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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20024J2481994-10-0707 October 1994 LER 94-012-00:on 940907,discovered Failure to Perform TS Surveillance Requirements.Caused by Misunderstanding & Inadequate Technical Reviews.Ts Bases for 3/4.8.1 Will Be revised.W/941007 Ltr ML20029E5581994-05-13013 May 1994 LER 94-005-00:on 940415,dicovered That Several Valves Were Not Being Tested Per Requirements of ASME Section Xi.Caused by Inappropriate Action.Corrective Action:Pump & Valve Team Has Been Formed to Perform in Depth reviews.W/940513 Ltr ML20029D9941994-05-11011 May 1994 LER 94-006-00:on 940415,determined That on 921103, Unidentified RCS Leak Rate of Greater than 1 Gpm Occurred. Caused by Error in RCS Mass Balance Equation.Approved Temporary Change to Procedure OP-903-024.W/940511 Ltr ML20045H4731993-07-15015 July 1993 LER 93-002-00:on 930615,reactor Tripped Due to High SG Level Caused by Failure of Feedwater Control Sys.Caused by Failure of Square Root Extractor in Feedwater Flow Circuit.Failed Components Replaced & Alarm Setpoints reviewed.W/930715 Ltr ML20029B6381991-03-0808 March 1991 LER 89-007-01:on 890331,inadequate Design of Air Accumulators Due to Inadequate Review of Design Requirements Implemented as Part of post-TMI Action Plan.Design Change 3195 Phase I implemented.W/910308 Ltr ML20029A8471991-02-28028 February 1991 LER 90-019-01:on 901212,both Trains of Control Room Heating Ventilation & Air Conditioning Sys Inoperable Due to Breach in Control Room Envelope.Caused by Air Flow Past Retaining Angle.Leakage Paths repaired.W/910228 Ltr ML20028G9631990-10-0202 October 1990 LER 90-013-00:on 900903,unsampled Gas Released from Gaseous Waste Mgt Sys.Caused by Internal Leakage Past Discharge Isolation Valves.Administrative Controls in Place to Ensure That Gas Decay Tanks Sampled Prior to release.W/901002 Ltr ML20028G9211990-09-24024 September 1990 LER 90-012-00:on 900825,reactor Tripped Due to Lightning Strike.Station Mod Request Issued to Provide Uninterruptable Power Source for Steam Bypass Control sys.W/900924 Ltr ML20044A6661990-06-27027 June 1990 LER 90-006-00:on 841218.determined That Shutdown Cooling Sys Relief Valve Setpoint Not Set,Per Tech Spec Requirement. Caused by Procedural Inadequacy.Procedure MM-007-006 revised.W/900627 Ltr ML20043G1961990-06-15015 June 1990 LER 90-001-01:on 900223,discovered Controlled Ventilation Area Sys Airlock Doors D-170 & D-171 Open.Caused by Inadequate Administrative Controls.Procedural Instructions Developed to Govern Control of Air Lock doors.W/900615 Ltr ML20043G2041990-06-14014 June 1990 LER 89-006-01:on 870105,safety Class Break Requirements Not Met.Caused by Programmatic Breakdown in Administrative Controls.Valves Closed & Design Drawings & Procedures revised.W/900614 Ltr ML20043B1121990-05-21021 May 1990 LER 90-005-00:on 900420,condenser Vacuum Pump Discharge Wide Range Gas Monitor Setpoint Discovered to Be Incorrect.Caused by Inadequate Change Procedure for Data Base Manual. Administrative Procedures revised.W/900521 Ltr ML20042F7501990-05-0707 May 1990 LER 90-004-00:on 900408,partial Actuation of Emergency Feedwater Sys Occurred During Scheduled Test of Plant Protection Sys.Caused by Test Circuit Malfunction.Relay Hold Pushbutton Assembly replaced.W/900507 Ltr ML20012D6671990-03-23023 March 1990 LER 90-001-00:on 900223,discovered Controlled Ventilation Area Sys Airlock Doors D-170 & D-171 Open.Caused by Inadequate Administrative Controls.Procedural Instructions Will Be developed.W/900323 Ltr ML19354E0181990-01-22022 January 1990 LER 89-024-00:on 891223,manual Trip of Plant Initiated in Response to Decreasing Level in Steam Generator.Caused Probably by Anomaly in Main Feed Regulating Valve Pneumatic Control Sys.Tent Erected Around valve.W/900122 Ltr ML19354E0171990-01-19019 January 1990 LER 89-023-00:on 890927,MSIV 2MS-124B,determined to Have Broken Stem.Caused by MSIV Hydraulic Control Unit Thermal Valve Leakage.Replacement MSIV Stems W/Increased Blend Radius Designed to Decrease Stress installed.W/900119 Ltr