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| {{#Wiki_filter:.PI%IT1 rlnn'nor M&*z)QVX%.L J REGULATO INFORMATION DISTRIBUTION | | {{#Wiki_filter:PI% IT1 rlnn'nor |
| ~TEM (RIDS)ACCESSION NBR:9707220413 DOC.DATE: 97/07/14 NOTARIZED: | | . |
| NO DOCKET.¹FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH.NAME AUTHOR AFFILIATION MOWREY,C.L. | | M&* z) QVX%. L J REGULATO INFORMATION DISTRIBUTION ~TEM (RIDS) |
| Florida Power 6 Light Co.HOVEY,R.J.
| | ACCESSION NBR:9707220413 DOC.DATE: 97/07/14 NOTARIZED: NO DOCKET .¹ FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION Florida MOWREY,C.L. |
| 'lorida Power 6 Light Co.RECIP.NAME RECIPIENT.AFFILIATION | | HOVEY,R.J. |
| | RECIP.NAME |
| | 'lorida Power 6 Light Co. |
| | Power 6 Light Co. |
| | RECIPIENT .AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| 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.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 PD2-3 PD NTERNAL: AEOD/SPD/RAB | | 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. |
| ','FILE'ENTER NRR/DE/EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2 FILE 01 XTERNAL: L ST LOBBY WARD NOAC POOREiW.NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME CROTEAUgR AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB LITCO BRYCEg J H NOAC QUEENERgDS NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1"1 1 1 1 1 1 1 0 D 0 C NOTE TO ALL"RIDS" RECIPIENTS:. | | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: |
| PLEASE HELP US TO REDUCE WASTE I CONTACT THE DOCUMENT CONTROL DES j(g ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS"YOU DON'T NEEDI c=+FULL TEXT CONVERSION REQUIRED OTAL,.@UMBER.OF.COPIES~REgUKED-LTTR 24 ENCL..x-24 | | 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 0 PD2-3 PD 1 1 CROTEAUgR 1 1 NTERNAL: AEOD/SPD/RAB 2 2 AEOD/SPD/RRAB 1 1 |
| | ', 'FILE'ENTER 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DET/EIB 1 "1 RGN2 FILE 01 1 1 D |
| | XTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEg J H 1 1 NOAC POOREiW. 1 1 NOAC QUEENERgDS 1 1 0 NRC PDR 1 1 NUDOCS FULL TXT 1 1 C |
| | NOTE TO ALL "RIDS" RECIPIENTS:. |
| | PLEASE HELP US TO REDUCE WASTE I CONTACT THE DOCUMENT CONTROL DES j(g ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS"YOU DON'T NEEDI c =+ |
| | FULL TEXT CONVERSION REQUIRED OTAL,.@UMBER.OF.COPIES~REgUKED- LTTR 24 ENCL..x-24 |
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| PPh JUL 14 t997 L-97-0169 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 Reportable Event: 97-005 Date of Event: June 18, 1997 Rea r lant Pum il Collection S stem 0 tside Desi Basis The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 t'o provide notiQcation of the subject event.Very truly yours, R.J.Hovey Vice President Turkey Point Plant CLM Attachment cc: Regional Administrator, USNRC Region II Senior Resident Inspector, USNRC, Turkey Point Plant/w~97072204%3 9'707%4 PDR ADOCK 05000250 S.PDR")Qg5'2" t 4e'F PL:Gr5up'd dmp'any">llllllllllllllllllllII)llllflllllllillll | | PPh JUL 14 t997 L-97-0169 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Reportable Event: 97-005 Date of Event: June 18, 1997 Rea r lant Pum il Collection S stem 0 tside Desi Basis The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 t'o provide notiQcation of the subject event. |
| | Very truly yours, R. J. Hovey Vice President Turkey Point Plant CLM Attachment cc: Regional Administrator, USNRC Region II |
| | /w~ |
| | Senior Resident Inspector, USNRC, Turkey Point Plant 97072204%3 9'707%4 PDR ADOCK 05000250 S . PDR |
| | ") Qg5'2" llllllllllllllllllllII)llllflllllllillll t |
| | 4e'F PL:Gr5up'd dmp'any" > |
