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| {{#Wiki_filter:ACCELERATE~ISTBIEUTION DEMOPOTATION SySTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9105010167 DOC.DATE: 91/04/26 NOTARIZED-NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit.1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION BACKUS,W.H. | | {{#Wiki_filter:ACCELERATE~ISTBIEUTION DEMOPOTATION SySTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| =Rochester Gas:&Electric Corp.MECREDY,R.C.
| | ACCESSION NBR:9105010167 DOC.DATE: 91/04/26 NOTARIZED- NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit. 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION BACKUS,W.H. = |
| Rochester Gas&Electric Corp.RECIP.'NAME RECIPIENT AFFILIATION I | | Rochester Gas:& Electric Corp. |
| | MECREDY,R.C. Rochester Gas & Electric Corp. |
| | RECIP.'NAME RECIPIENT AFFILIATION I |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 91-004-00:on 910328,manual start&loading of"B" emerqency diesel generator. | | LER 91-004-00:on 910328,manual start & loading of "B" emerqency diesel generator. Caused by severe weater & |
| Caused by severe weater&justa.fiable conservatism on part of plant staff.No corrective actions noted.W/910426 ltr.DISTRXBUTION CODE: IE22T COPIES RECEIVED:LTR f ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER),incident Rpt, etc.NOTES:License Exp date i.n accordance with 10CFR2,2.109(9/19/72). | | justa.fiable conservatism on part of plant staff.No corrective actions noted.W/910426 ltr. |
| 05000244 RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB SD NRR/DSX/SP~S D1 REG~XXiE P~0 RGN1 l.I1R 01 EXTERNAL EG&G BRYCE I J~H NRC PDR NSIC POORE,W.COPIES LTTR ENCL 1 1 1 1 2 2 1 1'1 1 1 1 1 1 1 1 1.-1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E'RR/DST/SRXB SE RES/DSXR/EIB L ST LOBBY WARD NSXC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1'1'2 2 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: | | DISTRXBUTION CODE: IE22T COPIES RECEIVED:LTR f ENCL SIZE: |
| PLEASE, HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.,20079) | | TITLE: 50.73/50.9 Licensee Event Report (LER),incident Rpt, etc. |
| TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBEROF COPIES REQUIRED: LTTR 31 ENCL 31 | | NOTES:License Exp date i.n accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H '1 1 NRR/DET/EMEB 7E 1 ' |
| | NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1' NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB SD 1 1 NRR/DST/SICB 7E 1 1 NRR/DSX/SP~S D1 1. -1 'RR/DST/SRXB SE 1 1 REG~XXiE P ~0 1 1 RES/DSXR/EIB 1 1 RGN1 l.I1R 01 1 1 EXTERNAL EG &G BRYCE I J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSXC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE, HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.,20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 |
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| Ak ROCHESTER GAS AND ELECTRlC CORPORA7ION t Ntv I~~Vv>>i"'!rr'ttAte~89 EAST AVENUE, ROCHESTER MY.14649 0001 ROBERT C.MECREDY Vice Pretrdent Cinnrr ttuclesr Production April 26, 1991 TELEPHONE AREA CODETt6 546 2700 U.S.Nuclear Regulatory Commission Document Control Desk , Washington, DC 20555 | | Ak t I~ ~ Vv>> |
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| | rr 'ttAte ROCHESTER GAS AND ELECTRlC CORPORA7ION ~ 89 EAST AVENUE, ROCHESTER MY. 14649 0001 ROBERT C. MECREDY TELEPHONE Vice Pretrdent AREA CODETt6 546 2700 Cinnrr ttuclesr Production April 26, 1991 U.S. Nuclear Regulatory Commission Document Control Desk |
| | , Washington, DC 20555 |
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| ==Subject:== | | ==Subject:== |
