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| | issue date = 10/20/1992 | | | issue date = 10/20/1992 |
| | title = LER 92-006-00:on 920927,identified That Required Surveillance Not Performed Per TS 4.5.2.b.1.Caused by Personnel Error.All Surveillances in Sys Verified to Have Been Performed Per TS.W/921020 Ltr | | | title = LER 92-006-00:on 920927,identified That Required Surveillance Not Performed Per TS 4.5.2.b.1.Caused by Personnel Error.All Surveillances in Sys Verified to Have Been Performed Per TS.W/921020 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:ACCELERA'l.'ED DLS'l'R18U'l'106 DEiV10iiS'L'HA'J AObt SYS'l'EiVL REGULATC INFORMATION DISTRIBUTION STEM (RIDS)ACCESSION NBR 9211020078 DOC'DATE 92/10/20 NOTARIZED NO DOCKET FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILZATION KNORR,J.E. | | {{#Wiki_filter:ACCELERA'l.'ED DLS'l'R18U'l'106 DEiV10iiS'L'HA'J AObt SYS'l'EiVL REGULATC INFORMATION DISTRIBUTION STEM (RIDS) |
| Florida Power&Light Co.PLUNKETT,T.F. | | ACCESSION NBR 9211020078 DOC'DATE 92/10/20 NOTARIZED NO DOCKET FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILZATION KNORR,J.E. Florida Power & Light Co. |
| Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION | | PLUNKETT,T.F. Florida Power & Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER 92-006-00:on 920927,identified that required surveillance not performed per TS 4.5.2.b.l.Caused by.personnel error.All surveillances in sys verified to have been performed per TS.W/921020 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR i ENCL)SIZE: TITLE: 50..73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:NRR RAGHAVAN,L 05000251 RECIPIENT ID CODE/NAME PD2-2 LA AULUCKFR 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 BRYCEFJ.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 S LB8D1 REG F LE 02 FILE 01 L ST LOBBY HARD NSIC MURPHY,G.A NUDOCS FULL TXT 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 ,0 NOTE TO ALL"RIDS.RECIPIENTS: | | LER 92-006-00:on 920927,identified that required surveillance not performed per TS 4.5.2.b.l.Caused by |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK.ROOM Pl-37 (EXT.504-'2065)
| | .personnel error.All surveillances in sys verified to have been performed per TS.W/921020 ltr. |
| TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!0'UL'L TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 0 0 I 60T RO1M L-92-293 10 CFR 50.73'.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
| | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR i ENCL) SIZE: |
| Re: Turkey Point Unit 4 Docket No.50-251 Reportable Event: 92-006-00 Two Mode Change Surveillances Not Performed in Accordance with Technical S ecifications The attached'icensee Event Report 251-92-006-00 is being provided in.accordance.with 10 CFR 50.73 (a)(2)(i)(B).'If there.are any questions please contact us.Very, truly.yours, 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 36009<9211020078
| | TITLE: 50..73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| '921020 PDR ADOCK 05000251 8 PDR an FPL'Groop.company Ib FACILITY NAME (1)LICENSEE EVENT REPORT (LER)DOCKET NUMBER (2)PAGE (3)TURKEY POINT UNIT 4 05000251 1 oF 3 TITLE (6)Two Mode Change Surveillances Not Performed in Accordance with Technical Specifications EveNF DATe (5)LER NUMBER(6)RPT DATE (7)OTHER FACILITZES INV (8)MON DAY YR YR SEQ 9 R)MON DAY YR FACILITY NAMES DOCKET I (S)09 27 92 OPERATING MODE (9)'i 92 006 00 10 27 92 TURKEY POINT UNIT 3 05000250 THIS REPORT IS SUBMITTED PURSUANT TO THE RE UIREMENTS OF 10 CFR 10 CFR 50.73 a 2 i B poweR I,Fvez, (10)0%LICENSEE CONTACT FOR THIS LER (12)James E.Knorr, Licensing Engineer COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED ZN THIS REPORT (13)TELEPHONE NUMBER 305-246-6757 CAUSE SYSTEM COMPONENT MANUFACTURER NPRDS2 cAUse SYSTEM coMpoNENT MANUFACTURER NPRDS2 