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| | issue date = 12/17/1992 | | | issue date = 12/17/1992 |
| | title = LER 92-010-00:on 921121,an Automatic Start of 4B EDG Occurred During 3B EDG Safeguards Test.Caused by Inadequate Procedure.Administrative Procedure 0-ADM-501 Will Be revised.W/921217 Ltr | | | title = LER 92-010-00:on 921121,an Automatic Start of 4B EDG Occurred During 3B EDG Safeguards Test.Caused by Inadequate Procedure.Administrative Procedure 0-ADM-501 Will Be revised.W/921217 Ltr |
| | author name = KNORR J E, PLUNKETT T F | | | author name = Knorr J, Plunkett T |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:ACCEI Etu.T DOCUMENT DIST UTION SYSTEM REGULATORY INFORMATION DISTRIBUTION STEM (RIDS)~ACCESS"ON'BR:9212220363 DOC.DATE: 92/12/17 NOTARIZED: | | {{#Wiki_filter:ACCEI Etu.T DOCUMENT DIST UTION SYSTEM REGULATORY INFORMATION DISTRIBUTION STEM (RIDS) |
| NO FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C AUTH.NAME AUTHOR AFFILIATION KNORRtJ.E. | | ~ ACCESS"ON'BR:9212220363 DOC.DATE: 92/12/17 NOTARIZED: NO DOCKET FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION KNORRtJ.E. Florida Power & Light Co. |
| Florida Power&Light Co.PLUNKETT,T.F.. | | PLUNKETT,T.F.. Florida Power & Light Co. |
| Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000251 | | RECIP.NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 92-.010-.00:on 921121,an automatic start of 4B EDG occurred during 3B EDG safeguards test.Caused by inadequate procedure..Administrative Procedure 0-ADM-501 wil be revised.W/921217 ltr.DISTRIBUTION CODE: ZE22T COPIES RECEIVED:LTR I ENCL/SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident.Rpt, etc.D NOTES: NRR RAGHAVANP L 05000251 A RECIPIENT ID CODE/NAME PD2-2 LA AULUCKPR INTERNAL: ACNW AEOD/DSP/TPAB NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPBll NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB EXTERNAL EG&G BRYCE s'J H NRC PDR NSIC POORE,W.NOTES: COPIES ,LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2.PD AEOD/DOA AEOD/ROAB/DSP NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR'ST SPLB8D1 G FIL 02 RGN2 LE 01 L ST LOBBY WARD NSIC MURPHYPG.A NUDOCS FULL TXT COPIES'TTR 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 D'D D-D NOTE TO ALL"RIDS" RECIPIENTS: | | LER 92-.010-.00:on 921121,an automatic start of 4B EDG occurred during 3B EDG safeguards test. Caused by inadequate D procedure..Administrative Procedure 0-ADM-501 wil be revised.W/921217 ltr. |
| PLEASE HELP US TO REDUCE WASTEl CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM'DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl D FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 0 | | DISTRIBUTION CODE: ZE22T COPIES RECEIVED:LTR I ENCL / SIZE: |
| P.Q.6ox 029100, Miam>, FL, 33102-9100 i=PL L-92-335 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: 92-010-00 Automatic Start of 4B Emer enc Diesel Generator The attached Licensee Event Report 251'-92-010-00 is being provided in accordance with 10 CFR 50.73 (a)(2)(iv).If there are any questions, please contact us.Very truly yours, my~/-g+T.F.Plunkett Vice President Turkey Point Nuclear TFP/JEK/jk enclosure cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Ross C.Butcher, Senior Resident Inspector, USNRC, Turkey Point Plant<4 9 t E a~~~92f2220363 92f2f7 PDR ADQCK 0500025i 8 PDR/p,$'
| | NOTES: NRR RAGHAVANPL 05000251 A D |
| | RECIPIENT COPIES RECIPIENT COPIES'TTR ID CODE/NAME ,LTTR ENCL ID CODE/NAME ENCL 'D PD2-2 LA 1 1 PD2-2. PD 1 1 AULUCKPR 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP ,2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 NRR'ST SPLB8D1 1 1 NRR/DST/SRXB 8E 1 1 G FIL 02 1 1 RES/DSIR/EIB 1 1 RGN2 LE 01 1 1 EXTERNAL EG&G BRYCE s'J H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYPG.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTES: 1 1 D |
| | -D D |
| | NOTE TO ALL"RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTEl CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM'DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 |
