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| {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9012180043 DOC.DATE: 90/12/12 NOTARIZED: | | {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH.NAME AUTHOR AFFILIATION POWELL,D.R. | | ACCESSION NBR:9012180043 DOC.DATE: 90/12/12 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION POWELL,D.R. 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 | | RECIP.NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 90-022-00:on 901114,discovered that Tech Spec required fire protection surveillance not performed within max allowed time interval.Caused by inadequate administrative controls.Memo issued.W/901212 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD2-2 LA EDISON,G INTERNAL: ACNW AEOD/DS P/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR/DST/SQLBS Dl REG-FXXB~~02 GN2 FILE 0 1 EXTERNAL EG&G BRYCE g J~H NRC PDR NSIC MURPHY,G.A COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPE B 1 0 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB 8E RES/DSIR/EIB L ST LOBBY WARD NSIC MAYS,G NUDOCS FULL TXT.COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: | | LER 90-022-00:on 901114,discovered that Tech Spec required fire protection surveillance not performed within max allowed time interval. Caused by inadequate administrative controls. Memo issued.W/901212 ltr. |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL.TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 DEC 12 1990 L-90-4'31 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen: | | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: |
| Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 Reportable Event: 90-022 Date of Event: November 13, 1990 Fire Protection Surveillance Not Performed Within Technical S ecification Maximum Allowed Time Interval The attached Licensee Event Report is being provided pursuant to the requirements of lOCFR50.73 to provide information on the subject event.Corrective Action g 4-corresponds to a corrective action previously identified in LER 50-250/90-020-0.
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| The scheduled date for completion of this corrective action is being escalated by Turkey Point Nuclear Plant management from February 15, 1991 to January 18, 1991 due to the additional instance of a missed Technical Specification surveillance described herein.Very truly yours, cP7+~~T.F.Plunkett Vice President Turkey Point Nuclear Plant TFP/DRP/dwh Attachment cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC, Senior Resident Inspectorr USNRCr Turkey Point Plant 9012180043 901212 PDR ADOCK 05000250 S-PPR an FPL Group company NRC Form 364 (903)LlCENSEE EVENT REPORT (LER)US.NUCLEAR REOULATORY COMMISSION APPROVED DMS NO.3160010C EXPIRESt SI$'II44 FACILITY NAME (I I Turkey Point Unit 3 PA DOCKET NUMSER (1)o 5 o o o 250 10F04 TITLE (Cl s re ro ec s on urve)ance o er orme 1 s n ec ns ca pec1 s ca on Maximum Allowed Time Interval MONTH OAY YKAR EVENT DATE ISI YEAR LER NVMSER (5)Ifcx$4QUENTIAI, NUM4ER.c:e,.NUM44ti MONTH DAY YEAR REPORT'ATE (7)OTHER FACILITIES INVOLVED (4)DOCKET NVMSER(SI o so o o 25 1 FACILITY NAMES Turkey Point Unit 4 1 390 9 0 0 2 00 12 1 2 9 0 0 5 0 0 0 OPERATINO MODE 14)POWER LEVEL (10)20.402(4)20A05 (e l(1)0)20A05(e l(1)(SI 20A054)(I l(iii)20A05 4)I I I lir)20.605 (e)ll I (el 20.e06(cl 50.$6(c)II I 50.35(cl(21 50.73(el(1)(il 50.7$(e l(21(4)S0.7 34)(2)I it i)LICENSEE CONTACT FOR THIS LER (11)50 73(e l(2)(irl 50.734)12)4)50.'1341(2l(r41 50.734)(2l(riiil(A) 50.73(e I (2)(ri 4 H 4 I 50.7$(e I (2 I (nl THIS REPORT IS SVSMITTKD PURSUANT TO THE REOUIREMENTS OF 10 CF R g: ICneee One Or mtye Of tne IOIIOw'npl (11)7$.71(4)73.71(cl OTHER (Specify In Apttrect pefow errf In Tert, HRC Form JFFAI NAME David R.Powell, Licensing Superintendent TELEPHONE NUMSER AREA CODE 30 524 6-559 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRISED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC TURER EPORTABLE TO NPRDS 4%4~$44: CAUSE SYSTEM COMPONENT MANVFAC.TURER EPORTASL TO NPRDS c4%%>~: SUPPLEMENTAL REPORT EXPECTED Ile)9er9:e'rr.L%'.<.