SUPPLEMENTAL REPORT EXPECTED (14)NO X Yes 0 (if Yee em@>lete EXPECTED SUBMISSION DATE)expFGTeD SUBMISSION DATE (15)DAY YEAR ABsTRAcT (16)On September 27'992I Turkey Point Unit 4 entered Mode 4 from Mode 5 at 0931 hours.At 1330 hours on September 28I 1992I Turkey Point personnel identified that a required surveillance had not been completed prior to the entry into Mode 4.Technical Specification 4.5.2.b.1 requires that at least once each 31 days plant personnel verify that the Emergency Core Cooling System (ECCS)piping is full of water by venting the ECCS pump casings and accessible discharge piping.This requirement applies during Modes 1, 2, 3 and 4.This surveillance was completed for Unit 4 at 1720 hours on September 28, 1992 and Unit 3 at 1400 hours on September 29, 1992.As part of the corrective action process for the above described event, a standby feedwater pump surveillance was also found to be incomplete. | | NOTES:NRR RAGHAVAN,L 05000251 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 AULUCKFR 1 1 ,0 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 NRR/DREP/PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 S LB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG F LE 02 1 1 |
| This surveillance is required to be complete prior to the entry into Mode 3.Unit 4 entered Mode 3 from Mode 4 at 0248 hours on September 28, 1992.This surveillance procedure was completed on September 29, 1992.The root cause of the two missed surveillances was an error during the change of dates in a.computerized surveillance tracking system.Corrective actions have been implemented to reduce the probability of this occurrence in the future.
| | 'RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL: EG&G BRYCEFJ.H 2 2 L ST LOBBY HARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTES: 1 1 NOTE TO ALL "RIDS. RECIPIENTS: |
| 4l I~l LICENSEE ENT REPORT (LER)TEXT NTINURTION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO.TURKEY POINT UNIT 4 05000251 92-006-00 02 oF 03 Z.EVENT DESCRIPTION On September 27, 1992, Turkey Point Unit 4 entered Mode 4 from Mode 5 at 0931 hours.At 1330 hours on September 28, 1992, Turkey Point personnel identified that a required surveillance had not been completed prior to the entry into Mode 4.Technical Specification 4'.2.b.1 requires that at least once each 31 days plant personnel verify that the Emergency Core Cooling System (ECCS)piping (EIIS-BP and BQ)is full of water by venting the ECCS pump casings (EZIS-BP and BQ, IEEE-P)and accessible discharge piping.This requirement applies during Modes 1, 2, 3 and 4.This surveillance is completed by implementation of operations support procedures 3/4-OSP-202.2,.ECCS Venting.4-0SP-0202.2 was completed at 1'720 hours on September 28, 1992.3-0SP-202.2 was completed at 1400 hours on September 29, 1992.As part of, the corrective action process, on September 29, 1992, a required surveillance, O-OSP-074.3,'A'tandby Feedwater Pump, was found to be incomplete.
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK. |
| Technical Specification 4.7.1.6.2 requires a completion of the surveillance at least monthly to verify the operability of the standby feedwater pumps (EIIS-BA, IEEE-P)by testing in recirculation on a staggered basis.The surveillance is also required to be complete prior to the entry into Mode 3.Unit 4 entered Mode 3 at 0248 hours on September 28, 1992.This surveillance procedure was completed on September 29, 1992.Both surveillances were last performed prior to the unit shutdown prior to hurricane And'rew on August 24, 1992.ZZ.EVENT CAUSE The root cause was a personnel error.Personnel responsible for surveillance tracking, attempted to reschedule a surveillance by changing a date on a computer based surveillance tracking system to provide a printout of the above required surveillances,to Operations personnel.