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| FACILITY NAHE (1)LICENSEE EVENT REPORT (LER)DOCKET NUHBER LT)PAGE LB)TURKEY POINT UNIT 3 05000250 1 Of TITLE<4)REACTOR COOLANT PUMP OZL COLLECTION SYSTEM OUTSIDE DESIGN BASIS EVENT DATE<5)NON DAY YR 18 97 OPERATING HDDE{9)LER NUMBER{6)YR SEO 0 Rl 97 05 00 RPT DATE{7)H)N DAY YR 7 14 97 OTNER FACILITIES INV.<8)FACILITY NAHES TURKEY POINT UNIT 4 DOCKET 6{S)05000251 PONER LEVEL Z10)100/100 10 CFR 50.73 (a)(2)(ii)LICENSEE CONTACT FOR THIS LER (12)C.L MONREYq COMPLIANCE SPECIALIST Telephone Number (305)246-6204 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEH S YSTZH NPRDSF N I<SUPPLEHENTAL REPORT EXPECTED t14)))0 YE 0 EXPECTED SUBHZSSZON DATE (15).ZIE yesr cceplete EXPECTED SUBHZSSZON DATE), ABSTRACT (16)I During planning for a modification, Florida'ower
| | LICENSEE EVENT REPORT (LER) |
| &Light Company determined that the design of the Reactor Coolant Pump (RCP)Oil Collection System does not capture leakage from all potential leakage sites.Specifically, the level switches, their associated piping flanges, the level sightglasses, and the lube oil cooler piping drain are not protected from being potential leakage sites, and are not piovided with leakage collection. | | FACILITY NAHE (1) DOCKET NUHBER LT) PAGE LB) |
| This condition places both turkey Point units outside the design basis as stated in the Updated Final Safety Analysis Report.The original RCP Oil Collection System design did not consider these component parts to be potential leakage sources.The NRC's Safety Evaluation Report approving Turkey Point's Oil Collection System was received several months prior to the time that lOCFR50 Appendix R was issued.It appears that when Appendix R was issued, the design was not reconciled with respect to.theexact wording of section III.O.The Oil Collection System will be modified to collect potential leakage from these points.In the interim, the Oil Collection System is considered operable. | | TURKEY POINT UNIT 3 05000250 1 Of TITLE <4) REACTOR COOLANT PUMP OZL COLLECTION SYSTEM OUTSIDE DESIGN BASIS EVENT DATE <5) LER NUMBER{6) RPT DATE {7) OTNER FACILITIES INV. <8) |
| | NON DAY YR YR SEO 0 Rl H)N DAY YR FACILITY NAHES DOCKET 6 {S) 18 97 97 05 00 7 14 97 TURKEY POINT UNIT 4 05000251 OPERATING HDDE {9) |
| | PONER LEVEL Z10) 100/100 10 CFR 50.73 (a) (2) (ii) |
| | LICENSEE CONTACT FOR THIS LER (12) |
| | Telephone Number C.L MONREYq COMPLIANCE SPECIALIST (305) 246-6204 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | CAUSE SYSTEH S YSTZH NPRDSF N |
| | I< |
| | SUPPLEHENTAL REPORT EXPECTED t14) ))0 YE 0 EXPECTED SUBHZSSZON DATE (15) |
| | .ZIE yesr cceplete EXPECTED SUBHZSSZON DATE) |
| | , ABSTRACT (16) |
| | I During planning for a modification, Florida'ower & Light Company determined that the design of the Reactor Coolant Pump (RCP) Oil Collection System does not capture leakage from all potential leakage sites. Specifically, the level switches, their associated piping flanges, the level sightglasses, and the lube oil cooler piping drain are not protected from being potential leakage sites, and are not piovided with leakage collection. This condition places both turkey Point units outside the design basis as stated in the Updated Final Safety Analysis Report. |
| | The original RCP Oil Collection System design did not consider these component parts to be potential leakage sources. The NRC's Safety Evaluation Report approving Turkey Point's Oil Collection System was received several months prior to the time that lOCFR50 Appendix R was issued. It appears that when Appendix R was issued, the design was not reconciled with respect to .the exact wording of section III.O. |
| | The Oil Collection System will be modified to collect potential leakage from these points. In the interim, the Oil Collection System is considered operable. |
