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| | issue date = 05/08/1990 | | | issue date = 05/08/1990 |
| | title = LER 90-003-02:on 900409,reactor Protection Sys Actuation Occurred Due to Failure of Reactor Coolant Pump Underfrequency Relay Power Supply Capacitor.Caused by Open Supply Breakers.Relay replaced.W/900508 Ltr | | | title = LER 90-003-02:on 900409,reactor Protection Sys Actuation Occurred Due to Failure of Reactor Coolant Pump Underfrequency Relay Power Supply Capacitor.Caused by Open Supply Breakers.Relay replaced.W/900508 Ltr |
| | author name = HARRIS K N, POWELL D R | | | author name = Harris K, Powell D |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:ACCELERATED DHUBUTION DEMONSTIZION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9005160071 DOC.DATE: 90/05/08 NOTARIZED: | | {{#Wiki_filter:ACCELERATED DHUBUTION DEMONSTIZION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO DOCKET FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION POWELL, D.R.Florida Power&Light Co.HARRIS,K.N. | | ACCESSION NBR:9005160071 DOC.DATE: 90/05/08 NOTARIZED: NO DOCKET FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION POWELL, D. R. Florida Power & Light Co. |
| Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION | | HARRIS,K.N. Florida Power & Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 90-003-02:on 900409,unit trip due to under frequency relay failure.W/9 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR | | LER 90-003-02:on 900409,unit trip due to under frequency relay failure. |
| !ENCL 1 SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD2-2 LA EDISON,G INTERNAL: ACNW AEOD/DSP/TPAB DEDRO NRR/DET/EMEB9H3 NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB SE RES/DSIR/EIB EXTERNAL EG&G STUART I V A LPDR NSIC MAYS,G NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 4 4 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD AEOD/DOA AEOD/ROAB/DS P NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB11 NRR/DST/SELB SD NRR DST SPLBSD1 a RGN2 FILE 01 L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A 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 1 1 1 1 NOTE TO ALL"RIDS" RECIPIEhHS: | | W/9 ltr. |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 34 ENCL 34 tF'.,! | | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ! ENCL 1 SIZE: |
| P..ox14000,Juno Beach,FL 33408 0420~AY Os tSBO L-90-143 10 CFR 50.73 U.,S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| Re: Turkey Point Unit 4 Docket No~50-251 Reportable Event: 90-003 Date of Event: April 9, 1990 Unit Tri Due to Underfre uenc Rela Failure The attached Licensee Event Report is being provided pursuant to the requirements, of 10 CFR 50.73 for notification of the subject event.Very r ly yqurs, de%N.Harris Vic resident Tur y Point Plant Nuclear KNH/DRP/JEK/rat cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant>Q0516ppp~
| | NOTES: |
| F QR aOOCV~~OODpgg Por-.an FPL Group company I
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 EDISON,G 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DS P 2 2 DEDRO 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB9H3 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB11 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB SD 1 1 NRR/DST/SICB 7E 1 1 NRR DST SPLBSD1 1 1 NRR/DST/SRXB SE 1 1 a 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL EG&G STUART I V A 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIEhHS: |
| HIIC roi~<<O tr42t LICENSEE EVENT REPORT (LER)U.S.HUCLSAA 1EOULATOAY CooaotSSIOH A~<<AOYED OMI HO f X<<IXII I/2)t SACILITY HAMt Ill Turkey Point Unit 4 TITLE ISI Urt it Trip Due To Under Fre uenc Rela Failure DOCXIT HU>al 1 ITI 0 5 0 0 0 25 1>pF0 IVIHT OATI tll LtA NUMOEA III It<<OAT DATE ITI OTKIA<<AC>LIT>IS INVOLVED a>MONT tr OAV YfAA VEAA SSQVSHTIAL Hutrst 1~rttsrsth OAY YEAA<<ACILI'TY HAtrto OOCXET HUMSIAISI 0 5 0 0 0 0 4 099 09 0 0 0 3 0005 0 8 9 0 0 5 0 0 0 OOEIIATINO MOOS I~>Ootsl A LlvlL 1 0 THIS Al<<OAT IS SUaslTTED<<UASUANT To TKE AIOUIAIMEHTS Oo 10 C<<A f: IC<<oos oos or~oa ot ths/ottoa rrl)ill x a.rSN>u>IH) 20.OOSI sl aMIs>Ill a.ssl<<u>a.res)u)I)a.r SN)ul It>a.rsN)u)a>20.IOSI~I 20.Oa>s)I>
| | 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! |
| IIO 20.oaN)>l))l>
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 34 ENCL 34 |
| 20.O Stol>1)INI SO.OINls)(1)
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| Ihl 20.oa is>II)Irl a.rS>o)u>)s>a.rSN>u))rtl
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| ~I.TSN)u)IVII I I A I'.rtlo>u)IKI)a>
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| a.rt>o)u)W LICE>t I CONTACT OOA TK>S LEA Ill)TS.T I I~I TS.TI I~)OTKEA ISOOCtry ri O<<r<<OCC~rroe rot>ii Trit Hoc<<ones ASSAI HAMf David R.Powel 1, Licensin Su erintendent TELE<<>tOHE HUMSEA AAIA CODE 30 524 6-655 COMPLETE ONE I,INI OOA tACK COAMONENT SAILUAI DISCI>ISO IN TH>S At<<OAT 1121 CAUSE SYSTEM COMOOHEHT MANU>tAC TUAIA EOOATASLE To HOODS SYSTEM COMOONEHT MANU<<AC.TUN IA EOOATAIL TO AMOS.o'%O J+X A 8 C A P G080 SV<<<<LEMINTAL AE<<OAT EX<<ECTED l>A>Ytl Ilt yrr.rt<<i<<toto tX<<tCTto SIISAIISSIOht OATtl AIITAAcT IL<<rK to Iooo At<<ca.t A.sooiorrrtsaty he>orts o<<Nsoosco tyooovt tao hors)IIII MOHTtr OAY EX<<ECTED SUISSISSION DATE lll>YEA<<On April 9, 1990 at 1814 EDT, with Unit 4 in Mode 1 (Power Operation) at 100 percent power, a Reactor Protection System actuation occurred due to a failure of a Reactor Coolant Pump (RCP)underfrequency relay power supply capacitor.
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| The reactor trip occurred because one of three reactor coolant pump power supply breakers opened with the reactor at greater than 45 percent power.The faulty underfrequency re'lay was replaced and Unit 4 was returned to serv'ce.'he RCP power supply underfrequency relays on'both Unit 3 and Unit 4 have been replaced with new models.A review of the failure modes of the replacement relays will be performed and planned maintenance will be developed as appropriate.