ML20005E0971989-12-29029 December 1989 LER 89-017-01:on 890819,automatic Reactor Trip Initiated by Plant Protection Sys Response to Variations in Core Axial Shape Index.Caused by Failure of Pulldown & Lower Gripper Coil Current Sensors.Equipment replaced.W/891229 Ltr ML20011D2541989-12-20020 December 1989 LER 89-022-00:on 891128,plant Operated in Condition Prohibited by Tech Specs When Emergency Diesel Generator a Inoperable More than 24 H.Caused by Personnel Error.Ltr Issued to All Shift supervisors.W/891220 Ltr ML20011F4591989-12-18018 December 1989 LER 89-021-00:on 891116,emergency Diesel Generator a Declared Inoperable When Essential Svcs Chiller a Declared Inoperable W/O Verifying Availability of Offsite Ac Power. Caused by Personnel Error.Supervisor counseled.W/891218 Ltr ML19332C5781989-11-20020 November 1989 LER 89-020-00:on 891031,containment Fan Cooler C Motor Ran in Reverse Direction Reducing Air Flow & Cooling Capacity. Caused by Personnel Not Performing Surveillance Testing. Motor Rewired for Correct Slow Speed operation.W/891120 Ltr ML19327C1111989-11-13013 November 1989 LER 89-002-01:on 890125,discovered That Safety Classification of Instrument Air Tubing That Supplies Outlet Isolation Valves Installed as non-nuclear Safety.Caused by Use of Weld Filler Matl.Tech Spec Change Sent ML19324C4611989-11-13013 November 1989 LER 89-019-00:on 891012,4.16-kV Bus 3A2 Metering Potential Transformer Fuse Door Inadvertently Opened,Causing Feeder Breaker & Supply Breaker to Open & Load Sequencer to Reset. Caused by Personnel Error.Drawers relabeled.W/891113 Ltr ML19327B3511989-10-23023 October 1989 LER 89-018-00:on 890921,while Testing Main Steam Safety Valve,Lift Pressure Found to Be Below Tech Spec Allowable Value.Caused by Error in Judgement by Plant Supervisors. Event Will Be Discussed by superintendent.W/891023 Ltr 1994-05-13
[Table view] Category:RO)
MONTHYEARML20024J2481994-10-0707 October 1994 LER 94-012-00:on 940907,discovered Failure to Perform TS Surveillance Requirements.Caused by Misunderstanding & Inadequate Technical Reviews.Ts Bases for 3/4.8.1 Will Be revised.W/941007 Ltr ML20029E5581994-05-13013 May 1994 LER 94-005-00:on 940415,dicovered That Several Valves Were Not Being Tested Per Requirements of ASME Section Xi.Caused by Inappropriate Action.Corrective Action:Pump & Valve Team Has Been Formed to Perform in Depth reviews.W/940513 Ltr ML20029D9941994-05-11011 May 1994 LER 94-006-00:on 940415,determined That on 921103, Unidentified RCS Leak Rate of Greater than 1 Gpm Occurred. Caused by Error in RCS Mass Balance Equation.Approved Temporary Change to Procedure OP-903-024.W/940511 Ltr ML20045H4731993-07-15015 July 1993 LER 93-002-00:on 930615,reactor Tripped Due to High SG Level Caused by Failure of Feedwater Control Sys.Caused by Failure of Square Root Extractor in Feedwater Flow Circuit.Failed Components Replaced & Alarm Setpoints reviewed.W/930715 Ltr ML20029B6381991-03-0808 March 1991 LER 89-007-01:on 890331,inadequate Design of Air Accumulators Due to Inadequate Review of Design Requirements Implemented as Part of post-TMI Action Plan.Design Change 3195 Phase I implemented.W/910308 Ltr ML20029A8471991-02-28028 February 1991 LER 90-019-01:on 901212,both Trains of Control Room Heating Ventilation & Air Conditioning Sys Inoperable Due to Breach in Control Room Envelope.Caused by Air Flow Past Retaining Angle.Leakage Paths repaired.W/910228 Ltr ML20028G9631990-10-0202 October 1990 LER 90-013-00:on 900903,unsampled Gas Released from Gaseous Waste Mgt Sys.Caused by Internal Leakage Past Discharge Isolation Valves.Administrative Controls in Place to Ensure That Gas Decay Tanks Sampled Prior to release.W/901002 Ltr ML20028G9211990-09-24024 September 1990 LER 90-012-00:on 900825,reactor Tripped Due to Lightning Strike.Station Mod Request Issued to Provide Uninterruptable Power Source for Steam Bypass Control sys.W/900924 Ltr ML20044A6661990-06-27027 June 1990 LER 90-006-00:on 841218.determined That Shutdown Cooling Sys Relief Valve Setpoint Not Set,Per Tech Spec Requirement. Caused by Procedural Inadequacy.Procedure