual Heat Removal System While In Cold Shutdown. These activities may include loss of cooling to the RHR system such as a CCW or service water systems. All off-site notifications were made per EPIP 1-5 (Notifications). |
| | Ginna Technical Specifications specifically allow for the removal of both RHR pumps for up to one (1) hour provided core outlet temperature is maintained at least 10 F below saturation and no operations are permitted that would cause dilution'f the reactor coolant system boron concentration. It is noted that although compliance to the Ginna Technical Specifications was being maintained, the Operations Shift Supervisor conservatively declared the Unusual Event. This conservative approach activated the response team to provide support should conditions further degrade. |
| | The RHR system was then run for two minutes every five minutes during the. isolation of CCW. |
|
| |
|
| At0027EST,April3,1991,MOV-738Bwasmanuallyplacedonitsbackseatandtheleakwasterminated.
| | At 0027 EST, April 3, 1991, MOV-738B was manually placed on its backseat and the leak was terminated. The "A" CCW pump was then started and the "A" RHR pump was restarted. RHR discharge temperature was not'ed to be approximately 8 F higher than prior to the event. |
| The"A"CCWpumpwasthenstartedandthe"A"RHRpumpwasrestarted. | | -At approximately 0122 EST, April 3, 1991, after the plant was returned to pre-event conditions and all concerns resolved, the Operations Shift Supervisor, with approval and concurrence from the Plant Manager, the Superintendent Ginna Production, and the Operations Manager declared the Unusual Event terminated in accordance with EPIP 3-4 (Emergency Declassification and Recovery). |
| RHRdischarge temperature wasnot'edtobeapproximately 8Fhigherthanpriortotheevent.-Atapproximately 0122EST,April3,1991,aftertheplantwasreturnedtopre-event conditions andallconcernsresolved, theOperations ShiftSupervisor, withapprovalandconcurrence fromthePlantManager,theSuperintendent
| | All off-site agencies were notified of the termination of the Unusual Event.}} |
| -GinnaProduction, andtheOperations ManagerdeclaredtheUnusualEventterminated inaccordance withEPIP3-4(Emergency Declassification andRecovery).
| |
| Alloff-siteagencieswerenotifiedofthetermination oftheUnusualEvent.}}
| |
Similar Documents at Ginna |
|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
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
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: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
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 DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9104090259 DOC.DATE: 91/04/03 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION SPECTOR,S.M. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
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 D terminated.
DISTRIB'STION CODE: IE22D COPIES RECEIVED:LTR ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), 4Incident Rpt, etc.
L SIZE:
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 A
RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 1 PD1-3 PD 1 1 D JOHNSON,A 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D 1
1 1
1 1
1 NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E 2,
1 1
2 1
1 N PLB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG FIL 02 1 1 RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST LOBBY WARD 1 NRC PDR 1 1 NSIC MAYS,G 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL'TXT 1 R D
A D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31
n f pa+
i <<<<t+
/Pgt "'"""I i
<<'l~i~i7i7'fi/I2!7 g ~ << ~% ~ A Q
. 104K, STATIC j~,!
r ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001
' C L E P < 0 <<<< f, A<<<<KA cooE 7lc 546 2700 April 3, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Follow-up Summary Of Close-Out Of April 3, 1991 Unusual Event.
R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with NUREG 0654, FEMA-REP-1, Rev. 1 reporting requirements which requires a written summary of "close-out or class reduction conditions", the attached close-out summary for
'the April 3, 1991 Unusual Event is hereby submitted.
This event has in no way affected the public's health and safety.
Very truly yours, xc'tanley U.S. Nuclear Regulatory Commission Region I Plant Manager Spector 475 Allendale Road
.King of Prussia, PA 19406 Ginna USNRC Senior Resident, Inspector Richard Beldue Robert C. Mecredy 9104090259 910403 PDR ADOCK 05000244 F'DR
ATTACHMENT FOR CLOSE-OUT OF APRIL 3 1991 UNUSUAL EVENT On April 2, 1991 at 2335 EST the reactor was in the refueling mode with refueling in progress. The Reactor Coolant System (RCS) temperature and pressure were approximately 60 F and 0 psig respectively. Maintenance personnel were in the process of repacking motor operated valve (MOV)-738B (CCW Inlet MOV to RHR HX B) which they believed to be isolated, but was not. At this time the Control Room was notified of a packing leak from MOV-738B. Subsequent investigation of plant piping and instrument drawings revealed that the leak was non-isolatable. An attempt was made to open MOV-738B electrically to place the valve on the backseat and stop the packing leak. This attempt caused the leak rate to increase to approximately 25 gallons per minute and Mov-738B was closed electrically.
At approximately 2341 EST, April 2, 1991 a plant announcement was made to inform personnel of the Component Cooling Water (CCW) spill in the Auxiliary Building Mezzanine Level.
At approximately 0003 EST, April 3, 1991, refueling operations were terminated and the Residual Heat Removal (RHR) system and CCW system were removed from service to manually .place MOV-738B on the back seat to stop the packing leak.
Also at approximately 0003 EST, April 3, 1991, the Operations Shift Supervisor declared an Unusual Event in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification",
EAL: Cold Shutdown Activities; Potential Loss of Core Cooling Due To Inability To Maintain Residual Heat Removal System While In Cold Shutdown. These activities may include loss of cooling to the RHR system such as a CCW or service water systems. All off-site notifications were made per EPIP 1-5 (Notifications).
Ginna Technical Specifications specifically allow for the removal of both RHR pumps for up to one (1) hour provided core outlet temperature is maintained at least 10 F below saturation and no operations are permitted that would cause dilution'f the reactor coolant system boron concentration. It is noted that although compliance to the Ginna Technical Specifications was being maintained, the Operations Shift Supervisor conservatively declared the Unusual Event. This conservative approach activated the response team to provide support should conditions further degrade.
The RHR system was then run for two minutes every five minutes during the. isolation of CCW.
At 0027 EST, April 3, 1991, MOV-738B was manually placed on its backseat and the leak was terminated. The "A" CCW pump was then started and the "A" RHR pump was restarted. RHR discharge temperature was not'ed to be approximately 8 F higher than prior to the event.
-At approximately 0122 EST, April 3, 1991, after the plant was returned to pre-event conditions and all concerns resolved, the Operations Shift Supervisor, with approval and concurrence from the Plant Manager, the Superintendent Ginna Production, and the Operations Manager declared the Unusual Event terminated in accordance with EPIP 3-4 (Emergency Declassification and Recovery).
All off-site agencies were notified of the termination of the Unusual Event.