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| On April 9, 1990, at 1914 EDT, a four hour report of the event was made to the NRC in accordance with 10 CFR 50.72.NAC Tore&1942>
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| NRC Form 3ddA<983 I LICENSEE NT REPORT (LER)TEXT CONTINUA N U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.3150&)04 EXPIAES.Bl31 85 FACILITY NAME 11)OOCKET NUMBEA 12I YEAR LER NUMBER ld)SEOVSNTIAL h~Mi;NVMSSR REVISION NVMSSR PAGE 13)TURKEY POINT UNIT 4 TEXT N more speciis reh)virid, use edChsiorhei HAC Form 38M's)l)T)I.EVENT DESCRIPTION o s o o o 0 0 3 0002 OF 0 4 On April 9, 1990 at 1814 Eastern Daylight Time (EDT), with Unit 4 in Mode 1 (Power Operations) at 100 percent power, a Reactor Protection System (EIIS:JC)actuation occurred causing a reactor trip.The trip was due to a failure of Reactor Coolant Pump underfrequency relay 4B2 (EIIS:AB Component:81).
| | tF '. |
| The underfrequency relay monitors the 4B 4160 volt bus (EIIS:EB Component:BU) for frequency and trips the 4B and 4C Reactor Coolant Pumps (EIIS:AB Component:P) when an underfrequency condition of 56.1 Hertz or less is sensed by one of two relays.Review of recorded frequency information indicated that no underfrequency condition existed at the time of the trip.The reactor trip occurred when of one of three reactor coolant pump breakers (EIIS:AB Component:BRK) opened with the reactor at greater than 45 percent power.After the trip, pressurizer level declined to a level resulting in letdown isolation.
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| Volume Control Tank (VCT)(EIIS:CB Component:TK) level declined to an indicated 5 percent level.As a result, the following occurred: Charging pump (EIIS:CB Component:P)"B" was started but tripped soon after starting.Charging pump suction did not switch automatically from the VCT to the Refueling Water Storage Tank (RWST)(EIIS:BP Component:TK)
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| .The transfer of charging pump suction from the VCT to the RWST was made manually.After a successful second attempt at starting the"B" charging pump, all three charging pumps were used to restore pressurizer level.Letdown was then restored.At 1845 EDT, with the unit stabilized in Mode 3 (Hot Shutdown), Control room personnel transferred from use of the Emergency Operating Procedures to General Operating Procedure 4-GOP-103,"Power Operation to Hot Standby." At 1914 EDT, a four hour report of the event was made to the NRC in accordance with 10 CFR 50.72.II.EVENT CAUSE The cause of the trip was the internal failure of an underfrequency relay.A capacitor (EIIS:AB Component:CAP) ih the relay's power supply failed causing the relay to change to the tripped position.This relay trip caused the trip of the supply breakers to the 4B and 4C Reactor Coolant Pumps which resulted in a Reactor Protection System trip of the reactor.NRC FORM SddA 19 83)
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| NAC form 366A I9431 LICENSEE ENT REPORT (LER)TEXT CONTINUA I ON U.S.NUCLEAR REGULATORY COMMISSION APPAOVEO OMB NO 3150mTICS EXPIRES;Bl31 85 FACILITY NAME 11)COCKET NUMBER 13)LER NUMBER l61 SEGVENTIAL NUMBER REVISION NVMBEA PAGE 131 TURKEY POINT UNIT 4 TEXT III moro spsseis rerrrrired, use eddin'encl HRC Form 3NA'sl lltl o s o o o 2 0 0 3 0 0 0 3 QF 0 4 III.EVENT SAFETY ANALYSIS Reactor Trip The failed underfrequency relay was part of a one out of two logic.If any of four underfrequency relays fail in a manner similar to that which occurred on April 9, the result is a reactor trip.A reactor trip from 100 percent power is a previously analyzed event.Since the reactor trip response occurred as designed, there was no impact on the'ealth or safety of plant personnel or the general public.2.Reduced Charging Flow.Loss of charging flow is a previously analyzed event that is covered by Emergency Operating Procedures. | | P.. ox14000,Juno Beach,FL 33408 0420 |
| In accordance with these procedures, the suction of the charging pumps was transferred from the VCT to the RWST.Charging was established and pressurizer program level was restored.Therefore there was no impact on the health or safety of plant personnel or the general public.This Licensee Event Report is submitted in accordance with 10 CFR 50.73 (a)(2)(iv).IV.CORRECTIVE ACTIONS Reactor Trip: The failed General Electric model 12SFF18C1A undervoltage relay has been replaced with a newer model 12SFF31D1A. | | ~AY Os tSBO L-90-143 10 CFR 50.73 U.,S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| The installed model is no longer available. | | Re: Turkey Point Unit 4 Docket No 50-251~ |
| The new model is a direct replacement which can be installed into the original case.The 12SFF18C1A and 12SFF23C1A reactor coolant pump underfrequency relays have been replaced on both Unit 3 and 4 with new 12SFF31D1A models.Due to apparent end-of-life internal component failure an appropriate maintenance program will be developed by September 1, 1990 to reduce the probability of relay or capacitor failure.NAC FORM 366A (9 831 NRC Form SddA (S 4131 LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCI.EAR REGULATORY COMMISSION APPAOVEO OMB NO.3(50M(04 EXPIRES.6/31'85 FACILITY NAME (11 TURKEY POINT UNZT 4 DOCKET NUMBER (21 osooo251 LER NUMBER (6)YEAR ggv SEGVSNTIAL S+>?REVISION NVMBSA'NVMSSA 9 0-0 0 3-0 0 I'AGE (31 4 OF 0 4 TEXT N'more spaceis required.use eddieorIe/NRC Farm SSSA'si (171 2.Reduced Charging Flow The effected VCT level transmitter (LT)was repaired and LT 112 and 115 were recalibrated to provide for the automatic transfer of charging pump suction from the VCT to the RWST based upon low VCT level.Calibration of the Unit 3 VCT level transmitters was accomplished during the 1990 spring refueling outage.The root cause of this failure is under investigation. | | Reportable Event: 90-003 Date of Event: April 9, 1990 Unit Tri Due to Underfre uenc Rela Failure The attached Licensee Event Report is being provided pursuant to the requirements, of 10 CFR 50.73 for notification of the subject event. |
| The evaluation will be complete and corrective action will be determined by July 15, 1990.V.ADDZTZONAL ZNFORMATZON Previous Events Similar trips due to the malfunction of underfrequency relays have occurred at Turkey Point in the past.Three trips occurred in late 1978;two on Unit 3 and one on Unit 4.In all three cases no relay failure mode was found.At that time the three relays were replaced with newer models.Until the failure of the capacitor on April 9 the new models have exhibited no malfunction tendencies. | | Very r ly yqurs, N. |