MM-007-006 revised.W/900627 Ltr ML20043G1961990-06-15015 June 1990 LER 90-001-01:on 900223,discovered Controlled Ventilation Area Sys Airlock Doors D-170 & D-171 Open.Caused by Inadequate Administrative Controls.Procedural Instructions Developed to Govern Control of Air Lock doors.W/900615 Ltr ML20043G2041990-06-14014 June 1990 LER 89-006-01:on 870105,safety Class Break Requirements Not Met.Caused by Programmatic Breakdown in Administrative Controls.Valves Closed & Design Drawings & Procedures revised.W/900614 Ltr ML20043B1121990-05-21021 May 1990 LER 90-005-00:on 900420,condenser Vacuum Pump Discharge Wide Range Gas Monitor Setpoint Discovered to Be Incorrect.Caused by Inadequate Change Procedure for Data Base Manual. Administrative Procedures revised.W/900521 Ltr ML20042F7501990-05-0707 May 1990 LER 90-004-00:on 900408,partial Actuation of Emergency Feedwater Sys Occurred During Scheduled Test of Plant Protection Sys.Caused by Test Circuit Malfunction.Relay Hold Pushbutton Assembly replaced.W/900507 Ltr ML20012D6671990-03-23023 March 1990 LER 90-001-00:on 900223,discovered Controlled Ventilation Area Sys Airlock Doors D-170 & D-171 Open.Caused by Inadequate Administrative Controls.Procedural Instructions Will Be developed.W/900323 Ltr ML19354E0181990-01-22022 January 1990 LER 89-024-00:on 891223,manual Trip of Plant Initiated in Response to Decreasing Level in Steam Generator.Caused Probably by Anomaly in Main Feed Regulating Valve Pneumatic Control Sys.Tent Erected Around valve.W/900122 Ltr ML19354E0171990-01-19019 January 1990 LER 89-023-00:on 890927,MSIV 2MS-124B,determined to Have Broken Stem.Caused by MSIV Hydraulic Control Unit Thermal Valve Leakage.Replacement MSIV Stems W/Increased Blend Radius Designed to Decrease Stress installed.W/900119 Ltr ML20005E0971989-12-29029 December 1989 LER 89-017-01:on 890819,automatic Reactor Trip Initiated by Plant Protection Sys Response to Variations in Core Axial Shape Index.Caused by Failure of Pulldown & Lower Gripper Coil Current Sensors.Equipment replaced.W/891229 Ltr ML20011D2541989-12-20020 December 1989 LER 89-022-00:on 891128,plant Operated in Condition Prohibited by Tech Specs When Emergency Diesel Generator a Inoperable More than 24 H.Caused by Personnel Error.Ltr Issued to All Shift supervisors.W/891220 Ltr ML20011F4591989-12-18018 December 1989 LER 89-021-00:on 891116,emergency Diesel Generator a Declared Inoperable When Essential Svcs Chiller a Declared Inoperable W/O Verifying Availability of Offsite Ac Power. Caused by Personnel Error.Supervisor counseled.W/891218 Ltr ML19332C5781989-11-20020 November 1989 LER 89-020-00:on 891031,containment Fan Cooler C Motor Ran in Reverse Direction Reducing Air Flow & Cooling Capacity. Caused by Personnel Not Performing Surveillance Testing. Motor Rewired for Correct Slow Speed operation.W/891120 Ltr ML19327C1111989-11-13013 November 1989 LER 89-002-01:on 890125,discovered That Safety Classification of Instrument Air Tubing That Supplies Outlet Isolation Valves Installed as non-nuclear Safety.Caused by Use of Weld Filler Matl.Tech Spec Change Sent ML19324C4611989-11-13013 November 1989 LER 89-019-00:on 891012,4.16-kV Bus 3A2 Metering Potential Transformer Fuse Door Inadvertently Opened,Causing Feeder Breaker & Supply Breaker to Open & Load Sequencer to Reset. Caused by Personnel Error.Drawers relabeled.W/891113 Ltr ML19327B3511989-10-23023 October 1989 LER 89-018-00:on 890921,while Testing Main Steam Safety Valve,Lift Pressure Found to Be Below Tech Spec Allowable Value.Caused by Error in Judgement by Plant Supervisors. Event Will Be Discussed by superintendent.W/891023 Ltr 1994-05-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 ML20195K3391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Waterford 3 Ses.With ML20195C3041999-05-28028 May 1999 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20206S7401999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Waterford 3.With ML20205T2621999-04-22022 April 1999 LER 99-S02-00:on 990216,contract Employee Inappropriately Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Security