Final Rept of Significant Const Deficiency 13 Re Defects in Containment Bldg Dome Concrete.Caused by Improper Random Vibration Due to Vibrators That Were Inadequate in Size & Number.Qualified Job Superintendent Will Be ProvidedML19309F201 |
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Waterford |
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04/08/1980 |
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From: |
Crnich J, Hartnett R, Milhiser R LOUISIANA POWER & LIGHT CO. |
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Shared Package |
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ML19309F195 |
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References |
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NUDOCS 8004280605 |
Download: ML19309F201 (6) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20207M9231999-03-12012 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 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 ML18065B1351998-01-0606 January 1998 Part 21 Rept Re Use of Deltstrat Code for RCS Flow Rate Determination.Code Corrects for Temps to Determine Hot Leg Bulk Coolant Temp ML20203J2521997-12-0101 December 1997 Deficiency Rept Re Failed Mdr Relays at Entergy Operations Inc,Waterford 3 Nuclear Generation Station.Caused by Contaminated Grease.Housekeeping Procedures Formalized & Added Enclosed Booth Isolating Mdr Final Assembly LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20117K9731996-09-10010 September 1996 Follow-up Part 21 Rept of Re Failures of Waterford 3 Dedication Testing Process of Seven Commercial Grade Barksdale Pressure Switches ML20116C7031996-07-29029 July 1996 Part 21 Rept Re Failures Identified by Waterford 3 Dedication Testing Process of 7 Commercial Grade Barksdale Pressure Switches ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept LD-94-019, Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info1994-03-16016 March 1994 Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info LD-93-177, Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested1993-12-23023 December 1993 Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested LD-93-003, Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared1993-01-13013 January 1993 Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127M5201992-11-24024 November 1992 Final Part 21 Rept Re Reject Lot Serial Numbers of Defective Fuel Nozzle Tips,Consisting of Corrected Page 6 of 921102 Rept Re Reject Lots for Fuel Injector Assembly ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20115D6331992-10-15015 October 1992 Part 21 Rept Re Nuclear Logistics Inc 10CFR21 Notification for Gnb Industrial Battery Co Batteries.Util Will Obtain Replacement Batteries from C&D Power Sys,Inc & Alarm Features to Be Tested by End of Refuel 5 ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20101Q9311992-07-0808 July 1992 Part 21 Rept Re Failure to Comply w/1 Minute Rating of NCX-17 Cells Mfg by Gnb Battery Co (Formally Gould).Addl Testing of Cell Sizes & End Voltages Scheduled to Begin on 920713 & Be Completed on 920815 L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl1991-01-0404 January 1991 Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20153D8861986-02-17017 February 1986 Part 21 Rept Re Failure of Penetration & Conduit Seal Configurations During Fire Tests.Initially Reported on 860214.Evaluation of Number & Location of Defective Seals in Progress.Nrc Assistance Requested ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl W3P85-1442, Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e)1985-08-0101 August 1985 Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e) ML20133G9741985-07-31031 July 1985 Part 21 Rept Re Anchor/Darling Valve Co Swing Check Valves W/Loose Set Screws &/Or Missing Lock Welds,Reported by Palo Verde Nuclear Generating Station.All Customers W/Similar Valves Notified.Ltr Re Waterford 3 Valves Encl W3P85-1420, Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Submittal of Written Rept on Deficiency Rescheduled for 8508011985-06-27027 June 1985 Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Submittal of Written Rept on Deficiency Rescheduled for 850801 W3P85-1400, Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time Needed to Evaluate Deficiency. Next Rept Will Be Submitted by 8507011985-05-29029 May 1985 Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time Needed to Evaluate Deficiency. Next Rept Will Be Submitted by 850701 ML20128G5101985-05-24024 May 1985 Part 21 Rept Re Heat Numbers to Be Added & Deleted from Sublist Sheet A,Based on Review of NRC W3P85-1240, Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Written Rept Submittal Date Extended Until 8505311985-04-29029 April 1985 Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Written Rept Submittal Date Extended Until 850531 W3P85-0785, Interim Deficiency Rept 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Required. Submittal of Written Rept Rescheduled for 8504301985-03-25025 March 1985 Interim Deficiency Rept 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Required. Submittal of Written Rept Rescheduled for 850430 W3P85-0551, Significant Const Deficiency Rept 93 Re Charging & Letdown Containment Isolation Valve.Potential Exists for Valve to Stick Open Due to Thermal Contraction.Testing Under Temp Conditions Being Performed1985-03-0606 March 1985 Significant Const Deficiency Rept 93 Re Charging & Letdown Containment Isolation Valve.Potential Exists for Valve to Stick Open Due to Thermal Contraction.Testing Under Temp Conditions Being Performed W3P85-0544, Supplemental Final Significant Const Deficiency 93 Re Failure of Containment Isolation Valve CVC-103 to Close After Plant Cooldown.Details Will Be Provided on Valve Failure When Info Obtained1985-02-27027 February 1985 Supplemental Final Significant Const Deficiency 93 Re Failure of Containment Isolation Valve CVC-103 to Close After Plant Cooldown.Details Will Be Provided on Valve Failure When Info Obtained W3P85-0509, Interim Rept of Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Needed.Next Rept Delayed Until 