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| {{#Wiki_filter:~AC CELE P<TED Dl STMBt'T1 0%DEMO~STRXT104&ZTEk REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8906140291 DOC.DATE: 89/06/05 NOTARIZED: | | {{#Wiki_filter:~ |
| NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION BACKUS,W.H. | | AC CELE P <TED Dl STMBt'T1 0% DEMO~ STRXT104 & ZTEk REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| Rochester Gas&Electric Corp.MECREDY,R.C. | | ACCESSION NBR:8906140291 DOC.DATE: 89/06/05 NOTARIZED: NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION BACKUS,W.H. Rochester Gas & Electric Corp. |
| Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION DOCKET g 05000244 | | MECREDY,R.C. Rochester Gas & Electric Corp. |
| | RECIP.NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 89-002-00:on 890506,safeguards bus undervoltage during relay testing due to inadequate procedure review.W/8 DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). | | LER 89-002-00:on 890506,safeguards bus undervoltage during relay testing due to inadequate procedure review. |
| 05000244 RECIPIENT ID CODE/NAME'D1-3,LA JOHNSON,A INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB DEDRO NRR/DEST/ADE 8H NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RES/DSIR/EIB RGN1 FILE 01 EXTERNAL: EG&G WILLIAMS, S L ST LOBBY WARD NRC PDR NSIC MURPHYIG A COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1-1 1 1 1 4'4 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP IRM/DCTS/DAB NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/PEB 10 REB/RPB 10 EG F 02 PRAB FORD BLDG HOY,A LPDR NSIC MAYS,G COPIES LTTR ENCL 1 1 2 2 1 1 2 2 1 1 1 0 1 1.1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 D S D S NOrE'IO ALL>>RIDS>>RECZPZZNrS: | | W/8 DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: |
| PLEASE HELP US K)REDUCE WASTE!CGNZACT'IHE DCKX>~r CXÃZK)L DESK, RXN Pl-37 (EXr.20079)K)ELIMINATE YOUR NAME~DIBTRIBVTION LISTS R)R DOCUMENIS YOU DON'T NEED!~TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL 42 D D S | | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| | NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID LTTR ENCL ID CODE/NAME LTTR ENCL CODE/NAME'D1-3,LA 1 1 PD1-3 PD 1 1 JOHNSON,A 1 1 D |
| | INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 S AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 IRM/DCTS/DAB 1 1 NRR/DEST/ADE 8H 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1. |
| | NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 1 REB/RPB 10 2 2 NUDOCS-ABSTRACT 1 1 EG F 02 1 1 RES/DSIR/EIB -1 1 PRAB 1 1 RGN1 FILE 01 1 1 EXTERNAL: EG&G WILLIAMS,S 4 '4 FORD BLDG HOY,A 1 1 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHYIG A 1 1 D S |
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| | NOrE 'IO ALL>>RIDS>> RECZPZZNrS: |
| | S PLEASE HELP US RXN Pl-37 (EXr. 20079) K) |
| | LISTS R)R DOCUMENIS K) REDUCE WASTE! |
| | ELIMINATE YOUR NAME YOU DON'T NEED! |
| | ~ |
| | CGNZACT 'IHE DCKX>~r CXÃZK)L DESK, DIBTRIBVTION |
| | ~ TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL 42 |
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| ROCHESTER GAS AND ELECTRIC CORPORATION | | ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001 June 5, 1989 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
| ~89 EAST AVENUE, ROCHESTER, N.Y.14649.0001 June 5, 1989 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | |
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| ==Subject:== | | ==Subject:== |
| LER-89-002, Safeguards Bus Undervoltage During Relay Testing Due To Inadequate Procedure Review Causes the"A" Emergency Diesel Generator To Automatically Start and Accept Load R.E.Ginna Nuclear Power Plant.Docket No.50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv) which requires a report of,"any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF)including the Reactor Protection System (RPS)", the attached Licensee Event Report LER-89-002 is hereby submitted. | | LER-89-002, Safeguards Bus Undervoltage During Relay Testing Due To Inadequate Procedure Review Causes the "A" Emergency Diesel Generator To Automatically Start and Accept Load R.E. Ginna Nuclear Power Plant. |
| This event has in no way affected the public's health and safet:y.XC: V ery truly yours, Robert C.Mecre General Manager Nuclear Production U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 890614029k 890605 PDR ADOCK 05000244 PDC 0 | | Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv) which requires a report of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF) including the Reactor Protection System (RPS)", the attached Licensee Event Report LER-89-002 is hereby submitted. |