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| FACILITY NAME l1)LICENSEE EVENT REPORT (LER}DOCKET NUMBER l2)PAGE l3)TURKEY POINT UNIT 4 05000251 oF 3 Automatic Start of 4B Emergency Diesel Generator MON EVENT DATE l5)DAY YR LER NUMBER l6)SEO 6 RPT DATE l1)MON DAY YR OTHER FACILITIES INV l8)FACILITY NANES DOCKET 6 lS)ll 21 92 OPERATING MODE{B)POllER LEVEL l10)100%92 010 00 12 17 92 TURKEY POINT UNIT 3 05000250 THIS REPORT IS SUBMITTED PURSUANT TO THE RE UIREMENTS OF 10 CFR 10 CFR 50.73 a 2 LICENSEE CONTACT FOR THIS LER (12}James E.Knorr, Licensing Engineer COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT l13).TELEPHONE NUMBER 305-246-6757 CAUSE SYSTEM COMPONENT NPRDST caUEE SYSTEM COMPONENT MANUFACTURER NPRDS?SUPPLEMENTAL REPORT EXPECTED{14)NO X YES 0{If yes, coeplete EXPECTED SUBMISSION DaTE)EXPECTED SUBMISSION DATE l15)MONTH DAY ABSTRACT l16)On November 21I 1992I at 1412 ESTF an automatic start of the 4B emergency diesel generator occurred during the 3B emergency diesel generator safeguards test.During this testing, procedure 3-0SP-203.2, Train B Safeguards Integrated Test, required the lifting of leads to prevent the start of the Unit 4 diesel generators upon the initiation of a safety injection signal on Train"B" of Unit 3.Incorrect leads were lifted, due to an inadequate procedure, resulting in the automatic start of the 4B emergency diesel generator upon the injection of a simulated safety injection signal on Unit 3 Train"B".The lead that was lifted resulted in no unexpected action other than the automatic start of the 4B emergency diesel generator.
| | 0 P.Q. 6ox 029100, Miam>, FL, 33102-9100 i=PL L-92-335 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| Therefore, the test of the 3B emergency diesel generator was successful. | | Re: Turkey Point Unit 4 Docket No. 50-251 Reportable Event: 92-010-00 Automatic Start of 4B Emer enc Diesel Generator The attached Licensee Event Report 251'-92-010-00 is being provided in accordance with 10 CFR 50.73 (a) (2) (iv) . |
| | If there are any questions, please contact us. |
| | Very truly yours, my~/- |
| | T. F. Plunkett g+ |
| | Vice President Turkey Point Nuclear TFP/JEK/jk enclosure cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Ross C. Butcher, Senior Resident Inspector, USNRC, Turkey Point Plant |
| | <49t E a~~ |
| | ~ |
| | /p, $ |
| | 92f2220363 92f2f7 PDR ADQCK 0500025i 8 PDR |
| | |
| | LICENSEE EVENT REPORT (LER} |
| | DOCKET NUMBER l2) PAGE l3) |
| | FACILITY NAME l1) |
| | TURKEY POINT UNIT 4 05000251 oF 3 Automatic Start of 4B Emergency Diesel Generator EVENT DATE l5) LER NUMBER l6) RPT DATE l1) OTHER FACILITIES INV l8) |
| | MON DAY YR SEO 6 MON DAY YR FACILITY NANES DOCKET 6 lS) ll 21 92 92 010 00 12 17 92 TURKEY POINT UNIT 3 05000250 OPERATING MODE {B) THIS REPORT IS SUBMITTED PURSUANT TO THE RE UIREMENTS OF 10 CFR 10 CFR 50.73 a 2 POllER LEVEL l10) 100% |
| | LICENSEE CONTACT FOR THIS LER (12} |
| | James E. Knorr, Licensing Engineer TELEPHONE NUMBER 305-246-6757 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT l13). |
| | CAUSE SYSTEM COMPONENT NPRDST caUEE SYSTEM COMPONENT MANUFACTURER NPRDS? |
| | SUPPLEMENTAL REPORT EXPECTED {14) NO X YES 0 EXPECTED SUBMISSION DATE l15) |
| | MONTH DAY |
| | {If yes, coeplete EXPECTED SUBMISSION DaTE) |
| | ABSTRACT l16) |
| | On November 21I 1992I at 1412 ESTF an automatic start of the 4B emergency diesel generator occurred during the 3B emergency diesel generator safeguards test. During this testing, procedure 3-0SP-203.2, Train B Safeguards Integrated Test, required the lifting of leads to prevent the start of the Unit 4 diesel "B" generators upon the initiation of a safety injection signal on Train of Unit 3. Incorrect leads were lifted, due to an inadequate procedure, resulting in the automatic start of the 4B emergency diesel generator upon the injection of a simulated safety injection signal on Unit 3 Train "B". The lead that was lifted resulted in no unexpected action other than the automatic start of the 4B emergency diesel generator. Therefore, the test of the 3B emergency diesel generator was successful. |