8503291985-02-26026 February 1985 Interim Rept of Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Needed.Next Rept Delayed Until 850329 W3P85-0337, Final Significant Const Deficiency Rept SCD-80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply shut-off Valves.Pneumatic Operators for Valves 2MS-V611A & V612 Replaced w/D-C Motors1985-02-22022 February 1985 Final Significant Const Deficiency Rept SCD-80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply shut-off Valves.Pneumatic Operators for Valves 2MS-V611A & V612 Replaced w/D-C Motors W3P85-0339, Final Significant Const Deficiency Rept SCD-93 Re Charging & Letdown Containment Isolation Valve Deficiency.Vendor Repaired Valve W/New Seats Sized for Max Interference Fit1985-02-21021 February 1985 Final Significant Const Deficiency Rept SCD-93 Re Charging & Letdown Containment Isolation Valve Deficiency.Vendor Repaired Valve W/New Seats Sized for Max Interference Fit W3P85-0338, Final Part 21 & Const Deficiency Rept SCD-37 Re Unreliable Temp Signals from Resistance Temp Detectors (Rtd).Initially Reported on 810710.Safety-related RTDs Replaced or Environmentally Sealed.Design Change Notice Issued1985-02-21021 February 1985 Final Part 21 & Const Deficiency Rept SCD-37 Re Unreliable Temp Signals from Resistance Temp Detectors (Rtd).Initially Reported on 810710.Safety-related RTDs Replaced or Environmentally Sealed.Design Change Notice Issued W3P85-0083, Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Safety-related & Environmentally Qualified Equipment Manuals to Be Reviewed.Next Rept Anticipated by 8502281985-01-14014 January 1985 Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Safety-related & Environmentally Qualified Equipment Manuals to Be Reviewed.Next Rept Anticipated by 850228 1999-03-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 05000382/LER-1999-014, :on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B1999-10-12012 October 1999
- on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B
ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with 05000382/LER-1999-013, :on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included1999-09-23023 September 1999
- on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included
05000382/LER-1999-012-01, :on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With1999-09-13013 September 1999
- on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With
ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With 05000382/LER-1999-011-01, :on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B1999-08-31031 August 1999
- on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B
05000382/LER-1999-010-01, :on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity1999-08-26026 August 1999
- on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity
05000382/LER-1999-009-01, :on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established1999-08-26026 August 1999
- on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established
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 05000382/LER-1999-008-01, :on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-021999-07-29029 July 1999
- on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-02
05000382/LER-1999-007-01, :on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff1999-07-23023 July 1999
- on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff
ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 05000382/LER-1999-006-01, :on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With1999-07-14014 July 1999
- on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With
ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with 05000382/LER-1999-005-01, :on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested1999-06-24024 June 1999
- on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested
ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20195J9741999-06-16016 June 1999 Safety Evaluation Supporting Amend 152 to License NPF-38 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 ML20195D5491999-06-0303 June 1999 Safety Evaluation Supporting Amend 151 to License NPF-38 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 05000382/LER-1999-004-02, :on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing1999-05-14014 May 1999
- on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing
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 ML20206A9641999-04-21021 April 1999 Safety Evaluation Supporting Amend 150 to License NPF-38 05000382/LER-1999-003-02, :on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With1999-04-0909 April 1999
- on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.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 05000382/LER-1999-002-03, :on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired1999-03-25025 March 1999
- on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired
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 ML20203H8151999-02-17017 February 1999 Safety Evaluation Supporting Amend 149 to License NPF-38 ML20203H8591999-02-17017 February 1999 Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 05000382/LER-1999-001, :on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With1999-02-0404 February 1999
- on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With
ML20202H9161999-02-0202 February 1999 Safety Evaluation Supporting Amend 148 to License NPF-38 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 05000382/LER-1998-020, :on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With1998-12-31031 December 1998
- on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With
ML20199C9101998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Waterford 3.With ML20198F4691998-12-21021 December 1998 Safety Evaluation Supporting Amend 147 to License NPF-38 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 1999-09-30
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LOUISIANA POWER & LIGHT COMPANY WATERFORD SES UNIT NO 3 l
FINAL REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NUMBER 13 REACTOR CONTAINMENT BUILDING DOME CONCRETE N.