| 2.Component Failures Underfrequency relay Manufactured by General Electric Model Number 12SFF18C1A NRC FORM Sdd*(9 831}} | | de% |
| | Harris Vic resident Tur y Point Plant Nuclear KNH/DRP/JEK/rat cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant |
| | >Q0516ppp~ |
| | F QR aOOCV |
| | ~~OODpgg Por-. |
| | an FPL Group company |
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| | I HIIC roi~ <<O U.S. HUCLSAA 1EOULATOAY CooaotSSIOH tr42t A ~ <<AOYED OMI HO LICENSEE EVENT REPORT (LER) f X<<IXII I/2)t SACILITY HAMt Ill DOCXIT HU>al 1 ITI Turkey Point Unit 4 0 5 0 0 0 25 1> pF0 TITLE ISI Urt it Trip Due To Under Fre uenc It<<OAT DATE ITI Rela Failure OTKIA <<AC>LIT>IS INVOLVED a> |
| | IVIHT OATI tll LtA NUMOEA III SSQVSHTIAL OAY YEAA <<ACILI'TY HAtrto OOCXET HUMSIAISI MONT tr OAV YfAA VEAA Hutrst 1 ~ rttsrsth 0 5 0 0 0 0 4 099 09 0 0 0 3 0005 0 8 9 0 |
| | ~oa ot ths rrl )ill 0 5 0 0 0 OOEIIATINO THIS Al<<OAT IS SUaslTTED <<UASUANT To TKE AIOUIAIMEHTSOo 10 C<<A f: IC<<oos oos or /ottoa TS.T I I~ I MOOS I~ > 20.IOSI ~ I 20.OOSI sl x a.rSN>u>IH) |
| | Ootsl A 20.Oa>s)I> IIO aMIs> Ill a.rS>o) u>)s> TS.TI I ~ ) |
| | LlvlL 20.oaN)>l))l> a.ssl<<u> a.rSN>u))rtl OTKEA ISOOCtry ri O<<r<<OCC 1 0 ~ rroe rot> ii Trit Hoc <<ones 20.O Stol>1)INI a.res) u) I) ~ I.TSN)u) IVIII IAI ASSAI SO.OINls)(1) Ihl a.r SN)ul It> '.rtlo>u)IKI)a> |
| | 20.oa is> II ) Irl a.rsN)u) a> a.rt>o) u) W LICE>t I CONTACT OOA TK>S LEA Ill) |
| | HAMf TELE<<>tOHE HUMSEA AAIA CODE David R. Powel 1, Licensin Su erintendent 30 524 6- 655 COMPLETE ONE I,INI OOA tACK COAMONENT SAILUAI DISCI>ISO IN TH>S At<<OAT 1121 MANU>tAC EOOATASLE COMOONEHT MANU<<AC. EOOATAIL CAUSE SYSTEM COMOOHEHT SYSTEM TUN IA TO AMOS .o'%O TUAIA To HOODS J + |
| | X A 8 C A P G080 SV<<<<LEMINTAL AE<<OAT EX<<ECTED l>A> MOHTtr OAY YEA<< |
| | EX<<ECTED SUISSISSION DATE lll> |
| | Ytl Ilt yrr. rt<<i<<toto tX<<tCTto SIISAIISSIOht OATtl AIITAAcTIL<<rK to Iooo At<<ca. t A. sooiorrrtsaty he>orts o<<Nsoosco tyooovt tao hors) IIII On April 9, 1990 at 1814 EDT, with Unit 4 in Mode 1 (Power Operation) at 100 percent power, a Reactor Protection System actuation occurred due to a failure of a Reactor Coolant Pump (RCP) underfrequency relay power supply capacitor. |
| | The reactor trip occurred because one of three reactor coolant pump power supply breakers opened with the reactor at greater than 45 percent power. The faulty underfrequency 'he re'lay was replaced and Unit 4 was returned to serv'ce. RCP power supply underfrequency relays on 'both Unit 3 and Unit 4 have been replaced with new models. A review of the failure modes of the replacement relays will be performed and planned maintenance will be developed as appropriate. |
| | On April 9, 1990, at 1914 EDT, a four hour report of the event was made to the NRC in accordance with 10 CFR 50.72. |
| | NAC Tore 1942> |
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| | NRC Form 3ddA U.S. NUCLEAR REGULATORY COMMISSION |
| | <983 I LICENSEE NT REPORT (LER) TEXT CONTINUA N APPROVEO OMB NO. 3150&)04 EXPIAES. Bl31 85 FACILITY NAME 11) OOCKET NUMBEA 12I LER NUMBER ld) PAGE 13) |
| | YEAR SEOVSNTIAL h~Mi; REVISION NVMSSR NVMSSR TURKEY POINT UNIT 4 o s o o o 0 0 3 0002 OF 0 4 TEXT N more speciis reh)virid, use edChsiorhei HAC Form 38M's) l)T) |
| | I. EVENT DESCRIPTION On April 9, 1990 at 1814 Eastern Daylight Time (EDT), with Unit 4 in Mode 1 (Power Operations) at 100 percent power, a Reactor Protection System (EIIS:JC) actuation occurred causing a reactor trip. The trip was due to a failure of Reactor Coolant Pump underfrequency relay 4B2 (EIIS:AB Component:81). The underfrequency relay monitors the 4B 4160 volt bus (EIIS:EB Component:BU) for frequency and trips the 4B and 4C Reactor Coolant Pumps (EIIS:AB Component:P) when an underfrequency condition of 56.1 Hertz or less is sensed by one of two relays. Review of recorded frequency information indicated that no underfrequency condition existed at the time of the trip. The reactor trip occurred when of one of three reactor coolant pump breakers (EIIS:AB Component:BRK) opened with the reactor at greater than 45 percent power. |
| | After the trip, pressurizer level declined to a level resulting in letdown isolation. Volume Control Tank (VCT) (EIIS:CB Component:TK) level declined to an indicated 5 percent level. As a result, the following occurred: |
| | Charging pump (EIIS:CB Component:P) "B" was started but tripped soon after starting. Charging pump suction did not switch automatically from the VCT to the Refueling Water Storage Tank (RWST) (EIIS:BP Component:TK) . The transfer of charging pump suction from the VCT to the RWST was made manually. After a successful second attempt at starting the "B" charging pump, all three charging pumps were used to restore pressurizer level. Letdown was then restored. At 1845 EDT, with the unit stabilized in Mode 3 (Hot Shutdown), |
| | Control room personnel transferred from use of the Emergency Operating Procedures to General Operating Procedure 4-GOP-103, "Power Operation to Hot Standby." |
| | At 1914 EDT, a four hour report of the event was made to the NRC in accordance with 10 CFR 50.72. |
| | II. EVENT CAUSE The cause of the trip was the internal failure of an underfrequency relay. A capacitor (EIIS:AB Component:CAP) ih the relay's power supply failed causing the relay to change to the tripped position. This relay trip caused the trip of the supply breakers to the Protection 4B and 4C Reactor Coolant Pumps which resulted in a Reactor System trip of the reactor. |
| | NRC FORM SddA 19 83) |
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| | NAC form 366A U.S. NUCLEAR REGULATORY COMMISSION I9431 LICENSEE ENT REPORT (LER) TEXT CONTINUA I ON APPAOVEO OMB NO 3150mTICS EXPIRES; Bl31 85 FACILITY NAME 11) COCKET NUMBER 13) LER NUMBER l61 PAGE 131 SEGVENTIAL REVISION NUMBER NVMBEA TURKEY POINT UNIT 4 o s o o o 2 0 0 3 0 0 0 3 QF 0 4 TEXT IIImoro spsseis rerrrrired, use eddin'encl HRC Form 3NA'sl lltl III. EVENT SAFETY ANALYSIS Reactor Trip The failed underfrequency relay was part of a one out of two logic. If any of four underfrequency relays fail in a manner similar to that which occurred on April 9, the result is a reactor trip. A reactor trip from 100 percent power is a previously analyzed event. |
| | Since the reactor trip response occurred as designed, there was no impact on the'ealth or safety of plant personnel or the general public. |
| | : 2. Reduced Charging Flow. |
| | Loss of charging flow is a previously analyzed event that is covered by Emergency Operating Procedures. In accordance with these procedures, the suction of the charging pumps was transferred from the VCT to the RWST. Charging was established and pressurizer program level was restored. Therefore there was no impact on the health or safety of plant personnel or the general public. |