| eeAC terre 200 I04)I LICENSEE EVENT REPORT (LER)US.NVCLCAA ACOULATO1Y COMMlSEION AttAOVCO OMO HO.2(50 0(Ore EX4150 0/Er/05 FACILITY NAME lll R.E.Ginna Nuclear Power Plant OOCXCT NVMOCA Ql 060004410F06 a egu s us n ervo tage During Re ay Testing Due To Inadequate Procedure Review Causes The NAN Emer enc Diesel Generator To Start and Acce CVCIIT CATE I~I LCA NVMEEA (4 ACFOAT OATC III OTNC1 FACILITIEC INVOLVCO III MOHTre OAY YEA)I YEAN 550UlNTIAL ee" ACVAIOee NUM051 rh reUeeetA MONTH OAY YEAN~ACILITY reAULO OOCXCT HVMOCA(5)0 5 0 0 0 0 5 0 6 8 9 8 9 0 02 00 60589 0 5 0 0 0 Ot 5 A AT INC MOOC (0)FOIYC1 LcvcL 0 0 0'CHIC t)CFOIIT IC CUOMITTCO W15VAHT T 00.)24)4 Illrl~OQ24IQIlrl
| | This event has in no way affected the public's health and safet:y. |
| ~O.T l(e)QI(re) 50,724)Q)lrW)IAI
| | Very truly yours, Robert C. Mecre General Manager Nuclear Production XC: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 890614029k 890605 PDR ADOCK 05000244 PDC |
| ~OQ24)(l)(rW I IOI 50.)l(~)Q)I~I 20.e00(el 00 J4(el()i~OM(e)QI 00.224IQII4 50,224)QI(0) 50.7 2 4 I 4 I I Wl 10.002 (0)20.000(e)ll)IO 20.400 ie)I)I I 5 I SO.COO 4)I)l(WI 20 ACE 4)(l)(H)2O.COE 4)II l le I LICCHCCE CONTACT tOll'TNIC LEA Ill)0 THC hlovIACMCNTC Ot 10cth fj:/crete rer ee errer el IIee leIIeeeeet/
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| Ill 22.)1(01 TS.T I (e)OTHCA/Stecrry Ie AArrrect terra rert Ie TrrL HAC teeter JCOA/NAME Wesley H.Backus Technical Assistant to the Operations Mana er At(CA COOC 315 TCLCFHOHC HUMEEA COMtLCTC ONE LINC tOA CACN COMFONENT FAILU15 OCCCAIECO IN THIS ACFOAT Ill)CAV5E 5YCTCM CO UFO H CHT MAHUFA('e TUACA EtOrll'AEI,C 4,'~yec+jgt@COMFOHEN'T MANVFAC TVAEA EFOATAOL IP;44%~@y+<4 EUttLCMCNTAL ACFOAT CXFECTCO (l4 YCC/I/yre, cterterre CXFCCTCO SVSMISSIOH OATS/HO AJCTAACT IL/eUt ce taxi terra, tr..rtteererrere/y IIIHar rletrretecr tytear1He Here)IIOI Axe x)yh.MONTH CAY YCAA EXFCCTCO LUI M<$5)ON CATE IIII On May 6, 1989 at 0946 EDST with the reactor in the Cold/Refueling Shutdown Condition, safeguards 480 volt Bus 14 tripped during offsite power modification relay testing.This caused the QAQ Emergency Diesel Generator to automatically start and connect to safeguards 480 volt Bus 14.The underlying cause of the event was due to a typographical error in the Modification Test Procedure that called for the wrong terminal block to be opened for blocking the above bus trip.This typographical error was due to inadequate proofread-ing of last minute changes to the procedure.
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| Corrective action taken was to identify and correct the procedure error and to restore safeguards 480 volt Bus 14 to its normal power supply.NAC Freer 200 (&45)
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| fj HAC Farm SSSA lslsl LICENSEE EVENT REPORT ILER)TEXT CONTINUATION U.S.IIUCLSA+IIlOULATOIY COMMISSIOM AFFIIOYSO OMs IIO SISO&IOo SXFIASS SISIISS FACILITY SIAM@III R.E.Ginna Nuclear Power Plant: TxxT/IF more AMoe e leeveee.Vee eoebFoneF HEMIC foml~'ll I ITS o s o o o 244 89 LSII IIUMSSII LSI SSQVSHTIAL MVM SA 002 ASYISION MVM Se-0 0 020~0 6 I~PRE-EVENT PLANT CONDITIONS The unit was in cold/refueling shutdown for the Annual Refueling Maintenance Outage.An offsite power reconfigura-tion modification was in progress per ERR-4525.DESCRIPTION OP EVENT'.DATES AND APPROXIMATE TIMES FOR MAJOR OCCURRENCES:
| | 0 eeAC terre 200 I04) I US. NVCLCAA ACOULATO1Y COMMlSEION AttAOVCO OMO HO. 2(50 0(Ore LICENSEE EVENT REPORT (LER) EX4150 0/Er/05 FACILITY NAME lll OOCXCT NVMOCA Ql R.E. Ginna Nuclear Power Plant a egu s us n ervo tage During Re ay Testing Due To Inadequate 060004410F06 Procedure Review Causes The NAN Emer enc Diesel Generator To Start and Acce CVCIIT CATE I ~ I LCA NVMEEA (4 ACFOAT OATC III OTNC1 FACILITIEC INVOLVCO III MOHTre OAY YEA)I YEAN 550UlNTIAL ee" ACVAIOee MONTH OAY ~ ACILITYreAULO OOCXCT HVMOCA(5) |
| o May 6, 1989, 0946 EDST: Event date and time.'May 6, 1989, 0946 EDST: Discovery date and time.o May 6, 1989, 0952 EDST: Safeguards Bus 14 Normal Power Supply Restored.o May 6, 1989, 0952 EDST: Safeguards Bus 14"A" Emergency Diesel Generator Power Supply Terminated and"Bss Emergency Diesel Generator Stopped and Lined Up for Auto Standby.B.EVENT: On May 6, 1989 at 0946 EDST, the reactor was in the cold/refueling shutdown condition.
