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| | number = ML17223A214 | | | number = ML17223A214 |
| | issue date = 07/05/1989 | | | issue date = 07/05/1989 |
| | title = LER 89-004-00:on 890605,Leak Rate on Containment Penetration 10 Exceeded Allowance,Per Tech Spec 4.6.1.7.3. Caused by Personnel Error.Technical Manual Change Request Submitted.W/890705 Ltr | | | title = LER 89-004-00:on 890605,leak Rate on Containment Penetration 10 Exceeded Allowance,Per Tech Spec 4.6.1.7.3. Caused by Personnel Error.Technical Manual Change Request submitted.W/890705 Ltr |
| | author name = HOLIFIELD C D, WOODY C O | | | author name = Holifield C, Woody C |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| | page count = 5 | | | page count = 5 |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:8907120017 DOC.DATE: 89/07/05 NOTARIZED: NO DOCKET FACIL:50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME 'UTHOR AFFILIATION HOLIFIELD,C.D.. Florida Power & Light Co. |
| | WOODY,C.O. |
| | Florida Power & Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION R |
| | |
| | ==SUBJECT:== |
| | LER 89-004-00:on 890605,containment local leak rate exceeds I |
| | TS due to valve closure stop out of adjustment. D DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: |
| | TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc. t ~ |
| | t NOTES'OPIES RECIPIENT RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 D NORRIS,J 1 1 D |
| | INTERNAL: ACRS MICHELSON. 1 1 ACRS 2 2 ACRS WYLIE 1 MOELLER'EOD/DOA 1 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 '2 DEDRO 1 1 IRM/DCTS/DAB 1 NRR/DEST/ADE, 8H '1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 1" |
| | NRR/DEST/MTB 9H 1 ,.1 NRR/DESTO''PSB 8D 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 NRR~REP/ PB 10 2 2 NUDOCS-ABSTRACT 1 REG 02 1 . 1 RES/DSIR/EIB 1 RES/DSR/PRAB 1 1 RGN2 FILE 01 1 1 EXTERNAL EG&G WILLIAMSg S 4 4 FORD BLDG HOY,A L ST LOBBY 'WARD 1 1 LPDR NRC PDR 1 1 NSIC MAYS,G NSIC MURPHYgG A 1' D |
| | 'S D |
| | D NOIR 'ZO ALL ''RIDS" R1KXEKENIS: |
| | EEZASE HELP US 'IO REDOCE %ASTH! CGMIRCZ GHE 1XXUMEÃZ CDÃGRL DESK, RXN P1-37 (EZT. 20079) Kl EKaIHQQZB ACR NAHB PKH DI895GEPXXQN LISTS EQR DOCUMEÃIS YOU DCSERT NERD! |
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES. REQUIRED: LTTR 43 ENCL 42 |
| | |
| | P.O. Box14000, Juno Beach, FL 33408.0420 JULY, 5 1989 L-89-238 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| | Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 89-04 Date of Event: 'June 5, 1989 Containment Local Leak Rate Exceeds Technical Specifications Due to Valve Closure Sto Out of Ad'ustment Due to Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event. |
| | Very truly yours, |
| | .C. 0. Wo Acting nior Vice President Nuclear COW/JRH/cm Attachment cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC |
| | / |
| | -:907120017 S9070 PDR ADGCK 05000389 PDC all I l l a>> < I |
| | |
| | NRC fornr 344 U.S. NUCLEAR REOULATORY COMMISSION 94)31 APPROVED OMS NO, 3150410C LICENSEE EVENT REPORT {LER) EXPIRES,'~ /31/$5 FACILITY NAME lll OOCKEt NUMSER (2) PAO I St. Lucie, Unit 2 o s oo o38 1 OF TITLE <<) Contaqnmen oca +a a e xcee s ec naca peer i ca n Closure Sto put of Adjustment Due to Personnel Error EVENT DATE (5I LER NUMSER (5) REtORT DATE (7) OTHER FACILITIES INVOLVED ISI S 4 0 u 4 N 7 I A I. "SYR~ FACILITYNAMES OOCRET NuMEER(s> |
| | MONTe DAY YEAR YEAR NVMSSA NVMSSR MONTH OAY YEAR N/A 0 5 0 0 0 05 989 004 0 0 0 7 8 9 0 5 0 0 0 OPS.AT(NO THIS REPORT IS SUSMITTEO tuRSUANT T 0 THE REOUIREMENTS OF 10 Cf R (Ir IChtce tilt or irioi' 0/ lht ltr/owrnf/ Ill MODE ( ~ I 1 20.402(4) 20AOS(cl 50.7$ (el(2) IN) 7$ .71( ~ I |
| | ~ DIVER 20A05( ~ )(IIIII 50.$ 5( ~ ) Ill 50.7 $ (e) 12)(y) 7$ .71I ~ I y p p Ill(yl 20.405( ~ )(I l(4) |
| | (10) 50.35(c)LTI 50.7 $ (el (2) (or( ) 0'tHER ISotciry in icollrtcl Ot/Ory end in Ttet, NRC FOnn 20AOS( ~ I (I l(ryl) 50.73( ~ I (2(III 50.7$ (c l(2) (ySI ) (AI 3FFll 20A05 (e I llI I ItI 50.7$ (e)(2)(4) 50.73(e)12)(y(4) ( ~ I 20A05(c I 50.73(e l(21(9(l 50.7$ ( ~ l(2)(el LICENSEE CONTACT FOR THIS LER 02) |