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| LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME TURKEY POINT UNIT 3 DOCKET NUMBER 05000250 LER NUMBER.97-005-00 PAGE NO.2 OF 4 I.DESCRIPTION OF THE EVENT On June 18, 1997, Florida Power&Light Company's (FPL)Turkey Point Units 3 and 4 were at 100 percent power.During the planning for a modification, FPL determined that the Reactor Coolant Pump (RCP)[AB:p], Oil Collection System was not designed to capture leakage from all potential leakage sites.Because Unit 3 and Unit 4 have similar RCP motors[AB:mtr]and Oil Collection Systems, the design deficiencies are applicable to both units.The existing RCP Oil Collection System design consists of oil spray enclosures (shields)and drip pans on each RCP motor.A gravity drain piping system is provided to transport any accumulated oil from these devices to a closed vented oil collection tank.The tank is located outside the secondary shield wall, away from any sources of heat greater than the oil's flashpoint. | | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO. |
| 10CFR50 Appendix R section III.O requires, in part, that,"Such collection systems shall be capable of.collecting lube oil from all potential pressurized and unpressurized. | | TURKEY POINT UNIT 3 05000250 .97-005-00 2 OF 4 I. DESCRIPTION OF THE EVENT On June 18, 1997, Florida Power & Light Company's (FPL) Turkey Point Units 3 and 4 were at 100 percent power. During the planning for a modification, FPL determined that the Reactor Coolant Pump (RCP) [AB:p], |
| leakage sites in the reactor coolant pump lube oil systems.... | | Oil Collection System was not designed to capture leakage from all potential leakage sites. Because Unit 3 and Unit 4 have similar RCP motors [AB:mtr] and Oil Collection Systems, the design deficiencies are applicable to both units. |
| Leakage points to be protected shall include lift pump and piping, ove'rflow lines, lube oil cooler, oil fill" and drain lines and'plugs, flanged connections on'oil lines, and lube oil reservoirs where=such features exist on the reactor coolant pumps." Turkey Point's interpretation of these requirements is that all possible leakage points shall be collected (if they are considered potential leakage points), or protected (from being potential leakage points).Therefore to satisfy 10CFR50 Appendix R section III.O, Turkey Point's Oil Collection System must collect potential leakage from all potential leakage sites, and protect other sites from being potential leakage sites.5 Appendix 9.6A of Turkey Point's Updated Final Safety Analysis Report (UFSAR)describes the plant's fire protection program.Section 2.5 of that appendix is a lineup of 10CFR50 Appendix R requirements and Turkey Point's method of conformance or alternative. | | The existing RCP Oil Collection System design consists of oil spray enclosures (shields) and drip pans on each RCP motor. A gravity drain piping system is provided to transport any accumulated oil from these devices to a closed vented oil collection tank. The tank is located outside the secondary shield wall, away from any sources of heat greater than the oil's flashpoint. |
| For 10CFR50 Appendix R, section III.O, the UFSAR states, in part,"The system collects potential leakage.from the oil lift pump and piping, lube oil cooler, flanged connections on oil lines, and lube oil reservoirs." Other possible sites are protected's follows,"The upper bearing'ssembly overflow/vent path is protected because oil would first leak through a shaft seal located below the overflow/vent connection. | | 10CFR50 Appendix R section III.O requires, in part, that, "Such collection systems shall be capable of. collecting lube oil from all potential pressurized and unpressurized. leakage sites in the reactor coolant pump lube oil systems.... Leakage points to be protected shall include lift |
| This oil would then be collected in the lower bearing oil reservoir collection assembly.. | | " and drain lines pump and piping, ove'rflow lines, lube oil cooler, oil and 'plugs, flanged connections on'oil lines, and lube fill oil reservoirs where =such features exist on the reactor coolant pumps." |