Personnel Performed Review of Work & Work Area That Individual Was Involved with ML20205N9671999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Waterford 3 Ses.With ML20205E8531999-03-30030 March 1999 Corrected Pages COLR 3/4 1-4 & COLR 3/4 2-6 to Rev 1, Cycle 10, Colr ML20205A6331999-03-25025 March 1999 SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3 ML20204H1401999-03-23023 March 1999 Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3 ML20204H1231999-03-22022 March 1999 Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping ML20204H2451999-03-22022 March 1999 Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3 ML20204F0791999-03-17017 March 1999 Rev 1 to Waterford 3 COLR for Cycle 10 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207F3491999-03-0505 March 1999 LER 99-S01-00:on 990203,contraband Was Discovered in Plant Protected Area.Bottle Was Determined to Have Been There Since Original Plant Construction.Bottle Was Removed & Security Personnel Performed Search of Area.With ML20204B5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Waterford 3.With ML20203H8591999-02-17017 February 1999 Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 ML20199H6261999-01-21021 January 1999 Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change ML20199C9101998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Waterford 3.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20206N4131998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Waterford 3.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20195E5161998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Waterford 3.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K0801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Waterford 3 Ses. with ML20151W8331998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Waterford,Unit 3. with ML20237B6831998-08-17017 August 1998 LER 98-S01-00:on 980723,discovered That Waterford 3 Physical Security Plan,Safeguards Document Was Not Under Positive Control of Authorized Person at All Times.Caused by Human Error/Inappropriate Action.Counseled Employee Involved ML20237C5661998-08-17017 August 1998 Safety Evaluation Accepting Licensee Request for Exemption from Section Iii.O of Appendix R to 10CFR50 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 ML20237B5261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Waterford 3 ML20236S9031998-07-22022 July 1998 SER Accepting Rev 19 to Quality Assurance Program for Waterford Steam Electric Station,Unit 3 ML20198H3911998-07-14014 July 1998 Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool ML20236N4181998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Waterford,Unit 3 ML20248E7781998-06-0101 June 1998 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20249A4711998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Waterford 3 Ses ML20196A4051998-05-31031 May 1998 Rept of Facility Changes,Tests & Experiments,Per 10CFR50.59 for 970601-980531. with ML20198H4681998-05-20020 May 1998 Non-proprietary Rev 1 to HI-981942, Independent Review of Waterford Unit 3 Spent Fuel Pool Cfd Model ML20247A3891998-05-0101 May 1998 SG Eddy Current Examination (8th Refueling Outage) ML20247F6761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Waterford,Unit 3.W/ ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20216B1751998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Waterford 3 Ses ML20217M1411998-03-0303 March 1998 Rev 2 of Waterford 3 Cycle 9 Colr 1999-09-30
[Table view] |
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Operations - u ma le ' . 6;3tPO D. F. Packer G.' r,.vce rA, mor nan, m..a ox G'.if e t f' WL13 W3F1-94-0058 A4.05 PR fiay 11, 1994 U.S. Nuc1 ear Regulatcry Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License flo. f4PF-38 Reporting of Licensee Event Report Gentlemen:
Attached is Licensee Event Report fiumber LER-94-006-00 for Waterford Steam Electric Station Unit 3. This Licensee Event Report is submitted in accordance with the requirements of 10CFR50.73(a)(2)(i)(B) and 10CFR50.36(c)(2).