| | NUM051 rh reUeeetA YEAN 0 5 0 0 0 0 5 0 6 8 9 8 9 0 02 00 60589 0 5 0 0 0 Ot 5 A AT INC |
| Relay testing was in progress on 4160 volt safeguards Bus 12A per step 6.2.5.1.1 of station modification procedure SM-4525.15.During the performance of relay testing on 12A, differential relay 87B/12A operated lockout bus relay 86B/12A, which tripped the station service transformer breaker (14SS-4160V) causing an under-voltage condition on 480 volt safeguards Bus 14.The"A" Emergency Diesel Generator Automatically started, as required, due to the undervoltage condition on 480 volt safeguards Bus 14 and sub-sequently connected to Bus 14 as required.'vAC FOAM SSSA IS4SI 4
| | 'CHIC t)CFOIIT IC CUOMITTCO W15VAHT T 0 THC hlovIACMCNTC Ot 10cth fj: /crete rer ee errer el IIee leIIeeeeet/ Ill MOOC (0) |
| NRC tat~2SSA I 0421 LICENSEE EVENT REPORT (LER)TEXT CONTINuATION U.S, NUCLCAR RlOULATORY COMMISSION AttROVCO OMS NO 2150MI04 Txt>RSS SISICSS tACILITY NAME III OOCKCT NUM02R 12I LSR NUM02R ISI*SSOVSNTIAL NUM SR RSVOlON NUM SR tAOI I21 R.E.Ginna Nuclear Power Plant T29cT Ilf ecece Nwce e~eee acccRAeMI NJIC Fcecn~'el IITI o s o o o 244 8 9 002-00 03OF06 C.D.E.INOPERABLE STRUCTURES t COMPONENTS t OR SYSTEMS THAT CONTRIBUTED TO THE EVENT: None.OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED: None.METHOD OF DISCOVERY:
| | : 10. 002 (0) 20.e00(el 00.) 24)4 Illrl 22.)1(01 FOIYC1 20.000(e) ll) IO 00 J4(el()i ~ OQ24IQIlrl TS.T I (e) |
| The event was immediately apparent due to alarms and indications in the Control Room.F.OPERATOR ACTION: Following the Bus 14 undervoltage and"ATI Emergency-Diesel Generator Automatic Start and the Tie Breaker Closure to Bus 14, the Control Room Operators immed-iately verified proper voltage on Bus 14 and that the"A" Emergency Diesel Generator displayed proper voltage and frequency. | | LcvcL 0 0 0 20.400 ie) I) I I 5 I ~OM(e)QI ~ O.T l(e)QI(re) OTHCA /Stecrry Ie AArrrect terra rert Ie TrrL HAC teeter SO.COO 4) I) l(WI 00.224IQII4 50,724)Q)lrW)IAI JCOA/ |
| G.SAFETY SYSTEM RESPONSES:
| | 20 ACE 4)(l ) (H ) 50,224)QI(0) ~ OQ24)(l) (rW I IOI 2O.COE 4) II l le I 50.7 2 4 I 4 I I Wl 50.)l( ~ )Q)I ~ I LICCHCCE CONTACT tOll 'TNIC LEA Ill) |
| The"A" Emergency Diesel Generator automatically started and tied into 480 volt safeguards Bus 14 due to a valid undervoltage signal on Bus 14.IZZ.CAUSE OP A.IMMEDIATE CAUSE: The automatic actuation of the"A" Emergency Diesel Generator and subsequent tie into Bus 14 was due to a valid undervoltage signal from the Bus 14 undervoltage monitoring system.wRc foRM ssee<942 I
| | NAME TCLCFHOHC HUMEEA Wesley H. Backus At(CA COOC Technical Assistant to the Operations Mana er 315 COMtLCTC ONE LINC tOA CACN COMFONENT FAILU15 OCCCAIECO IN THIS ACFOAT Ill) |
| | CAV5E 5YCTCM CO UFO H CHT MAHUFA('e TUACA EtOrll'AEI,C 4, '~ yec+jgt@ COMFOHEN'T MANVFAC TVAEA EFOATAOL IP;44%~@y+<4 Axe x)yh. |
| | EUttLCMCNTAL ACFOAT CXFECTCO (l4 EXFCCTCO MONTH CAY YCAA LUIM<$5)ON CATE IIII YCC /I/yre, cterterre CXFCCTCO SVSMISSIOH OATS/ HO AJCTAACT IL/eUt ce taxi terra, tr.. rtteererrere/y IIIHar rletrretecr tytear1He Here) IIOI On May 6, 1989 at 0946 EDST with the reactor in the Cold/Refueling Shutdown Condition, safeguards 480 volt Bus 14 tripped during offsite power modification relay testing. This caused the QAQ Emergency Diesel Generator to automatically start and connect to safeguards 480 volt Bus 14. |
| | The underlying cause of the event was due to a typographical error in the Modification Test Procedure that called for the wrong terminal block to be opened for blocking the above bus trip. This typographical error was due to inadequate proofread-ing of last minute changes to the procedure. |
| | Corrective action taken was to identify and correct the procedure error and to restore safeguards 480 volt Bus 14 to its normal power supply. |
| | NAC Freer 200 |