| LER 91-004, Manual Start and Loading of"B" Emergency Diesel Generator, Due To Potential Severe Weather ,Conditions While Operating at Reduced Inventory In The RCS R.E.Ginna Nuclear Power Plant Docket No.50-244 This event is being voluntarily reported using the guidance of NUREG 1022, and Supplement No.1 to NUREG 1022.This event is related to, but does not meet, the reporting requirements of 10 CFR 50.73, items-(a)(2}(iii}and (a)(2)(iv).Item (a)(2)(iii)requires reporting of"any natural phenomenon or other external condition that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant." Item (a)(2)(iv) requires reporting of"any event or condition that resulted in the manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS).However, actuation of an ESF, including the RPS, that resulted from and was part of the pre-planned sequence during testing or reactor operation need not be reported." The attached Licensee Event.Report LER 91-004 is hereby voluntarily submitted. | | LER 91-004, Manual Start and Loading of "B" Emergency Diesel Generator, Due To Potential Severe Weather |
| This event has in no way affected the public's health and safety.Ver truly yours, XC: 9105010167 91042c'n PDR aDOCK O-OOO=44 8 PDR Robert C.Me dy U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector p/ | | ,Conditions While Operating at Reduced Inventory In The RCS R.E. Ginna Nuclear Power Plant Docket No. 50-244 This event is being voluntarily reported using the guidance of NUREG 1022, and Supplement No. 1 to NUREG 1022. This event is related to, but does not meet, the reporting requirements of 10 CFR 50.73, items -(a) (2} (iii} and (a)(2) (iv) . Item (a) (2)(iii) requires reporting of "any natural phenomenon or other external condition that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant." Item (a)(2)(iv) requires reporting of "any event or condition that resulted in the manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS). However, actuation of an ESF, including the RPS, that resulted from and was part of the pre-planned sequence during testing or reactor operation need not be reported." The attached Licensee Event .Report LER 91-004 is hereby voluntarily submitted. |
| | This event has in no way affected the public's health and safety. |
| | Ver truly yours, Robert C. Me dy XC: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector p 9105010167 91042c'n PDR 8 |
| | aDOCK O-OOO=44 PDR |
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| 0 MRC form 555A I943 I I;ICENSEE EVENT REPORT (LERI TEXT CONTINUATION U 5 IIUCLKAR RTOULATORY COMMITSIOH ASSROVEO OMI RO 3I50&IOI f TRSIR55 TITlr55 fACILITY NAM5 III OOCK5T NUMRKR ITI v TAII LTR MVM05R I~I 554VTrrTIAL v'TYrOKlrr RVM TR I'rVM~A45 Ol I R.E.Ginna NUclear Power Plant TTIIT IA'R>>>>M>>CO,>>~.
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| v~frrTCfrs~LUIITI 0 5 0 0 0 2 4 4 004-000 2OF 0 7 PRE-EVENT PLANT CONDITIONS The.plant was in the cold shutdown.condition for the Annual Refueling/Maintenance Outage.Reactor Coolant System (RCS)pressure was zero (0)psig and the average of the four (4)connected core exit thermocouples (CETs)was approximately 100 P.The"BLT Residual Heat Removal (RHR)pump was in operation for reactor core decay heat removal.The plant was being maintained at RCS reduced inventory per operating procedure 0-2.3.1 (Draining and'peration at Reduced Inventory of the Reactor Coolant System)with RCS Loop Level at approximately 12 inches.At approximately 0120 EST, March 28, 1991, the Rochester Gas and Electric Corporation (RG6E)Power Control Dispatcher
| | ~ ~ i ~ ~ ~ s 0 ~ ~ - ~ ' |
| .notified the Ginna Control Room of adverse weather condi-tions, (i.e.tornadoes and thunderstorms) in Ontario, Canada, approximately 50 miles north of the Ginna Nuclear Power Plant.At approximately 0130 EST, March 28, 1991, the RG&E Power Control Dispatcher notified the Ginna Control Room of thunderstorms and losses of power in Buffalo, New York, approximately 60 miles west of the plant.They indicated that the storm was moving east at approximately 70 miles per hour.Discussions were held between the Operations Shift Super-visor and the Outage Coordinator about the weather concerns and the fact the plant was operating with the RCS in a reduced inventory condition.
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| Due to the sensitivity to loss of RHR, it was decided that a prudent action would be to start and load a diesel generator.