| | NOTES: |
| @at MONTH DAY YEAR EXPECTED SVSMISSION DATE (ISI YES III yeL comptete fXPf CTED SVSMISSIOH DATfl NO AssTRAcT (Limit to 1400 tpeceL I e., epprorimeteiy ftf4en tinpie tpece typewNHen linet)116)On November 14, 1990, with Unit 3 and Unit 4 in Mode 1 at 100 percent power, FPL personnel discovered that a Technical Specification (TS)surveillance requirement had not been performed within the maximum allowed time interval.TS 4.15.4.a.1 requires the Unit 3 and Unit 4 fire hose stations to be visually inspected at least once per 31 days.TS 4.0.1 allows this specified interval to be adjusted plus or minus 25 percent to accommodate normal test schedules.
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 EDISON,G 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 1 NRR/ DLPQ/LPE B 1 0 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SQLBS Dl 1 1 NRR/DST/SRXB 8E 1 1 REG -FXXB~~ 02 1 1 RES/DSIR/EIB 1 1 GN2 FILE 01 1 1 EXTERNAL EG &G BRYCE g J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT. 1 1 NOTE TO ALL "RIDS" RECIPIENTS: |
| The TS 4.15.4.a.1 surveillance requirement is implemented by performance of Appendix A to Maintenance Procedure (MP)15537.5,"Fire Protection Equipment Surveillance." On November 13p 1990p Appendix A to procedure MP 15537'was performed as scheduled by Operating Surveillance Procedure O-OSP-200.1,"Schedule of Plant Checks and Surveillances." Appendix A to procedure MP 15537.5 was previously performed on October 4, 1990, five days earlier than scheduled by procedure 0-OSP-200.1.The maximum time interval allowed by TS between these surveillances was exceeded.The cause for this condition was inadequate administrative controls.A non-cognitive error by a non-licensed utility individual contributed to this event.A memorandum concerning this event has been issued to plant departmental supervisors responsible for the performance of surveillances identified in procedure O-OSP-200.1.
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| NRC Form 366 (9 8)I
| | FULL. TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 |
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| NRC Form 3SSA I84)3)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMS NO.3180M)Cd EXPIRES: 8/31/88 FACILITY NAME 11)DOCKET NUMBER I2)LER NUMSER IS)/P/P/SSOVSNTIAL PW ASVISION NVMSSA iArd NVMSSII PACE 13)Turkey Point Unit 3 TEXT///moro/poco/d/or/o/rod, o/o odd//lono/HRC Fomr 3//843/))7)0 5 0 0 0 250 gp 0 2 OF DESCRIPTION OF THE EVENT On November 14/1990/with Unit 3 and Unit 4 in-Mode 1 at 100 percent power, FPL personnel discovered that a Technical Specification (TS)surveillance requirement had not been performed within the maximum allowed time interval.TS 4.15.4.a.1 requires the Unit 3 and Unit 4 fire hose stations to be visually insp'ected at least once per 31 days.Per TS 4.0.1, this specified interval may be adjusted plus or minus 25 percent to accommodate normal test schedules.
| | DEC 12 1990 L-90-4'31 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| The TS 4.15.4.a.1 surveillance requirement is implemented by performance of Appendix A to Maintenance Procedure (MP)15537.5,"Fire Protection Equipment Surveillance." Procedure MP 15537.5 is scheduled by Operating Surveillance Procedure 0-OSP-200.1,"Schedule of Plant Checks and Surveillances/U to be performed on the second Tuesday of each month.Depending on which day of the month the second Tuesday falls, the normal scheduled time interval between surveillances can be either 28 days or 35 days.The normal scheduled time interval between the October and November surveillances was 35 days.For the month of October, procedure MP 15537.5 was scheduled to be performed on October 9, 1990.On October 4, 1990, Appendix A to procedure MP 15537.5 was completed five days earlier than scheduled.
| | Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Reportable Event: 90-022 Date of Event: November 13, 1990 Fire Protection Surveillance Not Performed Within Technical S ecification Maximum Allowed Time Interval The attached Licensee Event Report is being provided pursuant to the requirements of 10CFR50.73 to provide information on the subject event. Corrective Action g 4- corresponds to a corrective action previously identified in LER 50-250/90-020-0. The scheduled date for completion of this corrective action is being escalated by Turkey Point Nuclear Plant management from February 15, 1991 to January 18, 1991 due to the additional instance of a missed Technical Specification surveillance described herein. |
| For the month of November, procedure MP 15537.'5 was scheduled to be performed on November,13, 1990.On November 13, 1990, Appendix A to procedure MP 15537.5 was completed as scheduled.