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| NIIC FaNN S~SA 10451 LICENSEE EVENT REPORT ILER)TEXT CONTINUATION U.S.NUCLSAII IISOULATOIIT COMMISSION AFFAOVEO OMS NO 315OWIOI SKFIIISS SISIISS FACILITY NAMS 111 R.E.Ginna Nuclear Power Plant'fQ(T IJT maat t 5 tt it Itt~K att~)YACC FaaIII JC54'll (171 OOCKST NUMSEII Ill o s o o o 24 489 LSII NUMSSII I~I 5 5 0 V 5 N'I I A L H V M t I II 0 0 2 hl VISION NVMtta 0 0 0 40i0 6 B.INTERMEDIATE CAUSE: The valid undervoltage signal was due to an operation of 86B/12A lock-out relay during Bus 12A relay testing which inadvertently tripped the station service transformer breaker (14SS-4160V) to Bus 14.The 86B/12A lock-out relay trip contacts for breaker (14SS-4160V) were not blocked from operating prior to testing because of a typographical error in the SM-4525.15 procedure which called for the wrong terminal block to be opened for blocking the trip (i.e.TFH-10 was opened and TFF-10 should have been opened).C.ROOT CAUSE: The root cause of the event was an inadequate technical.proofreading review of a retyped version of SM-4525.15 subsequent to some last minute changes.This led to the typographical error that caused the event not being identified and corrected prior to the procedures use.ANALYSIS OF EVENT The event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv), which requires reporting of,"any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF)including the Reactor Protection System (RPS)".The starting of the"A" Emergency Diesel Generator was an automatic actuation of an ESF system.An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions:
| | U.S. IIUCLSA+ IIlOULATOIYCOMMISSIOM fj HAC Farm SSSA lslsl LICENSEE EVENT REPORT ILER) TEXT CONTINUATION AFFIIOYSO OMs IIO SISO&IOo SXFIASS SISIISS FACILITY SIAM@ III LSII IIUMSSII LSI SSQVSHTIAL ASYISION MVM SA MVM Se R.E. Ginna Nuclear Power Plant: o s o o o 244 89 002 0 0 020~0 6 TxxT /IF more AMoe e leeveee. Vee eoebFoneF HEMIC foml ~'ll I ITS I ~ PRE-EVENT PLANT CONDITIONS The unit was in cold/refueling shutdown for the Annual Refueling Maintenance Outage. An offsite power reconfigura-tion modification was in progress per ERR-4525. |
| NIIC FOSM SC A 5 ll
| | DESCRIPTION OP EVENT'. |
| | DATES AND APPROXIMATE TIMES FOR MAJOR OCCURRENCES: |
| | o May 6, 1989, 0946 EDST: Event date and time.' |
| | May 6, 1989, 0946 EDST: Discovery date and time. |
| | o May 6, 1989, 0952 EDST: Safeguards Bus 14 Normal Power Supply Restored. |
| | o May 6, 1989, 0952 EDST: Safeguards Bus 14 "A" Emergency Diesel Generator Power Supply Terminated and "Bss Emergency Diesel Generator Stopped and Lined Up for Auto Standby. |
| | B. EVENT: |
| | On May 6, 1989 at 0946 EDST, the reactor was in the cold/refueling shutdown condition. Relay testing was in progress on 4160 volt safeguards Bus 12A per step 6.2.5.1.1 of station modification procedure SM-4525.15. During the performance of relay testing on 12A, differential relay 87B/12A operated lockout bus relay 86B/12A, which tripped the station service transformer breaker (14SS-4160V) causing an under-voltage condition on 480 volt safeguards Bus 14. |
| | The "A" Emergency Diesel Generator Automatically started, as required, due to the undervoltage condition on 480 volt safeguards Bus 14 and sub-sequently connected to Bus 14 as required. |
| | 'vAC FOAM SSSA IS4SI |
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| NIIC farm 554A 10411 LICENSEE EVENT REPORT ILER)TEXT CONTINUATION U.S.NUCLfAII ASOULATONY COMMISSION AffIIOVfO OMS NO SISOWIOS f X~Illf 5 llSI/55 5 AC I LITT N AM 5 I 1 I OOCIIfT NUMlfll If)Lfll NUMOflI ISI SSQVSHTIIL
| | 4 U.S, NUCLCAR RlOULATORY COMMISSION NRC tat~ 2SSA I 0421 LICENSEE EVENT REPORT (LER) TEXT CONTINuATION AttROVCO OMS NO 2150MI04 Txt>RSS SISICSS tACILITYNAME III OOCKCT NUM02R 12I LSR NUM02R ISI tAOI I21 |
| >>VLI 5 1 rr 5 v rs ro N rrV>>SA fAOf ISI R.E.Ginna NUclear'Power Plant>get IIf more N>>ce>>reer>>ee.r>>e osrv>>reI HlIC forrrr~5 I IITI o s o o o 2 4 4 8 9-0 0 2 0005 OF 0 6 There were no operational or safety consequences or implications attributed to the starting of the"A" Emergency Diesel Generator and subsequent tie breaker closure to Bus 14 because: 0 0 The"A" Emergency Diesel Generator and tie-breaker closure to Bus 14 operated as designed.Bus 14 normal power was restored in approximately 6 minutes.0 The other train of safeguards power was energized and available at all times.0 Offsite power was available throughout the event.V.CORRECTIVE ACTION A.ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS: 0.The error in the procedure was identified and changed.The terminal blocks were then changed to their required positions.