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| | 0 MRC form 555A U 5 IIUCLKAR RTOULATORY COMMITSIOH I943 I I;ICENSEE EVENT REPORT (LERI TEXT CONTINUATION ASSROVEO OMI RO f 3I50&IOI TRSIR55 TITlr55 fACILITYNAM5 III OOCK5T NUMRKR ITI LTR MVM05R I~ I ~ A45 Ol v TAII 554VTrrTIAL v 'TYrOKlrr RVM TR I 'rVM I |
| | R. E. Ginna NUclear Power TTIIT IA'R>>>>M>>CO,>>~. v ~frrTCfrs Plant 0 5 0 0 0 2 4 4 004 000 2OF 0 7 |
| | ~LUIITI PRE-EVENT PLANT CONDITIONS The. plant was in the cold shutdown condition for the . |
| | Annual Refueling/Maintenance Outage. Reactor Coolant System (RCS) pressure was zero (0) psig and the average of the four (4) connected core exit thermocouples (CETs) was approximately 100 P. The "BLT Residual Heat Removal (RHR) pump was in operation for reactor core decay heat removal. |
| | The plant was being maintained at RCS reduced inventory per operating procedure 0-2.3.1 (Draining and 'peration at Reduced Inventory of the Reactor Coolant System) with RCS Loop Level at approximately 12 inches. |
| | At approximately 0120 EST, March 28, 1991, the Rochester Gas and Electric Corporation (RG6E) Power Control Dispatcher |
| | . notified the Ginna Control Room of adverse weather condi-tions, (i.e. tornadoes and thunderstorms) in Ontario, Canada, approximately 50 miles north of the Ginna Nuclear Power Plant. |
| | At approximately 0130 EST, March 28, 1991, the RG&E Power Control Dispatcher notified the Ginna Control Room of thunderstorms and losses of power in Buffalo, New York, approximately 60 miles west of the plant. They indicated that the storm was moving east at approximately 70 miles per hour. |
| | Discussions were held between the Operations Shift Super-visor and the Outage Coordinator about the weather concerns and the fact the plant was operating with the RCS in a reduced inventory condition. Due to the sensitivity to loss of RHR, it was decided that a prudent action would be to start and load a diesel generator. |
| | 4RCSORM TOSA I545I |
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| MAC terrrr 55AA I%431 LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.5.IIUCLf A1 154ULATOAT COMMITSIOM A&AOVCO OM5 rIO 5IM&IOA 5)ltr155'5/$1%5 I'ACILITY MAM5 lll OOCK5T MUM451 151 I.j1 IIUM451 I~I N 5 4 Mi rr T I A L M rr5 v r IO rr M 1 PA45 15I R.E.Ginna Nuclear Power Plant TEXT III rrrer rrce r rreerrr.rrar ereoere frrC fere~5 I I ITI o s o o o 244 91-004-00 0 40'7 METHOD OP DISCOVERY:
| | ~ |
| The potential event was made apparent by notification from the RGGE Power Control Dispatcher on weather conditions.
| | ~ I I i i i ~ I I i g g I ~ |
| OPERATOR ACTION: The Control Room operators started the"B" Emergency Diesel Generator and tied it into Safeguards 480 Volt Bus f17.Subsequently, after the storm had passed through the area, the Control Room operators removed the"B" Emergency Diesel Generator from service and realigned it for auto standby.Higher supervision and the Nuclear Regulatory Com-mission (NRC)were notified of the'B" Emergency Diesel Generator operation.
| | I N' ~ t N I I 'r' ~ I ~ I ~ |
| G.SAFETY SYSTEM RESPONSES:
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| The"B" Emergency.Diesel Generator, after it was manually started and tied to safeguards 480 Volt Bus f17, operated as designed.III CAUSE OR&TENT A.'MMEDIATE CAUSE: The manual starting and tying into Safeguards 480 Volt Bus f17 of the"B" Emergency Diesel Generator was due to a potential severe weather condition materializing, while the plant was operating with the RCS in a reduced inventory condition.
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| | MAC terrrr 55AA U.5. IIUCLfA1 154ULATOAT COMMITSIOM I%431 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION A&AOVCO OM5 rIO 5IM&IOA 5)ltr155 '5/$ 1%5 I'ACILITYMAM5 lll OOCK5T MUM451 151 I. j1 IIUM451 I ~ I PA45 15I N5 4 Mirr T I A L M |
| t IIAC fons$AAA ISA I l.'ICENSEE EVENT REPORT lLER)TEXT CONTlNUATlON
| | rr5 v M |
| ~I'I.I.NIICLTAA AEOULATOIIY COVVI$$ION Aff AOV$0 OVI NO 3ITO~IIV I$IIfIR$$$QI%$fACILITY NAV$III R.E.Ginna Nuclear Power Plant TEXT III~NVcf e newel.vs~IIIIC AWw~TI I I TI OOCIIAT NIIVICR ITI o 5 o o o 24 491 LtII IILIVO$%I$I$AQMANTIAL:
| | r IO rr 1 |
| YOKlH V A Y V A-,,00 4-00 IIAON ITI 0 6 oF 0 7 However, due to the sensitivity of the plant being in the RCS reduced inventory condition at the time of the forecast of severe weather, a voluntary LER is deemed appropriate.
| | R.E. Ginna Nuclear Power Plant o s o o o 244 91 004 00 0 40' 7 TEXT IIIrrrer rrce r rreerrr. rrar ereoere frrC fere ~ 5 I I ITI METHOD OP DISCOVERY: |
| An assessment was performed considering both the safety consequences and implications.