J ich, site Manager A V/ M a r a R J Miihisef, Project Superintendent
/ /
R A Hartnett, (A Site Supervisor J Hart, Project Licensing Engineer' hb b April 8, 1980
I SECTION I -
SUMMARY
During the placement of concrete for Reactor Containment Building dome parapet wall placement 521-15, improper consolidation of concrete in the lower portion of the wall occurred. Proper consolidation of the concrete as required per Fegles Power Services' Procedure CP-303-3 and Ebasco Con-crate Masonry Specification LOU 1564.472 was not achieved. Upon removal of the exterior wall forms, numerous honeycomb and rock pockets randomly distributed in the lower portion of the wall were evident. Tegles Power Services initiated Nonconformance Report W3-1576 describing these defects.
The concrete defects were primarily due to improper, random vibration during the concrete placement. ,
I SECTION II - DESCRIPTION OF DEFICIENCY l
The Reactor Containment Building dome placement 521-1B is a curved re-inforced concrete structure 118'-7" long, 3'-0" thick, and 11'-6" in height. The placement is between elevation +179.00' to +190.50' with a haunch for the initial section of the dome concrete. The concrete place-ment commenced at 6:15 a.m. on August 8, 1979. At approximately 10:00 a.m., the concrete pump line plugged and the placement continued by plac- l ing the concrete with the use of crane and buckets. The concrete vibra-tors in use were inadequate in both size and number to provide proper vib-ration of the concrete. In some situations, concrete was allowed to fall without the use of the tremies in excess of the specified limit of five (5) feet. Concrete was also allowed to dry on the reinforcing steel and measures taken to remove it were inadequate.
At approximately 12:00 (noon), additional vibrators, men, and wire brushes were added to the existing placement crews to insure proper vibration of the concrete and cleaning of the reinforcing steel of dry concrete. The placement proceeded without further incident and was completed by 6:00 p.m.
On August 13, 1979, the outside wall forms were removed. Numerous surface honeycomb and voids were encountered in the lower portion of the placement with some of these areas extending past the embedded reinforcing steel. ,
This indicated that consolidation of the concrete as required by Fegles l Procedure CP-303-3 and Ebasco Specification LOU 1564.472 was not achieved. '
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l SECTION III - ANALYSIS OF THE SAFETY IMPLICATIONS l
Had this deficiency been l'fte uncorrected, this noncompliance with concrete l
placement practices would compromise the ability of the Reactor Containment Building to satisfy some of the design bases loads and loading combinations as set forth in Sub-section 3.8.4 of the Final Safety Analysis Report.
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Pego 2 SECTION IV - CORRECTIVE ACTION AND INVESTIGATION / EVALUATION / REPAIR l
A) Corrective Action:
i The immediate corrective action taken during the placement of the done south parapet wall after the discovery of the inadequate concrete con-solidation was to add an adequate number of vibrators, laborers, and j j
inspectors to ensure proper placement of the concrete. Tremies were replaced back onto the placement to ensure that the concrete drop was within the specified limit of five (5) feet. Additional laborers with l l
' wire brushes were assigned to remove dried concrete from the resteel. _
Af ter the removal of the wall forms, Fegles initiated Nonconformance Report W3-1576 on August 13, 1979.
Corrective action implemented to prevent the recurrence of the pro-blems encountered was the issuance of a Stop Work Order on any addi-tional done concrete placement by Feglas Power Services until the fol-lowing corrective actions were completed:
i 1. Tegles shall provide a qualified job Superintendent.
! 2. Fegles shall assign an experienced placement supervisor who has ultimate charge at the placement to direct the overall placement.
Additionally, one general foreman shall be assigned for each separate placement (each side).
- 3. Fegles personnel shall be indoctrinated and trained to the require-ments of Ebasco Specification LOU 1564.472 for concrete placement with particular attention to lif t height restrictions, vibration requirements, cold joint determination and subsequent action re-quirements. This training shall take place at the Waterford Site.
I LP&L and Ebasco shall review the plans for this training and shall be notified when the training classes will take place so that the i training may be witnessed by LP&L and Ebasco. Tegles personnel who shall be trained shall include the following: .
- a. Project Superintendent I
- b. Concrete Supervisors i
- c. Foreman
- d. QC Personnel i
' Vibrator operators shall be trained in the use of vibrators and l the proper method of vibration.
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- 4. A third concrete pump shall be supplied as backup.
- 5. Gas driven generators shall be provided as backup for vibrators.
- 6. Larger vibrators shall be provided.
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- 7. A " bull" hose and air manifold shall be set up to supply the dome area and the pneumatic vibrators which shall be available.
- 8. More lights shall be used to light the dome.
- 9. A sufficient number of trained craf t personnel shall be available to adequately place concrete, vibrate concrete, and to clean ex-posed resteel and forms of concrete spillage.
- 10. The concrete lines shall be modified to eliminate severe bends. i
- 11. Adequate concrete buckets shall be supplied for backup.