| Corrective actions require the inclusion of applicable wire numbers fo lifted leads in procedures requiring leads to be lifted. | | Corrective actions require the inclusion of applicable wire numbers fo lifted leads in procedures requiring leads to be lifted. |
| 0 I LXCENSEE ENT REPORT (LER)TEXT NTXNUATZON FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO.TURKEY POINT UNIT'05000251 92-010-00 02 or 03 EVENT DESCRIPTION On November 21I 1992I at 1412 EST, and automatic start of the 4B emergency diesel generator (EIIS-EK)(IEEE-DG)occurred during the 3B emergency diesel generator safeguards test.At Turkey Point, four safety injection pumps (EIIS-BJ)(IEEE-P)are shared between Units 3 and 4.Each safety injection pump is supplied power from its own safeguards bus (EIIS-EB)(IEEE-BU).Therefore, upon a valid or simulated safety injection signal from either unit, all four emergency-diesel generators automatically start.During safeguards testing of the 3B emergency diesel generator, test procedure 3-OSP-203.2, Train B Safeguards Integrated Test, required the lifting of leads to prevent the start of the Unit 4 emergency diesel generators upon the injection of a simulated safety injection signal on Train B of Unit 3.The terminal location for the lifted leads was specified; however, the specific lead to be lifted of three leads on the terminal was not specified. | | |
| The wrong lead was lifted resulting in the 4B,emergency diesel generator automatically starting on the injection of a simulated Unit 3 safety injection signal.Given the configuration of the jumpers at the time of the test, the 4B emergency diesel generator started as designed.This event was reported to the NRC operations center in accordance with 10 CFR 50.72 (b)'(2)(ii)-ZI.EVENT CAUSE The root cause of the automatic start of the 4B emergency diesel generator was an inadequate procedure. | | 0 I |
| As discussed above, operations surveillance procedure 3-0SP-203.2 did not specify in sufficient detail the actual jumper to be lifted to prevent the 4B emergency diesel generator from starting during the test.IZI.EVENT SAFETY ANALYSIS The 4B emergency diesel generator operated as designed during the integrated safeguards test procedure. | | |
| The automatic start would not have prevented the 4B emergency diesel generator from performing its intended function had a loss of offsite power occurred concurrently. | | LXCENSEE ENT REPORT (LER) TEXT NTXNUATZON FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO. |
| | TURKEY POINT UNIT' 05000251 92-010-00 02 or 03 EVENT DESCRIPTION On November 21I 1992I at 1412 EST, and automatic start of the 4B emergency diesel generator (EIIS-EK) (IEEE-DG) occurred during the 3B emergency diesel generator safeguards test. At Turkey Point, four safety injection pumps (EIIS-BJ) (IEEE-P) are shared between Units 3 and 4. Each safety injection pump is supplied power from its own safeguards bus (EIIS-EB) (IEEE-BU) . Therefore, upon a valid or simulated safety injection signal from either unit, all four emergency -diesel generators automatically start. During safeguards testing of the 3B emergency diesel generator, test procedure 3-OSP-203.2, Train B Safeguards Integrated Test, required the lifting of leads to prevent the start of the Unit 4 emergency diesel generators upon the injection of a simulated safety injection signal on Train B of Unit 3. The terminal location for the lifted leads was specified; however, the specific lead to be lifted of three leads on the terminal was not specified. The wrong lead was lifted resulting in the 4B,emergency diesel generator automatically starting on the injection of a simulated Unit 3 safety injection signal. Given the configuration of the jumpers at the time of the test, the 4B emergency diesel generator started as designed. |