| | The potential event was made apparent by notification from the RGGE Power Control Dispatcher on weather conditions. |
| of this event with the following results and conclusions:
| | OPERATOR ACTION: |
| o The"B" Emergency Diesel Generator operated as designed.o Both offsite power sources were.either in service or available throughout the event.o Due to the potential for severe weather conditions while the plant was operating with the RCS in the'educed inventory condition, the decision, to start the"B" Emergency Diesel Generator was justifiable.
| | The Control Room operators started the "B" Emergency Diesel Generator and tied Bus f17. |
| Based on the above, it can be concluded that the public's, health and safety was assured at all times.CORRECTIVE ACTION A ACTXON TAKEN TO XU"HEW AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS After the storm had passed'the"B" Emergency Diesel Generator was removed from service and realigned for auto standby.B.ACTZON TAKEN OR PLANNED TO PREVENT RECURRENCE Since the potential severe weather conditions were a natural phenomenon, no corrective actions to prevent recurrence are warranted.
| | it into Safeguards 480 Volt Subsequently, after the storm had passed through the area, the Control Room operators removed the "B" Emergency Diesel Generator from service and realigned it for auto standby. |
| NAC fOAV$AAA I$43 I
| | Higher supervision and the Nuclear Regulatory Com-mission (NRC) were notified of the 'B" Emergency Diesel Generator operation. |
| | G. SAFETY SYSTEM RESPONSES: |
| | The "B" Emergency . Diesel Generator, manually started and tied to safeguards after 480 Volt it was Bus f17, operated as designed. |
| | III CAUSE OR &TENT A.'MMEDIATE CAUSE: |
| | The manual starting and tying into Safeguards 480 Volt Bus f17 of the "B" Emergency Diesel Generator was due to a potential severe weather condition materializing, while the plant was operating with the RCS in a reduced inventory condition. |
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| | $ IIfIR$$ $ QI %$ |
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| | $ AQMANTIAL: YOKlH V A Y V A TEXT III~ NVcf e newel. vs ~ |
| | R.E. Ginna Nuclear Power Plant IIIIC AWw ~ TI I I TI o 5 o o o 24 491 ,,00 4 00 0 6 oF 0 7 However, due to the sensitivity of the plant being in the RCS reduced inventory condition at the time of the forecast of severe weather, a voluntary LER is deemed appropriate. |
| | An assessment was performed considering both the safety consequences and implications. of this event with the following results and conclusions: |
| | o The "B" Emergency Diesel Generator operated as designed. |
| | o Both offsite power sources were. either in service or available throughout the event. |
| | o Due to the potential for severe weather conditions while the plant was operating with the RCS in the |
| | 'educed inventory condition, the decision, to start the "B" Emergency Diesel Generator was justifiable. |
| | Based on the above, it health and safety was assured at all times. |
| | can be concluded that the public's, CORRECTIVE ACTION A ACTXON TAKEN TO XU"HEW AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS After the storm had passed'the "B" Emergency Diesel Generator was removed from service and realigned for auto standby. |
| | B. ACTZON TAKEN OR PLANNED TO PREVENT RECURRENCE Since the potential severe weather conditions were a natural phenomenon, no corrective actions to prevent recurrence are warranted. |
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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
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
ML17265A3671998-07-14014 July 1998
LER 98-002-00:on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R37.W/980714 Ltr
ML17265A1921998-03-11011 March 1998
LER 98-001-00:on 980209,discovered That Boraflex Degradation in SPF Was Greater than Was Assumed.Caused by Dissolution of Boron on Boraflex Matrix,Per 10CFR50.21.Removed Spent Fuel Assemblies from Selected Degraded Storage Rack Cells
ML17265A1641998-02-0606 February 1998
LER 97-007-01:on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified
ML17265A1601998-02-0606 February 1998
LER 97-006-01:on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status
ML17264B1441997-12-17017 December 1997
LER 97-007-00:on 971117,NF Low Range Trip Circuitry for Channel N-44 Was Not Placed in Tripped Condition.Caused by Technical Inadequacies in Procedures.Implemented EWR 4862 to Resolve Design deficiency.W/971217 Ltr
ML17264B1291997-12-0303 December 1997
LER 97-006-00:on 971103,NIS Audible Count Rate Function Was Inoperable.Caused by Misinterpretation of Event Sequence Due to Not Verifying Boron Concentration.B Verification Occurred Every 12 H Per ITS LCO Action 3.9.2.C.3.W/971203 Ltr