Very truly you s, CM /
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D.F. Packer General flanager Plant Operations DFP/RWP/ssf Attachment cc: L.J. Callan, NRC Region IV G.L. florreich J.T. Wheelock - INPC Records Center R.B. McGehee N.S. Reynolds f1RC Resident Inspectors Office y Administrator - LRPD /
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Waterford Steam Electric Station Unit 3 05000 382 10F 04 pru m -
uError (nRCSMassBalanceEquation EVEtJT DATE (5) LER NUMBER (6' REPORT NUMBER (7) OTHER FACILITIES itJVOLVED (8) atiA , mon f AM ( NAW M I NUMut,H
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11 03 92 L 94 006 00 05 11 94 t1/A 05000 OPERATING THIS REPORT IS SUBMITTED PURSUAtJT TO THE REQUIREMEtJTS OF 10 CFR 1: (Check one or more) (11)
MODE (9) 5 20 402(b) 20 405(c, so.73(a)(2)0v) 73.73 (n)
POWER 20 405(aH1)W 50.36(cH 1) 50 73(a)(2)(v) 73 71(c)
LEVEL (10) 0 20 405faH1Hid X 50 30(::H2) So.73(a)(2)lvu) OTHER 20 405(aHI)0n) X 50 73(aH2'(0l 50.73(a)(2Hviii)(A) W/
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LICENSEE COf1 TACT FOR THIS LER (12) m vs - tuu m Nuve rw4,..cm D.W. Vinci,_0perations Superintendent (504) 464-3178 COMPLETE ONE ilNE FOR EACH COMPONEfJT FAILURE DESCRIBED IN THIS RLPORT (13) cemt m ri u m uacNtNr uANor scTuna E R E
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ADSTRACT (Lim,t to 1400 spaces. t e , a;; proximate:y 15 mngle spaced typeetten kne?) (16)
On April 15, 1994, Waterford SES Unit 3 was shutdown for refueling in Mode 5 while conducting a compliance review check of previous Reactor Coolant System (RCS) leak rate calculations that were based on Attachment 10.4 of Revision 8 to Operating Procedure OP-903-024. At this time it was determined that on Noverrber 3,1992, during the previous refueling outage (Refuel 5), that an unidentified RCS leak rate ;
of >l GPM had occurred during Mode 5 before entering Mode 4, which constituted noncompliance with Technical Specification (TS) 3.0.4.
The root cause of this event was inadequate technical review of a change made to the RCS mass balance equation in Attachment 10.4 of Revision 8 to OP-903-024. Immediate corrective action included a tetrporary approved change to Attachment 10.4, correcting the equation. Action to prevent recurrence will be to have Operations personnel review this event. The event did not compromise the health and safety of the public.
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TEXT CONTINUATlON $$j'aSO8e$'*$$'"'w%10*%"*ccS'l34$"UETe" u a10 THE PAPERWORa( REDUCTCN PRCAJECT Q150 0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 29603 F ACILITV N AME p) DOCH ET NUMBLR (2) LER NUMBE R H) PAGE (3)
SEOVENTAL HEvtscN WR NyVBER
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NUMBER Waterford Steam Electric Station 05000 382 ~ ~
02cF 04 Unit 3 94 006 00 um, .,, . w. . . ..n .a. -. .m-. m... ., ec o+ um p n REPORTABLE OCCURRENCE On flovember 3,1992, during the previous refueling outage (Refuel 5), an unidentified RCS (EIIS Identifier AB) leak rate of 1.4424 GPM had occurred.
Due to incorrect calculational methods, the unidentified RCS leak rate at l
the time, during Refuel 5, was calculated to be <1 GPM; therefore, no ,
action was taken to prevent from proceeding to Mode 4. TS 3.0.4 states that entry into an operational mode shall not be made unless the conditions of the LCO are met without reliance on provisions contained in the action requirements. Also, TS 3.4.5.2 states that RCS leakage shall be limited to 1 GPM unidentified leakage for Modes 1, 2, 3 and 4. Therefore, upon entry into Mode 4, a condition prohibited by the plant's Technical Specifications had occurred; and, per 10CFR50.73(a)(2)(i)(B) and 10CFR50.36(c)(2) the event is reportable as an LER.