| The fill lines are protected by being above normal operating levels and by being sealed with screw caps.The drain lined are protected by having valves and by being plugged with threaded caps to ensure leak-tight integrity." | | Turkey Point's interpretation of these requirements is that all possible leakage points shall be collected (if they are considered potential leakage points), or protected (from being potential leakage points) . Therefore to satisfy 10CFR50 Appendix R section III.O, Turkey Point's Oil Collection System must collect potential leakage from all potential leakage sites, and protect other sites from being potential leakage sites. 5 Appendix 9.6A of Turkey Point's Updated Final Safety Analysis Report (UFSAR) describes the plant's fire protection program. Section 2.5 of that appendix is a lineup of 10CFR50 Appendix R requirements and Turkey Point's method of conformance or alternative. For 10CFR50 Appendix R, section III.O, the UFSAR states, in part, "The system collects potential leakage .from the oil lift pump and piping, lube oil cooler, flanged connections on oil lines, and lube oil reservoirs." Other possible sites are protected's follows, "The upper bearing'ssembly overflow/vent path is protected because oil would first leak through a shaft seal located below the overflow/vent connection. This oil would then be collected in the lower bearing oil reservoir collection assembly.. The fill lines are protected by being above normal operating levels and by being sealed with screw caps. The drain lined are protected by having valves and by being plugged with threaded caps to ensure leak-tight integrity." |
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| LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME TURKEY POINT UNIT 3 DOCKET NUMBER 05000250 LER NUMBER 97-005-00 PAGE NO.3 OF 4 UFSAR Appendix 9.6A, section 3.10.3, further describes'he Oil Collection System,"Oil collection assemblies are provided for the oil lift pump system, lower bearing oil reservoir and the bearing oil cooler.The bearing oil cooler collection assembly collects oil from the bearing oil cooler upper pipe flange, lower pipe flange, upper end flange and lower end flange." The UFSAR describes neither collection nor protection.for the upper and lower level switch assemblies and associated piping flanges,.-.the level sightglasses, and the lube oil cooler piping drain.FPL therefore determined that the design of the RCP Oil Collection System was deficient in that not all potential oil leakage sources have provisions for collection. | | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO. |
| II.CAUSE OF THE EVENT The original RCP Oil Collection System design did not consider these component parts to be potential leakage sources because they were essentially. | | TURKEY POINT UNIT 3 05000250 97-005-00 3 OF 4 UFSAR Appendix 9.6A, section 3.10.3, further describes'he Oil Collection System, "Oil collection assemblies are provided for the oil lift pump system, lower bearing oil reservoir and the bearing oil cooler. The bearing oil cooler collection assembly collects oil from the bearing oil cooler upper pipe flange, lower pipe flange, upper end flange and lower end flange." |
| unpressurized and.considered unlikely to develop.a...significant rate or volume of leakage.The reservoirs operate at atmospheric pressure or at a slightly positive pressure.Therefore, design features were not provided to collect oil from these locations. | | The UFSAR describes neither collection nor protection .for the upper and lower level switch assemblies and associated piping flanges,.-.the level sightglasses, and the lube oil cooler piping drain. FPL therefore determined that the design of the RCP Oil Collection System was deficient in that not all potential oil leakage sources have provisions for collection. |
| The NRC's Safety Evaluation Report approving.Turkey Point's Oil Collection System was received several months prior to the time that 10CFR50 Appendix R was issued.It appears that when Appendix R was issued, the design was not reconciled with respect to the exact wording of section III.O.III.ANALYSIS OF THE EVENT The uncollected potential leakage sites were assessed in order to characterize any postulated leakage and the.resultant. | | II. CAUSE OF THE EVENT The original RCP Oil Collection System design did not consider these component parts to be potential leakage sources because they were essentially. unpressurized and .considered unlikely to develop .a ... |