| | This event was reported to the NRC operations center in accordance with 10 CFR 50.72 (b)'(2) (ii)- |
| | ZI. EVENT CAUSE The root cause of the automatic start of the 4B emergency diesel generator was an inadequate procedure. As discussed above, operations surveillance procedure 3-0SP-203.2 did not specify in sufficient detail the actual jumper to be lifted to prevent the 4B emergency diesel generator from starting during the test. |
| | IZI. EVENT SAFETY ANALYSIS The 4B emergency diesel generator operated as designed during the integrated safeguards test procedure. The automatic start would not have prevented the 4B emergency diesel generator from performing its intended function had a loss of offsite power occurred concurrently. |
| Therefore, the health and safety of plant personnel or the general public were not compromised by the automatic start of the 4B emergency diesel generator. | | Therefore, the health and safety of plant personnel or the general public were not compromised by the automatic start of the 4B emergency diesel generator. |
| IV.CORRECTIVE ACTIONS 1.Administrative procedure O-ADM-501, Duties and Responsibilities of System Engineers, will be revised to require the field verification of the adequacy of work operations. | | IV. CORRECTIVE ACTIONS |
| This revision is scheduled to be completed by January 31, 1993. | | : 1. Administrative procedure O-ADM-501, Duties and Responsibilities of System Engineers, will be revised to require the field verification of the adequacy of work operations. This revision is scheduled to be completed by January 31, 1993. |
| Ot LICENSEE EINT REPORT (LER)TEXT 4NTINUATION FACILE'TY NAME DOCKET NUMBER LER NUMBER PAGE NO.TURKEY POZNT UNIT'4 05000251 92-010-00 03 or 03 2.3.Administrative Procedure O-ADM-101, Procedure Writers Guide, will be revised to require the originator of procedure steps requiring lifting of leads or installation of jumpers to field verify.the adequacy'of terminal and or wire identification steps in the procedure steps added.This procedure change is scheduled to be complete by January 31, 1993.An internal memo was issued to all'department heads.The memo directed managers to inform personnel of their responsibility when writing a procedure step, which requires the lift of a wire or installation of a jumper, to provide detail sufficient to result in a unique description of the work location.V.ADDZTZONAL ZNFORMKTZON No other unexpected actuations of engineered.safety features from opposite train testing have occurred in the past two years.}} | | |
| | Ot LICENSEE EINT REPORT (LER) TEXT 4NTINUATION FACILE'TY NAME DOCKET NUMBER LER NUMBER PAGE NO. |
| | TURKEY POZNT UNIT'4 05000251 92-010-00 03 or 03 |
| | : 2. Administrative Procedure O-ADM-101, Procedure Writers Guide, will be revised to ofrequire the originator of procedure steps or installation of jumpers to field requiring lifting leads verify. the adequacy'of terminal and or wire identification steps in the procedure steps added. This procedure change is scheduled to be complete by January 31, 1993. |
| | : 3. An internal memo was issued to all'department heads. The memo directed managers to inform personnel of their responsibility when writing a procedure step, which requires the or installation of a jumper, to provide detail lift sufficient of a wire to result in a unique description of the work location. |
| | V. ADDZTZONAL ZNFORMKTZON No other unexpected actuations of engineered .safety features from opposite train testing have occurred in the past two years.}} |
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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
[Table view] |
Text
ACCEI Etu.T DOCUMENT DIST UTION SYSTEM REGULATORY INFORMATION DISTRIBUTION STEM (RIDS)
~ ACCESS"ON'BR:9212220363 DOC.DATE: 92/12/17 NOTARIZED: NO DOCKET FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION KNORRtJ.E. Florida Power & Light Co.