| | This Licensee Event Report is submitted in accordance with 10 CFR 50.73 (a) (2) (iv) . |
| | IV. CORRECTIVE ACTIONS Reactor Trip: |
| | The failed General Electric model 12SFF18C1A undervoltage relay has been replaced with a newer model 12SFF31D1A. The installed model is no longer available. The new model is a direct replacement which can be installed into the original case. The 12SFF18C1A and 12SFF23C1A reactor coolant pump underfrequency relays have been replaced on both Unit 3 and 4 with new 12SFF31D1A models. Due to apparent end-of-life internal component failure an appropriate maintenance program will be developed by September 1, 1990 to reduce the probability of relay or capacitor failure. |
| | NAC FORM 366A (9 831 |
| | |
| | NRC Form SddA U.S. NUCI.EAR REGULATORY COMMISSION (S 4131 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPAOVEO OMB NO. 3(50M(04 EXPIRES. 6/31'85 FACILITY NAME (11 DOCKET NUMBER (21 LER NUMBER (6) I'AGE (31 YEAR ggv SEGVSNTIAL NVMBSA ' S+>? |
| | REVISION NVMSSA TURKEY POINT UNZT 4 osooo251 9 0 0 0 3 0 0 4 OF 0 4 TEXT N'more spaceis required. use eddieorIe/NRC Farm SSSA'si (171 |
| | : 2. Reduced Charging Flow The effected VCT level transmitter (LT) was repaired and LT 112 and 115 were recalibrated to provide for the automatic transfer of charging pump suction from the VCT to the RWST based upon low VCT level. Calibration of the Unit 3 VCT level transmitters was accomplished during the 1990 spring refueling outage. The root cause of this failure is under investigation. The evaluation will be complete and corrective action will be determined by July 15, 1990. |
| | V. ADDZTZONAL ZNFORMATZON Previous Events Similar trips due to the malfunction of underfrequency relays have occurred at Turkey Point in the past. |
| | Three trips occurred in late 1978; two on Unit 3 and one on Unit 4. In all three cases no relay failure mode was found. At that time the three relays were replaced with newer models. Until the failure of the capacitor on April 9 the new models have exhibited no malfunction tendencies. |
| | : 2. Component Failures Underfrequency relay Manufactured by General Electric Model Number 12SFF18C1A NRC FORM Sdd* |
| | (9 831}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6121997-08-29029 August 1997 LER 97-007-00:on 970730,automatic Reactor Trip Occurred. Caused by Closure of B Main Steam Isolation Valve.Failed W Relay & Equivalent Relays Were replaced.W/970829 Ltr ML17354A6081997-08-18018 August 1997 LER 97-006-00:on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power cabinets.W/970818 Ltr ML17354A5801997-07-14014 July 1997 LER 97-005-00:on 970618,RCP Oil Collection Sys Was Found Outside Design Basis.Caused Because Design Did Not Consider Component Parts to Be Potential Leakage Sources.Entire RCP Oil Collection Sys Was reviewed.W/970714 Ltr ML17354A5141997-05-22022 May 1997 LER 97-002-00:on 970423,automatic Reactor Tripped.Caused by Actuation of Turbine Overspeed Protection Circuit. Administrative Procedures Governing Inadequate Work Controls Will Be Revised to Capture Lessons learned.W/970522 Ltr ML17354A5061997-05-0909 May 1997 LER 97-003-00:on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in drain.W/970509 Ltr ML17354A5051997-05-0909 May 1997 LER 97-004-00:on 970411,auxiliary Feedwater Automatic Start Upon Trip of All Main Feedwater Pumps,Occurred.Caused by Mispositioned Valve Closing.Valves Listed as Inappropriately Positioned Were repositioned.W/970509 Ltr ML17354A4781997-04-25025 April 1997 LER 97-001-00:on 970327,ECCS Recirculation Loop Leakage Was Found to Be in Condition Outside Design Basis Due to Gasket Movement During Installation During Spring 1966 Reassembly. Gasket Replaced & Pump tested.W/970425 Ltr ML17354A4581997-03-28028 March 1997 LER 97-002-00:on 970303,manual Reactor Trip Following Rod Control Urgent Failure Alarm Occurred.Caused by Phase Failure Detection on Stationary a Circuits of 2BD Rod Control Cabinet.Air Conditioning replaced.W/970328 Ltr ML17354A4511997-03-26026 March 1997 LER 97-001-00:on 970118,missed Surveillance on CR Position Verification Occurred Due to Inoperable Rod Deviation Monitor.Faulty Circuit Common Connection Was Corrected & Rdm Operability Was restored.W/970326 Ltr ML17354A4061997-02-0303 February 1997 LER 96-004-03:on 970107,identified Three Instances of Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Surveillance Procedures Revised ML17354A3771996-12-27027 December 1996 LER 96-012-00:on 961204,determined Containment Average Temp Being Determined Based on Only Two Temp Elements Instead of Three as Required by Tss.Caused by Log Only Requiring One Entry.Log revised.W/961227 Ltr ML17354A3261996-11-0606 November 1996 LER 96-011-00:on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures revised.W/961106 Ltr ML17354A3071996-10-22022 October 1996 LER 96-010-00:on 960924,manual Reactor Shutdown Occurred. Caused by Failed Rod Control Sys Regulation Card in 2AC Power cabinet.2AC Power Cabinet DC Power Supplies,Cabling & Connectors checked.W/961022 Ltr ML17353A8711996-08-27027 August 1996 LER 96-009-00:on 960729,failed to Reflect Heavy Load Design Info in Procedural Controls.Caused by Failure to Incorporate 1982 Procedure Changes.Suspended Lifting of Heavy Loads & Took Turbine Bldg Crane OOS.W/960827 Ltr ML17353A7411996-06-18018 June 1996 LER 96-008-00:on 960521,surveillance Method for Testing Emergency Diesel Generators (EDG) Determined Inadequate. Caused by Personnel Error.All Four EDGs Rapid Start Tested & EDG Surveillance Procedures modified.W/960618 Ltr ML17353A7401996-06-18018 June 1996 LER 96-004-02:on 960524,identified Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Entered Tech Spec Statements,Tested Required Instruments Functions & Revised Plant procedure.W/960618 Ltr ML17353A6901996-05-13013 May 1996 LER 96-004-01:on 960220,identified Potential Tech Spec non-compliance Associated W/Surveillance Testing of AFW Actuation Circuitry on Sg.Caused by Inadequate Surveillance Procedures.Procedures revised.W/960513 Ltr ML17353A6741996-05-0606 May 1996 LER 96-001-00:on 960409,manual Rt Occurred Due to Turbine Governer Control Oil Perturbation.Disassembled & Inspected Governor Valve for Cleanliness & Corrosion products.W/960506 Ltr ML17353A6651996-04-29029 April 1996 LER 96-007-00:on 960329,inadvertent ESF Actuation Occurred During Refueling Outage Due to Cognitive Personnel Error. Personnel Involved Counseled & Integrated Safeguards Test Procedures Being revised.W/960429 Ltr ML17353A6601996-04-25025 April 1996 LER 96-006-00:on 960327,manual Rt Occurred Due to 3C