| | ROOM Pl-37 (EXT. 504-'2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| The date change was made to allow the computer to print out the required surveillances on a"Daily Task Sheet" form or a"Seven Day Look-Ahead Schedule" form.If the date had not been changed the surveillance requirements would have appeared on two forms;1)Mode Change Report;2)Surveillance Past Scheduled Date Report.If the surveillances had appeared on either form as incomplete, the surveillances would have been completed prior to the respective mode change.The date change however changed the status of the surveillance in the computer system,to current.That is to say, the surveillance tracking system was automatically updated as if the surveillances were complete and,therefore, did not need to be done for the next 31 days.The surveillances did appear on the Mode Change Report but were indicated as complete.ZZZ.EVENT SAFETY ANALYSIS Prior to the entry into Mode 4, cooling of the reactor coblant system was supplied by the running of a residual heat removal (RHR)pump through a heat exchanger transferring heat to the component cooling water system.The RHR.pumps were.successfully run.The safety 0 J I ICENSEE ENT REPORT (LER)TEXT NTINUATION rACILZTY NAME DOCKET'UMBER LER NUMBER PAGE NO.TURKEY POINT UNIT 4 05000251 92-006-00'3.or 03 injection pumps were run as part of a Temporary Procedure TP-887, High Head Safety Injection Pump Readiness Test, prior to changing to Mode 4 and the system showed no evidence of needing venting of the piping or the pump casings.The RHR and safety injection systems were walked down to verify valve alignment on September 29, 1992.The ECCS system surveillances were later implemented, as discussed above, and the systems were proven to be operable.Prior to entry into Mode 3 the standby feedwater pumps were run as part of Temporary Procedure TP-893, Standby Feedwater Readiness Test[Post Andrew].Both pumps were run on recirculation on.September 16, 1992.The system readiness tests did not examine all the parameters that are reviewed during the surveillance test.However, the subsequent surveillance testing performed on the pumps proved them operable.The standby feedwater system is not a safety grade system.The health and safety of plant personnel and the general public were not compromised as a result of the missed surveillances. | | 0'UL'L TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 |
| IV..CORRECTIVE ACTIONS The surveillances.
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| were completed within 24 hours of discovery.
| | 0 0 I 60T RO1M L-92-293 10 CFR 50.73'. |
| See the discussion in the Event Description above.2.All surveillances in the computerized, tracking system were independently verified to have been performed, as required by Technical Specifications, to allow a mode change from Mode 4 to Mode 3, Mode 3 to Mode 2, and Mode 2 to Mode 1..3~4~The, person making the date change was counselled to not make changes to dates in the computer tracking system without written approval for the change from the Operations Support Supervisor.
| | S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| Procedure changes were made to implement this policy.The purpose of the surveillance tracking system was discussed with the planning and scheduling department personnel to emphasize the necessity for care and accuracy'.
| | Re: Turkey Point Unit 4 Docket No. 50-251 Reportable Event: 92-006-00 Two Mode Change Surveillances Not Performed in Accordance with Technical S ecifications The attached'icensee Event Report 251-92-006-00 is being provided in .accordance .with 10 CFR 50. 73 (a) (2) (i) (B) . |
| V,.ADDITIONAL INFORMATION This event was considered reportable in accordance with 10 CFR 50.73 (a)(2)(i)(B).