| | Very truly yours, cP7+~~ |
| The total elapsed time interval between these surv'eillances exceeded the maximum time interval allowed by TS.CAUSE OF THE EVENT The cause for exceeding the maximum allowed TS interval between fire hose station surveillances was inadequate administrative controls.If surveillances are performed on the date scheduled by procedure O-OSP-200.1, the surveillances will be performed within maximum time intervals allowed by TS.If a surveillance is not performed by the scheduled date, Control Room personnel will identify this condition during their daily review of procedure O-OSP-200.1 scheduling sheets and track the surveillance to completion.
| | T. F. Plunkett Vice President Turkey Point Nuclear Plant TFP/DRP/dwh Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC, Senior Resident Inspectorr USNRCr Turkey Point Plant 9012180043 901212 PDR ADOCK 05000250 S - PPR an FPL Group company |
| However, if a surveillance is performed earlier than scheduled by procedure O-OSP-200.1, no guidance or controls exist to ensure the maximum time interval allowed by TS is not exceeded.NAC FOAM SddA
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| NRC Form 366A (983)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO, 3)50-0IOE EXPIRES: 8/31/68 FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)YEAR Po)" SEQUENTIAL | | NRC Form 364 US. NUCLEAR REOULATORY COMMISSION (903) |
| %I(1 REVISION~??NUMSER NN NUMSER PACE (31 Turkey Point Unit 3 TEXT//f moro E/Moo/E roEV/rod, u>>odd/o'ooo/rYRC Forrrr 36//AS/(17)o s o o o 9 0 2 2 0 0 03 oF 0 4 A contributing factor was a non-cognitive error by a non-.licensed utility individual. | | APPROVED DMS NO. 3160010C LlCENSEE EVENT REPORT (LER) EXPIRESt SI$ 'II44 FACILITYNAME (I I DOCKET NUMSER (1) PA Turkey Point Unit 3 o 5 o o o 250 10F04 TITLE (Cl s re ro ec s on urve) ance o er orme 1 s n ec ns ca pec1 s ca on Maximum Allowed Time Interval EVENT DATE ISI LER NVMSER (5) REPORT'ATE (7) OTHER FACILITIES INVOLVED (4) |
| Procedure O-OSP-200.1 provides a schedule for performing TS required surveillances and identifies the department responsible for each surveillance.
| | MONTH OAY YKAR YEAR Ifcx $ 4QUENTIAI, MONTH DAY YEAR FACILITYNAMES DOCKET NVMSER(SI NUM4ER .c:e,. NUM44ti Turkey Point Unit 4 o so o o 25 1 1 390 9 0 0 2 00 12 1 2 9 0 0 5 0 0 0 THIS REPORT IS SVSMITTKD PURSUANT TO THE REOUIREMENTS OF 10 CF R g: ICneee One Or mtye Of tne IOIIOw'npl (11) |
| When the scheduled dates in procedure O-OSP-200.1 are not met, the responsible plant departmental TS surveillance scheduler should ensure the interval between surveillances is within the maximum time interval allowed by TS.ANALYSIS OF THE EVENT Performance of Appendix A to procedure MP 15537.5 within the TS maximum allowed time interval demonstrates continued operability of the Unit 3 and Unit 4 fire hose stations.If the TS maximum allowed time interval between surveillances is exceeded, then the fire hose stations are technically inoperable. | | OPERATINO MODE 14) 20.402(4) 20.e06(cl 50 73(e l(2) (irl 7$ .71(4) |
| Appendix A to procedure MP 15537.5 was satisfactorily completed on November 13, 1990.Therefore, the Unit 3 and Unit 4 fire hose stations were in fact physically capable of performing their intended function.CORRECTIVE ACTIONS 1.Appendix A to procedure MP 15537.5 was satisfactorily completed on November 13, 1990.2.The requirement for performing TS surveillances within the maximum time interval allowed by TS was conveyed to the TS surveillance planner responsible for procedure MP 15537.5.3.A memorandum has been issued to plant departmental supervisors responsible for the performance of surveillances identified in procedure O-OSP-200.1. | | POWER 20A05 (e l(1) 0) 50.$ 6(c) II I 50.734) 12)4) 73.71(cl LEVEL (10) 20A05(e l(1 )(SI 50.35(cl(21 50.'1341(2l(r41 OTHER (Specify In Apttrect pefow errf In Tert, HRC Form 20A054) (I l(iii) 50.73(el(1) (il 50.734) (2l(riiil(A) JFFAI 20A05 4) I I I lir) 50.7 $ (e l(21(4) 50.73(e I (2)(ri 4 H 4 I 20.605 (e) llI (el S0.7 34)(2) I iti) 50.7$ (e I (2 I (nl LICENSEE CONTACT FOR THIS LER (11) |