Transformer Lockout & Loss of 3B SG Mfp.Replaced SAM Timer Relay in 3AC16.W/960425 Ltr ML17353A6491996-04-23023 April 1996 LER 96-005-00:on 960326,certain Safety Injection Accumulator Filled Evolutions Resulted in cross-tied Configuration.C/A: Night Order Written & Operations Procedure 3/4-OP-064 revised.W/960423 Ltr ML17353A6051996-03-18018 March 1996 LER 96-003-00:on 960222,two Arpi Inoperable & TS 3.0.3 Entered.Proposed License Amend Submitted to Revise Allowed Misalignment from +/-12 Steps to =/-18 Steps Between Arpi & Dpi at Less than 90% power.W/960318 Ltr ML17353A6041996-03-18018 March 1996 LER 96-004-00:on 960220,surveillance Testing of AFW Actuation Circuitry Was Inadequate.Caused by Inadequate Surveillance Procedures.Tested Untested Portions of Actuation Logic for AFW Automatic Start signal.W/960318 Ltr ML17353A5861996-03-0606 March 1996 LER 96-002-00:on 960209,automatic Turbine Trip/Rt Occurred Due to High SG Level.Caused by Personnel Error.Replaced Both Hinge Pins on B Sgfp Discharge Check valve.W/960306 Ltr ML17353A5761996-03-0101 March 1996 LER 96-001-00:on 960131,intake CWS Flow Rates Found W/ Potential to Be Less than Required by Design Basis.Caused by Influx of Aquatic Grass & Algae Onto Basket Strainers of Icw Flow Path.Mechanically Cleaned strainers.W/960301 Ltr ML17353A4451995-11-0909 November 1995 LER 95-007-00:on 951017,manual Rt Occurred Following Drop of Four Control Rods.Caused by Water Intrusion Into Rod Control Power Cabinet 2BD.Inspected Control Power Cabinet 2BD for Other Water damage.W/951109 Ltr ML17353A4241995-10-12012 October 1995 LER 95-006-00:on 950913,analysis Showed That CCW Exchangers Susceptible to Damage Due to flow-induced Vibration.Ccw Sys Has Been Flow Balanced to Closer tolerances.W/951012 Ltr ML17353A3601995-09-13013 September 1995 LER 95-005-00:on 950818,containment Pressure Testing Procedure Resulted in Inhibiting Both Trains of Containment Pressure from Initiated Esf.Revised Procedure to Require Testing of Each Train separately.W/950913 Ltr ML17353A2951995-07-17017 July 1995 LER 94-005-02:on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer ML17352B1581995-05-0505 May 1995 LER 95-004-00:on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies replaced.W/950505 Ltr ML17352B1181995-04-0707 April 1995 LER 95-003-00:on 950309,intake Cooling Water Flow Rate Through CCW Heat Exchangers Fell Below Assumed Design Basis. Caused by an Influx of Aquatic Grass & Algae Onto Basket Strainers.Strainers cleaned.W/950407 Ltr ML17352B0701995-03-13013 March 1995 LER 95-002-00:on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4.W/950313 Ltr ML17352B0321995-02-0909 February 1995 LER 94-005-01:on 941103,design Defect Found in Safeguards Bus Sequencer Test Logic,Placing Facility Outside Design Basis.Design Mods to Eliminate Software Logic Problems Will Be Implemented During Next Refueling outages.W/950209 Ltr ML17352B0101995-01-20020 January 1995 LER 94-006-00:on 941226,C Main Feedwater Control Valve Failed Closed,Causing Reactor & Turbine Trips.Caused by Loose Screw Terminal Connection.I/P Transducers Replaced W/ New Model W/Different Design Wire connection.W/950120 Ltr ML17352A9511994-12-13013 December 1994 LER 94-006-00:on 941130,Unit 4 Tripped Automatically.Caused by Failure of Flexible Link Connection Between Main Generator B Phase Bus & Associated Isolated Phase Bus Bar. All Bolts on Flexible Link checked.W/941213 Ltr ML17352A8871994-11-10010 November 1994 LER 94-005-00:on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI signal.W/941110 Ltr ML17352A8851994-11-10010 November 1994 LER 94-004-00:on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to automatic.W/941110 Ltr ML17352A8421994-10-21021 October 1994 LER 94-004-00:on 940923,Unit 4 Tripped Automatically from Rated Power.Caused by Faulty Regulator Transistor.Faulty Backup Power Supply Replaced & Maint History for Power Supplies reviewed.W/941021 Ltr ML17352A8431994-10-20020 October 1994 LER 94-005-00:on 940924,Unit 4 Manually Tripped.Caused by Manual Actuation.Light Bulb & Socket replaced.W/941020 Ltr ML17352B1671994-08-16016 August 1994 LER 94-003-00:on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced 1999-07-20
[Table view] Category:RO)
MONTHYEARML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6121997-08-29029 August 1997 LER 97-007-00:on 970730,automatic Reactor Trip Occurred. Caused by Closure of B Main Steam Isolation Valve.Failed W Relay & Equivalent Relays Were replaced.W/970829 Ltr ML17354A6081997-08-18018 August 1997 LER 97-006-00:on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power cabinets.W/970818 Ltr ML17354A5801997-07-14014 July 1997 LER 97-005-00:on 970618,RCP Oil Collection Sys Was Found Outside Design Basis.Caused Because Design Did Not Consider Component Parts to Be Potential Leakage Sources.Entire RCP Oil Collection Sys Was reviewed.W/970714 Ltr ML17354A5141997-05-22022 May 1997 LER 97-002-00:on 970423,automatic Reactor Tripped.Caused by Actuation of Turbine Overspeed Protection Circuit. Administrative Procedures Governing Inadequate Work Controls Will Be Revised to Capture Lessons learned.W/970522 Ltr ML17354A5061997-05-0909 May 1997 LER 97-003-00:on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in drain.W/970509 Ltr ML17354A5051997-05-0909 May 1997 LER 97-004-00:on 970411,auxiliary Feedwater Automatic Start Upon Trip of All Main Feedwater Pumps,Occurred.Caused by Mispositioned Valve Closing.Valves Listed as Inappropriately Positioned Were repositioned.W/970509 Ltr ML17354A4781997-04-25025 April 1997 LER 97-001-00:on 970327,ECCS Recirculation Loop Leakage Was Found to Be in Condition Outside Design Basis Due to Gasket Movement During Installation During Spring 1966 Reassembly. Gasket Replaced & Pump tested.W/970425 Ltr ML17354A4581997-03-28028 March 1997 LER 97-002-00:on 970303,manual Reactor Trip Following Rod Control Urgent Failure Alarm Occurred.Caused by Phase Failure Detection on Stationary a Circuits of 2BD Rod Control Cabinet.Air Conditioning replaced.W/970328 Ltr ML17354A4511997-03-26026 March 1997 LER 97-001-00:on 970118,missed Surveillance on CR Position Verification Occurred Due to Inoperable Rod Deviation Monitor.Faulty Circuit Common Connection Was Corrected & Rdm Operability Was restored.W/970326 Ltr ML17354A4061997-02-0303 February 1997 LER 96-004-03:on 970107,identified Three Instances of Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Surveillance Procedures Revised ML17354A3771996-12-27027 December 1996 LER 96-012-00:on 961204,determined Containment Average Temp Being Determined Based on Only Two Temp Elements Instead of Three as Required by Tss.Caused by Log Only Requiring One Entry.Log revised.W/961227 