PLUNKETT,T.F.. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 92-.010-.00:on 921121,an automatic start of 4B EDG occurred during 3B EDG safeguards test. Caused by inadequate D procedure..Administrative Procedure 0-ADM-501 wil be revised.W/921217 ltr.
DISTRIBUTION CODE: ZE22T COPIES RECEIVED:LTR I ENCL / SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident. Rpt, etc.
NOTES: NRR RAGHAVANPL 05000251 A D
RECIPIENT COPIES RECIPIENT COPIES'TTR ID CODE/NAME ,LTTR ENCL ID CODE/NAME ENCL 'D PD2-2 LA 1 1 PD2-2. PD 1 1 AULUCKPR 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP ,2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 NRR'ST SPLB8D1 1 1 NRR/DST/SRXB 8E 1 1 G FIL 02 1 1 RES/DSIR/EIB 1 1 RGN2 LE 01 1 1 EXTERNAL EG&G BRYCE s'J H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYPG.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTES: 1 1 D
-D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEl CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM'DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30
0 P.Q. 6ox 029100, Miam>, FL, 33102-9100 i=PL L-92-335 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: 92-010-00 Automatic Start of 4B Emer enc Diesel Generator The attached Licensee Event Report 251'-92-010-00 is being provided in accordance with 10 CFR 50.73 (a) (2) (iv) .
If there are any questions, please contact us.
Very truly yours, my~/-
T. F. Plunkett g+
Vice President Turkey Point Nuclear TFP/JEK/jk enclosure cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Ross C. Butcher, Senior Resident Inspector, USNRC, Turkey Point Plant
<49t E a~~
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92f2220363 92f2f7 PDR ADQCK 0500025i 8 PDR
LICENSEE EVENT REPORT (LER}
DOCKET NUMBER l2) PAGE l3)
FACILITY NAME l1)
TURKEY POINT UNIT 4 05000251 oF 3 Automatic Start of 4B Emergency Diesel Generator EVENT DATE l5) LER NUMBER l6) RPT DATE l1) OTHER FACILITIES INV l8)
MON DAY YR SEO 6 MON DAY YR FACILITY NANES DOCKET 6 lS) ll 21 92 92 010 00 12 17 92 TURKEY POINT UNIT 3 05000250 OPERATING MODE {B) THIS REPORT IS SUBMITTED PURSUANT TO THE RE UIREMENTS OF 10 CFR 10 CFR 50.73 a 2 POllER LEVEL l10) 100%
LICENSEE CONTACT FOR THIS LER (12}
James E. Knorr, Licensing Engineer TELEPHONE NUMBER 305-246-6757 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT l13).
CAUSE SYSTEM COMPONENT NPRDST caUEE SYSTEM COMPONENT MANUFACTURER NPRDS?