| The requirement for performing TS surveillances within the maximum time interval allowed by TS was re-emphasized. | | NAME TELEPHONE NUMSER AREA CODE David R. Powell, Licensing Superintendent 30 524 6- 559 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRISED IN THIS REPORT (13) |
| 4.In Licensee Event Report (LER)50-250/90-020-0, dated November 9, 1990, FPL committed to perform a management review of the generic problem of surveillance scheduling and tracking to determine applicable corrective actions to reduce the number of missed surveillances. | | MANUFAC EPORTABLE CAUSE SYSTEM COMPONENT MANVFAC. EPORTASL CAUSE SYSTEM COMPONENT TURER TO NPRDS TURER TO NPRDS 4%4~$44: c4%%>~: |
| The incident described in this LER will be included in the management review.The scheduled date for completion of the review is being escalated from February 15, 1991 to January 18, 1991 due to the additional instance of a missed TS surveillance described herein.A supplement to LER 50-250/90-020-0 will NRC FORM 366A O.ESI D | | 9er9:e'rr.L%'.<. @at SUPPLEMENTAL REPORT EXPECTED Ile) MONTH DAY YEAR EXPECTED SVSMISSION DATE (ISI YES IIIyeL comptete fXPfCTED SVSMISSIOH DATfl NO AssTRAcT (Limit to 1400 tpeceL I e., epprorimeteiy ftf4en tinpie tpece typewNHen linet) 116) |
| NRC Form 3ddA (9 83)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.3ISOW104 EXPIRES: 8/31/88 FACILITY NAME (I)DOCKET NUMBER (2)YEAR LER NUMBER (8)SEOUENTIAL NUMSEII II E V Id I 0 N NUM ER PACE (3)Turke Point Unit 3 TEXT///moro r/rrco/r>>r/vtrrd, v>>odd/rroor///RC Form SSSA'r/(17)6 0 0 0 25 090 0 2 2'00 0 OF 0 4 be submitted to report the results of this management review and the corrective actions determined to be necessary. | | On November 14, 1990, with Unit 3 and Unit 4 in Mode 1 at 100 percent power, FPL personnel discovered that a Technical Specification (TS) surveillance requirement had not been performed within the maximum allowed time interval. TS 4.15.4.a.1 requires the Unit 3 and Unit 4 fire hose stations to be visually inspected at least once per 31 days. TS 4.0.1 allows this specified interval to be adjusted plus or minus 25 percent to accommodate normal test schedules. The TS 4.15.4.a.1 surveillance requirement is implemented by performance of Appendix A to Maintenance Procedure (MP) 15537.5, "Fire Protection Equipment Surveillance." On November 13p 1990p Appendix A to procedure MP 15537 ' was performed as scheduled by Operating Surveillance Procedure O-OSP-200.1, "Schedule of Plant Checks and Surveillances." Appendix A to procedure MP 15537.5 was previously performed on October 4, 1990, five days earlier than scheduled by procedure 0-OSP-200.1. The maximum time interval allowed by TS between these surveillances was exceeded. The cause for this condition was inadequate administrative controls. A non-cognitive error by a non-licensed utility individual contributed to this event. |
| ADDITIONAL INFORMATION Incidents of missed TS surveillances have been reported in previous Licensee Event Reports (LERs).However, those~incidents did not share the same root cause as identified in this LER.NRC FORM dddA}} | | A memorandum concerning this event has been issued to plant departmental supervisors responsible for the performance of surveillances identified in procedure O-OSP-200.1. |
| | NRC Form 366 (9 8) I |
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| | NRC Form 3SSA U.S. NUCLEAR REOULATORY COMMISSION I84)3) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3180M)Cd EXPIRES: 8/31/88 FACILITYNAME 11) DOCKET NUMBER I2) LER NUMSER IS) PACE 13) |
| | /P/P/ SSOVSNTIAL PW ASVISION NVMSSA iArd NVMSSII Turkey Point Unit 3 0 5 0 0 0 250 gp 0 2 OF TEXT /// moro /poco /d /or/o/rod, o/o odd//lono/HRC Fomr 3//843/ ) )7) |
| | DESCRIPTION OF THE EVENT On November 14/ 1990/ with Unit 3 and Unit 4 in- Mode 1 at 100 percent power, FPL personnel discovered that a Technical Specification (TS) surveillance requirement had not been performed within the maximum allowed time interval. |