Ltr ML17354A3261996-11-0606 November 1996 LER 96-011-00:on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures revised.W/961106 Ltr ML17354A3071996-10-22022 October 1996 LER 96-010-00:on 960924,manual Reactor Shutdown Occurred. Caused by Failed Rod Control Sys Regulation Card in 2AC Power cabinet.2AC Power Cabinet DC Power Supplies,Cabling & Connectors checked.W/961022 Ltr ML17353A8711996-08-27027 August 1996 LER 96-009-00:on 960729,failed to Reflect Heavy Load Design Info in Procedural Controls.Caused by Failure to Incorporate 1982 Procedure Changes.Suspended Lifting of Heavy Loads & Took Turbine Bldg Crane OOS.W/960827 Ltr ML17353A7411996-06-18018 June 1996 LER 96-008-00:on 960521,surveillance Method for Testing Emergency Diesel Generators (EDG) Determined Inadequate. Caused by Personnel Error.All Four EDGs Rapid Start Tested & EDG Surveillance Procedures modified.W/960618 Ltr ML17353A7401996-06-18018 June 1996 LER 96-004-02:on 960524,identified Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Entered Tech Spec Statements,Tested Required Instruments Functions & Revised Plant procedure.W/960618 Ltr ML17353A6901996-05-13013 May 1996 LER 96-004-01:on 960220,identified Potential Tech Spec non-compliance Associated W/Surveillance Testing of AFW Actuation Circuitry on Sg.Caused by Inadequate Surveillance Procedures.Procedures revised.W/960513 Ltr ML17353A6741996-05-0606 May 1996 LER 96-001-00:on 960409,manual Rt Occurred Due to Turbine Governer Control Oil Perturbation.Disassembled & Inspected Governor Valve for Cleanliness & Corrosion products.W/960506 Ltr ML17353A6651996-04-29029 April 1996 LER 96-007-00:on 960329,inadvertent ESF Actuation Occurred During Refueling Outage Due to Cognitive Personnel Error. Personnel Involved Counseled & Integrated Safeguards Test Procedures Being revised.W/960429 Ltr ML17353A6601996-04-25025 April 1996 LER 96-006-00:on 960327,manual Rt Occurred Due to 3C Transformer Lockout & Loss of 3B SG Mfp.Replaced SAM Timer Relay in 3AC16.W/960425 Ltr ML17353A6491996-04-23023 April 1996 LER 96-005-00:on 960326,certain Safety Injection Accumulator Filled Evolutions Resulted in cross-tied Configuration.C/A: Night Order Written & Operations Procedure 3/4-OP-064 revised.W/960423 Ltr ML17353A6051996-03-18018 March 1996 LER 96-003-00:on 960222,two Arpi Inoperable & TS 3.0.3 Entered.Proposed License Amend Submitted to Revise Allowed Misalignment from +/-12 Steps to =/-18 Steps Between Arpi & Dpi at Less than 90% power.W/960318 Ltr ML17353A6041996-03-18018 March 1996 LER 96-004-00:on 960220,surveillance Testing of AFW Actuation Circuitry Was Inadequate.Caused by Inadequate Surveillance Procedures.Tested Untested Portions of Actuation Logic for AFW Automatic Start signal.W/960318 Ltr ML17353A5861996-03-0606 March 1996 LER 96-002-00:on 960209,automatic Turbine Trip/Rt Occurred Due to High SG Level.Caused by Personnel Error.Replaced Both Hinge Pins on B Sgfp Discharge Check valve.W/960306 Ltr ML17353A5761996-03-0101 March 1996 LER 96-001-00:on 960131,intake CWS Flow Rates Found W/ Potential to Be Less than Required by Design Basis.Caused by Influx of Aquatic Grass & Algae Onto Basket Strainers of Icw Flow Path.Mechanically Cleaned strainers.W/960301 Ltr ML17353A4451995-11-0909 November 1995 LER 95-007-00:on 951017,manual Rt Occurred Following Drop of Four Control Rods.Caused by Water Intrusion Into Rod Control Power Cabinet 2BD.Inspected Control Power Cabinet 2BD for Other Water damage.W/951109 Ltr ML17353A4241995-10-12012 October 1995 LER 95-006-00:on 950913,analysis Showed That CCW Exchangers Susceptible to Damage Due to flow-induced Vibration.Ccw Sys Has Been Flow Balanced to Closer tolerances.W/951012 Ltr ML17353A3601995-09-13013 September 1995 LER 95-005-00:on 950818,containment Pressure Testing Procedure Resulted in Inhibiting Both Trains of Containment Pressure from Initiated Esf.Revised Procedure to Require Testing of Each Train separately.W/950913 Ltr ML17353A2951995-07-17017 July 1995 LER 94-005-02:on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer ML17352B1581995-05-0505 May 1995 LER 95-004-00:on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies replaced.W/950505 Ltr ML17352B1181995-04-0707 April 1995 LER 95-003-00:on 950309,intake Cooling Water Flow Rate Through CCW Heat Exchangers Fell Below Assumed Design Basis. Caused by an Influx of Aquatic Grass & Algae Onto Basket Strainers.Strainers cleaned.W/950407 Ltr ML17352B0701995-03-13013 March 1995 LER 95-002-00:on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4.W/950313 Ltr ML17352B0321995-02-0909 February 1995 LER 94-005-01:on 941103,design Defect Found in Safeguards Bus Sequencer Test Logic,Placing Facility Outside Design Basis.Design Mods to Eliminate Software Logic Problems Will Be Implemented During Next Refueling outages.W/950209 Ltr ML17352B0101995-01-20020 January 1995 LER 94-006-00:on 941226,C Main Feedwater Control Valve Failed Closed,Causing Reactor & Turbine Trips.Caused by Loose Screw Terminal Connection.I/P Transducers Replaced W/ New Model W/Different Design Wire connection.W/950120 Ltr ML17352A9511994-12-13013 December 1994 LER 94-006-00:on 941130,Unit 4 Tripped Automatically.Caused by Failure of Flexible Link Connection Between Main Generator B Phase Bus & Associated Isolated Phase Bus Bar. All Bolts on Flexible Link checked.W/941213 Ltr ML17352A8871994-11-10010 November 1994 LER 94-005-00:on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI signal.W/941110 Ltr ML17352A8851994-11-10010 November 1994 LER 94-004-00:on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to automatic.W/941110 Ltr ML17352A8421994-10-21021 October 1994 LER 94-004-00:on 940923,Unit 4 Tripped Automatically from Rated Power.Caused by Faulty Regulator Transistor.Faulty Backup Power Supply Replaced & Maint History for Power Supplies reviewed.W/941021 Ltr ML17352A8431994-10-20020 October 1994 LER 94-005-00:on 940924,Unit 4 Manually Tripped.Caused by Manual Actuation.Light Bulb & Socket replaced.W/941020 Ltr ML17352B1671994-08-16016 August 1994 LER 94-003-00:on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced 1999-07-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML17355A4471999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With 991008 Ltr ML17355A4121999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With 990909 Ltr ML17355A3981999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Turkey Point,Units 3 & 4.With 990809 Ltr ML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17355A3841999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Turkey Point,Units 3 & 4.With 990713 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17355A3611999-06-30030 June 