| | 'If there .are any questions please contact us. |
| Ib)/}}
| | Very,truly. yours, 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 36009< |
| | 9211020078 '921020 PDR ADOCK 05000251 8 PDR an FPL'Groop.company |
| | |
| | Ib LICENSEE EVENT REPORT (LER) |
| | FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3) |
| | TURKEY POINT UNIT 4 05000251 1 oF 3 TITLE (6) Two Mode Change Surveillances Not Performed in Accordance with Technical Specifications EveNF DATe (5) LER NUMBER(6) RPT DATE (7) OTHER FACILITZES INV (8) |
| | MON DAY YR YR SEQ 9 R) MON DAY YR FACILITY NAMES DOCKET I (S) 09 27 OPERATING MODE (9) poweR I,Fvez, (10) 92 |
| | 'i 92 006 00 10 27 92 TURKEY POINT UNIT 3 THIS REPORT IS SUBMITTED PURSUANT TO THE 10 CFR 50.73 a 2 i RE UIREMENTS OF 10 CFR B |
| | 05000250 0% |
| | LICENSEE CONTACT FOR THIS LER (12) |
| | James E. Knorr, Licensing Engineer TELEPHONE NUMBER 305-246-6757 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED ZN THIS REPORT (13) |
| | CAUSE SYSTEM COMPONENT MANUFACTURER NPRDS2 cAUse SYSTEM coMpoNENT MANUFACTURER NPRDS2 SUPPLEMENTAL REPORT EXPECTED (14) NO X Yes 0 expFGTeD SUBMISSION DAY YEAR DATE (15) |
| | (if Yee em@>lete EXPECTED SUBMISSION DATE) |
| | ABsTRAcT (16) On September 27'992I Turkey Point Unit 4 entered Mode 4 from Mode 5 at 0931 hours. At 1330 hours on September 28I 1992I Turkey Point personnel identified that a required surveillance had not been completed prior to the entry into Mode 4. Technical Specification 4.5.2.b.1 requires that at least once each 31 days plant personnel verify that the Emergency Core Cooling System (ECCS) piping is full of water by venting the ECCS pump casings and accessible discharge piping. This requirement applies during Modes 1, 2, 3 and 4. This surveillance was completed for Unit 4 at 1720 hours on September 28, 1992 and Unit 3 at 1400 hours on September 29, 1992. |
| | As part of the corrective action process for the above described event, a standby feedwater pump surveillance was also found to be incomplete. This surveillance is required to be complete prior to the entry into Mode 3. |
| | Unit 4 entered Mode 3 from Mode 4 at 0248 hours on September 28, 1992. This surveillance procedure was completed on September 29, 1992. |
| | The root cause of the two missed surveillances was an error during the change of dates in a .computerized surveillance tracking system. Corrective actions have been implemented to reduce the probability of this occurrence in the future. |
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| | LICENSEE ENT REPORT (LER) TEXT NTINURTION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO. |
| | TURKEY POINT UNIT 4 05000251 92-006-00 02 oF 03 Z. EVENT DESCRIPTION On September 27, 1992, Turkey Point Unit 4 entered Mode 4 from Mode 5 at 0931 hours. At 1330 hours on September 28, 1992, Turkey Point personnel identified that a required surveillance had not been completed prior to the entry into Mode 4. Technical Specification 4 '.2.b.1 requires that at least once each 31 days plant personnel verify that the Emergency Core Cooling System (ECCS) piping (EIIS-BP and BQ) is full of water by venting the ECCS pump casings (EZIS-BP and BQ, IEEE-P) and accessible discharge piping. This requirement applies during Modes 1, 2, 3 and 4. This surveillance is completed by implementation of operations support procedures 3/4-OSP-202.2, |
| | .ECCS Venting. 4-0SP-0202.2 was completed at 1'720 hours on September 28, 1992. 3-0SP-202.2 was completed at 1400 hours on September 29, 1992. |
| | As part of,the corrective action process, on September 29, 1992, a required surveillance, O-OSP-074.3, 'A'tandby Feedwater Pump, was found to be incomplete. Technical Specification 4.7.1.6.2 requires a completion of the surveillance at least monthly to verify the operability of the standby feedwater pumps (EIIS-BA, IEEE-P) by testing in recirculation on a staggered basis. The surveillance is also required to be complete prior to the entry into Mode 3. Unit 4 entered Mode 3 at 0248 hours on September 28, 1992. This surveillance procedure was completed on September 29, 1992. |
| | Both surveillances were last performed prior to the unit shutdown prior to hurricane And'rew on August 24, 1992. |