| | NAME TELE/ NONE NUMSER Charles D. Holifield, Shift Technical Advisor AREA CODE 407 465 - 35 p COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRI ~ EO IN THIS REtOR'T (1$ l MANUFAC. ftORtASLE MANVFAC EPORTASLE CAUSE SYSTEM COMPONENT TVRER TO NPROS A CAVSf SYSTEM COMtONENT Y TVRER TO NPROS SuttLEMKNTAL RftORT EXtECTEO (1iu MONTii OAV YEAR EXPECTED SUSMISSION DATE USI YES III yn, Ctetrtrt EXPECTED SUSMISSIOAI DATE/ NO ASSTRACT ILieit lo lc00 roectl, I ~,, toproeietltry Irlletn petit Iotct cyotwn(Nn rinNI ll~ I On June 5, 1989, at 1220, with Unit 2 in Mode 1 at, 100% power, a routine local leak rate surveillance test was performed on Containment Penetration 10. This penetration, which contains the exhaust line for the Containment. Purge System, is subject to Type C testing and revealed an "as-found" leakage rate across FCV-25-5 in excess of 3,171,840 standard cubic centimeters per minute (SCCM) . This leakage rate is in excess of the allowable leakage of .05 La, or 48,500 SCCM, as per Technical Specification 4.6.1.7 ' |
| | root cause of the high measured leakage was personnel error in |
| | 'he that the valve adjustment stop was not properly locked down by contractor personnel when the valve was previously adjusted. A contributing factor was lack of guidance in the technical manual on how to tighten the adjustment screw locknut. |
| | Corrective actions included confirming that the fuses for FCV 6 (a second valve in the containment purge exhaust line) were pulled, leak testing FCV-25-6, adjusting and locking down the stop for closing of FCV-25-5, and re-testing FCV-25-5, with satisfactory results. A technical manual change request will also be submitted. |
| | N RC fore 344 |
| | /9 53 ~ |
| | |
| | NRC Form 3SSA U.S. NUCLEAR RECULATORY COMMISSIC (943( |
| | LICENSEE EVENT REPORT tLER) TEXT CONTINUATION APPROVED OMB NO, 3150-0(04 EXPIRES.'8/31/88 FACILITY NAME ((I DOCKET NUMBER (2( LER NUMBER (SI ~ ACE (3) |
| | ~ YEAR >>M SECUCNTIAI IN/I RCvrsroN NUMBER NUMSC/I St. Lucie, Unit 2 o s o o o 89 0 04 00 02 oF 03 TEXT llfmore srrese is eorrired, rrso sddrdorro/ HRC %%drm 3/(SA's/ ((TI DESCRIPTION OF THE EVENT On June 5, 1989, at 1220, with Unit. 2 in Mode 1 at 1004 power, a routine local leak rate surveillance test on Containment Penetration 10 revealed a leakage rate across FCV-25-5 (EIIS:ISV) in excess of 3,171,840 Standard Cubic Centimeters per Minute (SCCM) which is the capacity of the test equipment. Penetration 10 contains a 48 inch exhaust line for the Containment Purge System, with three butterfly valves, two of which (FCV-25-4 and FCV-25-5) are subject to Type C testing, as per Unit 2 Technical Specification 3.6.1.2.b, Table 3.6.-1 and Surveillance 4.6.1.7.3. |
| | Local leak rate testing is performed by pressurizing the piping between FCV-2S-4 and FCV-25-5. Test instrumentation is connected to a test tap between the two valves, and the change in pressure over time is recorded and used to calculate the leakage rate. The as-found leakage of the penetration was in excess of the allowable leakage of .05 La, or 48,500 SCCM. In accordance with Technical Specification 3.6.1.1.7, action was undertaken to restore the leakage rate to within the specified limit within 24 hours. Also in accordance with Technical Specification 3.6.3., the fuses on FCV-25-6, an additional valve .in series with FCV-25-5, were verified to be pulled and this valve was leak tested. Following an adjustment, the valve seat stop adjustment screw was locked down-, and the leakage rate across FCV-25-5 was reduced to 200 SCCM. |
| | CAUSE OF THE EVENT The root cause of this event was personnel error by contractor maintenance personnel in that the valve travel adjustment screw locknut was only hand tightened the last time the valve travel was adjusted. A contributing factor to this event is the lack of guidance in the Technical Manual on how to tighten the adjustment drift and resulted in the tight screw locknut. The hand locknut allowed the valve travel to excessive leakage across FCV-25-S. There were no unusual characteristics of the work location that directly contributed to the personnel error. |
| | |
| | NRC form 344A U.S. NUCLEAR REOULATORY COMMISSIO I9431 LICENSE ENT REPORT ILER) TEXT CONTIN ION APPROVEO OMS NO. 3I 50&I04 EXPIRES: 4/31/bb PACILITY NAME III OOCKET NUMSER IEI LER NUMSER ISI PACE I3) |
| | YEAR IN+l 44ovENTIAL |
| | '>+r NVM44R gP'lfvleloN |
| | 'v |
| | ~ |