| | TS 4.15.4.a.1 requires the Unit 3 and Unit 4 fire hose stations to be visually insp'ected at least once per 31 days. Per TS 4.0.1, this specified interval may be adjusted plus or minus 25 percent to accommodate normal test schedules. |
| | The TS 4.15.4.a.1 surveillance requirement is implemented by performance of Appendix A to Maintenance Procedure (MP) 15537.5, "Fire Protection Equipment Surveillance." Procedure MP 15537.5 is scheduled by Operating Surveillance Procedure 0-OSP-200.1, "Schedule of Plant Checks and Surveillances/U to be performed on the second Tuesday of each month. Depending on which day of the month the second Tuesday falls, the normal scheduled time interval between surveillances can be either 28 days or 35 days. The normal scheduled time interval between the October and November surveillances was 35 days. |
| | For the month of October, procedure MP 15537.5 was scheduled to be performed on October 9, 1990. On October 4, 1990, Appendix A to procedure MP 15537.5 was completed five days earlier than scheduled. For the month of November, procedure MP 15537.'5 was scheduled to be performed on November,13, 1990. On November 13, 1990, Appendix A to procedure MP 15537.5 was completed as scheduled. The total elapsed time interval between these surv'eillances exceeded the maximum time interval allowed by TS. |
| | CAUSE OF THE EVENT The cause for exceeding the maximum allowed TS interval between fire hose station surveillances was inadequate administrative controls. If surveillances are performed on the date scheduled by procedure O-OSP-200.1, the surveillances will be performed within maximum time intervals allowed by TS. If a surveillance is not performed by the scheduled date, Control Room personnel will identify this condition during their daily review of procedure O-OSP-200.1 scheduling sheets and track the surveillance to completion. However, if a surveillance is performed earlier than scheduled by procedure O-OSP-200.1, no guidance or controls exist to ensure the maximum time interval allowed by TS is not exceeded. |
| | NAC FOAM SddA |
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| | NRC Form 366A U.S. NUCLEAR REOULATORY COMMISSION (983) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO, 3)50-0IOE EXPIRES: 8/31/68 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PACE (31 YEAR Po)" SEQUENTIAL %I(1 REVISION |
| | ~?? NUMSER NN NUMSER Turkey Point Unit 3 o s o o o 9 0 2 2 0 0 03 oF 0 4 TEXT //f moro E/Moo /E roEV/rod, u>> odd/o'ooo/rYRC Forrrr 36//AS/ (17) |
| | A contributing factor was a non-cognitive error by a non-. |
| | licensed utility individual. TSProcedure O-OSP-200.1 provides a schedule for performing required surveillances and identifies the department responsible for each surveillance. |
| | When the scheduled dates in procedure O-OSP-200.1 are not met, the responsible plant departmental TS surveillance scheduler should ensure the interval between surveillances is within the maximum time interval allowed by TS. |
| | ANALYSIS OF THE EVENT Performance of Appendix A to procedure MP 15537.5 within the TS maximum allowed time interval demonstrates continued operability of the Unit 3 and Unit 4 fire hose stations. |
| | the TS maximum allowed time interval between surveillances is If exceeded, then the fire hose stations are technically inoperable. Appendix A to procedure MP 15537.5 was satisfactorily completed on November 13, 1990. Therefore, the Unit 3 and Unit 4 fire hose stations were in fact physically capable of performing their intended function. |
| | CORRECTIVE ACTIONS |
| | : 1. Appendix A to procedure MP 15537.5 was satisfactorily completed on November 13, 1990. |
| | : 2. The requirement for performing TS surveillances within the maximum time interval allowed by TS was conveyed to the TS surveillance planner responsible for procedure MP 15537.5. |