| fire potential. | | significant rate or volume of leakage. The reservoirs operate at atmospheric pressure or at a slightly positive pressure. Therefore, design features were not provided to collect oil from these locations. |
| Any postulated leakage would be from a low or zero pressure source.Therefore, postulated oil leakage would not be sprayed (atomized), but would result in only min'or drips of uncollected oil.The fire potential of such leakage i's minimal;-if a drip were to come in contact with a hot surface (temperature over the oil ignition temperature) it would not accumulate; the drop would burn but not support further combustion.. | | The NRC's Safety Evaluation Report approving .Turkey Point's Oil Collection System was received several months prior to the time that 10CFR50 Appendix R was issued. It appears that when Appendix R was issued, the design was not reconciled with respect to the exact wording of section III.O. |
| If it comes in'ontact. | | III. ANALYSIS OF THE EVENT The uncollected potential leakage sites were assessed in order to characterize any postulated leakage and the. resultant. fire potential. |
| with a cool surface it could locally accumulate, but would eventually migrate to the floor.Oil accumulating on the floor would flow to floor drains based on floor slope.Lubricating oil on the floor or in the sump is not subject to'gnition because the floor is a vast heat sink which will maintain the oil at a low temperature and prevent it from reaching its ignition point.Therefore, the potential for a fire resulting from minor oil leakage from these locations is not considered credible. | | Any postulated leakage would be from a low or zero pressure source. |
| LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME TURKEY POINT UNIT 3 DOCKET NUMBER 05000250 LER NUMBER 97-005-00 PAGE NO.4 OF 4 Since no significant lea'kage has been experienced from the uncollected potential leakage sites, and since these sites are not expected to suffer any significant leakage, the condition reported herein did not compromise the health or safety of plant personnel or the general public.IV.CORRECTIVE ACTIONS 1.The entire RCP Oil Collection System was reviewed to ensure that all potential leakage sites were identified. | | Therefore, postulated oil leakage would not be sprayed (atomized), but would result in only min'or drips of uncollected oil. The fire if potential of such leakage i's minimal;- a drip were to come in contact with a hot surface (temperature over the oil ignition temperature) would not accumulate; the drop would burn but not support further it combustion.. it it If comes in'ontact. with a cool surface could locally accumulate, but would eventually migrate to the floor. Oil accumulating on the floor would flow to floor drains based on floor slope. Lubricating oil on the floor or in the sump is not subject because the floor is a vast heat sink which will maintain the it to'gnition oil at a low temperature and prevent from reaching its ignition point. Therefore, the potential for a fire resulting from minor oil leakage from these locations is not considered credible. |
| 2.A modification will be implemented on the Unit 4 RCP Oil Collection System to ensure that any future oil leakage from the uncollected potential leakage sites would be captured by the system.FPL intends to complete this modification during the Cycle 17 refueling outage, scheduled'to start in early September. | | |
| Should design, procurement, or construction difficulties arise which prevent, completion, the modification will be completed no'ater than the Cycle 18 refueling.outage,.presently scheduled.for the spring of 1999.3.Similar modifications will be implemented on the Unit 3 RCP Oil Collection System.These modifications.are presently scheduled to be.completed during the Cycle 17 refueling outage (fall 1998).V.ADDITIONAL INFORMATION Similar events: Licensee Event Report 250/89-016 also reported a condition of the RCP Oil Collection System outside the design basis.The size of the collection tank was determined to be less than that required by an approved exemption to 10CFR50 Appendix R, section III.O, as a result of replacement. | | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO. |