| | * SSOVSNTIAL RSVOlON NUM SR NUM SR 244 002 00 03OF06 T29cT Ilfecece Nwce e ~ |
| 0 Normal power was restored to Bus 14 and the"A" Emergency Diesel Generator was stopped and'ealigned for automatic standby.N II C f 0 Ir rrr 554 L IS 551
| | R.E. Ginna Nuclear Power Plant eee acccRAeMI NJIC Fcecn ~'el IITI o s o o o 8 9 C. INOPERABLE STRUCTURES t COMPONENTS t OR SYSTEMS THAT CONTRIBUTED TO THE EVENT: |
| | None. |
| | D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED: |
| | None. |
| | E. METHOD OF DISCOVERY: |
| | The event was immediately apparent due to alarms and indications in the Control Room. |
| | F. OPERATOR ACTION: |
| | Following the Bus 14 undervoltage and "ATI Emergency-Diesel Generator Automatic Start and the Tie Breaker Closure to Bus 14, the Control Room Operators immed-iately verified proper voltage on Bus 14 and that the "A" Emergency Diesel Generator displayed proper voltage and frequency. |
| | G. SAFETY SYSTEM RESPONSES: |
| | The "A" Emergency Diesel Generator automatically started and tied into 480 volt safeguards Bus 14 due to a valid undervoltage signal on Bus 14. |
| | IZZ. CAUSE OP A. IMMEDIATE CAUSE: |
| | The automatic actuation of the "A" Emergency Diesel Generator and subsequent tie into Bus 14 was due to a valid undervoltage signal from the Bus 14 undervoltage monitoring system. |
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| N(IC rrrM 555A 19r151 LICENSEE EVENT REPORT ILER)TEXT CONTINUATION U.5.NUCLCAII (15QULA'IOIIY COMMISSION ATTIIOVSO OMO NO, 5190WIOS 5XI'1155 e(SI(55 SACILITY NAMC 111 R.E.Ginna Nuclear Power Plant 55XT ((I'rr(re rr neaeeC wt rrMMSAS((Y(IC Feme~'r(117)OOCI(5T NU~SII 111 o 5 o o o 24 489 Llll NUMOlll I~I SSOUSNTIAL NUM Sw-0 0 2 iSVISIOH NUM~A-0 rAOS 151 0 6 0 6 B.ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE' The existing station policy and guidance on procedure change proofreading and technical review was re-evaluated and is adequate.The need for adherence to this policy was re-inforced by issuance of a letter to the appro-priate groups by the modification support coordinator. | | U.S. NUCLSAII IISOULATOIIT COMMISSION NIIC FaNN S~SA 10451 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION AFFAOVEO OMS NO 315OWIOI SKFIIISS SISIISS FACILITY NAMS 111 OOCKST NUMSEII Ill LSII NUMSSII I ~ I 5 5 0 V 5 N 'I I A L hl VISION H VM tI II NVMtta R.E. Ginna Nuclear Power Plant |
| 0 The consequences of the inadequate technical review will be reviewed again with those respon-sible for preparing modification test procedures, prior to the 1990 Annual Refueling and Maintenance Outage.0 Meaningful cut-off dates will be established for engineering design outputs for the l990 outage, to ensure adequate review of all required tests, and prevent"last minute requirements from being inserted into test procedures without adequate technical review." VI.ADDITIONAL INFORMATION: | | 'fQ(T IJT maat t 5 tt it Itt~ K att ~ )YACC FaaIII JC54'll (171 o s o o o 24 489 0 0 2 0 0 0 40i0 6 B. INTERMEDIATE CAUSE: |
| A.B.FAILED COMPONENTS: | | The valid undervoltage signal was due to an operation of 86B/12A lock-out relay during Bus 12A relay testing which inadvertently tripped the station service transformer breaker (14SS-4160V) to Bus 14. |
| None.PREVIOUS LERs ON SIMILAR EVENTS: A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause at Ginna Station could be identified. | | The 86B/12A lock-out relay trip contacts for breaker (14SS-4160V) were not blocked from operating prior to testing because of a typographical error in the SM-4525.15 procedure which called for the wrong terminal block to be opened for blocking the trip (i.e. TFH-10 was opened and TFF-10 should have been opened). |
| C.SPECIAL COMMENTS: None.NAC rOklM'SSSA | | C. ROOT CAUSE: |
| <9551 if}} | | The root cause of the event was an inadequate technical . |
| | proofreading review of a retyped version of SM-4525.15 subsequent to some last minute changes. This led to the typographical error that caused the event not being identified and corrected prior to the procedures use. |
| | ANALYSIS OF EVENT The event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv), which requires reporting of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF) including the Reactor Protection System (RPS)". The starting of the "A" Emergency Diesel Generator was an automatic actuation of an ESF system. |
| | An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions: |
| | NIIC FOSM SC A 5 ll |
| | |
| | U.S. NUCLfAIIASOULATONY COMMISSION NIIC farm 554A 10411 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION AffIIOVfOOMS NO SISOWIOS fX ~ Illf5 llSI/55 5 AC I LITT N AM5 I1 I OOCIIfT NUMlfllIf) Lfll NUMOflI ISI fAOf ISI SSQVSHTIIL rr 5 v rs ro N |