SUPPLEMENTAL REPORT EXPECTED {14) NO X YES 0 EXPECTED SUBMISSION DATE l15)
MONTH DAY
{If yes, coeplete EXPECTED SUBMISSION DaTE)
ABSTRACT l16)
On November 21I 1992I at 1412 ESTF an automatic start of the 4B emergency diesel generator occurred during the 3B emergency diesel generator safeguards test. During this testing, procedure 3-0SP-203.2, Train B Safeguards Integrated Test, required the lifting of leads to prevent the start of the Unit 4 diesel "B" generators upon the initiation of a safety injection signal on Train of Unit 3. Incorrect leads were lifted, due to an inadequate procedure, resulting in the automatic start of the 4B emergency diesel generator upon the injection of a simulated safety injection signal on Unit 3 Train "B". The lead that was lifted resulted in no unexpected action other than the automatic start of the 4B emergency diesel generator. Therefore, the test of the 3B emergency diesel generator was successful.
Corrective actions require the inclusion of applicable wire numbers fo lifted leads in procedures requiring leads to be lifted.
0 I
LXCENSEE ENT REPORT (LER) TEXT NTXNUATZON FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO.
TURKEY POINT UNIT' 05000251 92-010-00 02 or 03 EVENT DESCRIPTION On November 21I 1992I at 1412 EST, and automatic start of the 4B emergency diesel generator (EIIS-EK) (IEEE-DG) occurred during the 3B emergency diesel generator safeguards test. At Turkey Point, four safety injection pumps (EIIS-BJ) (IEEE-P) are shared between Units 3 and 4. Each safety injection pump is supplied power from its own safeguards bus (EIIS-EB) (IEEE-BU) . Therefore, upon a valid or simulated safety injection signal from either unit, all four emergency -diesel generators automatically start. During safeguards testing of the 3B emergency diesel generator, test procedure 3-OSP-203.2, Train B Safeguards Integrated Test, required the lifting of leads to prevent the start of the Unit 4 emergency diesel generators upon the injection of a simulated safety injection signal on Train B of Unit 3. The terminal location for the lifted leads was specified; however, the specific lead to be lifted of three leads on the terminal was not specified. The wrong lead was lifted resulting in the 4B,emergency diesel generator automatically starting on the injection of a simulated Unit 3 safety injection signal. Given the configuration of the jumpers at the time of the test, the 4B emergency diesel generator started as designed.
This event was reported to the NRC operations center in accordance with 10 CFR 50.72 (b)'(2) (ii)-
ZI. EVENT CAUSE The root cause of the automatic start of the 4B emergency diesel generator was an inadequate procedure. As discussed above, operations surveillance procedure 3-0SP-203.2 did not specify in sufficient detail the actual jumper to be lifted to prevent the 4B emergency diesel generator from starting during the test.
IZI. EVENT SAFETY ANALYSIS The 4B emergency diesel generator operated as designed during the integrated safeguards test procedure. The automatic start would not have prevented the 4B emergency diesel generator from performing its intended function had a loss of offsite power occurred concurrently.
Therefore, the health and safety of plant personnel or the general public were not compromised by the automatic start of the 4B emergency diesel generator.
IV. CORRECTIVE ACTIONS
- 1. Administrative procedure O-ADM-501, Duties and Responsibilities of System Engineers, will be revised to require the field verification of the adequacy of work operations. This revision is scheduled to be completed by January 31, 1993.
Ot LICENSEE EINT REPORT (LER) TEXT 4NTINUATION FACILE'TY NAME DOCKET NUMBER LER NUMBER PAGE NO.
TURKEY POZNT UNIT'4 05000251 92-010-00 03 or 03
- 2. Administrative Procedure O-ADM-101, Procedure Writers Guide, will be revised to ofrequire the originator of procedure steps or installation of jumpers to field requiring lifting leads verify. the adequacy'of terminal and or wire identification steps in the procedure steps added. This procedure change is scheduled to be complete by January 31, 1993.
- 3. An internal memo was issued to all'department heads. The memo directed managers to inform personnel of their responsibility when writing a procedure step, which requires the or installation of a jumper, to provide detail lift sufficient of a wire to result in a unique description of the work location.
V. ADDZTZONAL ZNFORMKTZON No other unexpected actuations of engineered .safety features from opposite train testing have occurred in the past two years.