| of the 3A RCP motor with a motor haying a larger oil capacity.The corrective actions for this event could not have been reasonably expected to result in discovery of the condition reported herein.L EIIS Codes are shown in the format[EIIS SYSTEM: IEEE component function identifier, second component identifier (if appropriate)].}} | | TURKEY POINT UNIT 3 05000250 97-005-00 4 OF 4 Since no significant lea'kage has been experienced from the uncollected potential leakage sites, and since these sites are not expected to suffer any significant leakage, the condition reported herein did not compromise the health or safety of plant personnel or the general public. |
| | IV. CORRECTIVE ACTIONS |
| | : 1. The entire RCP Oil Collection System was reviewed to ensure that all potential leakage sites were identified. |
| | : 2. A modification will be implemented on the Unit 4 RCP Oil Collection System to ensure that any future oil leakage from the uncollected potential leakage sites would be captured by the system. FPL intends to complete this modification during the Cycle 17 refueling outage, scheduled 'to start in early September. |
| | Should design, procurement, or construction difficulties arise which prevent, completion, the modification will be completed than the Cycle 18 refueling .outage,.presently scheduled .for no'ater the spring of 1999. |
| | : 3. Similar modifications will be implemented on the Unit 3 RCP Oil Collection System. These modifications .are presently scheduled to be. completed during the Cycle 17 refueling outage (fall 1998). |
| | V. ADDITIONAL INFORMATION Similar events: Licensee Event Report 250/89-016 also reported a condition of the RCP Oil Collection System outside the design basis. |
| | The size of the collection tank was determined to be less than that required by an approved exemption to 10CFR50 Appendix R, section III.O, as a result of replacement. of the 3A RCP motor with a motor haying a larger oil capacity. The corrective actions for this event could not have been reasonably expected to result in discovery of the condition reported herein. |
| | L EIIS Codes are shown in the format [EIIS SYSTEM: IEEE component function identifier, second component identifier (if appropriate)].}} |
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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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ACCESSION NBR:9707220413 DOC.DATE: 97/07/14 NOTARIZED: NO DOCKET .¹ FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION Florida MOWREY,C.L.
HOVEY,R.J.
RECIP.NAME
'lorida Power 6 Light Co.
Power 6 Light Co.
RECIPIENT .AFFILIATION
SUBJECT:
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.
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 0 PD2-3 PD 1 1 CROTEAUgR 1 1 NTERNAL: AEOD/SPD/RAB 2 2 AEOD/SPD/RRAB 1 1
', 'FILE'ENTER 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DET/EIB 1 "1 RGN2 FILE 01 1 1 D
XTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEg J H 1 1 NOAC POOREiW. 1 1 NOAC QUEENERgDS 1 1 0 NRC PDR 1 1 NUDOCS FULL TXT 1 1 C
NOTE TO ALL "RIDS" RECIPIENTS:.
PLEASE HELP US TO REDUCE WASTE I CONTACT THE DOCUMENT CONTROL DES j(g ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS"YOU DON'T NEEDI c =+
FULL TEXT CONVERSION REQUIRED OTAL,.@UMBER.OF.COPIES~REgUKED- LTTR 24 ENCL..x-24
PPh JUL 14 t997 L-97-0169 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Reportable Event: 97-005 Date of Event: June 18, 1997 Rea r lant Pum il Collection S stem 0 tside Desi Basis The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 t'o provide notiQcation of the subject event.