| | : 3. A memorandum has been issued to plant departmental supervisors responsible for the performance of surveillances identified in procedure O-OSP-200.1. The requirement for performing TS surveillances within the maximum time interval allowed by TS was re-emphasized. |
| | : 4. In Licensee Event Report (LER) 50-250/90-020-0, dated November 9, 1990, FPL committed to perform a management review of the generic problem of surveillance scheduling and tracking to determine applicable corrective actions to reduce the number of missed surveillances. The incident described in this LER will be included in the management review. The scheduled date for completion of the review is being escalated from February 15, 1991 to January 18, 1991 due to the additional instance of a missed TS surveillance described herein. A supplement to LER 50-250/90-020-0 will NRC FORM 366A O.ESI |
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| | D NRC Form 3ddA U.S. NUCLEAR REOULATORY COMMISSION (9 83) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3ISOW104 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (8) PACE (3) |
| | YEAR SEOUENTIAL IIE V Id I0 N NUMSEII NUM ER Turke Point Unit 3 6 0 0 0 25 090 0 2 2 '00 0 OF 0 4 TEXT ///moro r/rrco /r>>r/vtrrd, v>> odd/rroor///RC Form SSSA'r/ (17) be submitted to report the results of this management review and the corrective actions determined to be necessary. |
| | ADDITIONAL INFORMATION Incidents of missed TS surveillances have been reported in previous Licensee Event Reports (LERs). However, those |
| | ~ |
| | incidents did not share the same root cause as identified in this LER. |
| | NRC FORM dddA}} |
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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
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9012180043 DOC.DATE: 90/12/12 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION POWELL,D.R. Florida Power & Light Co.
PLUNKETT,T.F. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 90-022-00:on 901114,discovered that Tech Spec required fire protection surveillance not performed within max allowed time interval. Caused by inadequate administrative controls. Memo issued.W/901212 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 EDISON,G 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 1 NRR/ DLPQ/LPE B 1 0 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SQLBS Dl 1 1 NRR/DST/SRXB 8E 1 1 REG -FXXB~~ 02 1 1 RES/DSIR/EIB 1 1 GN2 FILE 01 1 1 EXTERNAL EG &G BRYCE g J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT. 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
FULL. TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31
DEC 12 1990 L-90-4'31 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Reportable Event: 90-022 Date of Event: November 13, 1990 Fire Protection Surveillance Not Performed Within Technical S ecification Maximum Allowed Time Interval The attached Licensee Event Report is being provided pursuant to the requirements of 10CFR50.73 to provide information on the subject event. Corrective Action g 4- corresponds to a corrective action previously identified in LER 50-250/90-020-0. The scheduled date for completion of this corrective action is being escalated by Turkey Point Nuclear Plant management from February 15, 1991 to January 18, 1991 due to the additional instance of a missed Technical Specification surveillance described herein.
Very truly yours, cP7+~~
T. F. Plunkett Vice President Turkey Point Nuclear Plant TFP/DRP/dwh Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC, Senior Resident Inspectorr USNRCr Turkey Point Plant 9012180043 901212 PDR ADOCK 05000250 S - PPR an FPL Group company
NRC Form 364 US. NUCLEAR REOULATORY COMMISSION (903)
APPROVED DMS NO. 3160010C LlCENSEE EVENT REPORT (LER) EXPIRESt SI$ 'II44 FACILITYNAME (I I DOCKET NUMSER (1) PA Turkey Point Unit 3 o 5 o o o 250 10F04 TITLE (Cl s re ro ec s on urve) ance o er orme 1 s n ec ns ca pec1 s ca on Maximum Allowed Time Interval EVENT DATE ISI LER NVMSER (5) REPORT'ATE (7) OTHER FACILITIES INVOLVED (4)