1999 Refueling Outage ISI Rept. ML17355A3511999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Turkey Point,Units 3 & 4.With 990609 Ltr ML17355A3331999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Turkey Point,Units 3 & 4.With 990511 Ltr ML20217B9871999-04-0808 April 1999 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408 ML17355A2881999-04-0505 April 1999 COLR for Turkey Point Unit 4 Cycle 18. ML17355A2911999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Turkey Point,Units 3 & 4.With 990414 Ltr ML17355A2551999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Turkey Point Nuclear Power Plant,Units 3 & 4.With 990315 Ltr ML17355A2261999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Turkey Point,Units 3 & 4.With 990211 Ltr ML17355A2201999-01-20020 January 1999 Refueling Outage ISI Rept. ML17355A1911998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Turkey Point,Units 3 & 4.With 990112 Ltr ML18008A0461998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Turkey Point,Units 3 & 4.With 981209 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1891998-11-0909 November 1998 Simulatory Certification Update 2. ML17354B1901998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Turkey Point,Units 3 & 4.With 981112 Ltr ML17354B1591998-10-23023 October 1998 COLR for Turkey Point Unit 3 Cycle 17. ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B1311998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Turkey Point Unit 3 & 4.With 981012 Ltr ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML17354B0981998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Turkey Points,Units 3 & 4.With 980915 Ltr ML17354B0771998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Turkey Point,Units 3 & 4.W/980810 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354B0241998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Turkey Point,Units 3 & 4.W/980709 Ltr ML17354B0171998-06-29029 June 1998 Rev 1 to PTN-FPER-97-013, Evaluation of Turbine Lube Oil Fire. ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML17354A9711998-05-31031 May 1998 Monthly Operating Repts for Turkey Point,Units 3 & 4. W/980611 Ltr ML17354A9231998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Turkey Point,Units 3 & 4.W/980511 Ltr ML17354A8821998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Turkey Point,Units 3 & 4.W/980409 Ltr ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354B0001998-03-18018 March 1998 Florida Power & Light Topical Quality Asurance Rept, Dtd June 1998 ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A8311998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Turkey Point,Units 3 & 4.W/980311 Ltr ML17354A7871998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Turkey Point,Units 3 & 4.W/980209 Ltr ML17354A7581997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Turkey Point,Unit 3 & 4.W/980112 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A7381997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Turkey Point,Units 3 & 4.W/971215 Ltr ML17354A7211997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Turkey Point,Units 3 & 4.W/971114 Ltr ML17354A7491997-10-13013 October 1997 SG Insp Rept. ML17354A8851997-10-13013 October 1997 FPL Units 3 & 4 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 960408-971013. ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6791997-10-0606 October 1997 COLR Unit 4 Cycle 17, for Turkey Point ML17354A6811997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Turkey Point,Units 3 & 4.W/971009 Ltr 1999-09-30
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ACCELERATED DHUBUTION DEMONSTIZION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9005160071 DOC.DATE: 90/05/08 NOTARIZED: NO DOCKET FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION POWELL, D. R. Florida Power & Light Co.
HARRIS,K.N. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 90-003-02:on 900409,unit trip due to under frequency relay failure.
W/9 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ! ENCL 1 SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 EDISON,G 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DS P 2 2 DEDRO 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB9H3 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB11 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB SD 1 1 NRR/DST/SICB 7E 1 1 NRR DST SPLBSD1 1 1 NRR/DST/SRXB SE 1 1 a 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL EG&G STUART I V A 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIEhHS:
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 34 ENCL 34
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P.. ox14000,Juno Beach,FL 33408 0420
~AY Os tSBO L-90-143 10 CFR 50.73 U.,S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: Turkey Point Unit 4 Docket No 50-251~
Reportable Event: 90-003 Date of Event: April 9, 1990 Unit Tri Due to Underfre uenc Rela Failure The attached Licensee Event Report is being provided pursuant to the requirements, of 10 CFR 50.73 for notification of the subject event.
Very r ly yqurs, N.
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Harris Vic resident Tur y Point Plant Nuclear KNH/DRP/JEK/rat cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant
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I HIIC roi~ <<O U.S. HUCLSAA 1EOULATOAY CooaotSSIOH tr42t A ~ <<AOYED OMI HO LICENSEE EVENT REPORT (LER) f X<<IXII I/2)t SACILITY HAMt Ill DOCXIT HU>al 1 ITI Turkey Point Unit 4 0 5 0 0 0 25 1> pF0 TITLE ISI Urt it Trip Due To Under Fre uenc It<<OAT DATE ITI Rela Failure OTKIA <<AC>LIT>IS INVOLVED a>
IVIHT OATI tll LtA NUMOEA III SSQVSHTIAL OAY YEAA <<ACILI'TY HAtrto OOCXET HUMSIAISI MONT tr OAV YfAA VEAA Hutrst 1 ~ rttsrsth 0 5 0 0 0 0 4 099 09 0 0 0 3 0005 0 8 9 0
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20.oa is> II ) Irl a.rsN)u) a> a.rt>o) u) W LICE>t I CONTACT OOA TK>S LEA Ill)
HAMf TELE<<>tOHE HUMSEA AAIA CODE David R. Powel 1, Licensin Su erintendent 30 524 6- 655 COMPLETE ONE I,INI OOA tACK COAMONENT SAILUAI DISCI>ISO IN TH>S At<<OAT 1121 MANU>tAC EOOATASLE COMOONEHT MANU<<AC. EOOATAIL CAUSE SYSTEM COMOOHEHT SYSTEM TUN IA TO AMOS .o'%O TUAIA To HOODS J +
X A 8 C A P G080 SV<<<<LEMINTAL AE<<OAT EX<<ECTED l>A> MOHTtr OAY YEA<<
EX<<ECTED SUISSISSION DATE lll>
Ytl Ilt yrr. rt<<i<<toto tX<<tCTto SIISAIISSIOht OATtl AIITAAcTIL<<rK to Iooo At<<ca. t A. sooiorrrtsaty he>orts o<<Nsoosco tyooovt tao hors) IIII On April 9, 1990 at 1814 EDT, with Unit 4 in Mode 1 (Power Operation) at 100 percent power, a Reactor Protection System actuation occurred due to a failure of a Reactor Coolant Pump (RCP) underfrequency relay power supply capacitor.