Very truly yours, R. J. Hovey Vice President Turkey Point Plant CLM Attachment cc: Regional Administrator, USNRC Region II
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Senior Resident Inspector, USNRC, Turkey Point Plant 97072204%3 9'707%4 PDR ADOCK 05000250 S . PDR
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LICENSEE EVENT REPORT (LER)
FACILITY NAHE (1) DOCKET NUHBER LT) PAGE LB)
TURKEY POINT UNIT 3 05000250 1 Of TITLE <4) REACTOR COOLANT PUMP OZL COLLECTION SYSTEM OUTSIDE DESIGN BASIS EVENT DATE <5) LER NUMBER{6) RPT DATE {7) OTNER FACILITIES INV. <8)
NON DAY YR YR SEO 0 Rl H)N DAY YR FACILITY NAHES DOCKET 6 {S) 18 97 97 05 00 7 14 97 TURKEY POINT UNIT 4 05000251 OPERATING HDDE {9)
PONER LEVEL Z10) 100/100 10 CFR 50.73 (a) (2) (ii)
LICENSEE CONTACT FOR THIS LER (12)
Telephone Number C.L MONREYq COMPLIANCE SPECIALIST (305) 246-6204 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEH S YSTZH NPRDSF N
I<
SUPPLEHENTAL REPORT EXPECTED t14) ))0 YE 0 EXPECTED SUBHZSSZON DATE (15)
.ZIE yesr cceplete EXPECTED SUBHZSSZON DATE)
, ABSTRACT (16)
I During planning for a modification, Florida'ower & Light Company determined that the design of the Reactor Coolant Pump (RCP) Oil Collection System does not capture leakage from all potential leakage sites. Specifically, the level switches, their associated piping flanges, the level sightglasses, and the lube oil cooler piping drain are not protected from being potential leakage sites, and are not piovided with leakage collection. This condition places both turkey Point units outside the design basis as stated in the Updated Final Safety Analysis Report.
The original RCP Oil Collection System design did not consider these component parts to be potential leakage sources. The NRC's Safety Evaluation Report approving Turkey Point's Oil Collection System was received several months prior to the time that lOCFR50 Appendix R was issued. It appears that when Appendix R was issued, the design was not reconciled with respect to .the exact wording of section III.O.
The Oil Collection System will be modified to collect potential leakage from these points. In the interim, the Oil Collection System is considered operable.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO.
TURKEY POINT UNIT 3 05000250 .97-005-00 2 OF 4 I. DESCRIPTION OF THE EVENT On June 18, 1997, Florida Power & Light Company's (FPL) Turkey Point Units 3 and 4 were at 100 percent power. During the planning for a modification, FPL determined that the Reactor Coolant Pump (RCP) [AB:p],
Oil Collection System was not designed to capture leakage from all potential leakage sites. Because Unit 3 and Unit 4 have similar RCP motors [AB:mtr] and Oil Collection Systems, the design deficiencies are applicable to both units.
The existing RCP Oil Collection System design consists of oil spray enclosures (shields) and drip pans on each RCP motor. A gravity drain piping system is provided to transport any accumulated oil from these devices to a closed vented oil collection tank. The tank is located outside the secondary shield wall, away from any sources of heat greater than the oil's flashpoint.
10CFR50 Appendix R section III.O requires, in part, that, "Such collection systems shall be capable of. collecting lube oil from all potential pressurized and unpressurized. leakage sites in the reactor coolant pump lube oil systems.... Leakage points to be protected shall include lift
" and drain lines pump and piping, ove'rflow lines, lube oil cooler, oil and 'plugs, flanged connections on'oil lines, and lube fill oil reservoirs where =such features exist on the reactor coolant pumps."
Turkey Point's interpretation of these requirements is that all possible leakage points shall be collected (if they are considered potential leakage points), or protected (from being potential leakage points) . Therefore to satisfy 10CFR50 Appendix R section III.O, Turkey Point's Oil Collection System must collect potential leakage from all potential leakage sites, and protect other sites from being potential leakage sites. 5 Appendix 9.6A of Turkey Point's Updated Final Safety Analysis Report (UFSAR) describes the plant's fire protection program. Section 2.5 of that appendix is a lineup of 10CFR50 Appendix R requirements and Turkey Point's method of conformance or alternative. For 10CFR50 Appendix R, section III.O, the UFSAR states, in part, "The system collects potential leakage .from the oil lift pump and piping, lube oil cooler, flanged connections on oil lines, and lube oil reservoirs." Other possible sites are protected's follows, "The upper bearing'ssembly overflow/vent path is protected because oil would first leak through a shaft seal located below the overflow/vent connection. This oil would then be collected in the lower bearing oil reservoir collection assembly.. The fill lines are protected by being above normal operating levels and by being sealed with screw caps. The drain lined are protected by having valves and by being plugged with threaded caps to ensure leak-tight integrity."