MONTH OAY YKAR YEAR Ifcx $ 4QUENTIAI, MONTH DAY YEAR FACILITYNAMES DOCKET NVMSER(SI NUM4ER .c:e,. NUM44ti Turkey Point Unit 4 o so o o 25 1 1 390 9 0 0 2 00 12 1 2 9 0 0 5 0 0 0 THIS REPORT IS SVSMITTKD PURSUANT TO THE REOUIREMENTS OF 10 CF R g: ICneee One Or mtye Of tne IOIIOw'npl (11)
OPERATINO MODE 14) 20.402(4) 20.e06(cl 50 73(e l(2) (irl 7$ .71(4)
POWER 20A05 (e l(1) 0) 50.$ 6(c) II I 50.734) 12)4) 73.71(cl LEVEL (10) 20A05(e l(1 )(SI 50.35(cl(21 50.'1341(2l(r41 OTHER (Specify In Apttrect pefow errf In Tert, HRC Form 20A054) (I l(iii) 50.73(el(1) (il 50.734) (2l(riiil(A) JFFAI 20A05 4) I I I lir) 50.7 $ (e l(21(4) 50.73(e I (2)(ri 4 H 4 I 20.605 (e) llI (el S0.7 34)(2) I iti) 50.7$ (e I (2 I (nl LICENSEE CONTACT FOR THIS LER (11)
NAME TELEPHONE NUMSER AREA CODE David R. Powell, Licensing Superintendent 30 524 6- 559 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRISED IN THIS REPORT (13)
MANUFAC EPORTABLE CAUSE SYSTEM COMPONENT MANVFAC. EPORTASL CAUSE SYSTEM COMPONENT TURER TO NPRDS TURER TO NPRDS 4%4~$44: c4%%>~:
9er9:e'rr.L%'.<. @at SUPPLEMENTAL REPORT EXPECTED Ile) MONTH DAY YEAR EXPECTED SVSMISSION DATE (ISI YES IIIyeL comptete fXPfCTED SVSMISSIOH DATfl NO AssTRAcT (Limit to 1400 tpeceL I e., epprorimeteiy ftf4en tinpie tpece typewNHen linet) 116)
On November 14, 1990, with Unit 3 and Unit 4 in Mode 1 at 100 percent power, FPL personnel discovered that a Technical Specification (TS) surveillance requirement had not been performed within the maximum allowed time interval. TS 4.15.4.a.1 requires the Unit 3 and Unit 4 fire hose stations to be visually inspected at least once per 31 days. TS 4.0.1 allows this specified interval to be adjusted plus or minus 25 percent to accommodate normal test schedules. The TS 4.15.4.a.1 surveillance requirement is implemented by performance of Appendix A to Maintenance Procedure (MP) 15537.5, "Fire Protection Equipment Surveillance." On November 13p 1990p Appendix A to procedure MP 15537 ' was performed as scheduled by Operating Surveillance Procedure O-OSP-200.1, "Schedule of Plant Checks and Surveillances." Appendix A to procedure MP 15537.5 was previously performed on October 4, 1990, five days earlier than scheduled by procedure 0-OSP-200.1. The maximum time interval allowed by TS between these surveillances was exceeded. The cause for this condition was inadequate administrative controls. A non-cognitive error by a non-licensed utility individual contributed to this event.
A memorandum concerning this event has been issued to plant departmental supervisors responsible for the performance of surveillances identified in procedure O-OSP-200.1.
NRC Form 366 (9 8) I
NRC Form 3SSA U.S. NUCLEAR REOULATORY COMMISSION I84)3)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3180M)Cd EXPIRES: 8/31/88 FACILITYNAME 11) DOCKET NUMBER I2) LER NUMSER IS) PACE 13)
/P/P/ SSOVSNTIAL PW ASVISION NVMSSA iArd NVMSSII Turkey Point Unit 3 0 5 0 0 0 250 gp 0 2 OF TEXT /// moro /poco /d /or/o/rod, o/o odd//lono/HRC Fomr 3//843/ ) )7)
DESCRIPTION OF THE EVENT On November 14/ 1990/ with Unit 3 and Unit 4 in- Mode 1 at 100 percent power, FPL personnel discovered that a Technical Specification (TS) surveillance requirement had not been performed within the maximum allowed time interval.
TS 4.15.4.a.1 requires the Unit 3 and Unit 4 fire hose stations to be visually insp'ected at least once per 31 days. Per TS 4.0.1, this specified interval may be adjusted plus or minus 25 percent to accommodate normal test schedules.
The TS 4.15.4.a.1 surveillance requirement is implemented by performance of Appendix A to Maintenance Procedure (MP) 15537.5, "Fire Protection Equipment Surveillance." Procedure MP 15537.5 is scheduled by Operating Surveillance Procedure 0-OSP-200.1, "Schedule of Plant Checks and Surveillances/U to be performed on the second Tuesday of each month. Depending on which day of the month the second Tuesday falls, the normal scheduled time interval between surveillances can be either 28 days or 35 days. The normal scheduled time interval between the October and November surveillances was 35 days.