| | NVM44R St. Lucie, Unit 2 o s o o o3 89 89 0 04 00 0 3oF 0 3 TEXT /// move opoce ro oovrvorL ooo ~ /enovvo///RC fr>>rrr 3/34A9/ I I TI ANALYSIS OF THE EVENT This, event has been deemed reportable as per the requirements of 10 CFR 50.73(a) (2) (i) (B), any operation or condition prohibited by the plant's Technical Specifications. local leak rate testing on Penetration 10 was performed previous The with satisfactory results during the normally scheduled refueling outage which ran from early February through April of 1989. Unit 2 Technical Specification Surveillance Requirement 4.6.1.7.3"requires testing of .the Purge Valves to be conducted at -intervals of at least once per 6 months on a staggered test basis. Therefore, the containment leakage rates, according to the requirements of this Technical Specification, were tested well within the bounds of the specified surveillance interval. |
| | The limits for containment leakage rates in the Unit 2 Technical Specifications are derived from the requirements of Appendix J to 10 CFR 50. Since the other two valves in the Containment Purge exhaust lines (FCV-25-4 and FCV-25-6) were operable, the, containment isolation safety function was maintained and the health and safety of the public was not threatened. |
| | CORRECTIVE ACTIONS Operations personnel confirmed that the fuses were pulled on FCV-25-6. |
| | : 2) The Technical Staff Test Group leak tested FCV-25-6. |
| | : 3) I & C adjusted and locked down the stop for closing of FCV-25-5. |
| | : 4) The Technical Staff Test Group re-tested FCV-25-5. |
| | : 5) The Instrument - & Control department will submit a change request to vendor Tech Manual 2998-4508 to provide more guidance on adjusting the valve travel and locking down the adjustment screw.. |
| | ADDITIONAL INFORMATION 1~ Com onent Identif'cat'on This event did not involve an NPRDS reportable component failure. |
| | 2 ~ Previous Similar Events r For a similar event, see LER N335-87-005, which pertains to excessive leakage past a containment purge valve on Unit. Nl. |
| | II N/lc PO/IM 344A I943 I}} |
|
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
ML17229A7381998-05-21021 May 1998
LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr
ML17229A7011998-04-27027 April 1998
LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr
ML17229A6761998-04-0202 April 1998
LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr
ML17229A6731998-03-26026 March 1998
LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr
ML17229A6551998-03-0505 March 1998
LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr
ML17229A6281998-02-19019 February 1998
LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr
ML17229A6211998-02-0909 February 1998
LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr
ML17229A6191998-02-0404 February 1998
LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr
ML17229A6161998-02-0303 February 1998
LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr
ML17229A6051998-01-27027 January 1998
LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr
ML17229A5501997-12-0505 December 1997
LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr
ML17309A9091997-12-0202 December 1997
LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr
ML17229A5391997-11-26026 November 1997
LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr
ML17229A5151997-11-0707 November 1997
LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr
ML17229A4991997-10-17017 October 1997
LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr
ML17309A9011997-08-27027 August 1997
LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr
ML17229A4311997-07-29029 July 1997
LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr
ML17229A4241997-07-25025 July 1997
LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr
ML17229A3971997-07-11011 July 1997
LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr
ML17229A3871997-06-19019 June 1997
LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr
ML17229A3841997-06-17017 June 1997
LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr
ML17229A3751997-06-0202 June 1997
LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr
ML17229A3611997-05-29029 May 1997
LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr
ML17229A3491997-05-21021 May 1997
LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr
ML17229A3441997-05-13013 May 1997
LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc
ML17229A3141997-04-30030 April 1997
LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr
ML17229A2951997-03-31031 March 1997
LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr
ML17229A2721997-03-21021 March 1997
LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr
1999-07-06
[Table view]
Category:RO)
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
ML17229A7381998-05-21021 May 1998
LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr
ML17229A7011998-04-27027 April 1998
LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr
ML17229A6761998-04-0202 April 1998
LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr
ML17229A6731998-03-26026 March 1998
LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr
ML17229A6551998-03-0505 March 1998
LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr
ML17229A6281998-02-19019 February 1998
LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr
ML17229A6211998-02-0909 February 1998
LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr
ML17229A6191998-02-0404 February 1998
LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr
ML17229A6161998-02-0303 February 1998
LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr
ML17229A6051998-01-27027 January 1998
LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr
ML17229A5501997-12-0505 December 1997
LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr
ML17309A9091997-12-0202 December 1997
LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr
ML17229A5391997-11-26026 November 1997
LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr
ML17229A5151997-11-0707 November 1997
LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr
ML17229A4991997-10-17017 October 1997
LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr
ML17309A9011997-08-27027 August 1997
LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr
ML17229A4311997-07-29029 July 1997
LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr
ML17229A4241997-07-25025 July 1997
LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr
ML17229A3971997-07-11011 July 1997
LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr
ML17229A3871997-06-19019 June 1997
LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr
ML17229A3841997-06-17017 June 1997
LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr
ML17229A3751997-06-0202 June 1997
LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr
ML17229A3611997-05-29029 May 1997
LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr
ML17229A3491997-05-21021 May 1997
LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr
ML17229A3441997-05-13013 May 1997
LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc
ML17229A3141997-04-30030 April 1997
LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr
ML17229A2951997-03-31031 March 1997
LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr
ML17229A2721997-03-21021 March 1997
LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr
1999-07-06
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4951999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for St Lucie,Units 1 & 2.With 991014 Ltr
ML17241A4741999-08-31031 August 1999
Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr.
ML17241A4591999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr
ML17241A4301999-07-31031 July 1999
Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A4091999-06-30030 June 1999
Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17355A3681999-06-30030 June 1999
Revised Update to Topical QA Rept, Dtd June 1999
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3631999-05-31031 May 1999
Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17241A3331999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0841999-04-0707 April 1999
Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines.
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0961999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229B0461999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for St Lucie,Units 1 & 2.With 990310 Ltr
ML17229B0051999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for St Lucie,Units 1 & 2.With 990211 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9961999-01-14014 January 1999
SG Tube Inservice Insp Special Rept.
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9831998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17241A3581998-12-0909 December 1998
Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period of 970526-981209.