| | ZZ. EVENT CAUSE The root cause was a personnel error. Personnel responsible for surveillance tracking, attempted to reschedule a surveillance by changing a date on a computer based surveillance tracking system to provide a printout of the above required surveillances,to Operations personnel. The date change was made to allow the computer to print out the required surveillances on a "Daily Task Sheet" form or a "Seven Day Look-Ahead Schedule" form. If the date had not been changed the surveillance requirements would have appeared on two forms; 1) Mode Change Report; 2) Surveillance Past Scheduled Date Report. If the surveillances had appeared on either form as incomplete, the surveillances would have been completed prior to the respective mode change. The date change however changed the status of the surveillance in the computer system,to current. That is to say, the surveillance tracking system was automatically updated as the surveillances were complete and,therefore, did not need to be if done for the next 31 days. The surveillances did appear on the Mode Change Report but were indicated as complete. |
| | ZZZ. EVENT SAFETY ANALYSIS Prior to the entry into Mode 4, cooling of the reactor coblant system was supplied by the running of a residual heat removal (RHR) pump through a heat exchanger transferring heat to the component cooling water system. The RHR .pumps were .successfully run. The safety |
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| | 0 J |
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| | I ICENSEE ENT (LER) TEXT NTINUATION |
| | '3 REPORT rACILZTY NAME DOCKET'UMBER LER NUMBER PAGE NO. |
| | TURKEY POINT UNIT 4 05000251 92-006-00 .or 03 injection pumps were run as part of a Temporary Procedure TP-887, High Head Safety Injection Pump Readiness Test, prior to changing to Mode 4 and the system showed no evidence of needing venting of the piping or the pump casings. The RHR and safety injection systems were walked down to verify valve alignment on September 29, 1992. |
| | The ECCS system surveillances were later implemented, as discussed above, and the systems were proven to be operable. |
| | Prior to entry into Mode 3 the standby feedwater pumps were run as part of Temporary Procedure TP-893, Standby Feedwater Readiness Test |
| | [Post Andrew] . Both pumps were run on recirculation on .September 16, 1992. The system readiness tests did not examine all the parameters that are reviewed during the surveillance test. However, the subsequent surveillance testing performed on the pumps proved them operable. The standby feedwater system is not a safety grade system. |
| | The health and safety of plant personnel and the general public were not compromised as a result of the missed surveillances. |
| | IV.. CORRECTIVE ACTIONS The surveillances. were completed within 24 hours of discovery. |
| | See the discussion in the Event Description above. |
| | : 2. All surveillances in the computerized, tracking system were independently verified to have been performed, as required by Technical Specifications, to allow a mode change from Mode 4 to Mode 3, Mode 3 to Mode 2, and Mode 2 to Mode 1. |
| | .3 ~ The, person making the date change was counselled to not make changes to dates in the computer tracking system without written approval for the change from the Operations Support Supervisor. |
| | Procedure changes were made to implement this policy. |
| | 4 ~ The purpose of the surveillance tracking system was discussed with the planning and scheduling department personnel to emphasize the necessity for care and accuracy'. |
| | V,. ADDITIONAL INFORMATION This event was considered reportable in accordance with 10 CFR 50.73 (a) (2) (i) (B) . |
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| | Ib ) |
| | /}} |
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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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ACCELERA'l.'ED DLS'l'R18U'l'106 DEiV10iiS'L'HA'J AObt SYS'l'EiVL REGULATC INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR 9211020078 DOC'DATE 92/10/20 NOTARIZED NO DOCKET FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILZATION KNORR,J.E. Florida Power & Light Co.
PLUNKETT,T.F. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 92-006-00:on 920927,identified that required surveillance not performed per TS 4.5.2.b.l.Caused by
.personnel error.All surveillances in sys verified to have been performed per TS.W/921020 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR i ENCL) SIZE:
TITLE: 50..73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:NRR RAGHAVAN,L 05000251 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 AULUCKFR 1 1 ,0 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 NRR/DREP/PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 S LB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG F LE 02 1 1
'RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL: EG&G BRYCEFJ.H 2 2 L ST LOBBY HARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTES: 1 1 NOTE TO ALL "RIDS. RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.
ROOM Pl-37 (EXT. 504-'2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
0'UL'L TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30
0 0 I 60T RO1M L-92-293 10 CFR 50.73'.