| | >>VLI 5 1 rrV>> SA R.E. Ginna NUclear'Power Plant o s o o o 2 4 4 8 90 0 2 0005 OF 0 6 |
| | >get IIfmore N>>ce>> reer>>ee. r>>e osrv>>reI HlIC forrrr ~ 5 I IITI There were no operational or safety consequences or implications attributed to the starting of the "A" Emergency Diesel Generator and subsequent tie breaker closure to Bus 14 because: |
| | 0 The "A" Emergency Diesel Generator and tie-breaker closure to Bus 14 operated as designed. |
| | 0 Bus 14 normal power was restored in approximately 6 minutes. |
| | 0 The other train of safeguards power was energized and available at all times. |
| | 0 Offsite power was available throughout the event. |
| | V. CORRECTIVE ACTION A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS: |
| | .The error in the procedure was identified and changed. |
| | 0 The terminal blocks were then changed to their required positions. |
| | 0 Normal power was restored to Bus 14 and the "A" Emergency Diesel Generator was stopped for automatic standby. and'ealigned N II C f 0 Ir rrr 554 L IS 551 |
| | |
| | U.5. NUCLCAII (15QULA'IOIIY COMMISSION N(IC rrrM 555A 19r151 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION ATTIIOVSO OMO NO, 5190WIOS 5XI'1155 e(SI(55 SACILITY NAMC 111 OOCI(5T NU~SII 111 Llll NUMOlll I ~ I rAOS 151 SSOUSNTIAL iSVISIOH NUM Sw NUM ~ A R.E. Ginna Nuclear Power Plant o 5 o o o 24 489 0 0 2 0 0 6 0 6 55XT ((I'rr(re rr neaeeC wt rrMMSAS((Y(ICFeme ~'r(117) |
| | B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE' The existing station policy and guidance on procedure change proofreading and technical review was re-evaluated and is adequate. |
| | The need for adherence to this policy was re-inforced by issuance of a letter to the appro-priate groups by the modification support coordinator. |
| | 0 The consequences of the inadequate technical review will be reviewed again with those respon-sible for preparing modification test procedures, prior to the 1990 Annual Refueling and Maintenance Outage. |
| | 0 Meaningful cut-off dates will be established for engineering design outputs for the l990 outage, to ensure adequate review of all required tests, and prevent "last minute requirements from being inserted into test procedures without adequate technical review." |
| | VI. ADDITIONAL INFORMATION: |
| | A. FAILED COMPONENTS: |
| | None. |
| | B. PREVIOUS LERs ON SIMILAR EVENTS: |
| | A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause at Ginna Station could be identified. |
| | C. SPECIAL COMMENTS: |
| | None. |
| | NAC rOklM'SSSA |
| | <9551 |
| | |
| | if}} |
Similar Documents at Ginna |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
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: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
~
AC CELE P <TED Dl STMBt'T1 0% DEMO~ STRXT104 & ZTEk REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8906140291 DOC.DATE: 89/06/05 NOTARIZED: NO DOCKET g 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
SUBJECT:
LER 89-002-00:on 890506,safeguards bus undervoltage during relay testing due to inadequate procedure review.
W/8 DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID LTTR ENCL ID CODE/NAME LTTR ENCL CODE/NAME'D1-3,LA 1 1 PD1-3 PD 1 1 JOHNSON,A 1 1 D
INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 S AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 IRM/DCTS/DAB 1 1 NRR/DEST/ADE 8H 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1.
NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 1 REB/RPB 10 2 2 NUDOCS-ABSTRACT 1 1 EG F 02 1 1 RES/DSIR/EIB -1 1 PRAB 1 1 RGN1 FILE 01 1 1 EXTERNAL: EG&G WILLIAMS,S 4 '4 FORD BLDG HOY,A 1 1 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHYIG A 1 1 D S
D D
NOrE 'IO ALL>>RIDS>> RECZPZZNrS:
S PLEASE HELP US RXN Pl-37 (EXr. 20079) K)
LISTS R)R DOCUMENIS K) REDUCE WASTE!
ELIMINATE YOUR NAME YOU DON'T NEED!
~
CGNZACT 'IHE DCKX>~r CXÃZK)L DESK, DIBTRIBVTION
~ TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL 42
ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001 June 5, 1989 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
LER-89-002, Safeguards Bus Undervoltage During Relay Testing Due To Inadequate Procedure Review Causes the "A" Emergency Diesel Generator To Automatically Start and Accept Load R.E. Ginna Nuclear Power Plant.
Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv) which requires a report of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF) including the Reactor Protection System (RPS)", the attached Licensee Event Report LER-89-002 is hereby submitted.
This event has in no way affected the public's health and safet:y.