For the month of October, procedure MP 15537.5 was scheduled to be performed on October 9, 1990. On October 4, 1990, Appendix A to procedure MP 15537.5 was completed five days earlier than scheduled. For the month of November, procedure MP 15537.'5 was scheduled to be performed on November,13, 1990. On November 13, 1990, Appendix A to procedure MP 15537.5 was completed as scheduled. The total elapsed time interval between these surv'eillances exceeded the maximum time interval allowed by TS.
CAUSE OF THE EVENT The cause for exceeding the maximum allowed TS interval between fire hose station surveillances was inadequate administrative controls. If surveillances are performed on the date scheduled by procedure O-OSP-200.1, the surveillances will be performed within maximum time intervals allowed by TS. If a surveillance is not performed by the scheduled date, Control Room personnel will identify this condition during their daily review of procedure O-OSP-200.1 scheduling sheets and track the surveillance to completion. However, if a surveillance is performed earlier than scheduled by procedure O-OSP-200.1, no guidance or controls exist to ensure the maximum time interval allowed by TS is not exceeded.
NAC FOAM SddA
NRC Form 366A U.S. NUCLEAR REOULATORY COMMISSION (983)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO, 3)50-0IOE EXPIRES: 8/31/68 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PACE (31 YEAR Po)" SEQUENTIAL %I(1 REVISION
~?? NUMSER NN NUMSER Turkey Point Unit 3 o s o o o 9 0 2 2 0 0 03 oF 0 4 TEXT //f moro E/Moo /E roEV/rod, u>> odd/o'ooo/rYRC Forrrr 36//AS/ (17)
A contributing factor was a non-cognitive error by a non-.
licensed utility individual. TSProcedure O-OSP-200.1 provides a schedule for performing required surveillances and identifies the department responsible for each surveillance.
When the scheduled dates in procedure O-OSP-200.1 are not met, the responsible plant departmental TS surveillance scheduler should ensure the interval between surveillances is within the maximum time interval allowed by TS.
ANALYSIS OF THE EVENT Performance of Appendix A to procedure MP 15537.5 within the TS maximum allowed time interval demonstrates continued operability of the Unit 3 and Unit 4 fire hose stations.
the TS maximum allowed time interval between surveillances is If exceeded, then the fire hose stations are technically inoperable. Appendix A to procedure MP 15537.5 was satisfactorily completed on November 13, 1990. Therefore, the Unit 3 and Unit 4 fire hose stations were in fact physically capable of performing their intended function.
CORRECTIVE ACTIONS
- 1. Appendix A to procedure MP 15537.5 was satisfactorily completed on November 13, 1990.
- 2. The requirement for performing TS surveillances within the maximum time interval allowed by TS was conveyed to the TS surveillance planner responsible for procedure MP 15537.5.
- 3. A memorandum has been issued to plant departmental supervisors responsible for the performance of surveillances identified in procedure O-OSP-200.1. The requirement for performing TS surveillances within the maximum time interval allowed by TS was re-emphasized.
- 4. In Licensee Event Report (LER) 50-250/90-020-0, dated November 9, 1990, FPL committed to perform a management review of the generic problem of surveillance scheduling and tracking to determine applicable corrective actions to reduce the number of missed surveillances. The incident described in this LER will be included in the management review. The scheduled date for completion of the review is being escalated from February 15, 1991 to January 18, 1991 due to the additional instance of a missed TS surveillance described herein. A supplement to LER 50-250/90-020-0 will NRC FORM 366A O.ESI
D NRC Form 3ddA U.S. NUCLEAR REOULATORY COMMISSION (9 83)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3ISOW104 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (8) PACE (3)
YEAR SEOUENTIAL IIE V Id I0 N NUMSEII NUM ER Turke Point Unit 3 6 0 0 0 25 090 0 2 2 '00 0 OF 0 4 TEXT ///moro r/rrco /r>>r/vtrrd, v>> odd/rroor///RC Form SSSA'r/ (17) be submitted to report the results of this management review and the corrective actions determined to be necessary.
ADDITIONAL INFORMATION Incidents of missed TS surveillances have been reported in previous Licensee Event Reports (LERs). However, those
~
incidents did not share the same root cause as identified in this LER.
NRC FORM dddA