S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: Turkey Point Unit 4 Docket No. 50-251 Reportable Event: 92-006-00 Two Mode Change Surveillances Not Performed in Accordance with Technical S ecifications The attached'icensee Event Report 251-92-006-00 is being provided in .accordance .with 10 CFR 50. 73 (a) (2) (i) (B) .
'If there .are any questions please contact us.
Very,truly. yours, 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 36009<
9211020078 '921020 PDR ADOCK 05000251 8 PDR an FPL'Groop.company
Ib LICENSEE EVENT REPORT (LER)
FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3)
TURKEY POINT UNIT 4 05000251 1 oF 3 TITLE (6) Two Mode Change Surveillances Not Performed in Accordance with Technical Specifications EveNF DATe (5) LER NUMBER(6) RPT DATE (7) OTHER FACILITZES INV (8)
MON DAY YR YR SEQ 9 R) MON DAY YR FACILITY NAMES DOCKET I (S) 09 27 OPERATING MODE (9) poweR I,Fvez, (10) 92
'i 92 006 00 10 27 92 TURKEY POINT UNIT 3 THIS REPORT IS SUBMITTED PURSUANT TO THE 10 CFR 50.73 a 2 i RE UIREMENTS OF 10 CFR B
05000250 0%
LICENSEE CONTACT FOR THIS LER (12)
James E. Knorr, Licensing Engineer TELEPHONE NUMBER 305-246-6757 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED ZN THIS REPORT (13)
CAUSE SYSTEM COMPONENT MANUFACTURER NPRDS2 cAUse SYSTEM coMpoNENT MANUFACTURER NPRDS2 SUPPLEMENTAL REPORT EXPECTED (14) NO X Yes 0 expFGTeD SUBMISSION DAY YEAR DATE (15)
(if Yee em@>lete EXPECTED SUBMISSION DATE)
ABsTRAcT (16) On September 27'992I Turkey Point Unit 4 entered Mode 4 from Mode 5 at 0931 hours0.0108 days <br />0.259 hours <br />0.00154 weeks <br />3.542455e-4 months <br />. At 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on September 28I 1992I Turkey Point personnel identified that a required surveillance had not been completed prior to the entry into Mode 4. Technical Specification 4.5.2.b.1 requires that at least once each 31 days plant personnel verify that the Emergency Core Cooling System (ECCS) piping is full of water by venting the ECCS pump casings and accessible discharge piping. This requirement applies during Modes 1, 2, 3 and 4. This surveillance was completed for Unit 4 at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> on September 28, 1992 and Unit 3 at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on September 29, 1992.
As part of the corrective action process for the above described event, a standby feedwater pump surveillance was also found to be incomplete. This surveillance is required to be complete prior to the entry into Mode 3.
Unit 4 entered Mode 3 from Mode 4 at 0248 hours0.00287 days <br />0.0689 hours <br />4.100529e-4 weeks <br />9.4364e-5 months <br /> on September 28, 1992. This surveillance procedure was completed on September 29, 1992.
The root cause of the two missed surveillances was an error during the change of dates in a .computerized surveillance tracking system. Corrective actions have been implemented to reduce the probability of this occurrence in the future.
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LICENSEE ENT REPORT (LER) TEXT NTINURTION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO.
TURKEY POINT UNIT 4 05000251 92-006-00 02 oF 03 Z. EVENT DESCRIPTION On September 27, 1992, Turkey Point Unit 4 entered Mode 4 from Mode 5 at 0931 hours0.0108 days <br />0.259 hours <br />0.00154 weeks <br />3.542455e-4 months <br />. At 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on September 28, 1992, Turkey Point personnel identified that a required surveillance had not been completed prior to the entry into Mode 4. Technical Specification 4 '.2.b.1 requires that at least once each 31 days plant personnel verify that the Emergency Core Cooling System (ECCS) piping (EIIS-BP and BQ) is full of water by venting the ECCS pump casings (EZIS-BP and BQ, IEEE-P) and accessible discharge piping. This requirement applies during Modes 1, 2, 3 and 4. This surveillance is completed by implementation of operations support procedures 3/4-OSP-202.2,
.ECCS Venting. 4-0SP-0202.2 was completed at 1'720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> on September 28, 1992. 3-0SP-202.2 was completed at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on September 29, 1992.