- 12. Four concrete inspectors shall be available. At least two of the inspectors shall be certified Level II concrete inspectors. The remaining inspectors shall at least be certified as Level I con-crate inspectors.
- 13. A pre-placement meeting shall be conducted at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to placement with Feglas, Ebasco, and LP&L in attendance, to dis-cuss in detail the plans for concrete placement.
- 14. LP&L QA will be notified at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to scheduled place-ment commencement so that LP&L can conduct a pre-placement inspec-tion and to verify that all of the above (Items 1 through 13) have been accomplished. .
All corrective action items listed above were accomplished, the Stop Work Order was rescinded and concrete placement for the Reactor Building Dome resumed.
B) Investigation / Evaluation / Repaint Investigations / Evaluations Investigation of the defects in dome concrete placement 521-13 was in a four phase program of: (1) surface chipping to sound concrete, (2) microseismic testing (Pulse Echo Method), (3) core drilling and (4) chipping of exploratory openings.
Findings from the investigation are:
a) All surface defects were located in the lower half of the wall and mostly in the eastern section. The overall defective area was estimated to be less than 10% of the wall surface.
The inside surface defects were in general superficial, i.e. not deeper than two (2) inches. In small local areas approximately two foot square the defect went beyond the surface reinforcement.
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- j The outside surface defects were relatively deeper as compared with those of inside surface. Nearly half of the defects went beyond the surface reinforcement. The depth of defective concrete was ap-proximately nine (9) inches at the maximum, and less than three (3) inches in average. The difference in the depth of defective con-crete is possibly due to the facts that there are three layers of rebars near the outside surface and only one layer of rebars near the inside surface, and this has made it more difficult for the con-crste to properly reach to the outside surface.
It is determined according to the above that the surface defects are
. superficial in their penetration, and the defects from both inside and outside surf aces are not interconnected through the three (3) i foot wall.
b) A total of approximately 600 pulse echo tests had been performed according to a preplanned grid system laid on 2 foot centers.
Where tests could not be performed due to surface roughness, the t grid system was locally modified for proper coverage. Where clear internal reflects were found, additional test points were selected.
! A majority of internal reflectors which could be considered as indi-cations of minor entrapped air voids, cold joints and cracking were obtained from tests on the outside surface. Less than 12% of the total echo tests, 71 out of 600 found internal reflectors. Only four (4) (less than 1%) of those with internal reflectors were found from tests on the inside surf ace, and only four (4) from tests on the top surface. These results indicated that the internal reflec-tors found in the horizontal tests were practically non-existent in the vertical test orientation.
According to the results of pulse scho tests, the possibility of cold joints,' which was the original major concern, exists only in l a few small (lateral extent less than 3 to 4 inches) areas. This l finding was confirmed by the results obtained from vertical and horizontal corings and exploratory chippings. The minimum insitu concrete compressive strength is 4900 psi and well above the de-sign strength 4000 psi. Therefore, it is concluded that the in-ternal defects are structurally insignificant, and are only re quired to be fixed in the areas where concrete had been removed !
for the investigation.
c) Debris was found on the exterior faces near the construction joint at EL 179.0. The debris did not extend to the interior of the joint and was traced from the outside. The condition was caused l by the surface contour of the joint, which formed a pocket between l the concrete and the form. Cores showed the interior of the joint to be roughened and well consolidated.
Repairs 1
Af ter completion of the above investigations / evaluations the following corrective action repairs to concrete placement 521-1B were effected.
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- 1) All surface defects were removed by chipping to sound concrete.
The surf ace areas of the wall were then repaired using a shot-crete process in accordance with F6cles Procedure CP-303-11,
" Concrete Repair by Shoterete Process".
- 2) The regions of unconsolidated concrete found in the exploratory chippings were repaired with dry pack bonded with epoxy in accord-ance with Fegles Procedure CP-303-05, " Concrete Repair and Inspec-tion".
- 3) As further outlined in Procedure CP-303-05, all debris as well as any improperly consolidated concrete was removed from the con-struction joint by chipping and repaired with dry pack grout se-cured with epoxy.
- 4) All core holes and exploratory windows have been repaired by coating the surfaces with epoxy and replacing the concrete in these areas.
Repair Verification In accordance with Fegles shoterete procedure, cores were taken of the shoterete repair for insitu strength and bond verification.
The shoterete exhibited good bond as evidenced by cracking through the aggregate at the joint in one core and a nearly invisible seam in the other. Also, in general, the shoterete appeared sound with a uniform distribution of air and fine aggregate. The compressive strength test results indicate values well over the design requirement.
To develop a higher level of confidence in the bond or repair addi-tional cores were taken in the shocrete repaired area. The bonding exhibited in these cores was also found to be acceptable.
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