ML17264B1271997-12-0101 December 1997
LER 97-005-00:on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset
ML17264B1211997-11-24024 November 1997
LER 97-004-00:on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage
ML17264B0461997-09-29029 September 1997
LER 97-003-01:on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped configuration.W/970929 Ltr
ML17264B0111997-08-27027 August 1997
LER 97-003-00:on 970730,high Steam Flow Bistable Instrument Setpoint Plus Instrument Uncertainty Could Exceed Allowable Value in ITS Was Identified.Caused by Entry Into ITS LCO 3.0.3.Switches Placed in Tripped configuration.W/970827 Ltr
ML17264A9941997-08-19019 August 1997
LER 97-002-00:on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17.W/970819 Ltr
ML17264A9911997-08-11011 August 1997
LER 96-009-02:on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe
ML17264A8271997-03-0303 March 1997
LER 97-001-00:on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F.W/970303 Ltr
ML17264A8071997-01-22022 January 1997
LER 96-015-00:on 961223,discovered Thermally Induced Overpressure Transient Could Occur.Caused by Thermal Expansion of Fluid During Design Basis Accident Condition. Installed Relief Valve on Affected line.W/970122 Ltr
ML17264A7471996-11-27027 November 1996
LER 96-013-00:on 961029,circuit Breakers Closed While in Mode 3 & Resulted in Condition Prohibited by TS Due to Personnel Error.Circuit Breakers for MOV-878B & MOV-878D Were re-opened.W/961127 Ltr
ML17264A6051996-09-19019 September 1996
LER 96-012-00:on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was replaced.W/960919 Ltr
ML17264A6061996-09-19019 September 1996
LER 96-009-01:on 960723,leakage Outside Containment Occurred,Due to Weld Defect,Resulting in Leak Rate Greater than Program Limits.Source of Leakage Isolated from RWST by Freeze Seal,Allowing Exit from ITS LCO 3.0.3.W/960919 Ltr
ML17264A5911996-09-0505 September 1996
LER 96-011-00:on 960807,improper Configuration of Circuit Breaker Occurred,Due to Undetected Internal Interference, Resulting in Automatic Start of Both Auxiliary Feedwater Pumps.Running AFW Pumps Were secured.W/960905 Ltr
ML17264A5921996-09-0505 September 1996
LER 96-010-00:on 960806,latching of Main Turbine While in Mode 4 Occurred,Due to Defective Procedure,Resulting in Automatic Start of Auxiliary Feedwater Pump.Caused by Defective Maint Procedure.Procedure revised.W/960905 Ltr
ML17264A5891996-08-22022 August 1996
LER 96-009-00:on 960723,determined Leak on Piping Sys Outside Containment Greater than Program Limit.Caused by Weld Defect.Pipe & Socket Welds Were Cut Out & Replaced. W/960822 Ltr
ML17264A5781996-08-0606 August 1996
LER 96-008-00:on 960707,main Feedwater Pump Breakers Opened. Caused by Change in Seal Water Differential Pressure Occurred During Sys Realignment.Afw Flow Controlled as Desired to Maintain S/G level.W/960806 Ltr
ML17264A5561996-07-12012 July 1996
LER 96-007-00:on 960612,CR Operators Identified Control Rods Misaligned & Not Moving in Proper Sequence.Caused by Faulty Firing Circuit Card in Rod Control Sys.Faulty Firing Circuit Card in 1BD Power Cabinet replaced.W/960712 Ltr
ML17264A5421996-06-20020 June 1996
LER 96-006-00:on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2.W/960620 Ltr
ML17264A5411996-06-17017 June 1996
LER 96-005-00:on 960516,PORC Determined Deficient Procedures Do Not Meet SRs for Testing safety-related Logic Circuits. Caused by Inadequancies in Individual Testing Procedures. Procedures Re Improved TSs revised.W/960617 Ltr
ML17264A5051996-05-17017 May 1996
LER 96-003-01:on 960308,identified That Both Pressurizer PORVs Inoperable Concurrently Due to Disconnection of Flex Hose to Both PORV Actuators to Install air-sets for Benchset & Limit Switch Activities.Hpes Completed
ML17264A4481996-04-0808 April 1996
LER 96-003-00:on 960308,both Pressurizer Relief Valves Inoperable.Hpes Evaluation Is Being Conducted to Determined Cause of Event.C/As:Both PORVs restored.W/960408 Ltr
ML17264A4471996-04-0808 April 1996
LER 96-002-00:on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography performed.W/960408 Ltr
ML17264A4101996-03-18018 March 1996
LER 96-001-00:on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled. W/960318 Ltr
ML17264A2971995-12-14014 December 1995
LER 95-009-00:on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ 951214 Ltr
ML17264A1711995-09-25025 September 1995
LER 95-008-00:on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating levels.W/950925 Ltr
1999-09-22
[Table view]
Category:RO)
MONTHYEARML17265A7541999-09-22022 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
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
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