ML17229A9421998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for St Lucie,Units 1 & 2.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17241A4931998-11-0101 November 1998
Statement of Account for Period of 981101-990930 for Suntrust Bank,As Trustee for Florida Municipal Power Agency Nuclear Decommissioning Trust (St Lucie Project).
ML17229A9051998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for St Lucie,Units 1 & 2.With 981110 Ltr
ML17229A8871998-10-19019 October 1998
Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length
ML17229A8781998-10-19019 October 1998
Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8721998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for St Lucie Units 1 & 2.With 981009 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8611998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for St Lucie,Units 1 & 2.With 980911 Ltr
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML17229A8481998-08-0707 August 1998
Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr.
ML17229A9461998-08-0707 August 1998
Rev 0 to PCM 98016, St Lucie Unit 2,Cycle 11 Colr.
ML17229A8301998-07-31031 July 1998
Monthly Operating Repts for July 1998 for St Lucie,Units 1 & 2.W/980814 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7981998-06-30030 June 1998
Monthly Operating Repts for June 1998 for St Lucie,Units 1 & 2.W/980713 Ltr
ML17229A7701998-05-31031 May 1998
Monthly Operating Repts for May 1998 for St Lucie,Units 1 & 2.W/980612 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
1999-09-30
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8907120017 DOC.DATE: 89/07/05 NOTARIZED: NO DOCKET FACIL:50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME 'UTHOR AFFILIATION HOLIFIELD,C.D.. Florida Power & Light Co.
WOODY,C.O.
Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION R
SUBJECT:
LER 89-004-00:on 890605,containment local leak rate exceeds I
TS due to valve closure stop out of adjustment. D DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc. t ~
t NOTES'OPIES RECIPIENT RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 D NORRIS,J 1 1 D
INTERNAL: ACRS MICHELSON. 1 1 ACRS 2 2 ACRS WYLIE 1 MOELLER'EOD/DOA 1 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 '2 DEDRO 1 1 IRM/DCTS/DAB 1 NRR/DEST/ADE, 8H '1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 1"
NRR/DEST/MTB 9H 1 ,.1 NRR/DESTOPSB 8D 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 NRR~REP/ PB 10 2 2 NUDOCS-ABSTRACT 1 REG 02 1 . 1 RES/DSIR/EIB 1 RES/DSR/PRAB 1 1 RGN2 FILE 01 1 1 EXTERNAL EG&G WILLIAMSg S 4 4 FORD BLDG HOY,A L ST LOBBY 'WARD 1 1 LPDR NRC PDR 1 1 NSIC MAYS,G NSIC MURPHYgG A 1' D
'S D
D NOIR 'ZO ALL RIDS" R1KXEKENIS:
EEZASE HELP US 'IO REDOCE %ASTH! CGMIRCZ GHE 1XXUMEÃZ CDÃGRL DESK, RXN P1-37 (EZT. 20079) Kl EKaIHQQZB ACR NAHB PKH DI895GEPXXQN LISTS EQR DOCUMEÃIS YOU DCSERT NERD!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES. REQUIRED: LTTR 43 ENCL 42
P.O. Box14000, Juno Beach, FL 33408.0420 JULY, 5 1989 L-89-238 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 89-04 Date of Event: 'June 5, 1989 Containment Local Leak Rate Exceeds Technical Specifications Due to Valve Closure Sto Out of Ad'ustment Due to Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.