The reactor trip occurred because one of three reactor coolant pump power supply breakers opened with the reactor at greater than 45 percent power. The faulty underfrequency 'he re'lay was replaced and Unit 4 was returned to serv'ce. RCP power supply underfrequency relays on 'both Unit 3 and Unit 4 have been replaced with new models. A review of the failure modes of the replacement relays will be performed and planned maintenance will be developed as appropriate.
On April 9, 1990, at 1914 EDT, a four hour report of the event was made to the NRC in accordance with 10 CFR 50.72.
NAC Tore 1942>
NRC Form 3ddA U.S. NUCLEAR REGULATORY COMMISSION
<983 I LICENSEE NT REPORT (LER) TEXT CONTINUA N APPROVEO OMB NO. 3150&)04 EXPIAES. Bl31 85 FACILITY NAME 11) OOCKET NUMBEA 12I LER NUMBER ld) PAGE 13)
YEAR SEOVSNTIAL h~Mi; REVISION NVMSSR NVMSSR TURKEY POINT UNIT 4 o s o o o 0 0 3 0002 OF 0 4 TEXT N more speciis reh)virid, use edChsiorhei HAC Form 38M's) l)T)
I. EVENT DESCRIPTION On April 9, 1990 at 1814 Eastern Daylight Time (EDT), with Unit 4 in Mode 1 (Power Operations) at 100 percent power, a Reactor Protection System (EIIS:JC) actuation occurred causing a reactor trip. The trip was due to a failure of Reactor Coolant Pump underfrequency relay 4B2 (EIIS:AB Component:81). The underfrequency relay monitors the 4B 4160 volt bus (EIIS:EB Component:BU) for frequency and trips the 4B and 4C Reactor Coolant Pumps (EIIS:AB Component:P) when an underfrequency condition of 56.1 Hertz or less is sensed by one of two relays. Review of recorded frequency information indicated that no underfrequency condition existed at the time of the trip. The reactor trip occurred when of one of three reactor coolant pump breakers (EIIS:AB Component:BRK) opened with the reactor at greater than 45 percent power.
After the trip, pressurizer level declined to a level resulting in letdown isolation. Volume Control Tank (VCT) (EIIS:CB Component:TK) level declined to an indicated 5 percent level. As a result, the following occurred:
Charging pump (EIIS:CB Component:P) "B" was started but tripped soon after starting. Charging pump suction did not switch automatically from the VCT to the Refueling Water Storage Tank (RWST) (EIIS:BP Component:TK) . The transfer of charging pump suction from the VCT to the RWST was made manually. After a successful second attempt at starting the "B" charging pump, all three charging pumps were used to restore pressurizer level. Letdown was then restored. At 1845 EDT, with the unit stabilized in Mode 3 (Hot Shutdown),
Control room personnel transferred from use of the Emergency Operating Procedures to General Operating Procedure 4-GOP-103, "Power Operation to Hot Standby."
At 1914 EDT, a four hour report of the event was made to the NRC in accordance with 10 CFR 50.72.
II. EVENT CAUSE The cause of the trip was the internal failure of an underfrequency relay. A capacitor (EIIS:AB Component:CAP) ih the relay's power supply failed causing the relay to change to the tripped position. This relay trip caused the trip of the supply breakers to the Protection 4B and 4C Reactor Coolant Pumps which resulted in a Reactor System trip of the reactor.
NRC FORM SddA 19 83)
NAC form 366A U.S. NUCLEAR REGULATORY COMMISSION I9431 LICENSEE ENT REPORT (LER) TEXT CONTINUA I ON APPAOVEO OMB NO 3150mTICS EXPIRES; Bl31 85 FACILITY NAME 11) COCKET NUMBER 13) LER NUMBER l61 PAGE 131 SEGVENTIAL REVISION NUMBER NVMBEA TURKEY POINT UNIT 4 o s o o o 2 0 0 3 0 0 0 3 QF 0 4 TEXT IIImoro spsseis rerrrrired, use eddin'encl HRC Form 3NA'sl lltl III. EVENT SAFETY ANALYSIS Reactor Trip The failed underfrequency relay was part of a one out of two logic. If any of four underfrequency relays fail in a manner similar to that which occurred on April 9, the result is a reactor trip. A reactor trip from 100 percent power is a previously analyzed event.
Since the reactor trip response occurred as designed, there was no impact on the'ealth or safety of plant personnel or the general public.
- 2. Reduced Charging Flow.
Loss of charging flow is a previously analyzed event that is covered by Emergency Operating Procedures. In accordance with these procedures, the suction of the charging pumps was transferred from the VCT to the RWST. Charging was established and pressurizer program level was restored. Therefore there was no impact on the health or safety of plant personnel or the general public.
This Licensee Event Report is submitted in accordance with 10 CFR 50.73 (a) (2) (iv) .
IV. CORRECTIVE ACTIONS Reactor Trip:
The failed General Electric model 12SFF18C1A undervoltage relay has been replaced with a newer model 12SFF31D1A. The installed model is no longer available. The new model is a direct replacement which can be installed into the original case. The 12SFF18C1A and 12SFF23C1A reactor coolant pump underfrequency relays have been replaced on both Unit 3 and 4 with new 12SFF31D1A models. Due to apparent end-of-life internal component failure an appropriate maintenance program will be developed by September 1, 1990 to reduce the probability of relay or capacitor failure.
NAC FORM 366A (9 831
NRC Form SddA U.S. NUCI.EAR REGULATORY COMMISSION (S 4131 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPAOVEO OMB NO. 3(50M(04 EXPIRES. 6/31'85 FACILITY NAME (11 DOCKET NUMBER (21 LER NUMBER (6) I'AGE (31 YEAR ggv SEGVSNTIAL NVMBSA ' S+>?
REVISION NVMSSA TURKEY POINT UNZT 4 osooo251 9 0 0 0 3 0 0 4 OF 0 4 TEXT N'more spaceis required. use eddieorIe/NRC Farm SSSA'si (171
- 2. Reduced Charging Flow The effected VCT level transmitter (LT) was repaired and LT 112 and 115 were recalibrated to provide for the automatic transfer of charging pump suction from the VCT to the RWST based upon low VCT level. Calibration of the Unit 3 VCT level transmitters was accomplished during the 1990 spring refueling outage. The root cause of this failure is under investigation. The evaluation will be complete and corrective action will be determined by July 15, 1990.
V. ADDZTZONAL ZNFORMATZON Previous Events Similar trips due to the malfunction of underfrequency relays have occurred at Turkey Point in the past.
Three trips occurred in late 1978; two on Unit 3 and one on Unit 4. In all three cases no relay failure mode was found. At that time the three relays were replaced with newer models. Until the failure of the capacitor on April 9 the new models have exhibited no malfunction tendencies.
- 2. Component Failures Underfrequency relay Manufactured by General Electric Model Number 12SFF18C1A NRC FORM Sdd*
(9 831