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
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
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
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
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
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
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
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
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
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
ML17265A3671998-07-14014 July 1998
LER 98-002-00:on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R37.W/980714 Ltr
ML17265A1921998-03-11011 March 1998
LER 98-001-00:on 980209,discovered That Boraflex Degradation in SPF Was Greater than Was Assumed.Caused by Dissolution of Boron on Boraflex Matrix,Per 10CFR50.21.Removed Spent Fuel Assemblies from Selected Degraded Storage Rack Cells
ML17265A1641998-02-0606 February 1998
LER 97-007-01:on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified
ML17265A1601998-02-0606 February 1998
LER 97-006-01:on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status
ML17264B1441997-12-17017 December 1997
LER 97-007-00:on 971117,NF Low Range Trip Circuitry for Channel N-44 Was Not Placed in Tripped Condition.Caused by Technical Inadequacies in Procedures.Implemented EWR 4862 to Resolve Design deficiency.W/971217 Ltr
ML17264B1291997-12-0303 December 1997
LER 97-006-00:on 971103,NIS Audible Count Rate Function Was Inoperable.Caused by Misinterpretation of Event Sequence Due to Not Verifying Boron Concentration.B Verification Occurred Every 12 H Per ITS LCO Action 3.9.2.C.3.W/971203 Ltr
ML17264B1271997-12-0101 December 1997
LER 97-005-00:on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset
ML17264B1211997-11-24024 November 1997
LER 97-004-00:on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage
ML17264B0461997-09-29029 September 1997
LER 97-003-01:on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped configuration.W/970929 Ltr
ML17264B0111997-08-27027 August 1997
LER 97-003-00:on 970730,high Steam Flow Bistable Instrument Setpoint Plus Instrument Uncertainty Could Exceed Allowable Value in ITS Was Identified.Caused by Entry Into ITS LCO 3.0.3.Switches Placed in Tripped configuration.W/970827 Ltr
ML17264A9941997-08-19019 August 1997
LER 97-002-00:on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17.W/970819 Ltr
ML17264A9911997-08-11011 August 1997
LER 96-009-02:on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe
ML17264A8271997-03-0303 March 1997
LER 97-001-00:on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F.W/970303 Ltr
ML17264A8071997-01-22022 January 1997
LER 96-015-00:on 961223,discovered Thermally Induced Overpressure Transient Could Occur.Caused by Thermal Expansion of Fluid During Design Basis Accident Condition. Installed Relief Valve on Affected line.W/970122 Ltr
ML17264A7471996-11-27027 November 1996
LER 96-013-00:on 961029,circuit Breakers Closed While in Mode 3 & Resulted in Condition Prohibited by TS Due to Personnel Error.Circuit Breakers for MOV-878B & MOV-878D Were re-opened.W/961127 Ltr
ML17264A6051996-09-19019 September 1996
LER 96-012-00:on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was replaced.W/960919 Ltr
ML17264A6061996-09-19019 September 1996
LER 96-009-01:on 960723,leakage Outside Containment Occurred,Due to Weld Defect,Resulting in Leak Rate Greater than Program Limits.Source of Leakage Isolated from RWST by Freeze Seal,Allowing Exit from ITS LCO 3.0.3.W/960919 Ltr
ML17264A5911996-09-0505 September 1996
LER 96-011-00:on 960807,improper Configuration of Circuit Breaker Occurred,Due to Undetected Internal Interference, Resulting in Automatic Start of Both Auxiliary Feedwater Pumps.Running AFW Pumps Were secured.W/960905 Ltr
ML17264A5921996-09-0505 September 1996
LER 96-010-00:on 960806,latching of Main Turbine While in Mode 4 Occurred,Due to Defective Procedure,Resulting in Automatic Start of Auxiliary Feedwater Pump.Caused by Defective Maint Procedure.Procedure revised.W/960905 Ltr
ML17264A5891996-08-22022 August 1996
LER 96-009-00:on 960723,determined Leak on Piping Sys Outside Containment Greater than Program Limit.Caused by Weld Defect.Pipe & Socket Welds Were Cut Out & Replaced. W/960822 Ltr
ML17264A5781996-08-0606 August 1996
LER 96-008-00:on 960707,main Feedwater Pump Breakers Opened. Caused by Change in Seal Water Differential Pressure Occurred During Sys Realignment.Afw Flow Controlled as Desired to Maintain S/G level.W/960806 Ltr
ML17264A5561996-07-12012 July 1996
LER 96-007-00:on 960612,CR Operators Identified Control Rods Misaligned & Not Moving in Proper Sequence.Caused by Faulty Firing Circuit Card in Rod Control Sys.Faulty Firing Circuit Card in 1BD Power Cabinet replaced.W/960712 Ltr