Very truly yours,
.C. 0. Wo Acting nior Vice President Nuclear COW/JRH/cm Attachment cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC
/
-:907120017 S9070 PDR ADGCK 05000389 PDC all I l l a>> < I
NRC fornr 344 U.S. NUCLEAR REOULATORY COMMISSION 94)31 APPROVED OMS NO, 3150410C LICENSEE EVENT REPORT {LER) EXPIRES,'~ /31/$5 FACILITY NAME lll OOCKEt NUMSER (2) PAO I St. Lucie, Unit 2 o s oo o38 1 OF TITLE <<) Contaqnmen oca +a a e xcee s ec naca peer i ca n Closure Sto put of Adjustment Due to Personnel Error EVENT DATE (5I LER NUMSER (5) REtORT DATE (7) OTHER FACILITIES INVOLVED ISI S 4 0 u 4 N 7 I A I. "SYR~ FACILITYNAMES OOCRET NuMEER(s>
MONTe DAY YEAR YEAR NVMSSA NVMSSR MONTH OAY YEAR N/A 0 5 0 0 0 05 989 004 0 0 0 7 8 9 0 5 0 0 0 OPS.AT(NO THIS REPORT IS SUSMITTEO tuRSUANT T 0 THE REOUIREMENTS OF 10 Cf R (Ir IChtce tilt or irioi' 0/ lht ltr/owrnf/ Ill MODE ( ~ I 1 20.402(4) 20AOS(cl 50.7$ (el(2) IN) 7$ .71( ~ I
~ DIVER 20A05( ~ )(IIIII 50.$ 5( ~ ) Ill 50.7 $ (e) 12)(y) 7$ .71I ~ I y p p Ill(yl 20.405( ~ )(I l(4)
(10) 50.35(c)LTI 50.7 $ (el (2) (or( ) 0'tHER ISotciry in icollrtcl Ot/Ory end in Ttet, NRC FOnn 20AOS( ~ I (I l(ryl) 50.73( ~ I (2(III 50.7$ (c l(2) (ySI ) (AI 3FFll 20A05 (e I llI I ItI 50.7$ (e)(2)(4) 50.73(e)12)(y(4) ( ~ I 20A05(c I 50.73(e l(21(9(l 50.7$ ( ~ l(2)(el LICENSEE CONTACT FOR THIS LER 02)
NAME TELE/ NONE NUMSER Charles D. Holifield, Shift Technical Advisor AREA CODE 407 465 - 35 p COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRI ~ EO IN THIS REtOR'T (1$ l MANUFAC. ftORtASLE MANVFAC EPORTASLE CAUSE SYSTEM COMPONENT TVRER TO NPROS A CAVSf SYSTEM COMtONENT Y TVRER TO NPROS SuttLEMKNTAL RftORT EXtECTEO (1iu MONTii OAV YEAR EXPECTED SUSMISSION DATE USI YES III yn, Ctetrtrt EXPECTED SUSMISSIOAI DATE/ NO ASSTRACT ILieit lo lc00 roectl, I ~,, toproeietltry Irlletn petit Iotct cyotwn(Nn rinNI ll~ I On June 5, 1989, at 1220, with Unit 2 in Mode 1 at, 100% power, a routine local leak rate surveillance test was performed on Containment Penetration 10. This penetration, which contains the exhaust line for the Containment. Purge System, is subject to Type C testing and revealed an "as-found" leakage rate across FCV-25-5 in excess of 3,171,840 standard cubic centimeters per minute (SCCM) . This leakage rate is in excess of the allowable leakage of .05 La, or 48,500 SCCM, as per Technical Specification 4.6.1.7 '
root cause of the high measured leakage was personnel error in
'he that the valve adjustment stop was not properly locked down by contractor personnel when the valve was previously adjusted. A contributing factor was lack of guidance in the technical manual on how to tighten the adjustment screw locknut.
Corrective actions included confirming that the fuses for FCV 6 (a second valve in the containment purge exhaust line) were pulled, leak testing FCV-25-6, adjusting and locking down the stop for closing of FCV-25-5, and re-testing FCV-25-5, with satisfactory results. A technical manual change request will also be submitted.
N RC fore 344
/9 53 ~
NRC Form 3SSA U.S. NUCLEAR RECULATORY COMMISSIC (943(
LICENSEE EVENT REPORT tLER) TEXT CONTINUATION APPROVED OMB NO, 3150-0(04 EXPIRES.'8/31/88 FACILITY NAME ((I DOCKET NUMBER (2( LER NUMBER (SI ~ ACE (3)
~ YEAR >>M SECUCNTIAI IN/I RCvrsroN NUMBER NUMSC/I St. Lucie, Unit 2 o s o o o 89 0 04 00 02 oF 03 TEXT llfmore srrese is eorrired, rrso sddrdorro/ HRC %%drm 3/(SA's/ ((TI DESCRIPTION OF THE EVENT On June 5, 1989, at 1220, with Unit. 2 in Mode 1 at 1004 power, a routine local leak rate surveillance test on Containment Penetration 10 revealed a leakage rate across FCV-25-5 (EIIS:ISV) in excess of 3,171,840 Standard Cubic Centimeters per Minute (SCCM) which is the capacity of the test equipment. Penetration 10 contains a 48 inch exhaust line for the Containment Purge System, with three butterfly valves, two of which (FCV-25-4 and FCV-25-5) are subject to Type C testing, as per Unit 2 Technical Specification 3.6.1.2.b, Table 3.6.-1 and Surveillance 4.6.1.7.3.