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO.
TURKEY POINT UNIT 3 05000250 97-005-00 3 OF 4 UFSAR Appendix 9.6A, section 3.10.3, further describes'he Oil Collection System, "Oil collection assemblies are provided for the oil lift pump system, lower bearing oil reservoir and the bearing oil cooler. The bearing oil cooler collection assembly collects oil from the bearing oil cooler upper pipe flange, lower pipe flange, upper end flange and lower end flange."
The UFSAR describes neither collection nor protection .for the upper and lower level switch assemblies and associated piping flanges,.-.the level sightglasses, and the lube oil cooler piping drain. FPL therefore determined that the design of the RCP Oil Collection System was deficient in that not all potential oil leakage sources have provisions for collection.
II. CAUSE OF THE EVENT The original RCP Oil Collection System design did not consider these component parts to be potential leakage sources because they were essentially. unpressurized and .considered unlikely to develop .a ...
significant rate or volume of leakage. The reservoirs operate at atmospheric pressure or at a slightly positive pressure. Therefore, design features were not provided to collect oil from these locations.
The NRC's Safety Evaluation Report approving .Turkey Point's Oil Collection System was received several months prior to the time that 10CFR50 Appendix R was issued. It appears that when Appendix R was issued, the design was not reconciled with respect to the exact wording of section III.O.
III. ANALYSIS OF THE EVENT The uncollected potential leakage sites were assessed in order to characterize any postulated leakage and the. resultant. fire potential.
Any postulated leakage would be from a low or zero pressure source.
Therefore, postulated oil leakage would not be sprayed (atomized), but would result in only min'or drips of uncollected oil. The fire if potential of such leakage i's minimal;- a drip were to come in contact with a hot surface (temperature over the oil ignition temperature) would not accumulate; the drop would burn but not support further it combustion.. it it If comes in'ontact. with a cool surface could locally accumulate, but would eventually migrate to the floor. Oil accumulating on the floor would flow to floor drains based on floor slope. Lubricating oil on the floor or in the sump is not subject because the floor is a vast heat sink which will maintain the it to'gnition oil at a low temperature and prevent from reaching its ignition point. Therefore, the potential for a fire resulting from minor oil leakage from these locations is not considered credible.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO.
TURKEY POINT UNIT 3 05000250 97-005-00 4 OF 4 Since no significant lea'kage has been experienced from the uncollected potential leakage sites, and since these sites are not expected to suffer any significant leakage, the condition reported herein did not compromise the health or safety of plant personnel or the general public.
IV. CORRECTIVE ACTIONS
- 1. The entire RCP Oil Collection System was reviewed to ensure that all potential leakage sites were identified.
- 2. A modification will be implemented on the Unit 4 RCP Oil Collection System to ensure that any future oil leakage from the uncollected potential leakage sites would be captured by the system. FPL intends to complete this modification during the Cycle 17 refueling outage, scheduled 'to start in early September.
Should design, procurement, or construction difficulties arise which prevent, completion, the modification will be completed than the Cycle 18 refueling .outage,.presently scheduled .for no'ater the spring of 1999.
- 3. Similar modifications will be implemented on the Unit 3 RCP Oil Collection System. These modifications .are presently scheduled to be. completed during the Cycle 17 refueling outage (fall 1998).
V. ADDITIONAL INFORMATION Similar events: Licensee Event Report 250/89-016 also reported a condition of the RCP Oil Collection System outside the design basis.
The size of the collection tank was determined to be less than that required by an approved exemption to 10CFR50 Appendix R, section III.O, as a result of replacement. of the 3A RCP motor with a motor haying a larger oil capacity. The corrective actions for this event could not have been reasonably expected to result in discovery of the condition reported herein.
L EIIS Codes are shown in the format [EIIS SYSTEM: IEEE component function identifier, second component identifier (if appropriate)].