ML17264A5421996-06-20020 June 1996
LER 96-006-00:on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2.W/960620 Ltr
ML17264A5411996-06-17017 June 1996
LER 96-005-00:on 960516,PORC Determined Deficient Procedures Do Not Meet SRs for Testing safety-related Logic Circuits. Caused by Inadequancies in Individual Testing Procedures. Procedures Re Improved TSs revised.W/960617 Ltr
ML17264A5051996-05-17017 May 1996
LER 96-003-01:on 960308,identified That Both Pressurizer PORVs Inoperable Concurrently Due to Disconnection of Flex Hose to Both PORV Actuators to Install air-sets for Benchset & Limit Switch Activities.Hpes Completed
ML17264A4481996-04-0808 April 1996
LER 96-003-00:on 960308,both Pressurizer Relief Valves Inoperable.Hpes Evaluation Is Being Conducted to Determined Cause of Event.C/As:Both PORVs restored.W/960408 Ltr
ML17264A4471996-04-0808 April 1996
LER 96-002-00:on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography performed.W/960408 Ltr
ML17264A4101996-03-18018 March 1996
LER 96-001-00:on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled. W/960318 Ltr
ML17264A2971995-12-14014 December 1995
LER 95-009-00:on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ 951214 Ltr
ML17264A1711995-09-25025 September 1995
LER 95-008-00:on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating levels.W/950925 Ltr
1999-09-22
[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
ACCELERATE~ISTBIEUTION DEMOPOTATION SySTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9105010167 DOC.DATE: 91/04/26 NOTARIZED- NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit. 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION BACKUS,W.H. =
Rochester Gas:& Electric Corp.
MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.'NAME RECIPIENT AFFILIATION I
SUBJECT:
LER 91-004-00:on 910328,manual start & loading of "B" emerqency diesel generator. Caused by severe weater &
justa.fiable conservatism on part of plant staff.No corrective actions noted.W/910426 ltr.
DISTRXBUTION CODE: IE22T COPIES RECEIVED:LTR f ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER),incident Rpt, etc.
NOTES:License Exp date i.n accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H '1 1 NRR/DET/EMEB 7E 1 '
NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1' NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB SD 1 1 NRR/DST/SICB 7E 1 1 NRR/DSX/SP~S D1 1. -1 'RR/DST/SRXB SE 1 1 REG~XXiE P ~0 1 1 RES/DSXR/EIB 1 1 RGN1 l.I1R 01 1 1 EXTERNAL EG &G BRYCE I J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSXC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE, HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.,20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31
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rr 'ttAte ROCHESTER GAS AND ELECTRlC CORPORA7ION ~ 89 EAST AVENUE, ROCHESTER MY. 14649 0001 ROBERT C. MECREDY TELEPHONE Vice Pretrdent AREA CODETt6 546 2700 Cinnrr ttuclesr Production April 26, 1991 U.S. Nuclear Regulatory Commission Document Control Desk
, Washington, DC 20555
Subject:
LER 91-004, Manual Start and Loading of "B" Emergency Diesel Generator, Due To Potential Severe Weather
,Conditions While Operating at Reduced Inventory In The RCS R.E. Ginna Nuclear Power Plant Docket No. 50-244 This event is being voluntarily reported using the guidance of NUREG 1022, and Supplement No. 1 to NUREG 1022. This event is related to, but does not meet, the reporting requirements of 10 CFR 50.73, items -(a) (2} (iii} and (a)(2) (iv) . Item (a) (2)(iii) requires reporting of "any natural phenomenon or other external condition that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant." Item (a)(2)(iv) requires reporting of "any event or condition that resulted in the manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS). However, actuation of an ESF, including the RPS, that resulted from and was part of the pre-planned sequence during testing or reactor operation need not be reported." The attached Licensee Event .Report LER 91-004 is hereby voluntarily submitted.
This event has in no way affected the public's health and safety.
Ver truly yours, Robert C. Me dy XC: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector p 9105010167 91042c'n PDR 8
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0 MRC form 555A U 5 IIUCLKAR RTOULATORY COMMITSIOH I943 I I;ICENSEE EVENT REPORT (LERI TEXT CONTINUATION ASSROVEO OMI RO f 3I50&IOI TRSIR55 TITlr55 fACILITYNAM5 III OOCK5T NUMRKR ITI LTR MVM05R I~ I ~ A45 Ol v TAII 554VTrrTIAL v 'TYrOKlrr RVM TR I 'rVM I
R. E. Ginna NUclear Power TTIIT IA'R>>>>M>>CO,>>~. v ~frrTCfrs Plant 0 5 0 0 0 2 4 4 004 000 2OF 0 7
~LUIITI PRE-EVENT PLANT CONDITIONS The. plant was in the cold shutdown condition for the .