I INIT_IAL_COND1TIONS Plant Power 0%
Plant Operating Mode Mode 5 Procedures Being Performed Specific to this Event OP-903-024 :
1 Technical Specification LCO's in 'l Effect Specific to this Event 3.4.b.2 l Major Equipment Out of Service l'
Specific to this Event lione l l
l l
I L
MC FORM 3M4 it 92)
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b NHC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROYED BY OMB HO. 3150-0104 li p sr, . EXPIRc3 2,/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY MTH Tws INFORMAT'CN COLLECTON REQUEST, 50 0 HRS. F054WA40 LICENSEE EVENT REPORT (LER) COuuE.c. REauoNG suROEN cSTiuAfs TO TmE i-Oavnou
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LEQUE NT AL RE asioN NUMBER NUMBER i Waterford Steam Electric Station 05000 382 -
03 OF 04 '
Unit 3 94 - 006 00 i
'iimm ,,., , ,, ..,,,,.w. m ,6., o ww,m> v n EVENT SEQUENCE On April 11, 1994, during Refuel 6 while attempting to use Attachment 10.4 l of OP-903-024 for an RCS leak rate calculation, it was realized that the i results were ur, realistic for plant conditions that existel at the time. On April 13, 1994, the results of an investigation revealed that the formula for the RCS mass balance equation (AGrcs), when Ta vg is <540*F, used in l step 8.1.1.5 of Attachment 10.4 of OP-903-024 was in error. The initial !
and final RCS inventories were reversed in the equation; i.e., the final !
I inventory should have been subtracted from the initial inventory to obtain !
i AG rcs. The investigation determined that this equation was revised by l
Revision 8 to OP-903-024 on September 6, 1991. The previous Revision 7 (dated February 13, 1990) equation was correct and the incorrect equation i
was introduced by Revision 8. The investigation also recommended that a 1 compliance review check be conducted of previous RCS leak rate calculations {
that were based on Attachment 10.4 of Revision 8 to OP-903-024. On April :
15, 1994, at 1637 hours0.0189 days <br />0.455 hours <br />0.00271 weeks <br />6.228785e-4 months <br />, Waterford 3 was shutdown for refueling in Made 5 while conducting the recommended compliance review check when it was determined that on November 3, 1992, that an unidentified RCS leak rate of
>l GPM had occurred during Mode 5 before entering Mode 4.
CAUSAL _ FACTORS i The root cause of this event was inadequate technical review of a change I
made to the RCS mass balance equation in Attachment 10.4 of Revision 8 to l
.l OP-903-024. l
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l l
l.
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INFOFWATON COLLECTION REQUEST. 50 0 HRS. FORWARD LICENSEE EVENT REPORT (LER) CouuevTs REauoNo BURotN EsTuaTE To THE woRMATcN AND RECORD 3 MANAGEMENT ORANCH (MNB8 771dL U S. NUCLEAR TEXT CONTINUATION Recut 4Tosu CoMutssroN. wAsMiNoToN, oc resss-ooo1 ANa To THE PAPERW1DR< REDUCTON PROJECT (31504104, # OFFICE 08 MANAGEMENT AND BUDGET. WASHINGTON DC 20503.
7 ACILITY N A ME p ) I DOCF ET NUMBER (2) LE.*l NUMBE R l8) P AGE 13)
Si;QUENTIAL hEV1LON ygg NUMBER NUMBER Waterford Steam Electric Station 05000 382 ~ -
04 & 04 006 00 u unit 3 94
, E a w n. n. . .u.n.a ... . m -., n m xm o n IMMEDIATE CORRECTIVE MEASURES Immediate corrective action for this event was to make a temporary approved change to Attachment 10.4 of OP-903-024 correcting the mass balance equation.
ACIIONS TO PREVENT RECURRENCE Given that Waterford 3 believes that this was an isolated case, action to prevent recurrence will be to have Operations personnel review this event. ,
1 This will be completed by June 15, 1994.
l SAFETY SIGNIFICANCE This event did not compromise the health and safety of the public because RCS components and support systems designed to accommodate RCS leakage were ;
not burdened during the time frame that the leakage could have occurred.
Also, when the surveillances were conducted upon exiting Refuel 5 during Modes 1 through 4, which were based on correct calculations in Attachment 10.1 of OP-903-024, RCS unidentified leakage was within LCO limits. The )
l incorrect methodology in Attachment 10.4 of Revision 8 to OP-903-024 was ,
l used only once to determine RCS leak rate, which was on November 3, 1992 j involving this event.
SIMILAR EVENTS )
None
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