Very truly yours, Robert C. Mecre General Manager Nuclear Production XC: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 890614029k 890605 PDR ADOCK 05000244 PDC
0 eeAC terre 200 I04) I US. NVCLCAA ACOULATO1Y COMMlSEION AttAOVCO OMO HO. 2(50 0(Ore LICENSEE EVENT REPORT (LER) EX4150 0/Er/05 FACILITY NAME lll OOCXCT NVMOCA Ql R.E. Ginna Nuclear Power Plant a egu s us n ervo tage During Re ay Testing Due To Inadequate 060004410F06 Procedure Review Causes The NAN Emer enc Diesel Generator To Start and Acce CVCIIT CATE I ~ I LCA NVMEEA (4 ACFOAT OATC III OTNC1 FACILITIEC INVOLVCO III MOHTre OAY YEA)I YEAN 550UlNTIAL ee" ACVAIOee MONTH OAY ~ ACILITYreAULO OOCXCT HVMOCA(5)
NUM051 rh reUeeetA YEAN 0 5 0 0 0 0 5 0 6 8 9 8 9 0 02 00 60589 0 5 0 0 0 Ot 5 A AT INC
'CHIC t)CFOIIT IC CUOMITTCO W15VAHT T 0 THC hlovIACMCNTC Ot 10cth fj: /crete rer ee errer el IIee leIIeeeeet/ Ill MOOC (0)
- 10. 002 (0) 20.e00(el 00.) 24)4 Illrl 22.)1(01 FOIYC1 20.000(e) ll) IO 00 J4(el()i ~ OQ24IQIlrl TS.T I (e)
LcvcL 0 0 0 20.400 ie) I) I I 5 I ~OM(e)QI ~ O.T l(e)QI(re) OTHCA /Stecrry Ie AArrrect terra rert Ie TrrL HAC teeter SO.COO 4) I) l(WI 00.224IQII4 50,724)Q)lrW)IAI JCOA/
20 ACE 4)(l ) (H ) 50,224)QI(0) ~ OQ24)(l) (rW I IOI 2O.COE 4) II l le I 50.7 2 4 I 4 I I Wl 50.)l( ~ )Q)I ~ I LICCHCCE CONTACT tOll 'TNIC LEA Ill)
NAME TCLCFHOHC HUMEEA Wesley H. Backus At(CA COOC Technical Assistant to the Operations Mana er 315 COMtLCTC ONE LINC tOA CACN COMFONENT FAILU15 OCCCAIECO IN THIS ACFOAT Ill)
CAV5E 5YCTCM CO UFO H CHT MAHUFA('e TUACA EtOrll'AEI,C 4, '~ yec+jgt@ COMFOHEN'T MANVFAC TVAEA EFOATAOL IP;44%~@y+<4 Axe x)yh.
EUttLCMCNTAL ACFOAT CXFECTCO (l4 EXFCCTCO MONTH CAY YCAA LUIM<$5)ON CATE IIII YCC /I/yre, cterterre CXFCCTCO SVSMISSIOH OATS/ HO AJCTAACT IL/eUt ce taxi terra, tr.. rtteererrere/y IIIHar rletrretecr tytear1He Here) IIOI On May 6, 1989 at 0946 EDST with the reactor in the Cold/Refueling Shutdown Condition, safeguards 480 volt Bus 14 tripped during offsite power modification relay testing. This caused the QAQ Emergency Diesel Generator to automatically start and connect to safeguards 480 volt Bus 14.
The underlying cause of the event was due to a typographical error in the Modification Test Procedure that called for the wrong terminal block to be opened for blocking the above bus trip. This typographical error was due to inadequate proofread-ing of last minute changes to the procedure.
Corrective action taken was to identify and correct the procedure error and to restore safeguards 480 volt Bus 14 to its normal power supply.
NAC Freer 200
(&45)
U.S. IIUCLSA+ IIlOULATOIYCOMMISSIOM fj HAC Farm SSSA lslsl LICENSEE EVENT REPORT ILER) TEXT CONTINUATION AFFIIOYSO OMs IIO SISO&IOo SXFIASS SISIISS FACILITY SIAM@ III LSII IIUMSSII LSI SSQVSHTIAL ASYISION MVM SA MVM Se R.E. Ginna Nuclear Power Plant: o s o o o 244 89 002 0 0 020~0 6 TxxT /IF more AMoe e leeveee. Vee eoebFoneF HEMIC foml ~'ll I ITS I ~ PRE-EVENT PLANT CONDITIONS The unit was in cold/refueling shutdown for the Annual Refueling Maintenance Outage. An offsite power reconfigura-tion modification was in progress per ERR-4525.
DESCRIPTION OP EVENT'.
DATES AND APPROXIMATE TIMES FOR MAJOR OCCURRENCES:
o May 6, 1989, 0946 EDST: Event date and time.'
May 6, 1989, 0946 EDST: Discovery date and time.
o May 6, 1989, 0952 EDST: Safeguards Bus 14 Normal Power Supply Restored.
o May 6, 1989, 0952 EDST: Safeguards Bus 14 "A" Emergency Diesel Generator Power Supply Terminated and "Bss Emergency Diesel Generator Stopped and Lined Up for Auto Standby.
B. EVENT:
On May 6, 1989 at 0946 EDST, the reactor was in the cold/refueling shutdown condition. Relay testing was in progress on 4160 volt safeguards Bus 12A per step 6.2.5.1.1 of station modification procedure SM-4525.15. During the performance of relay testing on 12A, differential relay 87B/12A operated lockout bus relay 86B/12A, which tripped the station service transformer breaker (14SS-4160V) causing an under-voltage condition on 480 volt safeguards Bus 14.
The "A" Emergency Diesel Generator Automatically started, as required, due to the undervoltage condition on 480 volt safeguards Bus 14 and sub-sequently connected to Bus 14 as required.
'vAC FOAM SSSA IS4SI
4 U.S, NUCLCAR RlOULATORY COMMISSION NRC tat~ 2SSA I 0421 LICENSEE EVENT REPORT (LER) TEXT CONTINuATION AttROVCO OMS NO 2150MI04 Txt>RSS SISICSS tACILITYNAME III OOCKCT NUM02R 12I LSR NUM02R ISI tAOI I21
- SSOVSNTIAL RSVOlON NUM SR NUM SR 244 002 00 03OF06 T29cT Ilfecece Nwce e ~
R.E. Ginna Nuclear Power Plant eee acccRAeMI NJIC Fcecn ~'el IITI o s o o o 8 9 C. INOPERABLE STRUCTURES t COMPONENTS t OR SYSTEMS THAT CONTRIBUTED TO THE EVENT:
None.