Local leak rate testing is performed by pressurizing the piping between FCV-2S-4 and FCV-25-5. Test instrumentation is connected to a test tap between the two valves, and the change in pressure over time is recorded and used to calculate the leakage rate. The as-found leakage of the penetration was in excess of the allowable leakage of .05 La, or 48,500 SCCM. In accordance with Technical Specification 3.6.1.1.7, action was undertaken to restore the leakage rate to within the specified limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Also in accordance with Technical Specification 3.6.3., the fuses on FCV-25-6, an additional valve .in series with FCV-25-5, were verified to be pulled and this valve was leak tested. Following an adjustment, the valve seat stop adjustment screw was locked down-, and the leakage rate across FCV-25-5 was reduced to 200 SCCM.
CAUSE OF THE EVENT The root cause of this event was personnel error by contractor maintenance personnel in that the valve travel adjustment screw locknut was only hand tightened the last time the valve travel was adjusted. A contributing factor to this event is the lack of guidance in the Technical Manual on how to tighten the adjustment drift and resulted in the tight screw locknut. The hand locknut allowed the valve travel to excessive leakage across FCV-25-S. There were no unusual characteristics of the work location that directly contributed to the personnel error.
NRC form 344A U.S. NUCLEAR REOULATORY COMMISSIO I9431 LICENSE ENT REPORT ILER) TEXT CONTIN ION APPROVEO OMS NO. 3I 50&I04 EXPIRES: 4/31/bb PACILITY NAME III OOCKET NUMSER IEI LER NUMSER ISI PACE I3)
YEAR IN+l 44ovENTIAL
'>+r NVM44R gP'lfvleloN
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NVM44R St. Lucie, Unit 2 o s o o o3 89 89 0 04 00 0 3oF 0 3 TEXT /// move opoce ro oovrvorL ooo ~ /enovvo///RC fr>>rrr 3/34A9/ I I TI ANALYSIS OF THE EVENT This, event has been deemed reportable as per the requirements of 10 CFR 50.73(a) (2) (i) (B), any operation or condition prohibited by the plant's Technical Specifications. local leak rate testing on Penetration 10 was performed previous The with satisfactory results during the normally scheduled refueling outage which ran from early February through April of 1989. Unit 2 Technical Specification Surveillance Requirement 4.6.1.7.3"requires testing of .the Purge Valves to be conducted at -intervals of at least once per 6 months on a staggered test basis. Therefore, the containment leakage rates, according to the requirements of this Technical Specification, were tested well within the bounds of the specified surveillance interval.
The limits for containment leakage rates in the Unit 2 Technical Specifications are derived from the requirements of Appendix J to 10 CFR 50. Since the other two valves in the Containment Purge exhaust lines (FCV-25-4 and FCV-25-6) were operable, the, containment isolation safety function was maintained and the health and safety of the public was not threatened.
CORRECTIVE ACTIONS Operations personnel confirmed that the fuses were pulled on FCV-25-6.
- 2) The Technical Staff Test Group leak tested FCV-25-6.
- 3) I & C adjusted and locked down the stop for closing of FCV-25-5.
- 4) The Technical Staff Test Group re-tested FCV-25-5.
- 5) The Instrument - & Control department will submit a change request to vendor Tech Manual 2998-4508 to provide more guidance on adjusting the valve travel and locking down the adjustment screw..
ADDITIONAL INFORMATION 1~ Com onent Identif'cat'on This event did not involve an NPRDS reportable component failure.
2 ~ Previous Similar Events r For a similar event, see LER N335-87-005, which pertains to excessive leakage past a containment purge valve on Unit. Nl.
II N/lc PO/IM 344A I943 I