As part of,the corrective action process, on September 29, 1992, a required surveillance, O-OSP-074.3, 'A'tandby Feedwater Pump, was found to be incomplete. Technical Specification 4.7.1.6.2 requires a completion of the surveillance at least monthly to verify the operability of the standby feedwater pumps (EIIS-BA, IEEE-P) by testing in recirculation on a staggered basis. The surveillance is also required to be complete prior to the entry into Mode 3. Unit 4 entered Mode 3 at 0248 hours0.00287 days <br />0.0689 hours <br />4.100529e-4 weeks <br />9.4364e-5 months <br /> on September 28, 1992. This surveillance procedure was completed on September 29, 1992.
Both surveillances were last performed prior to the unit shutdown prior to hurricane And'rew on August 24, 1992.
ZZ. EVENT CAUSE The root cause was a personnel error. Personnel responsible for surveillance tracking, attempted to reschedule a surveillance by changing a date on a computer based surveillance tracking system to provide a printout of the above required surveillances,to Operations personnel. The date change was made to allow the computer to print out the required surveillances on a "Daily Task Sheet" form or a "Seven Day Look-Ahead Schedule" form. If the date had not been changed the surveillance requirements would have appeared on two forms; 1) Mode Change Report; 2) Surveillance Past Scheduled Date Report. If the surveillances had appeared on either form as incomplete, the surveillances would have been completed prior to the respective mode change. The date change however changed the status of the surveillance in the computer system,to current. That is to say, the surveillance tracking system was automatically updated as the surveillances were complete and,therefore, did not need to be if done for the next 31 days. The surveillances did appear on the Mode Change Report but were indicated as complete.
ZZZ. EVENT SAFETY ANALYSIS Prior to the entry into Mode 4, cooling of the reactor coblant system was supplied by the running of a residual heat removal (RHR) pump through a heat exchanger transferring heat to the component cooling water system. The RHR .pumps were .successfully run. The safety
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I ICENSEE ENT (LER) TEXT NTINUATION
'3 REPORT rACILZTY NAME DOCKET'UMBER LER NUMBER PAGE NO.
TURKEY POINT UNIT 4 05000251 92-006-00 .or 03 injection pumps were run as part of a Temporary Procedure TP-887, High Head Safety Injection Pump Readiness Test, prior to changing to Mode 4 and the system showed no evidence of needing venting of the piping or the pump casings. The RHR and safety injection systems were walked down to verify valve alignment on September 29, 1992.
The ECCS system surveillances were later implemented, as discussed above, and the systems were proven to be operable.
Prior to entry into Mode 3 the standby feedwater pumps were run as part of Temporary Procedure TP-893, Standby Feedwater Readiness Test
[Post Andrew] . Both pumps were run on recirculation on .September 16, 1992. The system readiness tests did not examine all the parameters that are reviewed during the surveillance test. However, the subsequent surveillance testing performed on the pumps proved them operable. The standby feedwater system is not a safety grade system.
The health and safety of plant personnel and the general public were not compromised as a result of the missed surveillances.
IV.. CORRECTIVE ACTIONS The surveillances. were completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery.
See the discussion in the Event Description above.
- 2. All surveillances in the computerized, tracking system were independently verified to have been performed, as required by Technical Specifications, to allow a mode change from Mode 4 to Mode 3, Mode 3 to Mode 2, and Mode 2 to Mode 1.
.3 ~ The, person making the date change was counselled to not make changes to dates in the computer tracking system without written approval for the change from the Operations Support Supervisor.
Procedure changes were made to implement this policy.
4 ~ The purpose of the surveillance tracking system was discussed with the planning and scheduling department personnel to emphasize the necessity for care and accuracy'.
V,. ADDITIONAL INFORMATION This event was considered reportable in accordance with 10 CFR 50.73 (a) (2) (i) (B) .
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