D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:
None.
E. METHOD OF DISCOVERY:
The event was immediately apparent due to alarms and indications in the Control Room.
F. OPERATOR ACTION:
Following the Bus 14 undervoltage and "ATI Emergency-Diesel Generator Automatic Start and the Tie Breaker Closure to Bus 14, the Control Room Operators immed-iately verified proper voltage on Bus 14 and that the "A" Emergency Diesel Generator displayed proper voltage and frequency.
G. SAFETY SYSTEM RESPONSES:
The "A" Emergency Diesel Generator automatically started and tied into 480 volt safeguards Bus 14 due to a valid undervoltage signal on Bus 14.
IZZ. CAUSE OP A. IMMEDIATE CAUSE:
The automatic actuation of the "A" Emergency Diesel Generator and subsequent tie into Bus 14 was due to a valid undervoltage signal from the Bus 14 undervoltage monitoring system.
wRc foRM ssee
<942 I
U.S. NUCLSAII IISOULATOIIT COMMISSION NIIC FaNN S~SA 10451 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION AFFAOVEO OMS NO 315OWIOI SKFIIISS SISIISS FACILITY NAMS 111 OOCKST NUMSEII Ill LSII NUMSSII I ~ I 5 5 0 V 5 N 'I I A L hl VISION H VM tI II NVMtta R.E. Ginna Nuclear Power Plant
'fQ(T IJT maat t 5 tt it Itt~ K att ~ )YACC FaaIII JC54'll (171 o s o o o 24 489 0 0 2 0 0 0 40i0 6 B. INTERMEDIATE CAUSE:
The valid undervoltage signal was due to an operation of 86B/12A lock-out relay during Bus 12A relay testing which inadvertently tripped the station service transformer breaker (14SS-4160V) to Bus 14.
The 86B/12A lock-out relay trip contacts for breaker (14SS-4160V) were not blocked from operating prior to testing because of a typographical error in the SM-4525.15 procedure which called for the wrong terminal block to be opened for blocking the trip (i.e. TFH-10 was opened and TFF-10 should have been opened).
C. ROOT CAUSE:
The root cause of the event was an inadequate technical .
proofreading review of a retyped version of SM-4525.15 subsequent to some last minute changes. This led to the typographical error that caused the event not being identified and corrected prior to the procedures use.
ANALYSIS OF EVENT The event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv), which requires reporting of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF) including the Reactor Protection System (RPS)". The starting of the "A" Emergency Diesel Generator was an automatic actuation of an ESF system.
An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions:
NIIC FOSM SC A 5 ll
U.S. NUCLfAIIASOULATONY COMMISSION NIIC farm 554A 10411 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION AffIIOVfOOMS NO SISOWIOS fX ~ Illf5 llSI/55 5 AC I LITT N AM5 I1 I OOCIIfT NUMlfllIf) Lfll NUMOflI ISI fAOf ISI SSQVSHTIIL rr 5 v rs ro N
>>VLI 5 1 rrV>> SA R.E. Ginna NUclear'Power Plant o s o o o 2 4 4 8 90 0 2 0005 OF 0 6
>get IIfmore N>>ce>> reer>>ee. r>>e osrv>>reI HlIC forrrr ~ 5 I IITI There were no operational or safety consequences or implications attributed to the starting of the "A" Emergency Diesel Generator and subsequent tie breaker closure to Bus 14 because:
0 The "A" Emergency Diesel Generator and tie-breaker closure to Bus 14 operated as designed.
0 Bus 14 normal power was restored in approximately 6 minutes.
0 The other train of safeguards power was energized and available at all times.
0 Offsite power was available throughout the event.
V. CORRECTIVE ACTION A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:
.The error in the procedure was identified and changed.
0 The terminal blocks were then changed to their required positions.
0 Normal power was restored to Bus 14 and the "A" Emergency Diesel Generator was stopped for automatic standby. and'ealigned N II C f 0 Ir rrr 554 L IS 551
U.5. NUCLCAII (15QULA'IOIIY COMMISSION N(IC rrrM 555A 19r151 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION ATTIIOVSO OMO NO, 5190WIOS 5XI'1155 e(SI(55 SACILITY NAMC 111 OOCI(5T NU~SII 111 Llll NUMOlll I ~ I rAOS 151 SSOUSNTIAL iSVISIOH NUM Sw NUM ~ A R.E. Ginna Nuclear Power Plant o 5 o o o 24 489 0 0 2 0 0 6 0 6 55XT ((I'rr(re rr neaeeC wt rrMMSAS((Y(ICFeme ~'r(117)
B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE' The existing station policy and guidance on procedure change proofreading and technical review was re-evaluated and is adequate.
The need for adherence to this policy was re-inforced by issuance of a letter to the appro-priate groups by the modification support coordinator.
0 The consequences of the inadequate technical review will be reviewed again with those respon-sible for preparing modification test procedures, prior to the 1990 Annual Refueling and Maintenance Outage.
0 Meaningful cut-off dates will be established for engineering design outputs for the l990 outage, to ensure adequate review of all required tests, and prevent "last minute requirements from being inserted into test procedures without adequate technical review."
VI. ADDITIONAL INFORMATION:
A. FAILED COMPONENTS:
None.
B. PREVIOUS LERs ON SIMILAR EVENTS:
A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause at Ginna Station could be identified.
C. SPECIAL COMMENTS:
None.
NAC rOklM'SSSA
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