Annual Refueling/Maintenance Outage. Reactor Coolant System (RCS) pressure was zero (0) psig and the average of the four (4) connected core exit thermocouples (CETs) was approximately 100 P. The "BLT Residual Heat Removal (RHR) pump was in operation for reactor core decay heat removal.
The plant was being maintained at RCS reduced inventory per operating procedure 0-2.3.1 (Draining and 'peration at Reduced Inventory of the Reactor Coolant System) with RCS Loop Level at approximately 12 inches.
At approximately 0120 EST, March 28, 1991, the Rochester Gas and Electric Corporation (RG6E) Power Control Dispatcher
. notified the Ginna Control Room of adverse weather condi-tions, (i.e. tornadoes and thunderstorms) in Ontario, Canada, approximately 50 miles north of the Ginna Nuclear Power Plant.
At approximately 0130 EST, March 28, 1991, the RG&E Power Control Dispatcher notified the Ginna Control Room of thunderstorms and losses of power in Buffalo, New York, approximately 60 miles west of the plant. They indicated that the storm was moving east at approximately 70 miles per hour.
Discussions were held between the Operations Shift Super-visor and the Outage Coordinator about the weather concerns and the fact the plant was operating with the RCS in a reduced inventory condition. Due to the sensitivity to loss of RHR, it was decided that a prudent action would be to start and load a diesel generator.
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MAC terrrr 55AA U.5. IIUCLfA1 154ULATOAT COMMITSIOM I%431 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION A&AOVCO OM5 rIO 5IM&IOA 5)ltr155 '5/$ 1%5 I'ACILITYMAM5 lll OOCK5T MUM451 151 I. j1 IIUM451 I ~ I PA45 15I N5 4 Mirr T I A L M
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R.E. Ginna Nuclear Power Plant o s o o o 244 91 004 00 0 40' 7 TEXT IIIrrrer rrce r rreerrr. rrar ereoere frrC fere ~ 5 I I ITI METHOD OP DISCOVERY:
The potential event was made apparent by notification from the RGGE Power Control Dispatcher on weather conditions.
OPERATOR ACTION:
The Control Room operators started the "B" Emergency Diesel Generator and tied Bus f17.
it into Safeguards 480 Volt Subsequently, after the storm had passed through the area, the Control Room operators removed the "B" Emergency Diesel Generator from service and realigned it for auto standby.
Higher supervision and the Nuclear Regulatory Com-mission (NRC) were notified of the 'B" Emergency Diesel Generator operation.
G. SAFETY SYSTEM RESPONSES:
The "B" Emergency . Diesel Generator, manually started and tied to safeguards after 480 Volt it was Bus f17, operated as designed.
III CAUSE OR &TENT A.'MMEDIATE CAUSE:
The manual starting and tying into Safeguards 480 Volt Bus f17 of the "B" Emergency Diesel Generator was due to a potential severe weather condition materializing, while the plant was operating with the RCS in a reduced inventory condition.
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IIAC fons $ AAA NIICLTAA AEOULATOIIYCOVVI$$ ION ISA I AffAOV$ 0 OVI INO l.'ICENSEE EVENT REPORT lLER) TEXT CONTlNUATlON 3ITO~IIV
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R.E. Ginna Nuclear Power Plant IIIIC AWw ~ TI I I TI o 5 o o o 24 491 ,,00 4 00 0 6 oF 0 7 However, due to the sensitivity of the plant being in the RCS reduced inventory condition at the time of the forecast of severe weather, a voluntary LER is deemed appropriate.
An assessment was performed considering both the safety consequences and implications. of this event with the following results and conclusions:
o The "B" Emergency Diesel Generator operated as designed.
o Both offsite power sources were. either in service or available throughout the event.
o Due to the potential for severe weather conditions while the plant was operating with the RCS in the
'educed inventory condition, the decision, to start the "B" Emergency Diesel Generator was justifiable.
Based on the above, it health and safety was assured at all times.
can be concluded that the public's, CORRECTIVE ACTION A ACTXON TAKEN TO XU"HEW AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS After the storm had passed'the "B" Emergency Diesel Generator was removed from service and realigned for auto standby.
B. ACTZON TAKEN OR PLANNED TO PREVENT RECURRENCE Since the potential severe weather conditions were a natural phenomenon, no corrective actions to prevent recurrence are warranted.
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